ML19324C313
| ML19324C313 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/08/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Miltenberger S Public Service Enterprise Group |
| Shared Package | |
| ML19324A911 | List: |
| References | |
| GL-88-01, GL-88-1, TAC-69140, NUDOCS 8911160115 | |
| Download: ML19324C313 (4) | |
Text
-
- G ef N,o,,
UNITED STATES D#'
NUCLEAR REGULATORY COMMISSION
- 8 WASHINo TON, o, C, 20555 k.....
November 8, 1989 Docket'No. 50-354-'
.s.
Mr. Stever E. Miltenberger Vice President and Chief Nuclear Officer.
Public Service Electric & Gas Company
' Post Office Bcx 236-Hancocks Bridge, New Jersey 08038
- i
Dear Mr..Miltenberger:
SUBJECT:
RESP 01SE TO GENERIC LETTER 88-01, INTERGRANULAR STRESS CORROSION
}
CRACKING (TAC NO. 69140)
Re:
H0DE CREEK GENERATING STATION By letter dated July 29, 1988 and supolemented on June 2,1989 Public Service j
. Electric & Gas Company (PSE&G) responded to Generic Letter (GL) 88-01 and a-request for additional information regarding intergranular stress corrosion i
cracking (IGSCC) in BWR austenitic stainless steel piping.
With the assistance of Viking Systems International (VSI), the staff has completed its review of the licensee's response to the GL, The staff's findings are provided in the enclosed safety evaluation report (SER). The staff concurs with the evaluation, conclusions, and recommendations contained in the enclosed VSI technical evaluation report (TER) and has concluded that 1
PSE&G's response is acceptable with the exception of the positions concerning leak detection and the piping ISI program. The staff's positions on these exceptions are discussed in Section 2.0 of the SER.
PSE&G's resocnse prc~=ed not iner,. Meting in its technical specification (TS) 1) the unidentifiet leakage limit of 2 gpm increase in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period or less, and 2) a statement regarding a piping in cervice inspection (ISI) program that would conform to the staff Dositions in GL 88-01.
Furthermore, the leakage n'onitoring frequency in the TS is once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> rather than once approximately every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Upon further investigation, the staff has concluded that monitoring leakage every four hours creates an unnecessary administrative hardship to plant operators. Thus, RCS leakage measurements mav be taken every eight hours instead of every four hours as reouired in GL 88-01.
In addition, the enclosed SE precludes the necessity for PSE&G to submit i
IGSCC inspection olans for each future outage since the inspection plans were submitted in PSE&G's response. The requirements of GL 88-01 will be incorporated in the Improved Standard TS for BWQs.
However, if flaws are found that do not meet Paragraph IWB-3500 criteria of Section XI of the Code for continued operation without evaluation, the evaluation and repairs of the flaws should be submitted to the NRC for review prior to startup.
8911160115 891108 ADOCK0500gg4 PDR P
p
~7 y
y..,,
c O.
j J
1 -..(
'l x
,GL 88-01 requested that. licensees incorporate the leak detection and piping ISI
.reou rements'in the "S.
SEAG should followuo on th ir reo y to GL 88 n1 snd subm t a TS amendment pac age that reflects the requ rement of the enclore=
i SE.
Sincerely.
[
/S/
a 7,
Walter R. Butler, Director Project Directorate I-2 4
Division of Reactor Projects'l/II t,.
Office of Nuclear. Reactor Regulation
Enclosures:
1..
Safety Evaluation o
iReport s
^T 2.
Technical Evaluation j,
. Report.
cc w/ enclosures:
See next page c
.+
/ enclosure:
M0'Brien-(2)
PDR/LPDR-
'SVarqa/8Boger g
PDI-2 Reading EJordan-l ACRS (10) h WButler j-BGrimes CShiraki/SBrown s
i L
E
[HC LETTER]l g
PDI-2/PM PDI-2/D CShiraki:tr WButler il/S/89 Q / /89 L
l 1,
7 t
1 e
.s 2-GL 88-01 requested that licensees incorporate the leak detection and pipino ISI requirements in the TS.
PSE&G should followup on their reply to GL 88-01 and submit a TS amendment package that reflects the reouirements of the enclosed SE.
Sincerely, fj Z 4
Walter R. Butler, Director Project Directorate I-?
Division of Reactor Projects !/II i
M fice of Nuclear Reactor Regulation
Enclosures:
I 1.
Safety Evaluation b
Report l
2.
Technical Evaluation Report cc w/ enclosures:
i See next page 1
I 1
I j
l
'I
4
- Mr. Steven E. Miltenberger Hope Creek Generating Station Public Service Electric & Gas Co.
4 CC*
M. J. Wetterhahn, Esquire Mr. Scott B. Ungerer Monacer Conner !.Wetterhahn Joint Generatien Pro,iects Department Suite 1050 Atlantic Electric Company 1747 Pennsylvania Avenue post Office Box 1500 Washington, D.C.
20006 Pleasantville, New Jersey 08?32 R. Fryling, Jr., Esquire Law Department Tower SE 80 Park Place Newark, New Jersey 07101 Desident Inspector U.S. Nuclear Regulatory Commission P.O. Box 241 Hancocks Bridge, New Jerse/ 08038 Mr. S. LaBruna Vice President - Nuclear Operations Nuclear Department P.O. Rox ??6 Hancocks Bridge, New Jersey 08038 Mr. J. J. Hagan General Manager - Hope Creek Opera + ions Hope Creek Generating Station P.O. Box 236 Hancocks Bridge, New Jersey OPn38 Mr. B. A. Preston, Manager l
Licensing and Regulation Nuclear Department l
P.O. Box 236 Hancocks Bridge, New Jersey 08038 L
Regional Administrator, Region I U.S.NuclearRegulatorf,dommission I
475 Allendale Road Viro of Prussia, Pennsylvania 19406 l
Dr. Jill Lipoti, Ph.D New Jersev Depar+ men + o# Environmen+al L
Pro +.ec+1on Radiation Pro +ec+1on Program L
S+ ate of New Jersey l
CN 415 Trenton, New t'ersey 0867F l
l l
l l
l
_