ML20206H920
| ML20206H920 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/24/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NLR-N86076, NUDOCS 8606260361 | |
| Download: ML20206H920 (3) | |
Text
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Public Service Electric and Gas Company Cerbin A. McNeill, Jr.
Public Service Electnc and Gas Company P O. Box 236, Hancocks Bruige, NJ 08033 609 339-4800 Vice President -
Nuclear June 24, 1986 NLR-N86076 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:
Ms. Elinor Adensam, Director Project Directorate #3 Division of BWR Licensing
Dear Ms. Adensam:
BAILEY 862 SOLID STATE LOGIC MODULE RELIABILITY PROGRAM HOPE CREEK GENERATING STATION DOCKET NO. 50-354 This letter documents the results of the telephone conference on June 23, 1986, between representatives of Public Service Electric and Gas Company (PSE&G) and the NRC, the purpose of which was to discuss the acceptance criteria PSE&G proposes to utilize for the Bailey 862 Solid State Logic Module (SSLM) reliability test program.
In this regard, PSE&G notes the following:
1)
PSE&G will demonstrate through the perf ormance of the Bailey 862 SSLM reliability test program that less than a 5% per year failure rate for the next cycle of operation (2 years) of module life will be achieved.
2)
Prior to the end of the first refueling outage, PSE&G will submit for NRC review, Bailey 862 SSLM reliability data as it relates to the following programs:
The accredited laboratory reliability test program The "In-house" Bailey 862 SSLM reliability program, representing at a minimum 18 months of data collection Data provided by Bailey to PSE&G representing the reliability of SSLMs compiled from other owners over a period of at least 18 months
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Ms. Elinor Adensam 6-24-86 l
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In addition to the above, PSE&G is providing clarification to a l
letter from C.
A.
McNe ill, Jr. (PSE&G) to E. Adensam (NRC) dated j
June 13, 1986 which presented our original proposed reliability I
test acceptance criteria.
These clarifications are noted by the
" marked-up" pages in the attached.
In the event there are any questions with respect to the above, do not hesitate to contact us.
Sincerely, i
4 A
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Mr.
D.
H. Wagner j
Licensing Project Manager Mr.
R.
W. Borchardt i
Senior Resident Inspector 4
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION BAILEY SSLM RELIABILITY PROGRAM RELIABILITY PROGRAM OUTLINE A.
DEVELOP PROGRAM PLAN, PROCEDURES AND CRITERIA DOCUMENT This initial activity will include detail planning and scheduling of all program activities.
A deta iled program plan document will be developed.
In addition, the following program documents will be prepared: OA procedure, Acceptance Criteria, Technical Approach and Methodology.
The following are typical standards that will be used for guidance in defining the requirements for the overall program:
IEEE Standards 279 (Required by 10CFR50.55(h)), 323, 352, 381, 500, 577, 603, and MIL Standard HD BK-217B.
The-Avveplence Criteria do""mant will addresc tha reli abi_ lit.y
.goa 1.ha t a ^5% confidence level-of succes s f ul Ope rat-ion fn r a-t
-pected of at least-twc years con Lc echieved.- The two year period is based upon compliance with IEEE standard 577 section 4.3.8.
The conf-idence laval i= avnransed as i 2 sigma h
--s-u;m i e -tt.c s te nd a t d de v ia t-iwM the --popula c io n di s ts ibut4cn,-
B.
DETERMINATION OF INITIAL SAMPLE SIZE An initial representative test sample will be established based upon the total population of applicable modules.
The--semplc -then mi l l b^ guba i v i riad_ -inte--::ve ral groups that will be 02jec;.ed to varying degrecc of dvance life tes ting ts dete mine tha nuaral1 e.f4a c t e of ag ing 4-i-re rr-a.es ali of - natural, Opera cional and~
env-i-scumencal pnenomena) ~f signif ivaut pu r-fo r= = n ce--
e%,, n e a r s a + < ~.
Op C.
IDENTIFY FAILURE MEC..ANISM OF MODULE / COMPONENTS Before meaningful aging can be performed, the failure mechanism j
of modules / components related to the aging parameters identified in item "D" will be ascertained in order to assure the validity of the life' prediction.
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