ML20038B344

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Summary of 811106 Meeting W/Util in Bethesda,Md Re Reporting of Tech Specs Fxy & Apdms Limits for Core Reloads in Special Repts (10CFR50.59)
ML20038B344
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 11/20/1981
From: Engle L
Office of Nuclear Reactor Regulation
To: Novak T
Office of Nuclear Reactor Regulation
References
NUDOCS 8112080047
Download: ML20038B344 (6)


Text

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NOV 2 01981

-Docket Nos. 50-333

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ISORANDUM FOR: Thomas M. Novak Assistant Pirector [gV[

for Operating Reactors gI Division of Licensing _

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' Robert ~ A. Clark. Chief H

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. Operating Reactors Branch f3

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Dhlsion of Licensing

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FRON:

Leon 8. Engle, Project Manager 3

Operating Reactors Branch #3 Division of Licensing I SUNMARY OF MEETING WITH VEPCO REGARDING THE REPORTIf6

SUBJECT:

- 0F TECHNICAL SPECIFICATION Fxy AND:APDMS LIMITS FOR CORE RELOADS'IN SPECIAL REPORTS (10 CFR PART 50.59)

A meeting was held on hovember 6, 198' with representatives of the syfeginia Electric and Power Company (VEPCO) and the NRC staff regarding

'tfe subject as noted above. A list of attendees is attached.

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Technical Specifications (TS) presently require that certa'in-limiting parameteFs which change by small increments between fuel cycles are re-calculated by licensees for each reload cycle and are submitted to the

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PEC for re9icw and approval.

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,s VEPCO Froposed that an enveloping equation based on NRC approved mefhodelogy b W sed as a basis for core reloads instead of the present nuusrical TS limits. The envelope would be reported in special reports pitse: int to 10 CFR Part 50.59.

own EC The VEPC0 proposal would provide substantial cost benefit savings by 3@

' reducing NRC staff and licensees workloads associated with core reloads.

gg The proposed changes would not lead to any unreviewed safety issue.

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VEPCO PRESENTATION:

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$3 The TS Power Distribution Limits are a function of the total heat flux 80*

factor limit, F K(Z) established by LOCA analysis. Adherence to the mum Power Distribut on Linits is evaluated during each reload evaluation.

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The analytically predicted total heat flux peaking. factor values'are

, determined to be within the envelope of the Fq.K(Z) curve for the Power Distribution timits safety evaluation.

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v The presently specified TS Fxy limits are used in developing the total heat flux peaking factor values but as specified in the TS are only surveillance limits.

It is the nuclear enthalpy hot channel factor Fyy,whichprovidestheradialpowerdistributionsafetyassurancefor reactor operation and is evaluated for each reload. Therefore VEPC0 proposed that the Fxy limits be specified in a supplemental report,

" Radial Peaking Factor Report", rather than in the TS since Fxy is used for surveillance and is not used alone as a safety limit.

The axial power distribution surveillance limit is expressed as a thres-hold power level, Po, above which axial power distribution surveillance is required. Similarly, the axial flux difference limits include a threshold power level, Pa, above which a 15 minute time limit for restoration to limits is required and a range for short term operation outside the axial flux difference target band. Axial power distribution surveillance and lowering of the axial flux distribution limits below the generic limits are only required if the analytically predicted total heat flux peaking. actor values exceed the Fg.K(Z) curve. Therefore, these threshold power levels are also evaluated prior to each reload.

VEPC0 stated that the renoval of the specific Pm and Pa threshold power levels are also evaluated prior to each reload. VEPC0 stated that the renoval of the specific Pa and Pa threshold power levels from the TS would not climinate any of the licensee responsibilities for operating the reactor in compliance with the appropriate threshold and axial flux range. These limits Pa and Pa, would be provided in a "Augumented Ccre Surveillance Report", in acco.aance with the provisions of 10 CFR Part 50.59. The limits would continue to be evaluated during the reload evaluation process as they presently are and the report would be provided to the f4RC at least 60 days prior to initial criticality for a given fuel cycle.

VEPC0 stated the proposed changes would climinate the costly and burdensene reload safety evaluation submittals which are required only to address TS changes related to the LOCA power distribution limits discussed above. Finally, VEPC0 stated the proposed changes would not result in any unreviewed safety question.

fiRC STAFF C0 mEf;TS:

The staff connented that the proposed change should be sireplified by making all the changes in terms of Pm. That is, Pa=0.9 Pm and the florth Anna (!!A) TS Figure 3.1-1 (Axial Flux Difference Lia s As A Function of Rated Thernal Power) could be expressed as equations in terms of Pm.

The staff suggested that VEPC0 consider that the axial power distribu-tion nonitoring APDMS system turn on point which is based on analys h of the cycle dependent peaking factor (function of height) be included in the proposed special report instead of the TS.

In addition the staff suggested that two VEPC0 reports be consolidated into one special report.

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Also the staff stated that the methodology used for determining the APDMS-turn on point should be included in TS bases and that the TS bases should be updated to describe how themargins of safety are maintained. Finally, the staff indicated VEPC0 should submit a TS change request;regarding.

the. items discussed above.

Original signed by:

Leon B. Engle, Project Manager Operating Reactors Branch #3 Division of Licensing i

Attachment:

List of Attendees cc: See next page i

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MEETING

SUMMARY

blSTRIBUTION Licensee:

Virginia ~ Electric-and Power Company CCopies also sent to those people on service (cc) list for subject plant (s).

Docket File NRC PDR L PDR NSIC TERA ORBf3 Rdg J01shinski JHeltemes, AE00 BGrimes RClark Project Manager Licensing _ Assistant ACRS (10)

Mtg Summary Dist.

NRC Participants

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r Virginia Electric and Power Company cc:

Richard M. Foster, Esquire Mr. James Torson Musick, Williamson, Schwartz, 501 Leroy leavenworth & Cope, P.C.

Socorro, New Mexico.87891 P. O. Box 4579 Boulder, Colorado 80306 Mrs. Margaret Dietrich Route 2, Box 568

' Michael W. Maupin, Esquire Gordonsville, Virginia 22042 Hunton, Williams, Gay and Gibson P. O. Box 1535-Mr. James C. Dunstance Richmond, Virginia 23212 State Corporation Commission Commonwealth of Virginia Alderman Library Blandon Building Manuscripts Department Richmond, Virginia 23209 University of Virginia Charlottesville, Virginia 22901 Mrs. June Allen North Anna Environmental Coalition Mr. Edward Kube 8720 Lockmoor Circle.

Board of Supervisors Wichita, Kansas 67207 Louisa County Courthouse P. O. Box 27 U~JS. Environmental Protection Agency Louisa, Virginia 23093 Region IFI Office ATTN:

Regional Radiation Representative Ellyn R. Weiss, Esquire Curtis Building _.

Sheldon, Harman, Roisman and Weiss 6th and 9alnut Streets.

3 1725 I Street, N.W. Suite 506 Philadelphia, Pennsylvania 19106 Washington, D. C.

20006 Mr. Paul W. Purdom Mr. W. R. Cartwright, Station Manager Environmental Studies Institute P. O. Box 402 Drexel University Mineral, Virginia 23117,

32nd and Chestnut Streets Philadelphia, Pennsylvania 19104 Mr. Anthony Ganbardella Office of the Attorney General Atomic Safety and Licensing 11 South 12th Street - Room 308 Appeal Board Panel Richmond, Virginia 23219 U.S. Nuclear Regulatory Commission Washington, D. C.

20555 Mr. Edward Webster Resident Inspector / North Anna c/o U.S.N.R.C.

Route 2, Box 78A Mineral, Virginia 23117 Mr. J. H. Ferguson Executive Vice President - Power Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261 S

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Attachment List Of Attendees Meeting On November 6, 1981 NRC D.S. Brinkman M. Dunenfeld D. Fieno.

L.B. Engle M.J. Virgilio VIRGINIA ELECTRIC AND POWER COMPANY R.W. Cross f!.D. Mann G.S. Slankle E.R. Smith, Jr.

J P.-Sbith C.T. Snow P

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