ML20213D996
| ML20213D996 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/11/1982 |
| From: | Knight J Office of Nuclear Reactor Regulation |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0460, CON-WNP-460, TASK-2.D.1, TASK-TM NUDOCS 8203020283 | |
| Download: ML20213D996 (2) | |
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I Docket ho.: 60-397 en, f e c as
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I;EiORANDUM FOR: Robert L. Tedesco, Assistant Director for Y i
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James P. Knight, Assistant Director for lC
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O-Components f. Structures Engineering, OE k
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If PUT TO M!P-2 SER k's
',Y The purpose of this rmnorandien is to forward the enclosed SER in')ut for
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'M'P-P with reqard to T"I fction Plan iten II.D.1, "Perfornance Testing
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of Poiling uator Reactor and Pressurized Mater Poactor Relief and Safety Valves."
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Janes P. Knight, Assistant Director f or Components E Structures Engineering Division of Engineering
Enclosure:
As stated cc:
R. Vollmer, DE H. Bosnak, UE F. Cherny, DE A. Schwencer, DL Z. Rosztoczy, DE i
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1 SAFETV EVALUATION REPORT INPUT WNP-2 TMI Action Plan Item II.D.1 - PERFORMANCE TESTING 0F BOILING WATER REACTOR AN PRESSURIZED WATER REACTOR RELIEF AND SAFETY VAL'VES (NUREG-0737, ITEM II.D.1)
On October 31, 1980, the staff issued, with Comission approval, NUREG-0737
" Clarification of TMI Action Plan Requirements" which is applicable for Operating Reactor Licensees, Applicants for Operating Licenses and Holders of Construction Permits.
This NUREG provides more specific guidance on the implementation of TMI Action Plan Items including, for Item II.D.1, specific detailed documentation submittal dates.
j To date in response to this Action Plan Item, the BWR-TMI Owners Group, of which the Applicant is a participant, has contracted with the General Electric Co. to develop and implement a generic test program, the results of which are intended to provide the basis for the participating BWR utilities to demonstrate qualifi-cation of the safety / relief and relief valves and associated discharge piping for their specific plants. Meetings were held on August 27, 1980, October 22, 1980, Februa ry 10, 1981, and March 10, 1981 between the NRC staff and representatives of the General Electric Co. and the BWR Owners Group.
The purpose of these meetings was to discuss the generic valve and piping qualification program developed by G.E.
and the analyses that have been performed by G.E. to define the program test condi-tions.
The BWR Owners Group has documented the proposed test program and the results of the analyses performed to define the program test conditions.
This information was submitted to NRC by letter dated September 17, 1980 from D. B. Waters to H. Denton. By letter f rom D. Eisenhut to D. B. Waters dated February 10, 1981, the staf f provided formal comments on the proposed test program.
The test program that was proposed and has now been completed provides for qualification of safety / relief and relief valves and associated discharge piping for low pressure water conditions (i.e. approximately 250 psig) which are expected during the Alternate Shut-down Cooling Mode.
In this mode, low pressure pumps inject cold water into the reactor vessel and the water is subsequently discharged through the safety / relief or relief valves back to the suppression pool. The position of the Owners Group is that for all higner pressure and temperature (steam, two phase, or liquid) conditions, valves and piping on all BWR's have been qualified by testing, operational experience and analyses, or some combinaton thereof, or the operating conditions are of such a low probability as regards to f requency of occurrence and ef fects on public health and I
safety that the valves and piping need not be specifically qualified for them.
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l In the October 22, 1980 meeting between the staff and the BWR Owners Group, it was jointly agreed that the NRC would perform a detailed review of the September 17, 1980 BWR Owners Group submittal and in parallel the BWR Owners Group would proceed with the implementation of the proposed low pressure test program with testing to be completed by July 1,1981 as required by the NRC Action Plan.
The NRC staff agreed to perform a detailed review of the September 17, 1980 submittal on as expeditious a basis as available resources would permit.
The NRC staff noted that at the completion of the staff review, if the staff was not in agreement with the adequacy of the low pressure test conditions as proposed by the BWR Owners Group, the NRC would require qualification of safety / relief and relief valves and associated piping for higher pressc e conditions possibly including sub-cooled liquid flow at normal reactor operating or slightly higher pressures i