Transmittal of NUREG-0763, "Guidelines for Confirmatory In-plant Tests of Safety-Relief Valve Discharges for BWR Plants," and NUREG-0783, "Suppression Pool Temperature Limits for BWR Containments." (Generic Letter No. 82-27)

                                UNITED STATES
                        NUCLEAR REGULATORY COMMISSION
                           WASHINGTON, D.C. 20555
                                     
                              November 15, 1982

ALL BOILING WATER REACTOR LICENSEES OF OPERATING REACTORS (EXCEPT LACROSSE, 
BIG ROCK POINT, DRESDEN 1, HUMBOLDT BAY) APPLICANTS FOR AN OPERATING LICENSE
AND HOLDERS OF CONSTRUCTION PERMITS. (GENERIC LETTER NO. 82-27 ) 

Gentlemen: 

SUBJECT:  TRANSMITTAL OF NUREG-0763, "GUIDELINES FOR CONFIRMATORY IN-PLANT 
          TESTS OF SAFETY-RELIEF VALVE DISCHARGES FOR BWR PLANTS," AND 
          NUREG-0783, "SUPPRESSION POOL TEMPERATURE LIMITS FOR BWR 
          CONTAINMENTS." 

Enclosed are copies of NUREGs-0763 and 0783. These documents are being 
issued to provide guidance that the NRC staff believes should be followed to 
meet the requirements 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 a requirement. However, an approach or method different 
from the guidance contained herein will be accepted if the substitute 
approach or method provides a basis for determining that the requirements of
General Design Criteria 16 and 29 have been met. 

NUREG-0763 provides guidance for: (1) determining if in-plant safety relief 
valve (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 Section 9 of the report. It should be noted, however, that the 
guidelines are intended for providing information for SRV in-plant tests 
which are still in the planning stage. 

If the licensees/applicants have performed or installed instrumentation for 
SRV in-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 pool
temperature limits, (2) the events required to analyze the suppression pool 
temperature response, (3) assumptions used for the analyses, and (4) 
requirements for the suppression pool temperature monitoring system. 
Implementation of this issue is described in Section 6 of the report. The 
acceptance criteria specified in the report can be considered a relaxation 
of the existing suppression pool temperature limit criteria which are 
specified in NUREG-0661 (Mark I) and NUREG-0487 "Mark II Containment Lead 
Program Load Evaluations and Acceptance Criteria." 

The application, reporting and record-keeping requirements contained in 
NUREG-0763 have been approved by the Office of Management and Budget: OMB 
approval No. 3150-0074 which expires July 31, 1983. 


8211230066 
.

                                    - 2 -

The application, reporting and record-keeping requirements contained in 
NUREG-0783 have been approved by the Office of Management and Budget; OMB 
Approval No. 3150-0082 which expires December 31, 1982. 


                                        Darrell G. Eisenhut, Director 
                                        Division of Licensing 
                                        Office of Nuclear Reactor Regulation

Enclosures as stated