Davis-Besse, Unit 1, Amendment 42, modifying TSs ... · GR 7 L O0 25 1 TECHNICAL SPECIFICATION...

Docket No. 50-346

Mr. Richard P. Crouse Vice President, Nuclear Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652

Dear Mr. Crouse:

SI•TRIBU199, -Da: kket File ) NRC PDR-L PDR TERA NSIC ORB#4 Rdg DEisenhut OELD AEOD IE-4 ACRS-1O TBarnhart-4

DECEMBER 2 3 1•i

OGC DBrinkman OPA RDiggs ADe Agazio RIngram Gray File +4 ASLAB EBI ackwood HOrnstein

LSchnieder The Commission has issued the enclosed Amendment No. 42 to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated November 5, 1981.

This amendment modifies the TSs concerning regulating rod groups position limits, axial power shaping rod position limits and surveillance requirement, and axial power imbalance limits and corrective action requirement.

The TS modifications concerning regulating rod groups position limits, axial power shaping rod position limits and axial power imbalance limits will accommodate extension of the present cycle length to 306 + 10-30 Effective Full Power Days.

The modification to the axial power shaping rod position surveillance requirement makes this surveillance requirement similar to the regulating rod position surveillance requirement. This modification was also requested by attachment 4 of your application dated December 26, 1980, but which has not previously been approved.

The modification to the axial power imbalance corrective action requirement relaxes the requirement to bring the unit to hot-standby if axial power imbalance exceeds the limits for more than 15 minutes. The modified TS permits continued operation at reauced power to restore operation within limits. This modification was also requested by attachment 4 of your application dated July 10, 1981, but which has previously not been approved.

of the Safety Evaluation and the Notice of Issuance are also enclosed.

Sincerely,

JohPn.F. -Stolcz!, Chief Operating Reactors Branch #4 Division of Licensing

CD sures: fvAendment No. 42

2. Safety EvaluationTi I*

OFFICE* .............. .............. ................ . SUR IE ccw/entlosures: Se? next page Rlngram;cfl ADe Agazio JStc

SURNAMEp .................. . ........................ .............. ... ..... ..... .......... ...........

"8201200720 811223 121/l781 .. 21/81 .2.. PI Ao CKoo 05000346. ......................... ....................... ,. ........... ,.... PDR ADOCK 0FF0003L 46 Sp PDR OFFICIAL RECORD COPY/

"OEQL D

1 2/,,_381

USGPO: 1981-335-960

J)Ah cv

Toledo Edison Company

cc w/enclosure(s):

Mr. Donald H. Hauser, Esq. The Cleveland Electric

Illuminating Company P. 0. Box 5000 Cleveland, Ohio 44101

Gerald Charnoff, Esq. Shaw, Pittman, Potts

and Trowbridge 1800 M Street, N.W. Washington, D. C. 20036

Paul M. Smart, Esq. Fuller & Henry 300 Madison Avenue P. 0. Box 2088 Toledo, Ohio 43603 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814

President, Board of County Commissioners of Ottawa County

Port Clinton, Ohio 43452

Attorney General Department of Attorney General 30 East Broad Street Columbus, Ohio 43215

Harold Kahn, Staff Scientist Power Siting Commission 361 East Broad Street Columbus, Ohio 43216

Mr. Ted Myers Manager, Nuclear Licensing Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652

U.S. Nuclear Regulatory Commission Resident Inspector's Office 5503 N. State Route 2 Oak Harbor, Ohio 43449

Mrs. Julia Baldwin, Librarian Government Documents Collection William Carlson Library University of Toledo 2801 W. Bancroft Avenue Toledo, Ohio 43606

Regional Radiation Representative EPA Reqion V 230 South Dearborn Street Chicago, Illinois 60604

cc w/enclosure(s) and incominq dtd.: 11/5/81

Ohio Department of Health ATTN: Radiological Health

Program Director P. 0. Box 118 Columbus, Ohio 43216

UNITED STATES , NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555

~ ~oTHE TOLEDO EDISON COMPANY

AND

THE CLEVELAND ELECTRIC ILLUMINATING COMPANY

DOCKET NO. 50-346

DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1

AMENDMENT TO FACILITY OPERATING LICENSE

Amendnent No, 42 License No. NPF-3

1. The Nuclear Regulatory Commissjon (the Comrmission) has found that:

A. The application for amendment by The Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated November 5, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I;

B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;

C. There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;

D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8201200725 811223 PDR ADOCK 05000346 P PDR

-2-

2. Accordingly, Facility Operating License No. NPF-3 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment:

Revise paragraph 2.C.(2) to read as follows:

Technical Specifications

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 42 , are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

(Johj F. Stolz, Chief Op ating Reactors B;anch #4 •-ivision of Licensing

Attachment: Changes to the Technical

Specifications

Date of Issuance: December 23, 1981

ATTACHMENT TO LICENSE AMENDMENT NO. 42

FACILITY OPERATING LICENSE NO. NPF-3

DOCKET NO. 50-346

Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

P2aes

3/4 1-26

3/4 1-28a

3/4 1-28b (new page)

3/4 1-29a

3/4 1-29b

3/4 1-34

3/4 1-36

3/4 1-38

3/4 1-39 (new page)

3/4 2-1

3/4 2-2a

3/4 2-2b (new page)

3/4 2-3a

3/4 2-3b (new page)

REACTIVITY CONTROL SYSTEMS

SAFETY ROD INSERTION LIMIT

LIMITING CONDITION FOR OPERATION

3.1.3.5 All safety rods shall be fully withdrawn.

APPLICABILITY: 1* and 2"#.

ACTION:

With a maximum of one safety rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:

a. Fully withdraw the rod or

b. Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS

4.1.3.5 Each safety rod shall be determined to be fully withdrawn:

a. Within 15 minutes prior to withdrawal of any regulating rod during an approach to reactor criticality.

b. At least once per 12 hours thereafter.

"*See Special Test Exception 3.10.1 and 3.10.2.

#With K > 1.0. eff .

DAVIS-BESSE, UNIT I 3/4 1.25


REGULATING ROD INSERTION LIMITS


3.1.3.6 The regulating rod groups shall be limited in physical insertion as shown on Figures 3.1-2a, 2b and 2c and 3.1-3a, 3b and 3c, with a rod group overlap of 25 ±5% between sequential withdrawn groups 5, 6, and 7.

APPLICABILITY: MODES 1* and 2*#.

ACTION:

With the regulating rod groups inserted beyond the above insertion limits (in a region other than acceptable operation %, or with any group sequence or overlap outside the specified limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:

a. Restore the regulating groups to within the limits within 2 hours, or

b. Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the rod group position using the above figures within 2 hours, or

c. Be in at least HOT STANDBY within 6 hours.

NOTE: If in unacceptable region, also see Section 3/4.1.1.1.

*See Special Test Exceptions 3,10.1 and 3.10.2.

#With keff ? 1.0.

Amendment No. 11, AZ, 4t,42

I

DAVIS-BESSE, UNIT 1 3/4 1-26

(280,5,t02)

(260,100)

POWER LEYEL CUTOFF 92%

UNACCEPTABLE OPERATION

SHUTDOWN LIMIT (FOR 1% AK/

(225.50)

:3 0

a

=

w

U,

a 0�

OPERATION

100 75 100

I I

0 25

200

Rod Index (S Witndrawn)

75 IC

0 GR 7 L

O0

25 1

TECHNICAL SPECIFICATION FIGURE 3.1-2b. Regulating Group Position Limits. 150 ±10 to 250 t10 ErPD, Four RCPs - Davis-Besse 1, Cycle 2

DAVIS-BESSE, UNIT NO. 1

100 (300, 102)

ACCEPTABLE

80

60

40

20

O1.a 0 0

GR 5 L

GR 6

300

100

3/4 1-28a Amendment No. 11, 33,42

W•I f

POWER LEVEL CUTOFF 92%


O"

€=.

E,_

C,

GR 60

(262,

SHUTDOWN LIMIT (FOR 1$ AK/K SHUTDOWN MARGIN)

(204,50) % k

(275,102)

? ? (300.,102)

80)

t00

60

40

20

0

GR 5

ACCEPTABLE OPERATION

100100

25

200 Rod Index (% withdrawn)

75

0 GR 7 1

)

100

25 1

O00 to

TECHNICAL SPECIFICATION FIGURE 3.1-2c. Regulating Group Position Limits, After 250 !10 EFPD, Four RCPs - Davis-Besse 1, Cycle 2


225,50)

7500

3/4 1-28b Amendment No. 42

I I J

i llr

%

Ito

#11 m,

-4 --4

C)(235

14

0

0.4

I00

80

60

40

20

0 0

GR 56

200 300 Rod Index ( % wlthdrawn)

75 160

i5 A

I GR 7 0

TECHNICAL SPECIFICATION FIGURE 3.1-3a Regulating Group Position Ltmits4 0 to 150 +10 EFPD, Three RCPs - Davis Besse 1, Cycle 2

UNACCEPTABLE OPERAT ION

SHUTDOWN LIUIT (for I% k/k

ACCEPTABLE OPERATION

100

',J

0

-J

t225,38)

(

GR 6 6 600

10o1 25

0%

c: (260,

100[

80

60

40

20

0


SHUTDOUN LIMIT (FOR it bM/K SHLTDOWN MARG

RESTRICTED

(300,77)

1.5)

0 120 ZUU JUU O 75 100 Rod Index (S Witndrawn)

0 25 75 100 GR 6 - , 1 f

GR 70 25 1100

TECHNICAL SPECIFICATION FIGURE 3.1-3b. Regulating Group Position Limits, 150 ±10 to 250 ±10 EFPD, Three RCPs Davis-Besse 1, Cycle 2

Amendment No. 11, $,42

(225.38)

ACCEPTABLE

OPERATION

GR 5

II i H I

q i II i

(280.5,77)1

.A_ JA•

3/4 1-29aDkVIS-BESSE, UNIT NO. 1

(262.77)

E.

6)

2

E-4

a.

(225,38)


75 100

0 25 75 GR6

GR 7

TECHNICAL SPECIFICATION FIGURE 3.1-3c. R A

Rod Index(% Witndrawn)

i00

25

10

I0

egulating Group Position Limits, .fter 250 -10 EYPD, Three RCPs avis-Besse 1, Cycle 2

Amendment No. U, 2, 42

SHUTDOWN LIMIT (FOR IS AX/K SHUTDOWN MARGIN)

t0o

80

40

20

(275,17(300.77)

0

GR 5

DAVIS-BESSE, UNIT NO. 1 3/4 1-29b

IREACTIVITY CONTROL SYSTEMS

XENON REACTIVITY


3.1.3.8 THERMAL POWER shall not be increased above the power level cutoff specified in Figure 3.1-2 unless one of the following conditions is satisfied:

a. Xenon reactivity is within 10 percent of the equilibrium value for RATED THERMAL POWER and is approaching stability, or

b. THERMAL POWER has been within a range of 87 to 92 percent of RATED THERMAL POWER for a period exceeding 2 hours in the soluble poison control mode, excluding xenon free start-ups.

APPLICABILITY: MODE 1.

ACTION:

With the requirements of the above specification not satisfied, reduce THERMAL POWER to less than or equal to the power level cutoff within 15 minutes.


4.1.3.8 Xenon reactivity shall be determined to be within 10% of the equilibrium value for RATED THERMAL POWER and to be approaching stability or it shall be determined that the THERMAL POWER has been in the range of 87 to 929 of RATED THERMAL POWER for > 2 hours, prior to increasing THERMAL POWER above the power level c-toff.

DAVIS-BESSE, UNIT I 3/4 1-33


AXIAL POWER SHAPING ROD INSERTION LIMITS


3.1.3.9 The axial power shaping rod group shall be limited in physical insertion as shown on Figures 3.1-5a, -5b, -5c, -5d and 5e.

APPLICABILITY: MODES 1 and 2*.

ACTION:

With the axial power shaping rod group outside the above insertion limits, either:

a. Restore the axial power shaping rod group to within the limits within 2 hours, or

b. Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the rod group position using the above figures within 2 hours, or

c. Be in at least HOT STANDBY within 6 hours.


4.1.3.9 The position of the axial power shaping rod group shall be determined to be within the insertion limits at least once every 12 hours except when the axial power shaping rod insertion limit alarm is inoperable, then verify the group to be within the insertion limit at least once every 4 hours.

*With kff Ž 1.0.

DAVIS-BESSE, UNIT 1 Amendment No. Aý,42

I

3/4 1-34

100

Be

so

20

0a 20 40 so 80

(100,45

100APSR Pnsitian (10 wi~nzTawn.)

* - FIGURE 3.1-5a APSR Postcioz Llls 0 to 150 -6-0 :7?n Tour ap~s - Dv.-.s ,cc1

~Av~s-z3$ýf .6 ~' Amendment .4o. .2

ca 0.

Z

04 cc

(12,102)

(8,92) (35,92) RESTRICTED REGION

(40,80)80)

(100,67.5)

0

E-.

b.

0

4Q.

a

0 a-.

20 40 60 80

APSR Position (% Witnarawn)

TECHNICAL SPECIFICATION FIGURE 3.1-5b. APSR Position Limit, 150 ±10 to 250 ±10 EFD, Four RCPs Davis-Besse 1, Cycle 2


100

0,70)

80

60

40 PERMISSIBLE OPERATING REGION

20

0

0 100

(30,10O2)

3/4 1-36 Amendment No. 33, 42

lea

40

20

0 20 so an 100AMS Position (S witfldrawn)

FIGURE 3.1 -5,c

APS2R Posit'on L=izs, 0 to 150 *10O MFD, Three U.~s -: Dav:Ls-3essa 1, Cycl~e 2

DAVS-3ZSSZ, 3/�& �"�J Amendnient �Io. 33

46

#a

.(100,34.25)

* Amendment ýfo. 3 33;-" 1-37

100

80(12,77)

(30,77)

(8,69.5)

60 F P(5,60.5)

40

0

i-d

0

0

RESTRICTED REGION

(35,69.5)

(40,60.5)

(100,54)0,53)

PERMISSIBLE OPERATING REGION

20 40 60 80

APSR Position (S Witndrawn)

TECHNICAL SPECIFICATION FIGURE 3.1-5d. APSR Position Limits, 150 ±10 to 250 ±10 EFPD, Three RCPsDavis-Besse 1, Cycle 2

DAVIS-BESSE, UNIT NO.1 Amendment No. 33,42

20

0 100

3/4 1-38

110

100

so

80

70 APSR INSERTION NOT ALLOWED

IN THIS TIME INTERVAL

60

50

40

30

20

10

0 I

0 10 20 30 40 50 60 70 80 90 100 APSR Position (% witf drawn)

TECHNICAL SPECIFICATION FIGURE 3.1-5e. APSR Position Limits, After 250 ±10 EFPD, Three or Four RCPs - Davis-Besse 1, Cycle 2


0

a..

E4

0

a-1

Amendment No. 423/4 1-39

3/4.2. POWER DISTRIBUTION LIMITS

AXIAL POWER IMBALANCE


3.2.1 AXIAL POWER IMBALANCE shall be maintained Figures 3.2-1a, -ib, -ic and 3.2-2a, -2b, -2c.

within the limits shown.on

APPLICABILITY: MODE 1 above 40% of RATED THERMAL POWER.*

ACTION:

With AXIAL POWER IMBALANCE exceeding the limits specified above, either:

a. Restore the AXIAL POWER IMBALANCE to within its limits within 15 minutes, or

b. Within one hour reduce power until imbalance limits are met or to 40% of Rated Thermal Power or less.


4.2.1 The AXIAL POWER IMBALANCE shall be determined to be within limits at least once every 12 hours when above 40% of RATED THERMAL POWER except when the AXIAL POWER IMBALANCE alarm is inoperable, then calculate the AXIAL POWER IMBALANCE at least once per hour.

*See Special Test Exception 3,10,1.

DAVIS-BESSE, UNIT 1

I

I

3/4 2-1 Amendment No. 33,42

-20 -0 -10 a +Z9

Axial Pouer lUavance (S)

FIGURE 3.2-la

Axial.2 ?ov.er Tzba1~ce Llm±:s, 0 to 150 to1 MD, ?our ZC~s - *Zav:Ls-3&ss* 1, Cycj.le Z

A~S3E3Z, N 13/42-2Amendment No. ;r-.1h 33ý,A,% -V-S-BESSZ, ;N.= I 3/4 Z-Z

+30-30 -20 -10 0 +10

AXIAL POWER

TEC1NICAL SPECIFICATION FIGURE 3.2-lb.

IMBALANCE (S)

AXIAL POWER I"'1RALANCw Limits, 150 ±10 to 250 ±10 EFPD, Four RCPs Davis-Besse 1, Cycle 2

Amendment No. 11, 33,423/4 2-2aDAVIS-BESSE, UNIT NO. 1

(-50,50)

.50 -40 -30 -20 -1O 0 10 20 30

AXIAL POWER LMBALANCE (0)

TECHNICAL SPECIFICATION FIGURE 3.2-ic. AXIAL POWER IMBALANCE Limits, After 250 ±10 EFPD, Four RCPs Davis-Besse 1, Cycle 2

DAVIS-BESSE, UNIT NO. 1 3/4 2-2b Amendment No. 42

% of RATED THERM4AL POWER

100

(-26.3,38) 4u (+18.75,

PERMISSIBLE

OPERATING 20 REGION

-30 -20 -10 0 10 20

AXIAL POWER IMALANCE (%) TECHNICAL SPECIFICATION FIGURE 3.2A2b AXIAL POWER IMBALANCE Limits,

150 1 10 to 250 ± 10 EFPD, Three RCPs Davis-Besse 1, Cycle 2

DAVIS-BESSE, UNIT NO. 1 3/4 2 -3a Amendment No. 12

30

., A,42

(-22.5,77)

RESTRiCTED REGION

(-23.25.69.5)

(-26.25,60.5)

(-37.5,38) U U,,

4,.

gU

U.

PERMISSIBLE OPERATING REGION

t00

80(11.2S,77)

(11.25,69.5)

(15.60.5)

40

20

(18.75,38)

-50 -40 -30 -20 -10

TECHNICAL SPECIFICATION FIGURE 3.2-2c.

10 20 30

AXIAL POWER IMBALANCE Limits, After 250 ±10 EFPD, Three RCPs - DavisBesse 1, Cycle 2

DAVIS-BESSE, UNIT NO. 1 3/4 2-3b

30

Amendment No. 42

Figure 3.2-3a Oeleted

Amendment No.., 3 3DAVIS-3ESSE, UNIT 1 3/4 2-4

,10, UNITED STATES - c NUCLEAR REGULATORY COMMISSION C WASHINGTON, D. C. 20555

SAFETY EVALUA T On• BY THE OFFICE OF NUCLEAR REACTOR REGULATION

SUPPORTING AMENDMENT NO. 4 2 TO FACILITY OPERATING LICENSE NO. NPF-3

TOLEDO EDISON COMPANY

AND

CLEVELAND ELECTRIC ILLUMINATING COMPANY

DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1

DOCKET NO. 50-346

1.0 Introduction

By letter of November 5, 1981 (Reference 1), Toledo Edison Company (TECo or the licensee) requested amendment to Facility Operating License NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1. The proposed amendment would modify the Technical Specifications (TSs) concerning regulating rod group position limits, axial power shaping rod group position limits, and axial power imbalance limits. Also proposed were modifications to the corrective action required by the TSs in the event axial power imbalance limits are exceeded and to the TS Surveillance Requirement applicable to the axial power shaping rod group position.

The proposed TS modifications would accommodate an extension of the present core cycle length to 306 + 10-30 Effective Full Power Days (EFPD) from the current expected 250 EFPD by allowing complete withdrawal of the axial power shaping rods at 250 EFPD and by coasting down power level towards the end of the cycle. The proposed modification to Cycle 2 operation would be used by TECo only, if upon reaching 250 EFPD, additional at-power operation is needed to enter the scheduled refueling outage period.

The proposed modification to the TS action requirement in the event axial power imbalance is not within allowable limits would relax the requirement to avoid unnecessary hot-shutdown of the unit. The proposed modification to the TS surveillance requirement for the axial power shaping rod group position would make this surveillance requirement similar to the requirement applicable to regulating rod group position.

2.0 Discussion and Evaluation

2.1 Nuclear Analysis

With the exception of the increased cycle length from approximately 250 to 306 EFPD and cycle burnup from 8240 to 10,167 MWd/mtU, there are no significant nuclear parameter differences between the original Cycle 2 design and that proposed for extended Cycle 2 operation. The end-of-cycl• (EOC) Dopplpr coefficient becomes more negative from -1.53 to -1.58 x'10- Ak[k/°F and the EOC 4moderator coefficient becomes more negative from -2.73 to -2.95 x 10- Ak/k/ 0 F. Both of these revised key safety analysis parameters,

8201200729 811223 PDR ADOCK 05000346 P PDR

-2-

as well as all others for Cycle 2, are bounded by the values used in the Final Safety Analysis Report (FSAR).

Analysis of shutdown margin shows that 1.57 percent Ak/k exists at EOC compared to the required 1.0 percent Ak/k for hot shutdown.

Based on the fact that approved methods have been used to obtain the revised Cycle 2 core characteristics, that margin exists to limiting values of the parameters, and that startup testing was used at the beginning of Cycle 2 to verify important parameters, we find the revised physics parameters for proposed modified Cycle 2 operation acceptable.

2.2 Thermal-Hydraulic Performance

The licensee has indicated that extended Cycle 2 operation is bounded by previously approved FSAR and Cycle 2 analysis with the following exception:

a) Rod Bow Departure from Nucleate Boiling Ratio (DNBR) Penalty - The rod bow DNBR penalty for extended Cycle 2 operation was calculated using approved methods (Ref. 2). The burnup used to calculate this penalty was 25,564 MWd/mtU compared to a burnup of 23,020 MWd/mtU for a normal Cycle 2. The resulting net rod bow penalty is 1.5% after a credit for one percent flow area reduction factor is included. The flux/flow trip setpoint for Cycle 2 operation and other plant operating limits are based on DNBR criteria that contain sufficient margin to offset the rod bow penalty (Ref. 3). We find this acceptable.

Based on the compatibility of the thermal-hydraulic parameters to values previously accepted for Cycle 2 operation and to the FSAR values, wqe conclude that the extended Cycle 2 operation of Davis-Besse with currently approved limits is acceptable.

2.3 Technical Specifications

We have reviewed the proposed TS revisions related to the extended operation of Cycle 2 which include the following changes in limiting conditions of operation:

1. Regulating Rod Insertion Limits 2. Axial Power Shaping Rod Insertion Limits 3. Axial Power Imbalance

The same techniques and models were used to derive the revised TSs for limiting conditions of operation as were used to derive those for Cycle 1 and the original Cycle 2 submittal. The modified TSs required to operate beyond 250 EFPD by completely withdrawing the axial power shaping rods and coasting down in power level to the EOC (approximately 306 EFPD) have been reviewed and discussed with TECo. On the basis of these discussions and the fact that previously approved methods are used, we conclude that the new specifications, to accommodate extended Cycle 2 operation to

-3-

306 + 10-30 EFPD if required by complete withdrawal of the axial power shaping rods at approximately 250 EFPD and coasting down in power level, are acceptable.

The present TS Limiting Conditions for Operation, 3.2.1, requires that if the axial power imbalance exceeds specified limits, the power imbalance must be restored to within the limits within 15 minutes or the unit must be brought to hot-standby within 2 hours. TS 3.2.1 is applicable only when the unit is operating above 40% of rated thermal power; at 40% or less of rated power there is no Limiting Conditions for Operation applicable to axial power imbalance. The proposed modification to the action requirement would relax the requirement to place the unit in hot-standby by requiring that within one hour the unit's power be reduced until imbalance limits are met or to 40% of rated thermal power or less. Because of the shape of the axial power imbalance limit envelope, a reduction in power may bring axial power imbalance within permissible limits. At 40% of rated power or less, the limiting condition for operation is no longer applicable. This proposed modification reduces the requirement for rapid shutdown of the unit since thermal power can be readily reduced within the specified time to restore axial power imbalance to within limits or to 40% rated power or less. We find this proposed TS modification acceptable.

The present TS Surveillance Requirement, 4.1.3.9, requires that the position of the axial power shaping rod group be determined to be within the insertion limits once every 4 hours. The Station Computer System provides an alarm to the operator whenever the axial power shaping rod group position is not within the acceptable region. The TSs require operation to be brought to within limits within 2 hours or be brought to hot-standby within 6 hours. However, with the Station Computer System alarm operating the operator is immediately alerted to the out-of-limit status of the axial power shaping rod group position and corrective action can be initiated. The proposed modification to the TSs would reduce the Surveillance Requirement to at least once every 12 hours instead of every 4 hours.

If the Station Computer System alarm is inoperative, the Surveillance Requirement would remain at least once every 4 hours. The proposed change would relieve the operator of excessive surveillance and would make the axial power shaping rod group position Surveillance Requirement identical to that for the regulating rod group position. We find this proposed TS modification acceptable.

-4-

3.0 Environmental Consideration

We have determined that the amendment does not authorize a change in effluent types'or total amounts nor an increase in power level and will not result in any Significant environmental impa~t. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR §51.5(d)(4), that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.

4.0 Conclusion

We have concluded, based on the considerations discussed above, that: (1) because the amendment does not involve a significant increase in the probability, or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Comm'nission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Dated: December 23, 1981

REFERENCES

1. Letter, R. P. Crouse (Toledo Edison) to J. F. Stolz (NRC), November 5, 1981.

2. Letter, Interim October

L. S. Rubenstein (NRC) to J. H. Taylor (B&W), "Evaluation of Procedure for Calculating DNBR Reductions Due to Rod Bow," 18, 1981.

3. Davis-Besse Nuclear Power Station, Unit 1, Cycle 2 Reload Report, BAW-1598, Rev. 2, Babcock and Wilcox, Lynchburg, VA., September 1981.

7590-01

UNITED STATES NUCLEAR REGULATORY COMMISSION

DOCKET NO. 50-346

THE TOLEDO EDISON COMPANY

AND

THE CLEVELAND ELECTRIC ILLUMINATING COMPANY

NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE

The U. S. Nuclear Regulatory Commission (the Commission) has issued

Amendment No. 4 2 to Facility Operating License No. NPF-3, issued to The

Toledo Edison Company and The Cleveland Electric Illuminating Company

(the licensees), which revised Technical Specifications (TSs) for operation of

the Davis-Besse Nuclear Power Station, Unit No. 1 (the facility) located

in Ottawa County, Ohio. The amendment is effective as of its date of

issuance.

This amendment modifies the TSs concerning regulating rod group

position limits, axial power shaping rod group position limits, and

axial power imbalance limits. It also modifies 1) the corrective action required

by the TSs in the event axial power imbalance limits are exceeded and

2) the surveillance requirement applicable to the axial power shaping rod

group position. These modifications will accommodate an extension of the

present core cycle length.

The application for the amendment complies with the standards and

requirements of the Atomic Energy Act of 1954, as amended (the Act), and

the Commission's rules and regulations. The Commission has made appropriate

findings as required by the Act and the Commission's rules and regulations

in 10 CFR Chapter I, which are set forth in the license amendment. Prior

public notice of this amendment was not required since the amendment does

not involve a significant hazards consideration.

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The Commission has determined that the issuance of this amendment will

not result in any significant environmental impact and that pursuant to

10 CFR 951.5(d)(4) an environmental impact statement or negative declaration

and environmental impact appraisal need not be prepared in connection with

the issuance of this amendment.

For further details with respect to this action, see (1) the application

for amendment dated November 5, 1981, (2) Amendment No.42 to License No.

NPF-3, and (3) the Commission's related Safety Evaluation. All of these

items are available for public inspection at the Commission's Public Document

Room, 1717 H Street, N.W., Washington, DC, and at the University of Toledo Library

Documents Department, 2801 West Bancroft Avenue, Toledo, Ohio 43606. A copy of items

(2) and (3) may be obtained upon request addressed to the U.S. Nuclear

Regulatory Commission, Washington, DC 20555, Attention: Director, Division

of Licensing.

Dated at Bethesda, Maryland, this, 23rd day of December 1981.

FOR THE NUCLEAR REGUJLATORY COMMISSION

F. Stolz, Chief erating Reactors Branch #4 vision of Licensing

Davis-Besse, Unit 1, Amendment 42, modifying TSs ... · GR 7 L O0 25 1 TECHNICAL SPECIFICATION...

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