ML19339B313

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Forwards NRC Staff Guidance for Preparing Pump & Valve Testing Program Descriptions & Associated Relief Requests Per 10CFR50.55a(g). Inservice Insp Program Submittals Should Have Same Level of Detailed Info
ML19339B313
Person / Time
Site: Yankee Rowe
Issue date: 01/13/1978
From: Schwencer A
Office of Nuclear Reactor Regulation
To: Groce R
YANKEE ATOMIC ELECTRIC CO.
Shared Package
ML19339B314 List:
References
NUDOCS 8011060714
Download: ML19339B313 (3)


Text

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JAN 131978 DockeyN.50-29 Yankee Atomic Electric Company ATTH: Mr. Robert H. Groce Licensing Engineer 20 Turnpike Road Westboro, Masachusetts 01581 Gentlemen:

RE: YANKEE-ROWE AT0 HIC POWER STATION Sy letter dated November 30, 1976, we sent you a document entitled "4RC Staff Guidance for Complying with Certain Provisions of 10 CFR 50.55a(g),

Inservice' Inspection Requirements".

In addition to clarifying the proper methods for coctplying with the regulation, this guidance provided a general outline of the type of information that the HRC staff would need to' review inservice inspection and testing programs, and to evaluate requests for relief from A5ME Code requirenents that are determined to be impractical for a facility.

After review 1h a number of submittals relating to s50.55a(g) requirements D

from various licensees, we have concluded that additional guidance would be useful to all licensees to aid in the preparation of these submittals, and to expedite the HRC staff review and approval of the proposed prograns and any requests for relief from certain AS!!E Code requirements. The need for this guidance is particularly evident for the pump and valve testinq requirenents.

Enclosed for your use is the "GC Staff Guidance for Preparing Pump and Yalve Testing Progran Descriptions and Associated Relief Requests Pursuant to 10 CFR 50.55a(g)". This enclosure defines the required scope of a pump and valve testing progran, itemizes the specific information needed for staff review, and provides guidelines for submitting infomation to support requests for relief from any ASME Code requirenents found to be impractical for a facility. The sar e inforuation is being sent to all nuclear power plant licensees and is intended to complement and expand on the guidance we provided to RP O

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Yankee Atomic Power Company JAN 131978 you in our previous letter. Although the enclosure specifically addresses pump and valve testing requirements only, the sane level

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of detailed infomation identified in this guidance should also be provided in inservice inspection program sutmittals.

We request that you follow the enclosed guidance to the greatest extent possible when submitting proposed inservice inspection and testing programs and requests for relief from ASME Code requirements, and when responding to additional infomation requests from the staff.

Your adherence to this guidance will minimize the NRC staff review time needed to approv_e your proposed programs and associated relief

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requests.

u If you have any questions regarding implementation of 10 CFR 50.55a(g) at your facility, please contact us.

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Si ncerely,.

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Operating Reactors Branch #1 Division of Operating Reactors DISTRIBUTION

Enclosure:

Docket NRC Staff Guidance NRC PDR LOCAL PDR cc w/ enclosure:

ORB #1 Reading i-See next page ASchwencer SMSheppard ABurger JWetmore OELD E[

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DEisenhut TBAbernathy JRBuchanan

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