ML20002C553

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Discusses Licensee Inquiries Re Compliance w/760428 Revised Inservice Insp Requirements.Forwards NRC Guidance Re Major Provisions & Licensee Concerns Re Relevance of ASME Boiler & Pressure Vessel Code & Practicality of Relief Process
ML20002C553
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 11/24/1976
From: Ziemann D
Office of Nuclear Reactor Regulation
To: Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
Shared Package
ML20002C554 List:
References
NUDOCS 8101100467
Download: ML20002C553 (3)


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Docket f.e. 50-155 HOV t 4 BIO i

Consuners Power Company ATTN:

F.r. Ralph B. Sewell huclear Licensing Adninistrator

.212 West Michigan Avenue Jackson, Michigan 49201 Gentleraen:

RE: BIG ROCK POINT, LICENSE NO. DPR-6 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 Register on February 12, 1976 (41 FR 6256).

The revised regulation changed the inservice inspection and testing require-ments for nuclear power plant components contained in paragraph (g) of ftic.55a.

A letter regaroing this subject was sent to you on April 28, 1976.

Since that tir e. the NRC 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 conpliance with the regulation:

1.

The detennination of which Ast4E Boiler and Pressure Vessel Code Edition and Addenda are applicable for any updated inservice inspction or testing program, 2.

The requirement to conform the Technical Specifications to a revised progra", and 3.

The process of obtaining relief from ASME Code requirements found to be impractical.

Consequently, we cre transmitting for your use Enclosure 1:

"NRC Staff Guidance For Complying with Certain Provisions of 10 CFR 50.55a(g), Inservice Inspection Requirenents". This enclosure describes the major provisions of the revised regulation, addresses the areas of licensee concern listed above, and pro-vides guidance on infomation which the NRC staff will need to review inservice g

inspection and testing programs and to evaluate recuests for relief fron i

ASt1E Code reautrenents that are detemined to be impractical. We believe this enclosure will serve to clarify the proper method (s) for irnplementing the 7

regulation in {veral important :reas.

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Consumers Power Company NOV ? e 1976 We reiterate our previous request that you subnit proposed Technical Specification changes to incorporate standard language referencing 550.55a(g), at least 6 months before the start of the next 40-nonth inspection period for your facility. Also, as discussed in Enclosure 1, you should submit a description of your planned inservice inspectior.

and testing programs, as well as any request for relief from ASME Code requirenents deten-ined to be inpractical for your facility, as far in advance as possible of, but at least 90 days before, the start of' any 40-nonth inservice inspection period, or 20-month pump and valve j

testing period.

In addition, we would like to emphasize an important point regarding the ASME Code Section XI requi ements to test selected pumps and valves, that are now incorporated in ?.0.55a(g):

The ASME Code Section XI I

requirer.ients apply only to seiected valves and pumps that can be tested without placing the plant in an unsafe condition. You should exercise l

care in planning your testing programs to ensure that no test will be i

conducted while the plant is in an operating mode that would make it I

vulnerable to a test error or a test failure.

Particular attention should be directed toward the valve exercising (cycling) tests..In this i

reoard, sone basic guidelines for excluding exercising (cycling) tests of certain valves during plant operation are contained in Enclosure 2.

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

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If you have any further questions regarding implementation of 10 CFR l

50.55a(g) at your facility, please contact us.

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Sincerely,

  • a*Sicedby*

""P00R ORIGINAL Dennis L. Ziemann, Chief Operating Reactors Branch f 2 l

Division of Operating Reactors I

DISTRIBUTION k

es ACRS (16) ff Guidance for Complying with Certain Provisions of Local PDR JWetmore 10 CFR 50.55a(g)

ORB #2 Reading OELD - Barth/KArman 2.

Guidelines for Excluding VStello 01&E(3)

Exercising (Cycling) Tests TJCarter DEisenhut j

of Certain Valves During D'.Ziemann TBAbernathy Plant Operation RMDiggs JRBtichanan s

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Consumers Power Comp'.ny A T>

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cc w/ enclosures:

Mr. Paul' A. Perry, Secretary Consumers Power Company 212' West liichigan Avenue Jackson, Michigan 49201 Charles F. Bayless Of Counsel Consumers Power Company 212 West 111cnigan Avenue Jackson,tiichigan 49201 George C. Freeman, Jr., Esquire Hunton, Williams, Gay and Gibson 700 East Main Street Richmond, Virginia 23212 Peter W. Steketee, Esquire Freihofer, Cook,. Hecht, Oosterhouse and De Boer Union Bank Building, Suite 950 Grand Rapids, !!ichigan 49502

' Charlevoix Public Library 107 Clinton Street Charlevoix, flichigan 49720 i

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