ML15156A926

FOIA/PA-2015-0204 - Resp 1 - Final

ML15156A926
Person / Time
Site:	Millstone, Davis Besse, Nine Mile Point, Oyster Creek, Pilgrim, North Anna, Vermont Yankee, San Onofre, Fort Calhoun, FitzPatrick
Issue date:	05/27/2015
From:	Andoh R Office of Information Services
To:	Shapiro S - No Known Affiliation
References
FOIA/PA-2015-0204
Download: ML15156A926 (12)

Text

NRC FORM 464 Part I U.S. NUCLEAR REGULATORY COMMISSION FOIAIPA RESPONSE NUMBER (01-2015)

RESPONSE TO FREEDOM OF 2014-0204 1

INFORMATION ACT (FOIA) / PRIVACY ACT(P)

RQUSTRESPONSE D-INTERI M

[*-jFINAL ACT (PA) REQUEST TYPE REQUESTER DATE Susan Shapiro I

ft 2 2 2G15 PART I. - INFORMATION RELEASED D No additional agency records subject to the request have been located.

D Requested records are available through another public distribution program. See Comments section.

G*ROUP Agency records subject to the request that are identified in the specified group are already available in public A

ADAMS or on microfiche in the NRC Public Document Room.

E GROUP Agency records subject to the request that are contained in the specified group are being made available in public ADAMS.

D GROUP Agency records subject to the request are enclosed.

D1 Records subject to the request that contain information originated by or of interest to another Federal agency have been referred to that agency (see comments section) for a disclosure determination and direct response to you.

SWe are continuing to process your request.

See Comments.

PART I.A -- FEES AMOUNT*

You will be billed by NRC for the amount listed.

[j None. Minimum fee threshold not met.

See comments H1 You will receive a refund for the amount listed.

[7 Fees waived.

for details F-D PART I.B -- INFORMATION NOT LOCATED OR WITHHELD FROM DISCLOSURE We did not locate any agency records responsive to your request. Note: Congress allowed agencies to treat three discrete categories of law enforcement and national security records as not subject to the FOIA ("exclusions").

See 5 U.S.C. 552(c). This is a standard notification that we give to all requesters; it should not be taken as an indication that any of these excluded records do, or do not, exist.

D We have withheld certain information in the records from disclosure pursuant to the FOIA exemptions described, and for the reasons stated, in Part II.

Because this is an interim response to your request, you may not appeal this determination at this time. We will D

notify you of your right to appeal any of the responses we have issued in response to your request when we issue our final determination on your request.

D You may appeal this final determination within 30 calendar days of the date of this response, by writing to the FOIA Officer, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555-0001.Please be sure to mark your letter/envelope or email that it is a "FOIA Appeal."

PART I.C COMMENTS ( Use attached Comments continuation page if required)

A listing of all ML Accession.Numbers for the approvals of high bum up fuels is provided in Group A, per the agreed upon narrowed scope conversation with your caseworker, Ms. Argent. We appreciate your patience while processing your request.

(I-A SIGNATURE - FREEDOMIDF INFORMATION ACT AND PRIVACY ACT OFFICER Roger Andoh NRC FORM 464 Part 1 (01-2015)

Page 2 of 3 NRC FORM 464 Part 1 (01-2015)

Page 2 of 3

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 ML040070238 Indian Point 2 & 3 ML003776428 ML003778517 Browns Ferry 1, 2 & 3 ML013620457 ML020070083 ML020100224

ADAMS Documents as of 04124/2015 11:45:37 AM Page 1 of I ADAMS Item IDý 011188007 ADAMS, P8 Document ID~.17C29-0627-4FB5.-A3BO-CB6DEFC8A73A)

Accession Nu~mer~ 9207020135~

Estimated Page Count 29 Document Date 6/22/1992 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 Burnup 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/05000317/P 920706 Microform Addresses 62284:312-62284:341 Distribution List Codes Text Source Flag Document Sensitivity Non-Sensitive

ADAMS Documents as of 04124/2015 11:05:33 AM Page 1 of I Accession Number ML052570659 ML052570317 ML052570319 Document Title Date 09/14/2005 SONGS Units 2 & 3, Issuance of Amendments on ZIRLO Clad Fuel.

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

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

ADAMS Documents as of 0412412015 11:02:41 AM Page 1 of I 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 11/30/2001 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.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-ODO0 Ree'd 2

Nuclear Licensing December 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.

.Glen Allen, Virginia 23060

SUBJECT:

SURRY, UNITS 1 AND 2, AND NORTH ANNA, UNITS I AND 2 - REMOVAL OF 45,000 MWD/MTU BATCH AVERAGE BURNUP RESTRICTION (TAC NOS. M87767, M87768, 1M87812, 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 ton of uranium), aspresently..specified-inNRC -letter--dated-AprilT..9 i-1984-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 WCAP-10125, entitled "Extended Burnup Evaluation of Westinghouse Fuel."

We have revi.ewed your request and have concluded that it is appropriate to increase the batch average burnup restriction to 50,000 WOD/MTU, 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 Federal Register (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 Project Directorate 11-2 Division of-Reactor Projects - I/Il Leon B. Engle, P(.9oect Manager Project Dj rectoraie 11-2 Division of Reactor Projects - I/lI

Enclosure:

As stated cc w/enclosure:

See next page

Virginia I lectric I Powpr Company cc:

Mr. William C. Porter, Jr.

County Administrator Louisa County P.O. Box 160 Louisa, Virginia 23093 Michael W. Maupin, ESQ.

Hunton and Villiams Riverfront Plaza, East lower 951 E. Byrd Street Richmond. Virginia 23219 Dr. W. 1. Lough Virginia State Corporation Cnmuission Oivi%-in of Energy Requlation P.O. anx 1197 Richmond, Virginia 23209 Old Dominion Electric Cooperative 4201 Dominion Blvd.

Glen Allen. Virginia 23060 Mr. M. t. Bowling, Manager Nuclear Licensing & Programs Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, Virginia 23060 Office of the Attorney General

,upreme Court Buildinq i.l North 8th Street Rirhmond. Virgini1 23219 Spnior Resident Inspector North Anna Power Station U.S. Nuclear Regulatory Comminslon Route 2, Box 78 Mineral, Virginia 23117 Robert B. Strobe, M.0.,

M.P.H.

State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Regional Administrator. RIi U.S. Nuclear Regulatory Commission 101 Marietta Street, NW. 42900 Atlanta, Georgia 30323 Mr. G. E. Kane, Manager North Anna Power Station P.O. Box 402 Mineral, Virginia 23117 Mr. W. L. Stewart Senior Vice President - Nuclear Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, Virginia 23060 Hr. Michael R. Kansler, Manager Surry Power Station Post Office'Box 166. Route I Surry, Virginia 23883 Mr. Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Senior Vice President Surry Power Station U.S. Nuclear Regulatory Commission Post Office Box 166, Route I Surry, Virginia 23BB3

UNITED STATES NUCLEAR REGULATORY COMMISSION

~JVJ%%1%r1 TO a C SAFETY EVALUATION BY THE OFFICE Of NUCLEAR REACTOR REGULATIQN V1RGINIA ELECTRIC AND POWER CO04PANY SURRY.

UNITS I AND 2 AND NORTH ANNA UNITS I AND 2

=LNO._*_SQ-Z80.

50-281. 50-338, AND 10-319 1.0 I*troductio By letter dated April 9, 1984, the NRC approved an increase In the batch average burnup restriction from 37.000 to 45,000 PWO/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 IMW/NTU, as presently %oeciffed in NRC letter dated April 9, 1984, for both the Surry and North Aniot facilities, and proposed instead to limit the burnup to limits consistent with the NRC safety evaluation report (SER) on a Westinghouse topical rtiort WCAP-10125, entitled Extended Burnup Evaluation of Westinghouse Fuel," which was transmitted to the Westinghouse Electric Corporation by NRC letter dated October I1, 1955.

The staff concludes that it Is acceptable to raise the limit to 50,000 HWD/MTU. or above, as long as the maximum rod average burnup of any fuel rod is no greater than 60 NWD/MTU pursuant to the limits specified in the Fegr3i.l ft~Qiter (S3 FR 6040).

2.0 L*viuat~on The WCAP-10125 report described the models and methodology used in the safety analysis of Westinghouse fuel at extended burnup and discusses the experimental data used to support those models.

As stated in 'he 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:

1. WCAP-1012S 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 identified no burnup-dependent phenomena which would Invalidate the analyses performed..

9312170201 931214 l llM 1i1l 11111 1111 111 1111 Il un mmliiii nmil ill PON ADOC 101 11 1j 9312170201

V

4.

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

The licensee has reviewed the Westinghouse report (WCAP-0125) and has determined that the results are applicable.

The NRC staff performed an Independent analysts of the radi,)Iogical consequences of extended fuel burnup and concluded that, wh'le there would be.

an increased thyroid dose resulting from the 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 SER. NUREG/CR-5009, entitled 'Assessment of the Use rf Extended Burnup Fuel in Light Water Power Reactors,'

was published In febr.,ary 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/IqTU.

3.0 Environmental Conslderations the staff prepared and published an environmental assessment and findi"q of no significant Impact from the use of extended burnup fuel in comiercial light water reactors in the Federal R~gster (53 FR 6040), which concluded that there are no significant adverse radiological or non-radiological impacts associated with the use of extended burnup fuel and that Its use will not significantly affect the quality of the human environment.

Therefore.

pursuant to 10 CFR 51.31, the Commission has determined that an environmental impact stitement need not be prepared for this action.

4.0 Conclusion We have concluded that increasing of the batch average burnup restriction to 50,000 MWD/NTU, or above, as long as the maximum rod average burnup of any fuel rod is no greater than 60 MWO/MTU for the Surry and North Anna facilities, is acceptable.

[mplicit in this evaluation Is that the fuel management scheme will continue to provide the limiting location of fuel during subsequent cycles of operation.

r.Pincipal Contributor:

B. Buckley Date:

December 14. 1993

j UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001

,jenam: z=:1 i o'~

c-,.~

Reed APR2 9 194 Nuclear Licensing April 20, 1994 Docket Nos. 50-280, 50-281 50-338, 50-339 Mr. W. L. Stewart Senior Vice President - Nuclear Virginia. Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, Virginia 23060

SUBJECT:

SURRY, UNITS 1.

AND 2, AND NORTH ANNA, UNITS 1 AND 2 -

REMOVAL OF 45,000 MWD/MTU BATCH AVERAGE BURNUP RESTRICTION (TAC NOS. M87767, 1487768, M87812, AND 1487813)

By NRC letter dated December 4.,

99.3, we.appr.ved..an increase in nthe.batclv.

average burnup restriction-from 45,000 MWD/MTU.(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 MWD/MTU.

The 60,000.MWD/MTU value, in several instances, was inadvertently displayed as 60 MWD/MTU.

The correct value is 60,000 MWD/MTU, Sincerely, Leon B. Engi roject Manager Project Direc ate 11-2 Division of Reactor Projects - I/I1 Office of Nuclear Reactor Regulation Bart C. Buckley, Sr. Project Manager Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:

See next page Ný

.. 1:4

September 9, 1988 MEMORANDUM FOR:

Sholly Coordinator FROM:

Vernon Rooney, Senior Project Manager Project Directorate 1-3 Division of Reactor Projects I/II

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 9ý 1988 Effective date:

30 days frQm dqte of issuance Amendment No.:

108 Facility Operating License No. DPR-28:

Amendment 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.

No significant hazards consideration comments received:

No.

Local Public Document Room Location:

Brooks Memorial Library, 2?4 Main Street, Brattleboro, Vermont 05301.

809150255 860§909 Vernon L. Rooney, Senior Project Manager CF ADOCK 05000271 Project Directorate 1-3 CNU Division of Reactor Projects I/II Distribution:

Docket File, PDI-3 r/f, MRushbrook,

VRooney, RWessman,

~~T~

PDI-3 P D 0/DOT R book VRooney:c-RWessman

/88F2,,----

Page I 0i, I ADAMS Documents as of 0310412015 08:42:09 AM Accession Number 8809190232 Document Date 919/1988 12:00:00AM Estimated Page Count 9 Document Type OPERATING LICENSES & AMENDMENTS TEXT-LICENSE APPLICATIONS & PERMITS Title Amend 108 to License DPR-28,revising Tech Specs to permit use of GE 8X8EB fuel type.

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 5 Document Type CORRESPONDENCE-LETTERS NRC TO UTILITY OUTGOING CORRESPONDENCE Title Forwards Amend 108 to License DPR-28 & safety evaluation. Amend revises Tech Specs to permit use of GE 8X8EB fuel type in response to util 880523 application & 880815, clarification.

Author Affiliation NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)

Author Name ROONEY V L Availability Publicly Available Microform Addresses 46898:054-46898:070 Document Sensitivity Non-Sensitive Package Number 8809190225*

Accession Number 8809190235 Document Date Estimated Page Count Document Type Title Author Affiliation Author Name Availability Microform Addresses Document Sensitivity Package Number 9/9/1988 12:00:00AM SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES TEXT-SAFETY REPORT Safety evaluation supporting Amend 108 to License DPR-28.

NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)

Publicly Available 46898:068-46898:070 Non-Sensitive 8809190225B