ML20031G874
| ML20031G874 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, Sterling, 05000484, 05000487  |
| Issue date: | 10/19/1981 |
| From: | Stright R STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Edison G NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| SLNRC-81-119, NUDOCS 8110260129 | |
| Download: ML20031G874 (4) | |
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SNUPPS I J hh[g g [h8f A -$:
Standardized Nuclear Unit e
Power Plant System w
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Rockwille, Maryland 20850 N/
(301)8648010 N./
October 19, 1981 4
SLNRC 81 119 FILE: 0290 SUBJ:
Meeting with Equipment Qualification Branch Dr. Gordon Edison Licensing Project Manager U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Dr. Edison:
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0.1 October 6,1981, the SNUPPS Utilities met with the NRC Staff's Equipment Qualification Branch. The NRC stated that the information provided in the SNUPPS FSAR Section 3.11 was insufficient for the NRC to complete its review of environmental qualification of equip-ment. The remainder of the meeting was spent discussing documen-tation requirements and technical issues concerning equipment qualification. -to this letter is a sunnary of the major points,1:ade in the meeting.
SNUPPS will assume that the NRC concurs with the attached meeting sunnary unless notified otherwise within two weeks of receipt of this letter.
is a list of-attendees.
Very truly yours, R. L. Stright RLS/mtk cc:
A. C. Passwater UE I
G. P. Rathbun KGE Q
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SLNRC 81 119 SUPf4ARY OF KEY POINTS 1.
The NRC stated that the information in the SNUPPS FSAR was insufficient to complete the review.
Further, the NRC stated that they preferred a submittal on equipment qualification be made that is independent of the FSAR. This submittal need only address the equipment located in a harsh environment.
SNUPPS stated that plans were to make this submittal using a format similar to that used by Comanche Peak. The NRC concurred that the Coitanche Peak format was satisfactory.
2.
Although all electrical equipment located inside containment is assumed to be subjected to harsh environments during a design basis event, a clear cut division between equipment located outside containment which can be expected to undergo harsh environment conditions, and equipment expected to undergo mild environment conditions does not exist. The NRC advised SNUPPS to define qualification parameter
'ines for harsh and mild environments outside containment The NC pointed out to SNUPPS that both the radiation source term as discussed in NUREG-0588 and the radiation source term as discussed in NUREG-0737 must be evaluated with respect to the SNUPPS plant design.
3.
SNUPPS expressed some doubt concerning the purpose of the required auditable equipment qualification file.
The NRC replied that the file system provides assurance to the NRC that the utilities have made a serious effort to qualify their equipment. Additionally the NRC felt that the file would be of greater benefit at some time in the future when qualification issues arise during the operating life of the plant.
For example; utility response may be required for bulletins concerning adverse experiences at other operating plants.
The file should contain enough information concerning qualification of the required equipment such that it can stand alone.
The NRC has no require-ments concerning the location of the file.
4.
The NRC has established guidelines for initial submittal contents as follows:
If between 70 and 84 percent of equipment qualification is complete at the time of submittal, then the NRC will l
review the submittal and perform at least two audits
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SLNRC 81 119
- a Page Two If at least 85% of equipment qualification is complete at the time of submittal then the NRC will perform only one audit.
i Mr DiBenedetto specified that by completed equipment qualification he meant that the equipment qualification files should be complete and action plans for qualification deficiences in place.
Mr. DiBenedetto also informed SNUPPS that they can expect an
- i SER in the area of Equipment Qualification approximately six j
to eight weeks after successfully completing the site audits.
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l SLNRC 81-119 l-ATTENDEES INRC BECHTEL SNUPPS I
P. DiBenedetto N. Goel R. Robinson KGE T. Le D. Quattrociocchi D. Walsh KGE P. Ward R. Dettenmeier UE WESTINGHOUSE C. Klee T. Serandos UE J. Merando T. Martin NUTECH W. Luce D. Gasda P,. Hutchings NUTECH A. Ball J. Prebula R. McDermott NUTECH i
E. Doolittle NUTECH R. Stright Staff
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