ML20059A411
| ML20059A411 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/20/1990 |
| From: | Stang J Office of Nuclear Reactor Regulation |
| To: | Orser W DETROIT EDISON CO. |
| References | |
| IEB-88-008, IEB-88-8, TAC-69630, NUDOCS 9008230045 | |
| Download: ML20059A411 (3) | |
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August 20, 1990 i
Docket No. 50-341 DISTRIBUTION
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ACRS(10) l Mr. William S. Orser NRC & LOCAL 'Rs OGC Senior Vice President - Nuclear BCLAYTON, hii SMEADOR Operations JZWOLINSKI JSTANG Detroit Edison Company TMARSH EJORDAN t
6400 North Dixie Highway DCRUTCHFIELD PD31 R/F Newport, Michigan 40166 l
Dear Mr. Orser:
SUBJECT:
FERMI-2 RESPONSE TO NRC BULLETIN 88-08 AND SUPPLEMENT 1, " THERMAL STRESSESINPIPlHGCONNECTEUTOREACTORCOOLANTSYSTEMS"(TACNO.69630) i By letter dated October 3,1988 (NRC-88-0236), Detroit Edison Company (Deco) responded to NRC Bulletin 88-08 and its supplement concerning thermal stresses i
in piping connected to the reactor coolant system (RCS). The Deco response l
indicated a comprehensive review of the applicable piping was performed.
It-l comprised a list of all reactor pressure vessel nozzles and pi branch lines, from the nozzle to the outboard isolation valve (ping. including s). Operating characteristics were examined to determine if there was any potential for-l either temperature stratification or oscillations that could be induced by.
leaking valves. The results of the review determined that under normal operating conditions Fermi-2 does not have any sections of piping. "ch could be isolated and which could be subject to unacceptable thermal cycle loadings due to leakage past valves.
In conclusion, the response stated.that Fermi-2 does not have any normally isolated cold water systems connected to the RCS that are pressurized above the normal operating pressure on a, continuous basis.
Therefore, it is not possible for potentially leaking isolation valves to allow cold water to be injected into the RCS and cause an unanalyzed thermal cyclic loading in RCS piping which cannot be isolated.
The staff has reviewed your response to the bulletin and finds your response has met all requirements of the bulletin and its supplement. - Therefore, the staff finds your response to Bulletin 88-08 and its supplement acceptable _ and i'
no additional action is required. The staff recomends that;the analysis 4
prepared in res:ense to Bulletin 88-08 and its supplement be kept'on file for further review )y NRC inspectors.
Sincerely,
@ signedby John F. Stang, Project Manager Project Directorate 111-1 Division of Reactor Projects - I i
!Y, V A Special-Projects Office of Nuclear Reactor Regulation cc:
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UNITED 8TATES NUCLEAR REGULATORY COMMISSION t
5 WASHINGTON, D. C. 706M August 20, 1990 Docket No. 50-341 Mr. William S. Orser i
Senior Vice President - Nuclear Operations Detroit Edison Company 6400 North Dixie Highway Newport, Michigan 48166
Dear Mr. Orser:
SUBJECT:
FFRMI-2 RESPONSE TO NRC BULLETIN 88-08 AND SUPPLEMENT 1. " THERMAL STRESSES IN PIPING CONNECTED TO PEACTOR COOLANT SYSTEMS" (TAC NO. 69630) 1 By letter dated October 3,1988 (NRC-88-0236), DetroitEdisonCompany(Deco) responded to NRC Bulletin 88-08 and its supplement concerning themal stresses in piping connected to.the reactor coolant system (RCS). The Deco response
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indicated a comprehensive review of the applicable p ping was performed.
It i
comprised a list of all reactor pressure vessel nozz es and pip ng, including branch lines, from the nozzle to the outbeard isolation valve (s. Operating t
characteristics were examined to determine if there was any potential for either temperature stratification or oscillations that could be induced by leaking valves. The results of the review determined that under normal-operating conditions fermi-2 does not have any sections of piping which could be isolated and which could be subject to unacceptable thermal cycle loadings due to leakage past valves..In conclusion, the response stated that Femi-2 does not have any normally isolated cold water systems connected to the RCS that are pressurized above the normal operating pressure on a continuous basis, i
Therefore, it is not possible for potentially leaking isolation valves to allow cold water to be injected into the RCS and cause an unanalyzed thermal cyclic loading in RCS piping which cannot be isolated.
The staff has reviewed your response to the bulletin and finds your response has met all requirements of the bulletin and its supplement. Therefore, the staff finds your response to Bulletin 88-08 and its supplement acceptable and no additional action is required. The staff recommends that the analysis prepared in response to Bulletin 88-08 and its supplement be kept on file for further review by NRC inspectors.
Sincerely, d
1 h
hn F. Sta
, Project 11anager l
ProjectDirectorateIII-1
.l Division of Reactor Projects - III.-
IV, Y & Special Projects Office of Nuclear Reactor Regulation i
cc: See next page l
l
.4 Mr. Williarn Orser fermi-2 Facility Detroit Edison Compary r
cc:
John Flynn, Esq.
Str.ior Attorney l
Detroit Edison Cortpany 2000 Secord Avenue Detroit, Michigan 48226 Nuclear Facilities and Environnental Ponitoring Section Office tivision of Radiological Health P. O. Box 30195 Lansing,flichigan 48909 Mr. Walt Rogers U.S. !!ccitar Regulatory Concission Pesident inspector's Office
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6450 U. Dixie Highway Newport, Michigan 48166 i
fionroe County Offite of Civil Preparedr.ess i
963 Scuth Raisinville 11onroe, Michigan 48161 Regiorel /dr.inistrator, Region III U.S. Nuclear Regulatory Corin.ission 799 Roosevelt F. cad Glen Ellyn, Illinois 60137 1
Ms. Lynne Goodnion Surtrviscr - Licensing 1
Detroit Edison Conpany Fern'i l' hit 2 6400 i: orth Dixie Highway flewport, Michigen 48166 t
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