NRC Generic Letter 1982-27
| ML031080532 | |
| Person / Time | |
|---|---|
| Issue date: | 11/15/1982 |
| From: | Eisenhut D G Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0763, NUREG-0783 GL-82-027, NUDOCS 8211230066 | |
| Download: ML031080532 (2) | |
November 15, 1982
ALL BOILING WATER REACTOR LICENSEES OF OPERATING REACTORS (EXCEPT LACROSSE,BIG ROCK POINT* DRESDEN 1, HUMBOLDT BAY) APPLICANTS FOR AN OPERATING LICENSEAND HOLDERS OF CONSTRUCTION PERMITS. -(GENERIC LETTER NO. 82.27)Gentlemen:
SUBJECT: TRANSMITTAL. OF NUREG-0763, "GUIDELINES FOR CONFIRMATORY IN-PLANTTESTS OF SAFETY-RELIEF VALVE DISCHARGES FOR BWR PLANTS," AND NUREG-0783v"SUPPRESSION POOL TEMPERATURE LIMITS FOR BWR CONTAINMENTS."Enclosed are copies of NUREGs-0763 and 0783. These documents are being issuedto provide guidance that the NRC staff believes should be followed to meet therquirements of General Design Criteria 16 and 29 of Appendix A to 10 CFR Part 50.These NUREGs are not a substitute for the regulations, and compliance is not arequirement. However, an approach or method different from the guidance containedherein will be accepted if the substitute approach or method provides a basis fordetermining that the requirements of General Design Criteria 16 and 29 have beenmet.NUREG-0763 provides guidance for: (1) determining if in-plant safety reliefvalve (SRV) tests are required ~(2) formulating appropriate test matrices, (3)establishing test procedures, (4) selecting necessary instrumentation, and (5)reporting test results. Implementation of the guidelines is described in Section9 of the report. It should be noted,, however, that the guidelines are intendedfor providing information for SRV in-plant tests which are still in the planningstage.If the licensees/applicants have performed or installed instrumentation for SRVin-plant tests in accordance with the acceptance criteria specified in NUREG-0661,"Mark I Containment Long Term Program," we find this approach acceptable.NUREG-0783 provides:( (1 acceptance criteria related to the suppression pooltemperature limits, (2) the events required to analyze the suppression pooltemperature response, (3) assumptions used for the analyses. and (4) require-ments for the suppression pool temperature monitoring system. Implementationof this Issue is described in Section 6 of the report. The acceptance criteriaspecified in the report can be considered a relaxation of the existing suppressionpool temperature limit criteria which are specified in NUREG-0661 (Mark I) andNUREG-0487 "Mark II Containment Lead Program Load Evaluations and AcceptanceCriteria."The application, reporting and record-keeping requirements contained in NUREG-0763have been approved by the Office of Management and Budget: 0MB approvalNo. 3150-0074 which expires July 31, 1983.8211230066OF IEO............F............F............ ............C............ ............ ............SUSMU............. ............. ............. ............ ............ ............E............DAED ............ ............. ............A............ ............ ............. ............NRC FORM 318 (10-80) NRCM 0240OFFICIAL RECORD COPYMGM 1981-4335-9W
-2 -The application, reporting and record-keeping requirements contained inNUREG-0783 have been approved by the Office of Management and Budget; oMBApproval No. 3150-0082 which expires December 31, 1982.Darrell G. Eisenhut, DirectorDivision of LicensingOffice of Nuclear Reactor RegulationEnclosures as statedcc Service List w/o enclosuresDL:-ORB#Z.... Sl rlw........ U.1. 4.2 ...........................SURNAME#DATEtO FFICIA LUSGPO: 1981-NRC FORM 318 (1080) NRCM 0240