ML20031D164

Safety Evaluation Supporting Amend 6 to License NPF-9

ML20031D164
Person / Time
Site:	McGuire
Issue date:	09/30/1981
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20031D163	List: ML20031D162 ML20031D164 ML20031D166
References
TAC-46812, NUDOCS 8110130012
Download: ML20031D164 (2)

Text

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SAFETY EVALUATION BY THE OFFICE CF NUCLEAR REACTOR RECULATION RELATED TO AMENDMENT NO. J TO LICENSE NPF-9 DUKE POWER COMPANY INTRODUCTION The McGuire Unit 1 Technical Specifications were issued on June 12, 1981, as an integral part of the Facility Operating License and are standard Westinghouse PWR Technical Specifications reflecting plant specific design.

Pursuant to Condition 2.C.(11)j the licensee was required to complete qualification tests of power operated relief valves (PORVs) and safety valves by October 1,1981, to meet the requirements for Item 11.0.1 in NUREG-0737.

In response, the licensee is participating in 'the generic program that is being conducted by the Electric Power Research Institute (EPRI) to qualify PWR relief and safety valves and associated dis-charge piping in accordance with NUREG-0737 requirements. As originall's scheduled, testing of all valves in the EPRI program was to be completed by July 1,1981, with the licenseo plant specific evaluation and documentation required by October 1,1981.

The licensee as a member of the PWR Owners' Group is not oble to meet this schedule due to a need for additional testing.

EVALUATION Anomalies have been observed in results of tests of some of the relief and safety valves tested in the EPRI program to date. As a result, the utilities sponsoring the test program the PWR Owners' Group, have requested EPRI to perform additional tests which will allow for core definitive characterization of the observed valve behavior.

On July 17, 1981, the staff met with EPRI and the PWR Owners' Group representatives to review the status of the safety and relief valve testing and to discuss the expanded test matrix. Although the exact number of additional tests will have to be determined as the progran progresses, the test program managers estimated that it could take from four to eight months longer than the original test completion date of July 1,1981, to complete the expanded test program.

The reported test results indicate that, while the initial screening criteria were not met in some cases, all PORVs tested will function in the primary mode (pressure relief) as required. Additional PORV tests are being planned to evaluate the effect of variable water seal temperature on valve closure times. The test results to date indicate that some valves axperience a delay of as as much as 70 seconds in closing '

time due to low or ambic..c water seal tenperatures. However, the valves closed on their own and on disassembly and inspection no damage was observed which might affect tieir ebility te open or cicae en du..:end.

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.z The testing of safety valves to meet the NRC requirements has necessitated the design and construction of a new facility at Corbustion Engineering. Th;s facility is the first of a kind with the capability to perform meaningful operability tests for large spring-loaded safety valves over a broad range of fluid inlet conditions.

The safety valve test results to date indicate a need for additional information regarding the effects of inlet piping configuration and adjusting ring settings on safety valve operation.

Based on our review of the EPRI' test progran to date, we have concluded that the program represents a fully responsive effort to meet Comission requirements and that the additional testing proposed will provide naeded information to assure that the technical requirements of item II.D.1 of HUREG-0737 will be met. Since testing to date has not uncovered problems with safety and relief valves which are considered significent to the safety of operating plants, we believe that good cause has been shown to extend the HUREG-0737 completion date for PORY and safety valve testing so that the extended EPRI program may be carried to completion on an orderly basis. The latest estfuated test completion date is March 31, 1982.

Based upon the above, we have concluded that the licensee has complied with the requirements of this license condition to the extent practicable at this time, and that it is in the best interest of the public to extend the date for full compliance with License Condition 2.C.(11)j to July 1,1982.

ENVIRONMENTAL CONSIDERATION We have~ determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any signi?i-cant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR Section 51.S(d)(4), that an environmental impact statenent or negative declaration and environmental impact appraisal need not be 3

prepared in connection with the issuance of this at.endment.

CONCLUSION We have concluded, based on the consideration discussed above, that: (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be con-ducted in conpliance with the Comission's regulations and the issuance of this amend-ment will not be inimical to the common defense and security or to the health and safety of the public.

Date: September 30, 1981 4

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