ML20209E124

Forwards Mechanical Engineering Branch Sser Re Inservice Testing Program for Pumps & Valves as Input to Next Sser. SER Provides Interim Approval of Inservice Testing Program for 2-yr Period from OL Issuance Date

ML20209E124
Person / Time
Site:	05000000, Diablo Canyon
Issue date:	03/22/1985
From:	Bosnak R Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
Shared Package
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References
FOIA-86-197 NUDOCS 8504020079
Download: ML20209E124 (3)

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UNITED STATES j

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NUCLEAR REGULATORY COMMISSION 3

E WASHINGTON, D. C. 20555 4.....l

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Docket No. 50-323 MEMORANDUM FOR: Thomas M. Novak, Assistant Director for Licensing Division of Licensing FROM:

Robert J. Bosnak, Acting Assistant Director for Components and Structures Engineering Division of Engineering

SUBJECT:

SER SUPPLEMENT FOR THE DIABLO C^NYON NUCLEAR POWER PLANT,. UNIT 2. SECTION 3.9.6 Attached is the Mechanical Engineering Branch (MEB) evaluation of the applicant's Inservice Testing (IST) program for pumps and valves for input to the next supplement to the Diablo Canyon SER.

Please note that the attached SER input provides an interim approval of the IST program for Diablo Canyon Unit 2 for a period of two years from the date of issuance of the Operating License. During the two year period MEB will complete its detailed review and issue the final IST SER which becomes a part i

of the plant Technical Specifications.

In the past we have issued the interim approval with no specific time limitation. As a result of recent discussions with another OL app ~licant we have concluded that the time limit should be included to assure more timely licensee interaction and cooperation in bringing the detailed review to completion.

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Robe t J. Bosnak, Acting Assistant Director for Components and Structures Engineering Division of Engineering

Attachment:

As stated cc: See Page 2 l

CONTACT:

R. Kirkwood, DE:MEB, X28436 s

(5,0162WR)h 1

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Thomas M. Novak 2-cc:

H. Thompson, DL F. Miraglia, DL i

B. Youngblood, DL 1

H. Schierling, DL

8. Buckley, DL J. Knight, DE F. Cherny, DE H. Bramer, DE J. Page, DE G. Hammer, DE

0. Rothberg, DE R. Kirkwood, DE 4

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ATTACHMENT.

Mechanical Engineering Branch

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Supplement to the Safety Evaluation Report Diablo Canyon Nuclear Power Plant Unit 2 Docket No. 50-323 3.9.6 Inservice Testing of Pumps and Valves To ensure that all ASME Section III, Code Class 1, 2 and 3 safety-related pumps and valves will be in a state of operational readiness to perform necessary safety functions throughout the life of the plant, a test program will be conducted which includes baseline preservice testing and periodic inservice testing. The program provides for both functional testing of the components in the operating state and for visual inspection for leaks and other signs of distress.

l The applicant has stated that the Inservice Testing Program for the above mentioned pumps and valves will be in compliance with the*1977 Edition of the ASME Boiler and Pressure Vessel Code,Section XI through the Summer 1978 Addenda to the Code. This Code Edition and Addenda is not in conformance with 10CFR50.55a(g) which requires compliance with the 1980 Edition of the ASME Boiler and Pressure Vessel Code,Section XI through the Winter 1981 Addenda.

The NRC staff has determined that there are few technical differences between the 1977 Edition and the 1980 Edition of Section XI of the Code. We will i

discuss this matter of code compliance with the applicant during our detailed review of the program. The applicant has requested relief from these code requirements pursuant to 10CFR50.55a(g)(1) for certain pump and valve tests.

At this time we have not completed our detailed review of the applicant's i

submittal. However, we have evaluated the applicant's requests for relief and, based on our review, we find that it is impractical within the limitations of design, geometry, and accessibility for the applicants to meet certain of the ASME Code requirements.

Imposition of those requirements would, in our view, result in hardships or unusual difficulties without a compensating increase in the level of quality or safety. Therefore, pursuant to 10CFR50.55a(g)(1), we believe that the relief that the applicant has requested from the pump and valve testing requirements of the 1977 Edition of ASME Section XI through Summer 1978 Addenda should be granted for a period of I

no' longer than two years from the date of issuance of the Operating License or until our detailed review has been completed, whichever comes first.

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completion of our review results in additional testing requirements, we will require that the applicant comply with them.

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