ML17037B668

Letter Regarding a Revision to 10 CFR Part 50, Section 50.55a and an Enclosed NRC Staff Guidance for Complying with Certain Provisions of 10 CFR 50.55a(g), Inservice Inspection Requirements.

ML17037B668
Person / Time
Site:	Nine Mile Point
Issue date:	11/22/1976
From:	Lear G Office of Nuclear Reactor Regulation
To:	Rhode G Niagara Mohawk Power Corp
References
41 FR 6256
Download: ML17037B668 (4)

Text

NOV 2 "2 1976 Distributi on ORB 83 Local PDR I NRC PDR Docket, Ho. 50-220 VStello TJCarter GLear CParrish Niagara ttohawk Power Corporation JWetmore ATTN: fir. Gerald K. Rhode SNowicki Vice President - Engineering 300 Erie Boulevard )lest Attorney ,OELD Syracuse, Hew York 13202 OI&E (3)

DEisenhut Gentlemen: TBAbernathy JRBuchanan RE: HIHE BILE POINT NUCLEAR STATION UHIT A@S 1(16)

Earlier this year we sent letters to licensees of operating nuclear power plants notifying them of a revision to 10 CFR Part, 50, Section 50.55a which was published in the Federal Regfster on February 12, 1976 (41 FR 6256).

The revised regulation changed the fnservfce inspection and testing require-

. ments for nuclear power plant components contained fn paragraph (g) of I50.55a.

A letter regarding this subject was sent to you on April 26, 1976.

Since that time, the HRC has received a number of inquiries from licensees regarding acceptable methods for complying with the regulation. In general, the inquiries have been directed toward three major areas relative to compliance with the regulation:

1. The determination of which ASME Boiler and Pressure Vessel Code Edition and Addenda are applicable for any updated fnservice inspection or testing program,

2. The requirement to conform the Technical Specifications to a revfsed program, and

3. The process of obtaining relief from AQ/E Code requirements found to be impr actical.

Consequently, we are transmitting for your use, Enclosure 1: "HRC Staff Guidance For Complying with Certain Provisions of 10 CFR 50.55a( g), Inservice Inspection Requirements". This enclosure describes the major provisions of the revised regulation, addresses the areas of licensee concern listed above,'and pro-vides guidance on information which the HRC staff will need to review inservice

'nspection and testing programs and'o evaluate requests for relief from ASHE Code requirements that are determined to be impractical. lie believe this enclosure will serve to clarify the proper method(s) for implementing the regulation in several important areas.

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1 NOV 2 2 t'-ohawk Power Corporation - 2- 197'iagara 1/e reiterate our previous request that you submit proposed Technical Specification changes to incorporate standard language referencing g50.55a(g), at least 6 months before the start of the next 40-month inspection period for your facility. Also, as discussed in Enclosure 1, you should submit a description of your planned inservice inspection and testing programs, as well as any request for rel'ief from AStiE Code requirements determined to be impractical for your facility, as far fn advance as possible of, but at least 90 days before, the start of any 40-month fnservice inspection period, or 20-month pump and valve testing period.

In addition, we would like to emphasize an important point regarding the AStfE Code Section XI r equfr ements to test selected pumps and valves, that are now incorporated in ii50.55a(g): The ASfiE Code Section XI requirements apply only to selected valves and pumps that can be tested without placing the plant fn an unsafe condition. You should exercise care in planning your testing programs to.ensure that no test will be conducted while the plant 'fs in an operating mode that would make ft vulnerable to a test error or a test, failure. Particular attention should be directed toward the valve exercising (cycling) tests. In this regard, some basic guidelines for excluding exercising (cycling) tests of certain valves during plant operation are contained fn Enclosure 2.

Valve leakage tests and other valve and pump tests required by the AShiE Code, should be reviewed for each component, relative to each plant oper ating mode, to ensure that no test will have an adverse impact on plant safety.

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

Sincerely,

/rhinal signed by George Lear, Chief Operating Reactors Branch ¹3 Division of Operating Reactors Encl osur es:

HRC Sta ff Gui dance for Compl yf ng with Certain Provisions of 10 CFR 60.65a(g)

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