ML18079A879
| ML18079A879 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/28/1979 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7908300512 | |
| Download: ML18079A879 (4) | |
Text
PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 August 28, 1979 Directer of Nuclear Reactor Regulation
- u. s. Nuclear Regulatory Commission Washing£on, D. c.
20555 Attention:
Gentlemen:
Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 Public Service Electric and Gas hereby transmits sixty (60) copies of supplemental information concerning environmental qualification of electrical cables in response to Section 8.4.8, Item 2 of Supplement 3 to* the Salem Safety Evaluation Report, dated December 29, 1978.
Should you have any questions in this regard, please do not hesitate to contact us.
Enclosure Very truly yours,
- f!/kzit~
R. -L. Mittl General Manager -
Licensing and Environment Engineering and Construction The Energy People
"'1903800 5°'1 ;;i.
.~
95-2001 (400M) 9-77
. '.\\ '*
SALEM NUC-AR GENERNrING S'l'l\\TION, Nc92 UNIT SUPPLEMENT NO. 3 TO SER DATED DEC~MBER 29, 1978 REF. 8.4.8(2) ENVIRONMENTAL QUALIFICATION OF ELECTRICAL CABLES All safety-related cables located inside containment have been qualified to LOCA environment.
For cables which were not tested to the MSLB peak temperature, peak surface temperatures were calculated by Stone & Webster Engineering Corporation.
These calculations were made utilizing the same method and similar assumptions used for the North Anna Power Station of Virginia Electric and Power Company.
Two conductor, No. 16 gauge cable geometry and data were pro*-
file starting at 120°F, remaining at 3S0°F for one minute6
~taying above 300°F for three minutes and dropping to 286 F for the duration of the accident, it was shown that the maximum surface temperature of the cable was 333°F.
Identical cables irradiated with a total dosage in excess of that en-countered in a MSLB, have successfully passed tests at 340°F for approximately three hours.
Therefore, PSE&G concludes that these and other cables tested at 349°F are qualified for use inside containment at the Salem Nuclear Generating Station *
. Some AIW control and instrumentation cables which were pre-viously tested to an acceptable temperature-pressure pro-file, but only irradiated with a total dose of 100 megarads, have been retested at Franklin Institute Research Laboratories (FIRL).
The results of this test have been reviewed by PSE&G and found acceptable.
These results are presented in FIRL Test Report F-C5115, dated April, 1979.
A summary of environmental qualification documentation for electrical cables has been added to Table Q7.30 (Attached).
This information has also been submitted as a supplemental response to our answer to NRC IE Bulletins No. 79-01 and 79-0lA, dated June 15, 1979.
Qualification test reports and analyses a-re available for review.
Table Q7.30 Electrical Po-,;er Cables
- Electrical Pcwer Cables Electrical Power control Cable Electrical Power control Cable Electrical Power Control Cable Electrical Control &
Instra.--:;entation Cable Cont'd *
~'"UFACTURER Rockbestos Anaconda Okonite Triangle Samuel Moore
& Company FUNCI'ION -
R:EX:'!UIRED OPERATION Electrical Po-...;er Feeds Electrical Power Feeds Electrical Power & control Feeds Electrical Power & control Feeds Elect'.cical Power & control Feeds control &
Instrumentation Feeds LO CA/MS LB LO CA/MS LB LO CA/MS LB LOCA/MSLB LO CA/MS LB LO CA/MS LB QUALIFICATION DATA
- LOCA
- MSLB
- LOCA
- HSLB
- LOCA
- MSLB
- LOCA
- MSLB
- LOCA
- MSLB
- LOCA
- MSLB
-cert. Test Report ~ Dated 12/22/76,
-Rockbestos Letter - Dated ~
1/24/79.
-Test Report Ro. F-C3341 -
Dated 1/73 & Anaconda Letter Dated 10/18/78
-Test Report No. 141, Dated 2/29/72,
-Okonite Letter - Dated 7/21/72 & Okonite Letter Dated 2/26/79
-Test Report - Dated 2/77 and Triangle Letter Dated 8/15/78
-Test Reports ~o. B910 -
Dated 5/75 & No. 760009 Da~ea 11/22/76 & BIW Letter Dated 10/19/78
-Test Report No. F-C3683 Dated 11/73
Table Q7.30 (Cont'd.}
1".ANUFACTURER Electrical Ard Pc-..; er, ~ntrol
& I~stru~entation Ca!Jle
~70TE:
CO~E?ITS FUNCTION REQUIRED OPERATION Electrical Power Control
& Instrumentation Feeds LO CA/MS LB QUALIFICATION DATA
- LOCA
- MSLB REF. DOCl:"Y..E!-."TS
-Test RePort No. F-C3463, Dated 9i72
-Test Report ~o. F-C4l~.
Da-tea 12/75
-Test RePort No. F-C5115, Dated 4i79
- All vital cables inside containment have been qualified to at least 271°F and 2 x 108 rads at 43.2 psig for LOCA environ~ent.
- Thermal analysis have been performed using the same model as VEPCO, which has previously been accepted by ~~e staff.
Results of this analysis show that the peak surface temperature of the worst case cable tvoe is 333°F.
Identical cables, irradiated with a total dosage in excess of that encountered in a
~.SLB have successfully passed tests at 340°F for= 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
See response to Sect. 8.4.8(2).
A.JG:vlf 08/79