REGULATUR@ONFORMATION DISTRIBUTION …Penetrations and Coaxial Cable); 2) NUREG-0737, Item II.F.1.6,...
Transcript of REGULATUR@ONFORMATION DISTRIBUTION …Penetrations and Coaxial Cable); 2) NUREG-0737, Item II.F.1.6,...
REGULATUR@ONFORMATION DISTRIBUTION SI)TEM (RIDS)
ACCESSION NbR:8303040399 DOC,DATE: 83/02/28 NOTARIZED: NO FACIL:SO-263 Monticello Nuclear Generating Plant, Northern States AUTH.NAME AUTHUR AFFILIATION MUSOLFD, Northern States Power Co, RECIP,NAME RECIPIENT AFFILIATION
Office of Nuclear Reactor Regulation, Director
SUBJECT: Forwards response to IE Bulletin 79-01B,Suppl 3, "Qualification of TMI Action Plan Equipment," covering containment monitors,
DISTRIBUTION CODE: A0488 COPIES RECEIVED:LTR 4 ENCL TITLE: OR/Licensing Submittal: Equipment Qualification
DOCKET # 0500 0263
SIZE; -
NOTES:
RECIPIENT ID CODE/NAME
NRR ORB2 BC 12
COPIES LTTR ENCL
1 0
RECIPIENT ID CODE/NAME
NICOLARASH 01
COPIES LTTR ENCL
1 1
INTERNAL: ELD/HDS1 IE FILE NRR/DE/EQ8 NRR/DL
EXTERNAL: ACRS NRC PDR NTIS
12 09 07 06 04
15 02 31
1 1 2 1 1
8 1 1
1 1 2 1 1
8 1 1
GC NRR CALVOJ NRR/DL DIR NRR/DSI/AEB RGN3
LPDR NSIC
TOTAL NUMBER OF COPIES REQUIRED: LTTR
13 1 1
14 1 1 1
1 1 1 1 1
1 1
03 05
1 1
25 ENCL 24
(0) ()
NORTHERN STATES POWER COMPANY
February 28, 1983
Director Office of Nuclear Reactor Regulation Attn: Document Control Desk U. S.. Nuclear Regulatory Commission Washington, D.C. 20555
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22
Response to IE Bulletin 79-01B Supplement No. 3 - Qualification of TMI ACTION Plan Equipment
Supplement No. 3 to IE Bulletin 79-01B requires submittal of environmental qualification information for TMI Action Plan equipment not requiring preimplementation review by the NRC.
Attached is the requested information for additional Action Plan equipment located in a harsh environment. The following equipment is included: 1) NUREG-0737, Item II.F.1.3, High Range Containment Monitor (Containment Penetrations and Coaxial Cable); 2) NUREG-0737, Item II.F.1.6, Containment Hydrogen Concentration Monitor.
This submittal completes our response to IE Bulletin 79-01B, Supplement No. 3. Please contact us if you have any questions related to our response.
David Musolf Manager - Nuclear Support ervices
DMM/slv
cc: Regional Director-III, NRC NRR Project Manager, NRC Resident Inspector, NRC G. Charnoff
8303040399 930228 PDR ADOCK 05000263 a PDR
Rev. 1 12/18/82
Ic SYSTEM: NUREG 0737, Item II.F.1 Accident Monitoring
PLANT IDENTIFICATION LOCATION N GENERIC NAME INSIDE PRIMARY OUTSIDE PRIMARY
NUMBER CONTAINMENT CONTAINMENT
RE 7960A-B Radiation Monitor X
PT 725LA-B Pressure Transmitter X
LT 7338A-B Level Transmitter X
AT 4018A-B Hydrogen Analyzer X
Heat Tracing System
SV 4001A-B Solenoid Valve X
SV 4002A-B Solenoid Valve X
SV 4003A-B Solenoid Valve X
SV 4004A-B Solenoid Valve X
SV 4005A-B Solenoid Valve X
SV 4020A-B Solenoid Valve X
C
0Rev. 1 12/8/82
COMPONENTS
PLANT IDENTIFICATION LOCATION
GENERIC NAME INSIDE PRIMARY OUTSIDE PRIMARY NUMBER CONTAINMENT CONTAINMENT
Rockbestos Firewall III Control Cable X
Samuel Moore Saelo o #1952Instrument Cable X Dakorad #1952
Raychem Rachem Splices X WCSF-N
D. G. O'Brien D.6 G Odles Electrical Penetratim X M06 & M62 Modules
Rockbestos Firewall III Coaxial Coaxial Cable X
Rockbestos Freall EPPower Cable X Firewall EP
Samuel Moorex De oora #1Instrument Cable X Dekorad #1962
Revision 0 12/27/82 II.F.1-4-1
COMPONENT EVALUATION WORKSHEET
ENVIRONMENT DOCUMENTATION REF. QUALIFI- OUTSTANDCATION ING
EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- HMETHOD ITEMS PARAMETER CATION CATION CATION CATION
Containment
PLANT 1.D. NO.: AT 4018A-B
COMPONENT: Hydrogen Analyzer
MANUFACTURER: Comsip-Delphi
MODEL NO.: K IV
FUNCTION: Indication
Spec NA Demo 2%
Containment Hydrogen Concentration
Reactor Bldg 935' elev.
OPERATING TIME
180 days 100 days Reference 3
Reference
1
Sequential
Test
Note 3
TEMPERATURE SEE ACCIDENT & (OF) TEST PROFILES Note 1 NA NA NA
PROVIDED
PRESSURE (PSIG) Note 1 NA NA NA
RELAT IVE HUMIDITY NA NA Note 1 NA NA NA
CHEMICAL SPRAY
RADIAT iON
(RADS)
AGING
NA
6.7 x 10 4
NA NA NA NA NA
1* I I -t *
1 x 106 Reference 2
Reference 1
NA NA
4. 4. 4 4 4 I
NA Various NA Reference 1
NA NA
SU 11MERGENCEj NA { NA NA NA NA NA
9
SYSTEM:
ACCURACY:
SERVICE:
LOCATION:
Revision 0 12/27/82 II.F.1-4-2
REFERENCES:
1. IEEE-323-1974 Prototype Qualification for Hydrogen Analyzer Systems K-III and K-IV, Project 1035-1, Revision 1, September, 1981.
2. Plant Shielding Design Review, Monticello Nuclear Plant, Bechtel Job 10040-048, June, 1981.
3. Combustible Gas Control System Design Specification NSP-63-105.
NOTES:
1. This equipment is not required to function for any event which results in a harsh pressure, temperature, or humidity environment.
2. Age sensitive components will be replaced at intervals, as recommended by the manufacturer.
3. The operating time specification is an extremely conservative assumption. However, additional testing is planned by the manufacturer to demonstrate operability for 180 days.
I*
40
ff
Revision 0 12/27/82 II.F.1-5-1
COMPONENT EVAL.UATION WORKSHEET
ENVIRONMENT DOCU4ENTATION REF. QUALIFI- OUTSTANDCATION ING
EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- METHOD ITEMS PARAMETER CATION CATION JCATION _
SYSTEM: Containment
PLANT 1.D. NO.: NA
COMPONENT: Heat Tracing
MANUFACTURER: Thermon
MODEL NO.:
FUNCTION:
ACCURACY:
SERVICE:
LOCATION:
NA
Sample Line Heating
NA
H2 Analyzer Sample Lines
Reactor Building, 935' Elev. & Torus Room
OPERATING TIME
180 days 180 days Reference 1
Note 1 Sequential
Test
None
TEMPERATURE SEE ACCIDENT & (OF) TEST PROFILES Note 2 NA NA NA
PROVIDED
PRESSURE (PSIG) Note 2 NA NA NA
RELATIVE HUMIDITY NA NA Note 2 NA NA NA
(%)
CHEMICAL SPRAY NA NA NA NA NA NA
RADIATION78 1 x 10 2.5 x 10 Reference Reference Seqential None
(RADS) 2 3 Test
AGING NA 30 yrs. NA Reference 3
Sequential Test
None
I I I
SUBMERGENCE
S
NA NA NA NA NA NA
. I
Revision 0 12/27/82 II.F.1-5-2
REFERENCES:
1. Combustible Gas Control System Design Specification NSP-63-105.
2. Plait Shielding Design Review, Monticello Nuclear Plant, Bechtel Job 10040-048, June, 1981.
3. Nuclear Component Qualification Test Report for Process Temperature Control System, SWRI-7033-001, September 25, 1982.
I
NOTES:
1. Since the only accident parameter of concern is radiation, use of the 180 day integrated dose values of Reference 2 as a qualification requirement provides adequate consideration of operating time.
2. This equipment is not required to function for any event which results in a harsh pressure, temperature, or humidity environment. 0
0s
Rev. 0 12/27/82 II.F.1-6-1
COMPONENT EVALUATION WORKSHEET
ENVIRONMENT DOCUMENTATION REF. QUALIFI- OUTSTANDCATION ING
EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- METHOD ITEMS PARAMETER CATION CATION CATION CATION
SYSTEM: Containment OPERATING TIME 180 days >180 days Reference Note 1 Sequential None
PLANT I.D. NO.: See Below 1 Test
COMPONENT: Solenoid Valve TEMPERATURE SEE ACCIDENT & (OF) TEST PROFILES Note 2 NA NA NA
MANUFACTURER: Valcor PROVIDED
MODEL NO.: V-526-5295-67 PRESSURE
FUNCTION: Sample Line Isolation (PSIG) Note 2 NA NA NA
ACCURACY: N/A RELATIVE HUMIDITY NA NA Note 2 NA NA NA
SERVICE: H2 Analyzer Sample
Lines CHEMICAL SPRAY NA NA NA NA NA NA
Plat ID-Nos:
SV 400ZA-B SV 4003A-B RADIATION 7 SV 4004A-B 1 x 10 2 x 108 Reference Reference Sequential None
SV 4005A-B (RADS) 2 3 Test
SV 4020A-B
AGING NA 8 yrs NA Reference Sequential Note 3
LOCATION: Reactor Bldg. 935' elev. 3,4 Test
SUBMERGENCE NA NA NA NA NA NA
Rev. 0 12/27/82 II.F.1-6-2
REFERENCES: I NOTES:
1. Combustible Gas Control System Design Specification NSP-63-105.
2. Plant Shielding Design Review, Monticello Nuclear Plant, Bechtel Job 10040-048, June, 1981.
3. Valcor Qualification Report QR52600-5940-2 with Valcor Comparison Report SK10848.
4. Letter, N. H. Boroson (Valcor) to P. M. Donnelly, Nutech, dated March 20, 1981.
1. Since the only accident parameter of concern is radiation, use of the 180 day integrated dose values of Reference 2 as a qualification requirement provides adequate consideration of operating time.
2. This equipment is not required to function for any event which results in a harsh pressure, temperature of humidity environment.
3. Age sensitive materials will be replaced as recommended by the manufacturer.
0
0
Revision 1 2/7/82 Comp-4-1
COMPONENT EVALUATION WORKSHEET
ENVIRONMENT DOCUMENTATION REF.. QUALIFI- OUTSTAND
EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- METHOD ITEMS PARAMETER CATION CATION CATION CATION
SYSTEM: Components OPERATING 180 days Sequential TIME Note 1 15 days Note 2 Reference Test/ None
PLANT 1.D. NO.: JX-106, JX-107 1,2,3 Analysis
COMPONENT: Electrical Penetration TEMPERATURE SEE ACCIDENT & USAR (OF) TEST PROFILES Figure Reference Sequential Note 4
MANUFACTURER: D. G. O'Brien PROVIDED 5.2-16 Reeec Test/ Note 3 Analysis
MODEL NO.: M06 M62 Modules PRESSURE USAR
FUNCTION: NA (PSIG) Figure Reference Sequential Note 4 5.2-15 1,2,3 Analysis
ACCURACY: NA RELATIVE FSAR HUMIDITY 100 100 Figure Reference Sequential
(%) 5232 123 Test/ None SERVICE: Drywell Radiation 1,2,3 Analysis
Monitor CHEMICAL 4000 ppm Sequential SPRAY Demin Boron Reference Reference Test/ None Wtr4 1,2,3 Water 2000 ppm Analysis
RADIATION 3.8 x 107 Reference 5 Reference Sequential
(RADS) gamma 8 2.2 x fo 8 Reference 4 1, 2, 3 Test/ Note 2 x 10 Analysis
AGING Reference Sequential NA 40 years NA 1,2,3 Test/ Note 5 LOCATION: Containment Analysis
FLOOD LEVEL ELEV: 922' SUBMERGENCE NA NA NA NA NA NA
ABOVE FLOOD LEVEL: YES X NO
0
0
Revision 1 2/7/83 Comp-4-2
REFERENCES: NOTES:
1. D. G. O'Brien, Inc., ER 287 Qualification Report.
2. D. G. O'Brien, Inc., Prototype Test Report, Low Voltage Power and Instrumentation Electrical Penetrations, DGO Report No. ER 268.
3. Letter, D. E. Dunfee & H. P. Hilberg (DGO) to G. W. Gunther (NSP) dated December 7, 1981, N-3423-63001.
4. Response to Equipment Qualification SER, EDS Report 04-0910-17, November 12, 1981.
5. Plant Shielding Design RLview, Monticello Nuclear Plant, Bechtel Job 10040-048, June, 1981.
1. Although the total required operating time is 180 days, the duration of the harsh pressure and temperature environment is approximately 12 days.
2. In FSAR Section 14-10.1.3, the post-accident cooling capability is evaluated for 180 days. This equipment could be required to operate for that period.
3. A margin of 20oF has been added to the referenced USAR figure. See Figure B.1, attached.
4. The test profile does not envelope the arbitrarily conservative accident profile of Figure B.1 from approximately 2.5 hrs. to 23 hrs. However, the total thermal stress resulting fromthe test profile is judged to be at least equivalent to that resulting from the accident profile. We are working with the supplier to resolve this outstanding item.
5. All radiation-sensitive materials are enclosed in metal or convered by Raychem sleeving with a wall thickness greater than 70 mi. Therefore, the beta dose to these materials is less than 1% of the gamma dose. The Raychem sleeving has been qualificed in other testing to 2.9 x 100 rads (Wyle Laboratories Report 58442-1).
0
Revision 0 2/7/83 Comp-4-3
TSAT +200 F 3j4 TFSAR +20OFA
TMAX = 309OF
- SEE NOTE1
-~ M-AX = 141. 5 PS IG
THE PLANT SPECIFIC LOCA RESPONSE IS KNOWN TO HAVE DEVIATED
FROM SATURATED CONDITIONS AT 5.4 x 101 SECONDS BECAUSE AT THIS POINT THE
WORST CASE CONTAINMENT TEMPERATURE RESPONSE CURVE IFSAR FIGURE 5-2-15 (E)1
DROPS BELOW 212'F. IT IS THEREFORE CONSERVATIVE TO ASSUME THAT THE CONTAINMENT
TEMPERATURE AT THIS POINT WILL BE 232*F (TFSAR+20'F MARGIN), 10 BE CONSISTENT
THROUGHOUT THE CURVE. IT IS ALSO CONSERVATIVE TO ASSUME THAT THE REMAINING
COOLDOWN TO AMBIENT CONDITIONS CAN BE APPROXIMATED BY THE PLANT SPECIFIC
TEMPERATURE RESPONSE IFSAR FIGURE 5-2-15 (E)1 BELOW 212*F BECAUSE THE AT
GENERATING' THAT RESPONSE is 20'F LESS THAN INDICATED HERE.
I I
I I I - I
0 I I3
10-1 100 101 102 10 104 5.4 05 106 2.5 7
TIME AFTER ACCIDENT (SECONDS)
FIGURE B-1 DRYWELL PRESSURE RESPONSE AND TEMPERATURE
PROFILE USED FOR EQUIPMENT QUALIFICATION
350
300
250
7
200
rn
3,
rn
,
Hn
150 p
60
50
z 3 m z
30~ m
rn
20
/ / / /
100
'"I
010
JO
1
E; l
I. .
Rev. 1 2/7/83 Comp -4-4
D. G. O BRIEN, INC.
SHEET _________ OF _________ TITLE Fic I
REPORT NO.
SHEET - OF
3190 F AT 66 P5IG.
400 SPRAY FOR RAPID COOL.
o F
400
300
250
200
150-
100
START
<705EC.
STEAM I LOCA EXPOSURE PROFILE QA-TN}- 220 ST7P
- APPLY HOT LOCA SPRAY
3400 F AT 66 PS/G OR SLIGHTLY HIGHER TO INSURE < 70 SEC. RISE IN TIME,
300-OF AT 52 P516 SATURATED,
2100 F AT ZERO PS/6 /00 % RH.
180 MIN. 15 DAYS
TE5T
14.0
350
300
350
200
150
100 -
END
BRIEF AS PRACTICAL TEST
0
< 70 SEC.
TITLE
COMPONENT EVALUATION WORKSHEET
Revision 0 12/8/82 Comp -.5 -1
ENVIRONMENT DOCUMENTATION REF.. QUALIFI- OUTSTANDCATION ING
EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- METHOD ITEMS PARAMETER CATION CATION CATION CATION
SYSTEM: NA OPERATING 180 days Reference Sequential TIME Note 1 30 days Note 3 1 Test None
PLANT 1.D. NO.: NA
COMPONENT: Coaxial Cable TEMPERATURE SEE ACCIDENT & USAR (OF) TEST PROFILES Figzure Reference Sequential
MANUFACTURER: Rockbestos PROVIDED 5.2-16 1 Test None
Note __
MODEL NO.: RSS-6-104-1081 PRESSURE
FUNCTION: NA (PSIG) USAR Reference Sequential Figure 1 Test None 5.2.15
ACCURACY: NA RELATIVE USAR HUMIDITY 100 100 Section Reference Sequential
(%) 5.2.3.2 1 Test None SERVICE: Drywell Radiation
Monitor (Nureg 0737, CHEMICAL 3000 ppm Item II.F.1) SPRAY Demin Boron Reference Reference Sequential
Na0H for 2 1 Test None pH 9-11 .
RADIATION 3.8 x 10 2.6 x 108 Reference 2 Reference 1 Sequential gamma Ts
(RADS) 2 x 108 gamma + Reference 3 Reference 4 Test N 2 0 eaEngr. None beta Analysis
Sequential AGING NA 40 years NA Reference Test None
LOCATION: Containment 1 Engr. Analysis
FLOOD LEVEL ELEV: 922' SUBMERGENCE NA NA NA NA NA NA
ABOVE FLOOD LEVEL: YES X NO
0
S
Revision 0 12/8/82 Comp-5-2
REFERENCES:
1. Report on Qualification Tests for Second Generation Solid Dielectric Coaxial Constructions and Cellular Dielectric Coaxial Constructions, Rockbestos Report #2806.
2. Response to Equipment Qualification SER, EDS Report 04-0910-17, November 12, 1981.
3. Plant Shielding Design Review, Monticello Nuclear Plant, Bechtel Job 10040-048, June, 1981.
4. EDS Calculation File 0910-204-EQ-01.
NOTES:
1. Although the total required operating time is 180 days, the duration of the harsh pressure and temperature environment is approximately 12 days.
2. A margin of 200 F has been added to the referenced USAR figure. See Figure Bl, attached.
3. In FSAR Section 14-10.1.3, the post-accident cooling capability is evaluated for 180 days. This equipment could be required to operate for that period.
0
Revision 0 12/8/82 Conna-5-3
TSAT +200F ,j- TFSAR +20F
TMAX = 309OF
f- SEE NOTE1
- PMAX = 41.5 PSIG
350
300
250
r- 200
T4 m m rn
150
-n
100
50
010-1 100 10 102 103 1 105 106 2.5 18
TIME AFTER ACCIDENT (SECONDS)
FIGURE B-1 DRYWELL PRESSURE RESPONSE AND TEMPERATURE
PROFILE USED FOR EQUIPMENT QUALIFICATION
-i
60
50
m
En (on
rn
20/
/
-1
0-1 10
A
\11"
THE PLANT SPECIFIC LOCA RESPONSE IS KNOWN TO HAVE DEVIATED 14
FROM SATURATED CONDITIONS AT 5.4 x 10 SECONDS BECAUSE AT THIS POINT THE
WORST CASE CONTAINMENT TEMPERATURE RESPONSE CURVE IFSAR FIGURE 5-2-15 (E)l
DROPS BELOW 212*F. IT IS THEREFORE CONSERVATIVE TO ASSUME THAT THE CONTAINMENT
TEMPERATURE AT THIS POINT WILL BE 232*F (TFSAR+20'F MARGIN), TO BE CONSISTENT
THROUGHOUT THE CURVE. IT IS ALSO CONSERVATIVE TO ASSUME THAT THE REMAINING
COOLDOWN TO AMBIENT CONDITIONS CAN BE APPROXIMATED BY THE PLANT SPECIFIC
TEMPERATURE RESPONSE IFSAR FIGURE 5-2-15 (E)1 BELOW 212'F BECAUSE THE AT GENERATING THAT RESPONSE is 20'F LESS THAN INDICATED HERE.
0
APPENDIX IV
LOCA Profile
*SPRAY APPLIED FOR FIRST 24-HOUR PERIOD
Revision 0 12/8/82 Comp-5-4
346*F/II3psig (min) WITHIN 3 TO 5 MIN
335F/93 psig
315*F/69 ps
---- 26
2800F/70 psig (min) WITHIN 10 SEC
Spray continuously*at rate of 0.15 &pm per square foot of spray area with solution of the following composition: 0.28 molar 113103 (3000 ppm boron) Na011 to make pil between 9-11 at 77o
5.F/28psig
212 OF/0 psi g
340L
320
250 Q
200
140
80 HR
II HR
V I
iR 4 DAYS
1 1I10
SEC
CD C
100 DAY
3 5 HR HR
1-'-
30 DAYS
1
/ . 212-F/Op5ig
I I I
I II
1
COMPONENT EVALUATION WORKSHEET
Rev. 0 12/8/82 Comnp-6-1
ENVIRONMENT DOCUMENTATION REF. QUALIFI- OUTSTANDCATION ING
EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- METHOD ITEMS PARAMETER CATION CATION CATION CATION
SYSTEM: NA
PLANT 1.D. NO.:
COMPONENT: Power Cable
MANUFACTURER: Rockbestos
MODEL NO.:
FUNCTION: P
ACCURACY:
Firewall EP
SERVICE: Heat Tracing and Hydrogen Analyzer (Nureg 0737, Item II.F.1)
OPERATING TIME
180 days 180 days Reference 3
Note 1 Sequential Test
None
TEMPERATURE SEE ACCIDENT & (OF) TEST PROFILES
PROVIDED
PRESSURE (PSIG) Note 2 NA NA NA
RELATIVE HUMIDITY NA NA Note 2 NA NA NA
CHEMICAL SPRAY NA NA NA NA NA NA
RAIIATI ON 6 8 (RADS) 2 x 10 2 x 10 Reference Reference Sequential None
2 1 Test
AG LNG NA Note 3 NA NA NA Note 3
0
NA
A P
LOCATION: Various
SUBMERGENCE NA NA NA NA NA NA
Rev. 0 12/8/82 Comp-6-2
REFERENCES: = NOTES:
1. Cerro Wire & Cable Co., Rockbestos Products, Firewall EP Certified Test Report, December 22, 1976.
2. Plant Shielding Design Review, Monticello Nuclear Plant, Bechtel Job 10040-048, June 1981.
3. Combustible Gas Control System Design Specification, NSP 63-105.
1. Since the only accident parameter of concern is radiation, use of the 180 day integrated dose values of Reference 2 as a qualification requirement provides adequate consideration of operating time.
2. This equipment is not required to function for any event which results in a harsh pressure, temperature, or humidity environment.
3. Thermal aging performed during qualification of this cable is being evaluated to determine the qualified life. The results of this evaluation will be included in the surveillance and maintenance program as appropriate.
0
Revision 0 12/8/82 Comp-7-1
COMPONENT EVAIUATION WORKSHEET
ENVIRONMENT DOCUMENTATION REF. QUALIFI- OUTSTAND
CAT ION ING EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- METHOD ITEMS
PARAMETER CATION CATION CATION CATION METHOD_ ITEM
SYSTEM: NA OPERATING 180 days 180 days Reference Note 1 Sequential None TIME 3 Test
PLANT 1.D. NO.: NA
COMPONENT: Instrument Cable TEMPERATURE SEE ACCIDENT & (OF) TEST PROFILES Note 2 NA NA NA
MANUFACTURER: Samuel Moore PROVIDED
MODEL NO.: 1962 PRESSURE
FUNCTION: NA (PSIG) Note 2 NA NA NA
ACCURACY: NA RELATIVE HUMIDITY NA NA Note 2 NA NA NA
(%) SERVICE: Heat Tracing
Temperature CHEMICAL Monitoring (Nureg 0737, SPRAY NA NA NA NA NA NA Item II.F.1)
RADIATION 7 8
(HADS) 1 x 10 2 x 10 Reference Reference Sequential None 2 1 Test
AGING NA Note 3 NA Reference Sequential Note 3
LOCATION: Various 1 Test
SUBMERGENCE NA NA NA NA NA NA
0
Revision 0 12/8/82 Comp-7-2
REFERENCES: NOTES:
1. Samual Moore Test Report, Qualification Test of Electric Cables under a Simulated LOCA/DBE, June, 1978.
2. Plant Shileding Design Review, Monticello Nuclear Plant, Bechtel Job 10040-048, June, 1981.
3. Combustible Gas Control System Design Specification NSP-63-105.
1. Since the only accident parameter of concern is radiation, use of the 180.day integrated dose values of Reference 2 as a qualification requirement provides adequate consideration of operating time.
2. This equipment is not required to function for any event which results in a harsh pressure, temperature, or humidity environment.
3. Thermal aging performed during qualification of this cable is being evaluated to determine the qualified life. The results of this evaluation will be included in the surveillance and maintenance program, as appropriate.