United States Nuclear Regulatory Commission - Protecting People and the Environment

Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves (Generic Letter No. 87-06)



                                UNITED STATES
                        NUCLEAR REGULATORY COMMISSION
                           WASHINGTON, D.C. 20655

                               March 13, 1987

TO:            All Holders of Operating Licenses 

Gentlemen: 

SUBJECT:       PERIODIC VERIFICATION OF LEAK TIGHT INTEGRITY OF PRESSURE 
               ISOLATION VALVES (GENERIC LETTER 87- 06) 

Pursuant to 10 CFR 50.54(f), NRC is seeking to verify the methods, if any, 
by which each operating reactor licensee is assuring the leak-tight 
integrity of all pressure isolation valves as independent barriers against 
abnormal leakage, rapidly propagating failure, and gross rupture of the 
reactor coolant pressure boundary. 

Pressure isolation valves (PIVs) are defined for each interface as any two 
valves in series within the reactor coolant pressure boundary which separate
the high pressure reactor coolant system (RCS) from an attached low pressure
system. These valves are normally closed during power operation. The reactor
coolant pressure boundary (RCPB) is defined in 10 CFR 50.2 and generally 
includes all PIVs. 

Periodic tests or verifications of the leak tight integrity of all pressure 
isolation valves are necessary in order to assure the integrity of the RCPB 
in accordance with 10 CFR 50, Appendices A and B. General Design Criterion 
(GDC) 14 of 10 CFR 50, Appendix A requires that "The reactor coolant 
pressure boundary shall be designed, fabricated, erected and tested so as to 
have an extremely low probability of abnormal leakage, of rapidly 
propagating failure and of gross rupture." GDC 30 requires that "The reactor 
coolant pressure boundary shall be designed, fabricated, erected, and tested 
to the highest quality standards practical . . ." GDC 32 states that 
"Components which are part of the reactor coolant pressure boundary shall be 
designed to permit (1) periodic inspection and testing of important areas 
and features to assess their structural and leak tight integrity . . ." 
Further, as outlined in Appendix B to 10 CFR 50, each licensee's quality 
assurance program must include planned and systematic actions which will 
provide adequate confidence that these components will perform 
satisfactorily in service.  

All plants licensed since 1979 have all PIVs listed in the Technical 
Specifications along with testing intervals, acceptance criteria and 
limiting conditions for operation. Certain older plants were required to 
periodically leak test, on an individual basis, only those PIVs which were 
listed in an order dated April 20, 1981 (Event V Order). That order was sent 
to 32 operating PWR's and 2 operating BWR's. Other older plants have had no 
specific requirements imposed to individually leak test any of their PIVs. 

A number of events have occurred in LWRs involving leakage past pressure 
isolation valves, failures of the valves, inadvertent actuation of the 
valves, or mispositioning of the valves. NRC is therefore seeking assurances
that the RCPB is being protected. 


8703160202 
.

                                     -2-

Accordingly, you are requested to submit a list of all pressure isolation 
valves in your plant. For each valve, describe the periodic tests or other 
measures performed to assure the integrity of the valve as an independent 
barrier at the RCPB along with the acceptance criteria for leakage, if any, 
operational limits, if any, and frequency of test performance. This 
information is required to be submitted within 90 days of this letter. If 
current plant Technical Specifications require leak rate testing of all of 
the PIVs in the plant, your reply to that effect will be sufficient. 

This request is covered by Office of Management and Budget Clearance Number 
3150-0111 which expires September 30, 1989. Comments on burden and 
duplication may be directed to the Office of Management and Budget, Room 
3208, New Executive Office Building, Washington, DC 20503. 

Our review of your submittal of information in response to this letter is 
not subject to fees under the provision of 10CFR170. 

                                   Sincerely, 


                                   Harold R. Denton, Director 
                                   Office of Nuclear Reactor Regulation 
Page Last Reviewed/Updated Thursday, June 27, 2013