NUREG-0531, Forwards NUREG-0531, Investigation & Evaluation of Stress Corrosion Cracking in Piping of LWR Plants & Notice of Issuance.W/O Rept.Fr Notice Encl
| ML20132A516 | |
| Person / Time | |
|---|---|
| Issue date: | 03/15/1979 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| References | |
| RTR-NUREG-0531, RTR-NUREG-531 GL-79-14, NUDOCS 7903300549 | |
| Download: ML20132A516 (2) | |
Text
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f NRC FUBUC m ua DCUMENT ROOM m u oara n,
i tccn uuc w Misstoy IN T a
March 15, ;g79 l
Mr. A. Edward Scherer
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Licensing Manager Nuclear Power Systems C-E Power Systems h@L (& Of rM C f
Combustion Engineering, Inc.
Windsor, Connecticut 06095
Dear Mr. Scherer:
On September 14, 1978, the Nuclear Regulatory Commission established a new Pipe Crack Study Group which was to evaluate recent pipe and safe end cracking experience relative to previous staff conclusions and recommendations. The bases for establishing the new Study Group were (1) the discovery of cracks in the inner surface of large-diameter i
austenttic stainless steel piping (recirculation lines) in a BWR and (2) questions concerning the capability of ultrasonic detection methods to detect small cracks.
The new PCSG reviewed existing infonnation that either was contained in written records or had been collected through meetings in this country and in foreign countries. The review was in the context of changes occurring since the preparation by the original Pipe Cracking Study Group of N'JREG-75/067 " Technical Report--Investigation and Evaluation of Cracking in Austenitic Stainless Steel Piping of Boiling Water Reactor Plants". The conclusions and recommendations of the new Pipe Crack Study Group are presented in the enclosed " Investigation and Evaluation of Stress Corrosion Cracking in Piping of Light Water Reactor Plants", NUREG-0531.
This report is for your infonnation and comment. Also enclosed is a copy of a related Federal Register, Notice.
The NRC staff will review the Study Group report and its conclusions /
recommendations and any comments received about the report. Following this review, the staff will decide what further actions, if any, are required for the licensing and operation of reactors.
Sincerely, Es hut, e y Director Division of Operating Reactors
Enclosures:
1.
NUREG-0531 go V l
2.
Notice J
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and Detecuce of IOSCC. ? D 1
e ses enablished hytthq States e====ni==saa $"'t eenMt of changes occurring slace the ;,,3 i
< Stuelear 4 - Regulatory gS i
(USNRC). to 3 interstanular; Gespasstles of NUREO 15/067 led to J j
< etrees correstos'eracking >OOSCC) in B n the preparatles of specific conclustons $d 9eGang Water Reactors (BWRal. De - and recommendadons relevant to the
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Oroup reported its'fladings concern. ; N serent' status of IOSCCi the signift. My hg stress. corrosion cracking in bygans ; eente of the probless.' and the rettsbib N a
a tines and core sprey pistag of austen.'
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ge agglaless steel in a report. TWohnt.
to correct at Wahahm IOSCC in exist.
est Aeporf-tsessftpation and Festus.
Ing and future plants. These conclu.
7 esos of Crschist.is Amstenfrie Riota.
elons and reconussadations are pre.
g auss Steel Pepine of Soutng Water Ae.. seated;ia) the q pewlyz lasued. PCSO p
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' erforMenf4 INUREO.TS/007).W M
' ' Port."" staff w01 refle'w th'e study l
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Durtng 1978.'IOSCC wasirsparkd DeNRC 1
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Ser the first time tra larse<linsneter Oroup report and its conclusions /ree.
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piping la a BWR.* Dis discovery, to.
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3 semer with genues the ments received.during h comment espabuity 2 et 4 e period. Moving this mvlew. the ataH ';
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amethods le desset smaR And to i n will (deelde) what I furthegr ons, if.
p9 the7tormation @f a new Pipe Cree
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- 1.' The altnificanet eracks resar.Driston of TechnicalInforma. 4 Stea and Docussent Control. 4 -
disenend la larstellaander pipes MI., A comments on this report should be aatte to las socclustees'andisesem*
sund4Wons set forth in the referenced sent to the Offlee of Nuclear Reactor report (NUREO.78/067) and its imple' Resulauen. U.S.'Muclear Reeulstorr Comantages. Washington. D.C. 2015!..
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- 3. Resolution of the soneerns esteed AtlantlantDuputy Director, Divis:en ;
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g Dated at BetheadMd, this 61.h day ADENCY: U.S. Nuclear Regulatory Witas.thisanatteri WWW6 +
8I%er the Ntadsay W com f8'UD -
Commission,
- d. The potent ACT10N: Recuest for public comument In t'WBs;
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y en NUREO 0631 "Invesussuon and theI Greek.
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SUMMARY
- On September 14. 1918.
or e tak
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"" M*N'"M *'"I the Nuclear Regulatory Commlaston De PC80 ilmated the esses of the established a new Pipe Crack Study study la BWR and PWR peplas and Group. The Oroup was to evaluate safe ends attached la the reestor pres.
j recent pipe and safe end cracking ex.
eure vessel The PCSO reviewed eaAst.
Pertence relative to previous staff con.
Ang lafonastion-eltber that contained clusions and recommendations. The la arritten records or that collected NRC seeks public commem on the through eseeungs in this country and report which summartses the Oroup's da foreign countries.The spectfac areas review and conclusions, seasidered are pressated la tibe etap.
DATES: The public comment period lers of this report:
espires May 15.1979, o SWR Cracking Mnes and Corrective Actions
.POR FURTHER Uf70RMATION e PWR Cracking Experience and CONTACT:
Corresure Acuens Darrell O. Elsenhut, Deputy Direc, o Metallurgy Assestated with Plpe ter for Operaung Reactors. Division Cracking e Beacter Coolant Chemistry
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