ML20148C635

Provides Insp Program Credit for Independent Safety Assessment at Maine Yankee.Recommends That Region I Take Full or Partial Credit for Listed Modules

ML20148C635
Person / Time
Site:	Maine Yankee
Issue date:	10/17/1996
From:	Merschoff E NRC
To:	Cooper R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20148C622	List: ML20148C615 ML20148C626 ML20148C629 ML20148C635 ML20148C640 ML20148C644 ML20148C651 ML20148C658 ML20148C679 ML20148C683 ML20148C689 ML20148C712 ML20149L616 ML20149L618 ML20149L619 ML20149L625 ML20149L627 ML20149L647 ML20149L914 ML20149L921 ML20149L924
References
NUDOCS 9705270173
Download: ML20148C635 (19)

Text

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t UNITED STATES p

j NUCLEAR REGULATORY COMMISSION R

WASHINGTON, D.C. 20555 4001 o

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October 17, 1996 l

1 l

l MEMORANDUM T0:

Richard W. Cooper, Director l

Division of Reactor Projects Region I FROM:

Ellis W. Merschoff, Team Leader W F/

i l

Maine Yankee Independent Safety Assessment Team

SUBJECT:

INSPECTION PROGRAM CREDIT FOR THE INDEPENDENT SA ETY ASSESSMET AT MAINE YANKEE The Maine Yankee Independent Safety Assessment (ISA) Team has compared the assessment done at Maine Yankee to the inspection program modules to establish appropriate credit. The ISA recommends that Region I take full or partial credit for the modules listed below.

The ISA recognizes that additional follow-up i

inspection may be needed in some areas based on performance observations l

documented in the ISA report.

l 35701, Quality Assurance Program Annual Review - 100% Close e

e 35702, Inspection of Quality Verification Function - 100% Close l

e 36800, Organization - 100% Close I

e 37700, Design, Design Changes, and Modifications - 100% Close i

e 37701, Facility Hodifications - 100% Close l

e 37828, Installation and Testing of Modifications - 75% Credit 38701, Procurement Program - 25% Credit e

e 38702, Receipt, Storage, and Handling of Equipment and Materials Program

- 25% Credit e

39702, Document Control Program - 100% Close e

40500, Evaluation of Licensee Self-Assessum w ility - 100% Close 40704, Implementation, Audit Program - 100% Close e

e 41500, Training and Qualification Effectiveness - 20% Credit l

l 42700, Plant Procedures - 50% Credit l

e 61700, Surveillance Procedures and Records - 90% Credit e

61701, Complex Surveillance - 50% Credit l

e 61726, Surveillance Observations - 100% Credit e

62700, Maintenance Program Implementation - 100% Credit e

62703, Maintenance Observations - 100% C* edit e

62704, Instrumentation Maintenance - 100% Credit e

62705, Electrical Maintenance - 100% Credit e

71500, Balance of Plant Inspection - 25% Credit e

71707, Plant Operations - 50% Credit e

71715, Sustained Control Room and Plant Observations - 100% Credit e

72701, Modification Testing - 100% Credit 73756, In-Service Testing of Pumps and Valves - 100% Credit e

i l

9705270173 970516 l

PDR ADOCK 05000309 H

PDR

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l Richard W. Cooper 2

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e 81042, Testing and Maintenance - 100% Credit i

e 82205, Shift Staffing and Augmentation - 100% Credit e

90700, Feedback of Operational Experience Information at Operating Power l

Reactors - 100% Close j

e 92720, Corrective Action - 100% Close e

93804, Risk-Based Operational Safety and Performance Inspection -

100% Credit The hours expended in the evaluation are not included as entry of these hours into RITS/MIPS would result in a financial charge to the licensee for this activity.

The NRC resource expenditure for this special evaluation was not directly assessed the subject licensee.

If there are any questions regarding this information, please contact me at (404) 331-5179.

l cc:

E. L. Jordan, AE0D H. J. Miller, RA/RI l

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1 October 17, 1996 MEMORANDUM T0:

Richard W. Cooper, Director Division of Reactor Projects, Region I FROM:

Ellis W. Merschoff, Team Leader

/S/

' Maine Yankee Independent Safety Assessment Team

SUBJECT:

INSPECTION PROGRAM CREDIT FOR THE INDEPENDENT SAFETY ASSESSMET AT MAINE YANKEE The Maine Yankee Independent Safety Assessment Team'(ISAT) has compared the assessment done at Maine Yankee to the inspection program modules to establish appropriate credit.

The ISAT recommends that Region I take full or partial credit for the modules listed below. The ISAT recognizes that additional follow-up inspection may be needed in some areas based on performance observations documented in the ISAT report.

35701, Quality Assurance Program Annual Review - 100% Close e

35702, Inspection of Quality Verification Function - 100% Close e

e 36800, Organization - 100% Close e

37700, Design, Design Changes, and Modifications - 100% Close e

37701, Facilit.y Modifications - 100% Close e

37828, Installation and Testing of Modifications - 75% Credit e

38701, Procurement Program - 25% Credit e

38702, Receipt, Storage, and Handling of Equipment and Materials Program

- 25% Credit e

39702, Document Control Program - 100% Close e

40500, Evaluation of Licensee Self-Assessment Capability - 100% Close e

40704, Implementation, Audit Program - 100% Close e'

41500, Training and Qualification Effectiveness - 20% Credit e

42700, Plant Procedures - 50% Credit e

61700, Surveillance Procedures and Records - 90% Credit e

61701, Complex Surveillance - 50% Credit e

61726, Surveillance Observations - 100% Credit e

62700, Maintenance Program Implementation - 100% Credit e

62703, Maintenance Observations - 100% Credit o

62704, Instrumentation Maintenance - 100% Credit e

62705, Electrical Maintenance - 100% Credit e

71500, Balance of Plant Inspection - 25% Credit e

71707, Plant Operations - 50% Credit e

71715, Sustained Control Room and Plant Observations - 100% Credit e

72701, Modification Testing - 100% Credit e

73756, In-Service Testing of Pumps and Valves - 100% Credit f

.sf

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)

i Richard W. Cooper 2

e 81042, Testing and Maintenance - 100% Credit e

82205, Shift Staffing and Augmentation - 100% Credit i

90700, Feedback of Operational Experience Information at Operating Power l

Reactors - 100% Close e

9272'J, Corrective Action - 100% Close l

93804, Risk-Based Operational Safety and Performance Inspection -

l 100% Credit l

The hours expended in the evaluation are.not included as entry of these hours j

into RITS/MIPS would result in a financial charge to the licensee for this activity.

The NRC resource expenditure for this special evaluation was not i

directly assessed the subject licensee.

If there are any questions regarding this information, please contact me at (404) 331-5179.

cc:

E. L. Jordan, AE0D H. J. Miller, RA/RI Distribution:

DFRoss EWMerschoff FJCongel DCS IRD R/F File 0916 DOCUMENT NAME:k:\\D0916\\INSPCDTA.ME To inseive a espy of thieJesiyuent, inlisato in the her *C* = Copy without enclosures

• E* = copy with enclosures

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NAME Mefschoff:obw DATE Atf/l?/96 10/

/96 10/ /96 10/

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OFFICIAL RECORD COPY l

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's WASHINGTON, D.C. 20566-0001 o

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September 11, 1996 Mr. Charles D. Frizzle President Maine Yankee Atomic Power Company 329 Bath Road Brunswick, Maine 04011

Dear Mr. Frizzle:

As part of the ongoing Independent Safety Assessment of the Maine Yankee Nuclear Station, on August 1, 1996, we provided you with the results of our review of component reliability data for the steam driven auxiliary feedwater pump.

In this memorandum which requested a review for factual errors, we noted that we were reviewing the treatment of early run failures. We have determined that certain early run failures would be more appropriately classified as failures to st' art, which has in turn changed the numerical determination of reliability of the pump.

We have enclosed the revised

. reliability graph for your information.

If you have any questions, Mr. Ron Lloyd can be reached at 301-415-5543.

Sincerely, (4,p' -

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Tdwar

. Jordan, % Director

/

Offic f r Analysis and Evaluation of 0 erational Data Docket No. 50-309

Enclosure:

As stated cc w/ enclosures:

See page 2

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I Mr. Charles D. Frizzle 2

cc/w enclosures:

Chairman Jackson Mr. James R. Hebert, Manager Commissioner Rogers Nuclear Engineering and Licensing Commissioner Dicus Maine Yankee Atomic Power Company I

Commissioner Diaz 329 Bath Road.

Commissioner McGaffigan Wiscasset, ME 04578 James M. Taylor, NRC SECY Mr. Robert W. Blackmore Plant Manager Mr. Charles B. Brinkman Maine Yankee Atomic Power Station Manager - Washington Nuclear P.O. Box 408 Operations Wiscasset, ME 04578 ABB Combustion Engineering 12300 Twinbrook Parkway, Suite 330 Mr. G. D. Whittier, Vice President Rockville, MD 20852 Licensing and Engineering Maine Yankee Atomic Power Company Thomas G. Dignan, Jr., Esquire 329 Bath Road Ropes & Gray Brunswick, ME 04011 One International Place Boston, MA 02110-2624 Mr. Patrick J. Dostie State of Maine Nuclear Safety Mr. Uldis Vanags Inspector State Nuclear Safety Advisor Maine Yankee Atomic Power Station State Planning Office P.O. Box 408 State House Station #38 Wiscasset, ME 04578 Augusta, ME 04333 Mr. Graham M. Leitch Mr. P. L. Anderson, Project Manager Vice President, Operations Yankee Atomic Electric Company Maine Yankee Atomic Power Station 580 Main Street P.O. Box 408 Bolten, MA 01740-1398

'# r - - "

" 04578 Regional Administrator, Region I Mary Ann Lynch, Esquire U.S. Nuclear Regulatory Commission Maine Yankee Atomic Power Company 475 Allendale Road 329 Bath Road King of Prussia, PA 19406 Brunswick, ME 04578 First Selectman of Wiscasset Mr. Jonathan M. Block Municipal Building Attorney at Law U.S. Route 1 P.O. Box 566 Wiscasset, ME 04578 Putney, VT 0E346-0566

• i Mr. J. T. Yerokun Senior Resident Inspector Maine Yankee Atomic Power Station U.S. Nuclear Regulatory Commission P.O. Box E Wiscasset, ME 04578 l

I l

L

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^ September 11, 1996 Mr. Charles D. Frizzle President Maine Yankee Atomic Power Company.

329 Bath Road-Brunswick, Maine 04011

Dear Mr. Frizzle:

As part'of the ongoing Independent' Safety Assessment of the Maine Yankee Nuclear Station, on August 1,1996, we provided you with the results of our review of component _ reliability data for the steam driven auxiliary feedwater

'l pump.

In this memorandum which requested a review for factual errors, we noted that we were reviewing the treatment of early run failures. -We have determined that certain early run failures would be more. appropriately classified as failures to start, which has in turn changed the numerical determination of reliability of the pump.

We have enclosed the revised reliability graph for your information.

If-you have any questions, Mr.'Ron Lloyd can be reached at 301-415-5543.

Sincerely, Of par ".

y.

61 c- :

Edward L. Jordan, Director Office for Analysis and of Operational Data Docket No. 50-309

Enclosure:

As stated cc w/ enclosures:

See page 2 Distribution:

See page 3 j

DOCUMENT NAME:

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09//D /96 09/

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H. Miller, RIII l

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