ML20155G295
| ML20155G295 | |
| Person / Time | |
|---|---|
| Issue date: | 07/15/1987 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Pickens T BWR OWNERS GROUP |
| Shared Package | |
| ML20155G292 | List: |
| References | |
| GL-83-28, NUDOCS 9811090011 | |
| Download: ML20155G295 (2) | |
Text
. -. . . --. - . . .- . _. . . . ...
4 JIN .8 tL dut15,R87
! Mr. Tcrry A. Pickens, Chaiman E W Cwners Group Northern States Powiir Corporation 414 Nicollet Mall Minneapolis, Minnesota 55401
Dear Mr. Pickens:
l
SUBJECT:
GENERAL ELECTRIC COMPANY (GE) TOPICAL REPORTS NEDC-30844, "BWR OWNERS GROUP kESPONSE TO NRC GENERIC LETTER 83-28,
AND NEDC-30851P, " TECHNICAL SPECIFICATION IMPROVEMENT ANALYSIS FOR BWR RPS" We have- completed our review of the subject topical reports submitted by the 1
6% Uwners Group by letters dated January 31, 1985 and May 31, 1985. .
Enclosure 1 provides our Safety Evaluation Report (SER). Our evaluation upplies only to the matters described in the report.
Ve find that NEDC-30844 provides an acceptable basis for resolving iterr 4.5.3 l- of Generic Letter 83-28, subject to confirn.ation of the plant-specific dpplicability of the generic analysis. Therefore, upon receipt of a letter with this confirmation from each licensee or applicant Item 4.5.3 of Generic Letter 83-28 will be closed out for that licensee or applicant.
Bued on our review of NEDC-30851P. we find that it provides an acceptable seneric basis for supporting plant-specific Technical Specification changes '
relt,ted to the reactor protection system (RPS) for plants using 6 relay RPS, subject to the conditions noted herein. We also have reviewed the topical report regarding Technical Specification (TS) changes on the solid-state PPS.
he needed and obtained additinnel infonnation for our review. The results 01 our review of the solid-state RPS reliability' analyses will be presented it: a future stoff SER.
As noted in the enclosed SER, each applicant for preposed Technical Specifi-cution changes for individual plants must: '
l 1. Confim the applicability of the generic analyses for NEDC-30851P tc its plant.
- i. Desnunstrate by use of current drif t information pro.?ded by the equipment vendor or plant-specific data, that the drif t characteristics for instrun,entation used in the RPS channels in the plant ore bi.unded by the assumptions used in NEDC-30851P when the functional test intervol 1 ..
extended frorr rnonthly te quarterly.
l I
. , 4.r.5) p /' O I ',
- . i. f D ,1
,' o , i t ript. GI s!
9811090011 981105 PDR TOPRP ENVQENE C PDR Ol//0 9 D D U .
tr
- 3. Confirm that the differences between the RPS in the plant and the RPS of the generic analysis plant were included in the plant-specific analysis using the procedures of Appendix K of NEDC-30851P, or provide plant-specific analyses to demonstrate that there is no appreciable change in RPS avail 6bility or public risk.
Enclosure 2 provides an acceptable format for proposed TS changes based on NEDC-30851P. Our review of plant-specific changes will consider only the applicability of the topical report to the specific plant. Because the proposed changes are voluntary and subject to the confirmatory actions noted above, we do not intend to issue a revision to the Standard Technical Specifications (STS) for BWR plants at this time. Eventually the STS will be revised to incorporate these changes as part of the NPC program for 15 improvements.
In accordance with procedures established in NUREG-0390. " Topical Reports Review Status." we request that the GE/BWR Owners Group publish accepted versions of NEDC-30851P, both proprietary and non-proprietary, within 3 months of receipt ci this letter. The accepted versions should (1) incorpot6te this
'etter end the enclosed Safety Evaluation Report between the title page ano the obstroct and (?) include an A (cesignated accepted) following the report identification symbol.
Should our acceptance criteria or regulations change so that nur conclusions at to the acceptability of the repvrts are no longer valid, the BWR Owners Gra p and/or the applicants referencing these topical reports will be v>pected te revise ano ri. submit their respective documentation, or subnit s ustifu.ation for the contine d applicabili:/ of the topical reports without revisiu of their respective dvcumentation.
Sincerely, attina y: ,
Ashc,k C. Thadani, Assistant birector for Systems Division of Engineering & Systems Technology Office of Nuclear Reactor Regulation inclosure-
- 1. Safety Evaluation Report
- 2. Form t for Technical Specification Changes v, v w w w w w ww wvv ww w te w wvvvvvva up wie IC C 4: C C O S O C C O O O O O D*O G 4 0 G J 3 3 3 D 9 9 8 '
ICGCCOSSODCCOO 00000300333JSSSS pO4GGGGGGOOOGGO00000000000@S9'
_ _ _ _ _ _ _ . . . . _ _ . - . _