ML15231A364

FOIA/PA-2014-0204 - Resp 1 - Final, Group a

ML15231A364
Person / Time
Site:	Millstone, Davis Besse, Browns Ferry, Nine Mile Point, Indian Point, Oyster Creek, Pilgrim, North Anna, Vermont Yankee, San Onofre, Fort Calhoun, FitzPatrick
Issue date:	05/27/2015
From:	Office of Information Services
To:
Shared Package
ML15231A284	List: ML15231A364
References
FOIA/PA-2014-0204
Download: ML15231A364 (11)

Text

Group A Records Already Publicly Available in ADAMS North Anna ML110750123 ML110750124 Fort Calhoun ML010750324 Vermont Yankee -. ML031560786 ML043030582 Oyster Creek ML031560786 ML043030582 Davis Besse ML021200037 Fitzpatrick ML010590482 Nine Mile 1 & 2 ML010990176 Pilgrim ML011920234 San Onofre ML052570659 ML052570317 ML052570319 Millstone 1 & 2 ML012850031

.Millstone 3 ML0400.70238 Indian Point 2 & 3 ML003776428 ML003778517 Browns Ferry 1, 2 & 3 ML013620457 ML020070083 ML020100224

ADAMS Documents as of 0412412015 11:02:41 AM Page 1 of 1 Accession Document Title Number Date ML013270001 1.1/16/2001 Submittal Of"-A" Accepted Version Of CENPD-404-P, Rev. 0 [Enclosure 1-P Contains Westinghouse Proprietary Class 2 Material]

ML013270010 1113012001 Part 1 of 2 of CENPD-404-NP-A, Rev 0, "Implementation of ZIRLO Cladding Material In CE Nuclear Power Fuel Assembly Designs".

ML013270095 11/30/2001 Part 2 of 2 of CENPD-404-NP-A, Rev. 0, "implementation of ZIRLO Cladding Material in CENP Fuel Desings,"

Chapter 7.0 Non-LOCA Accidents.-

ADAMS Documents as of 0412412015 11:45:37 AM Page 1 of 1 Estimated Page Count 29 Document Date 6/2211992 Document Type CORRESPONDENCE-LETTERS OUTGOING CORRESPONDENCE Availability Publicly Available Title Forwards SE supporting approval of C-E Topical Rept CEN-386-P, "Verification of Acceptability of 1-Pin Bumup Limit of 60 MWD/kg for C-E 16X16 PWR Fuel."

Author Name THADANI A C Author Affiliation NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)

• Author Affiliation Class N Addressee Name SCHERER A E Addressee Affiliation ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY Addressee Affiliation Class MV Docket Number 05000317 License*Number Case/Reference Number Document/Report Number TAC-M82192 Keyword ADEQUACY APPROVALS BURNUP FUELS LIMITS PDR Category P PINS PRESSURIZED WATER REACTORS*

SELENIUM TOPICAL REPORTS

- - - . .VERIFICATION . ... . .. .

Package Number 9207100126A Date Docketed Related Date Comment Document Status XA Media Type Microform Physical File Location PDR:ADOCK-05000317-P-920706,PDR:ADOCK/0500031 7/P 920706 Microform Addresses 62284:312-62284:341 Distribution List Codes Text Source Flag Document Sensitivity Non-Sensitive

ADAMS Documents as of 0412412015 11:05:33 AM Page 1 of 1 Accession Document Title Number Date ML052570659 09/14/2005 SONGS Units 2 & 3, issuance of Amendments on ZIRLO Clad Fuel.

ML052570317 09/14/2005 SONG Unit 2, Tech Specification Pages re ZIRLO Clad Fuel.

ML052570319 09/14/2005 SONGS Unit 3, Technical Specification Pages Re ZIRLO Clad Fuel.

UNITED STATES NUCLEAR REGULATORY COMMISSION

• edI g 9fjq WASHINGTON, D.C. 20555-0001 e'DEC21 NRI "9 Deoembe=. 14, 1993 Docket Nos. 50-280, 50-281 50-338 and 50-339 Mr. W. L. Stewart

.Senior Vice President - Nuclear

• Virginia Electric and Power Co.

5000 Dominion Blvd.

• len Allen, Virginia 23060

SUBJECT:

SLJRRY, UN:ITS 1 AND 2, AND NORTH ANNA, UNITS 1 AND 2 - REMOVAL OF 45,000 MWD/MTLJ BATCH AVERAGE BURNUP RESTRICTION (TAC NOS. M87767,.

M87768, M87812, AND 1487813)

By letter dated November 25, 1992, you requested relaxation of the batch average burnup restriction of 45,000 MWD/MTU (megawatt days per metric tori of

_u....

rani urn),....as- presenity.specifi ed-in.NRC-i1etterzLdated-April1-9-184--for~ the-Surry and North Anna Power Stations, and proposed, instead, that the fuel burnups at both stations be limited to levels~ consistent with the NRC Safety

• EvaluationReport on the Westinghouse Electric Corporation's TOpical.Report I'CAP-10125, entitled ,Extended .Burnup .Evaiua~tion of Wes~tinghouse-~Fuel-.-"

We have revi~ewed your request and have concluded that it is appropriate to increase the batch average burnup restriction to 50,000 MWD/MlTU, or above, as long as the maximum rod average burnup of any fuel rod is no greater, than 60 MWD/MTU pursuant to the limits specified in'the~ederal Reciister (53 FR 6040) dated February 29, 1988. Our safety evaluation isenclosed. Implicit in our evaluation is that the fuel management scheme will.continue to provide the limiting location of the fuel during subsequent cycles of operation.

Bart C. Buckley, Sr. Project Manager Leon B. Engle, Pf9*ect Manager Project Directorate II-2 Project D~irectoralte II-2 Division of'Reactor projects - I/If Division of Reactor Projects - I/lI

Enclosure:

As stated cc w/enclosure:

See next page

Vartinia Ilt~ctric & Power Company Cc; Mr. Wii llam C. Porter, Jr.

County Administrator *Robert B. Strobe, State Health M.D., M.P.H.

Conmissioner Louisa County Office of the Commuissioner P.O. Box 160 Vfrginia Department of Health Louisa. Virginia 23093 P.O, Box 2448 Richmond, Virginia 232T8 Michael V. Haupin, Esq.

Hunton and idilliams Regional Administrator, RII Riverrront Plaza, East lower U.S, Nuclear Regulatory Commission 951 1. Byrd Street 101 Marietta Street, N.W, *zgO0 Richmond. Virginia 23219 Atlanta, Georgia 30323 Dr, V. 1. t~ough Virginia State Corporation Cnmmission Hr. G. C. Kane, Manager Dlvis*',n of Energy Regulation North Anna Power Station P.O. finx 1197 P.O, Box 402 Richmond, Virginia 23209 Mineral, Virginia 23117 Old Dominion Electric Cooperative *Hr. V. L. Stewart 4201 DominionnBlvd. Senior Vice President - Nuclear Gipn Allen, Virginia 23060 Virginia Electric and Power Company Innsbrook Technical Center Mr. 14.L. Bowling, Manager 5000 Dominion Blvd.

Nuclear Licensing & Programs Glen Allen, Virginia 23060 Virginia Electric and Powe~r Company Ennibrook ;ethnical Center Hr.I Michael R. Kansler, Manager 5000 Dominion Blvd." Surry Power Station Glen Allen, Virginia 23060 Post Office Box 166, Route I Surry, Virginia 23883 Oflfice Of the Attorney General supreme Court Buildinq Mr. Sherlock Hotmes, Chairman 1(1 North 8th Street Board of SUpervisors

• of Surry County Surry County Courthouse Senior Resident Inspector Surry, Virginia 23683 North Anna Power Station U.S. Nuclear Regulatory Cormiission Route 2. Box 78 Mineral, Virginia 23117 Senior Vice President Surry Power Station U.S. Nuclear Regulatory Commission Post Office Box 166, Route !

Surry, Virginia 23883

• . _L It ... ..

-1B~.F'..

$. UNITED STATES NUCLEAR REGULATORY COMMISSION

.iA.'~HfIAGT(Jfi 0 C .. ' ". S 1 t~w SAFETy EVALUATION. BY THE OFFICE OF NUCLEAR REACTOR REGUAllT1OI VIlRGINIA ELECTRIC AND POWER CO~4PANY SIJRRY. UNITS I AND 2 AND NORTH ANNA UNITS ] AN~DA 1.0 Introduction By letter dated April 9, 1984. the NRC approved an~increase in the batch average burnup restriction from 37,000 to 45,000 MWO/MTU (megawatt days per metric ton of uranium) for both the Surry and North Anna Power Stations, Subsequently, by letter dated November 25, 1992. the Virginia Electric and Power Company (the licensee) requested relaxation of the batch average burnup restriction of 45,000 MWD/NTU, as presently Foecified in NRC letter dated April 9, 1984, for both the Surry and North Ani.* facilities, and proposed instead to Itmlt the burnup to limits consistent with the NRC Safety evaluation report (SER) on a Westinghouse topical ri~ort WCAP-10125, entitled "Extended Burnup Evaluation of Westinghouse Fuel." which was transmitted to the Westinghouse Electric Corporation by NRC letter dated October 11, 1985.

The staff concludes that it is acceptable to raise the limit to 50,000 HUD/MTU, or above, as long as the maximum rod average burnup of any fuel .rod is no greater than 60 IWD/MTU pursuant to the limits specified in the *Qr*

R~tgii (53 FR 6040).

2.0 Ly ua~t~on The WCAP-10125 report described .tthe models and methodology used in the safety analys~is of Westinghouse fuel at extended burnup and discusses the experimental data used to support those models. As stated in the above-cited NRC letter dated October 11, 1985, we found the topical report to be acceptable for referencing in license applications to the extent specified and under the limitations delineated in the topical report and the associated NRC SER. The staff review of the topical report found that:

I. WCAP-10125 not only discussed models, methodology and data, but also applied these models to show that existing "limits continue to be met over a burnup range exceeding that requested by the licensee.

2. The models used have been previously reviewed and approved by the NRC without explicit burnup limits. The analysis simply applied these.

unchanged models over a burnup range not previously considered, but did not address radiological aspects, which are discussed below.

3. Westinghouse examined the application of the existing methodology at extended burnup and identifiled no burnup-dependent phenomena which would invalidate the analyses pierformed.

Q3I2170*0 PDR ADOCI1 931;214 O*XOOO;tg0 P PIVM I11111i1!Illiliil11111111t1111111I IItllii(Il1111 9312170201

I

4. Results of Westinghouse extended burnup Lead Assembly programs at a number rof Westinghouse plants (including Surry and North Anna) support the Westinghouse conclusion (excluding radiological aspects discussed below).

The $icensee has reviewed the Westinghouse report (gCAP-liOZS) and has determiuned that the results are applicable.

The NRC staff performed an independent analys~is of the radrl',oglcal consequences of extended fuel burnup and concluded that, while there would be.

an increased thyroid dose resulting fromthe fuel..handling accident, the calculated Increase was nct significant. The increased thyroid dose meets the acceptance criteria of the Standard Review. Plan Section 15.7.4 and the dose.

guidelines set forth in 10 CFR Part 100. Subsequent to the issuance of the NRC SRE, NUREG/CR-5O0g, entitled "Assessment of the Use rt Extended Burnup Fuel in Light Water Power Reactors," was published In Febrary 1988 to document a study conducted by Pacific Northwest Laboratory for the NRC. This report concluded that there are no significant adverse environmental effects

• associated with increases in the burnup level to a maximum rod .average burnup or 60,000 MWD/NTU.

3.0 Environmental Considertitons The staff prepared and published an environmental assessment and findi'~q of no significant impact from the use of extended burnup fuel in connercial light water reactors in the 'fgdra!1 Reaister (53 FR 6040), whlt¢' concluded that there are no significant. adverse radiological or non-radiological impacts associated with the use of extended burnup fuel and that tts use will not significantly affect the quality-of the human environment. Therefore.

_pUursuant* to1CFR_ 51_31, theComei_.Ssion has determi!ned that an environmental impact statement need not be prepared for this action.

4.0 Conicluston We have concluded that Increasing of the batch average burnup restriction to 50,000 NWDtMTU, or above, as long as the maximum rod average burnup of any fuel rod is no greater than 60 MVO1I/NTU for the Surry and North Anna facilities, is acceptable. lnplicit in this evaluation is that the 'fuel management scheme will continue to provide the limiting location of fuel during subsequent cycles of operation.

.r.'Inclpal Contributor: B. Buckley Date: December 14, 19.3

. ... I [ ._ I._.[ ...... I ... ........ I I.... .. . . .... i ijllmal ... .. .... ..

.~enai~ ~i-i v~ C)C-'

UNITED ,STATES" NUCLEAR REGULATORY COMMISSION ~ec'd APR29 1994 WASHINGTON, D.C. 20555-0001 Nuclear Licensing Aprl 20, 1994 Docket Nos. 50-280, 50-281 50-338, 50-339 Mr. W.. 1. Stewart Senior Vice President - Nuclear Virginia. Electric and Power Company-Innsbrook Technical Center

.5000 Dominion Blvd.

Glen Allen, Virginia 23060

SUBJECT:

SLJRRY, UNITS 1.AND 2, AND NORTH ANNA, UNITS 1 AND 2 - REMOVAL. OF 45,000 MW*D/I4TU BATCH AVERAGE BURNUP RESTRICTION (TAC NOS. M487767, 1487768, 1487812, AND 1487813)

... _By..NRC..let.t~er dat~ed.De.cember. 14, .. 9.93,.we.appro~ved.an..in_r~e~a~se in._t~he_ ba~tch..

average burnup restriction, from 45,000 MWD/l4TU..(megawatt days per metric ton-of uranium) to 50,000 MWD/MTU, or above, as long as the maximum rod average burnup of any fuel rod is no greater than 60,000 M4WD/MTIJ.

Thie--60,000l).MWD/MT v-al-ue-,--in several instances, was inadvertently displayed as 60 MWD/MTU. The correct value is 60,000 MWD/MTTU.

Sincerely, Project Direcbor-ae 11-2aae Bart C. Buckley, r.Poject Manager Project Directorate II-2 Division of Reactor Projects - I/LI Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Office of.Nuclear Reactor Regul ation cc: See next page N

.o v ~September 9, 1988 -.

MEMORANDUM FOR: Sholly Coordinator FROM: Vernon Rooney, Senior Project Manager Project Directorate I-3 Division of Reactor Projects I/If

SUBJECT:

REQUEST FOR PUBLICATION IN BI-WEEKLY FR NOTICE - NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE Vermont Yankee Nuclear Power Corporation,. Docket No. 50-271, Vermont Yankee Nuclear Power Station, Vernon, Vermont Date of application for amendment-: May 23, 1988, as supplemented on August 15, 1988.

Brief description of amendment: The amendment revises the Technical Specifications to permit the use of the fuel type designated as GE 8X8EB.

Date of issuance: $eptember 9.*1988.

Effective date: 30 days. fr~ni d~te of i~ssuance.

Amendment No.: lOS Facility Operating License No. DPR-28: Anmendment revised the Technical Specifications. Date of initial notice in Federal Register: June 15, 1988 (53 FR 22408). The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated September 9, 1988.i No significant hazards consideration comments received: No.

Local Public Document Room Location: Brooks Memorial .Library, 2?4 Main Street, Brattleboro,. Vermont 05301.

• BSO01IO255 880 -909 "i .... Vernon L. Rooney, Senior Project Manager CF ADOCK 050027.1 Project Directorate 1-3" CNU

• Division* of Reactor Projects 1/11 Distribution: Docket File, P01-3 r/f., MRushbrook, VRooney, RWessman,

~bbook VRooney:ck*--RWessman

Page 1 ofi I A

Dase of10104881201508:42:9A AASDocuments Accession Number 8809190232 Document Date 91911988 12:00:00AM Estimated Page Count 9 i, Document Type OPERATING LICENSES & AMENDMENT[S TEXT-LICENSE APPLICATIONS & PERMITS Title Amend 108 to License DPR-28,revising Tech Specs to permit use of GE 8X8EB fuel type.

i ,

Author Affiliation NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)

Author Name WESSMAN R H.,

Availability Publicly Available Microform Addresses 46898:059-46898:067 Document SensitiVity Non-Sensitive Package Number 8809190225A Accession Number 8809190225 Document Date 9/9/1988 12:00:00AM  !

Estimated Page Count Document Type 5CORRESPONDENCE-LETTERS -

NRC TO UTILITY OUTGOING CORRESPONDENCE Title Forwards Amend 1.08 to License DPR-28 & safety evaluation. Amend revises Tech Specs td permit use of GE 8X8EB fuel type in response to util 880523 application & 880815 clardfication.

Author Affiliation NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)

Atifhnr INJmr. PN~flbJV 'V I Document Accession Number 9/9/1988 12:00:00AM Date 8809190225 Microform Availability.

Addresses Publicly Available 46898:054-46898:070 Document Sensitivity Non-Sensitive Package Number 8809190225*

Accession Number 8809190235 Document Date 9/9/1988 12:00:00AM Estimated Page Count 3 Document Type SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES TEXT-SAFETY REPORT -,

Title Safety evaluation supporting Amend 108 to License DPR-28.

Author Affiliation NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)

Author Name Availability Publicly Available Microform Addresses 46898:068-46898:070 DocUment Sensitivity Non-Sensitive -

Package Number 8809190225B