ML18143A212

R. E. Ginna - Forwards Copies of Application for Amendment to Operating License

ML18143A212
Person / Time
Site:	Ginna
Issue date:	01/06/1977
From:	LeBoeuf, Lamb, Leiby & MacRae, Rochester Gas & Electric Corp
To:	Case E Office of Nuclear Reactor Regulation
References
Download: ML18143A212 (20)

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',DKSTRPBUTION AFTER ISSUANCE OF OP'r TING LlCENSE NRC'I OAM 195 UA. NUCI 8AR RSQULATQRY COMMISSION DOC@ST NUMBS R (8 7S)

PII 8 NUMBSR NRQ DISTRIBUTION PQR PART 50 OOCKET MATERIAL TO= FROM: OATS QP DOCUMSNT I LaBoeuf, Lamb, Leiby & MacRae 1/6/78 Mr. Edson G>> Case Washington, D C>>

I OATS ASCSIVSD I LeBoeuf, Lamb, Leiby & MacRae 1/9/78

>>'TTSR OTOA IZSD PAQP INPUT POAM NUMBSR QP COPISS APCSIVSD OAIG INANE NCLA5SI P I SD COPY

'ESCRIPTION License No>> DPR g8 Appl for Amen tech specs proposed change concerning operatio of the Ginna plant in connection with the comm-encement of Fuel Cycle 8 ~ >>notorised 1/4/78

.whatt Certificate of Service>> >>and reports

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entitled, "Plant Transient Analysis for the R>>

E>> Ginna Unit 1 Nuclear Pwr Plant" - ZN<<NF-77

-40, 93.>>E>> Ginna Nuclear Plant Cycle 8 Safety Analysis Rept," - XN>>NF<<77-53, and "ECCS Analysis for the R>>E>> Ginna Reactor with ENC WREM-2 RWR Evaluation Model" >> XN>>NF-77-58 (2-P)+(1/2" ) '2-P)

RJL 1/9/78 PLAb~ NAME: R,E>> Ginna Unit No. 1 Qe Cys Ga Heucc. Rec. 4

. t'aep m e e~>vot<ey I cv cea aF sec, &a~'4 SAP EZY FOR ACTION/INFORMATI N BRANCH CHIEF: 7 INTERNAL 0 RI8UTION

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IIIflLIttIlNYIJ+ggg ] goPy LEBOEUFI LAMB, LEIBY 8L MAC RAE I757 N STREET, N.W.

WAsHINGToN, D. C. 20036 TELEPHONE 202 487.7500 CABLE ADDRESS LEON A. ALLEN'R CAMCRON F. MAcRAE 4 RANOALL J. L4BOCUF,JR. I929 l975 CAMKRON F MAcRAE,IK 4 LESWIN,WASNINOTON, D.C.

JOSEPH K.BACHCI.DER.IK AORIAN C. LCIBY I952 I970 CRNEST S. BALLARD JR. GERARO A.MAHER TELEX: 440274 G. S PCTER BERGEII 4

~ SHEILA H. MARSHALL GCOFFRY O. C. BEST JAMES G. McKLROY DAVID P. BICKS JAMES P. McGRANERY,JRP4 07 COCNSCL TAYLOR R. 8 RIG 0 8 PHILIP PALMER McGUIGAN CHARLES N.BURGER JAMES O'MALLKY JR.4 ARVIN C. UPTON THOMAS E.BURKE J. MICHAEL PARISH ROGER D. FKLDMAN44 CUGENE R. FIDELL 4 i JOHN A.RUBY PAUL G.RUSSELL JACOB FRICDLANDER HAROLD M. SEIDEI. I40 BROADWAY DONALD J.GREENE CHARLES P. SIFTON JAMES A.GRECR~II4 HAI.CYON G. SKINNCR NEW YORKsN Y IOOOS JOHN L.GROSE 4 JOSEPH S STRAUSS DOUGLAS W.HAWKS CARL D. HO 8 E LMAN MICHACL IOVENKO 4r~

SAMUEL M.SUGDCN EUGENE 8 THOMAS JR ~ 4 January 6, 1977 TELEPHONE 2I2 289 IIOO JAMES F. JOHNSON, LEONARD M. TROSTEN44 CABLE AOORESS RONALD D.JONES HARRY H.VOIGTi4 LKX K.LARSON44 H. RICHARD WACHTKL LCBWIN,NEW YORK GRANT S.LEWIS GERARD P. WATSON TELCXI 4224IS 4 RESIDENT PARTNERS WASHINGTON OFFICE 4 ADMITTED TO THE DISTRICT OF COLUMBIA BAR ItIA, Mr. Edson G. Case Acting Director +4)CAICII Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Wlashington, D.C. 20555 Re: Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Station, Unit. No. 1 Docket No. 50-244

Dear Mr. Case:

As counsel for Rochester Gas and Electric Corporation, we hereby transmit three (3) signed originals and nineteen (19) copies of a document entitled, "Application for Amendment to Operating License." This Application seeks to amend the Technical Specifications set forth in Appendix A to Provisional Operating License No. DPR-18 to permit operation of the Ginna plant in connection with the commencement of Fuel Cycle 8.

The proposed technical specifications changes are set forth in Attachment A to this Application, and a safety evaluation is set forth in Attachment B. Forty (40) copies of these two documents are transmitted herewith.

Attachment B references a report XN-76-40 and Addendum.

That report is a topical report which was submitted to the NRC by Exxon Nuclear Company in February 1977. Attachment B also refers to a report entitled NR. E. Ginna Nuclear Plant Cycle 8 Safety Analysis Report ' December 1977N prepared by Exxon Nuclear Company,,Inc. (XN-NF-77,.-53).II Forty (40) copies of that report are supplied. he'rewith.

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The report XN-NF-77-53 references in turn three other reports prepared by Exxon Nuclear Company, as follows:

1. XN-NF-77-40,'Plant Transient Analysis for the R. E. Ginna Unit 1 Nuclear Power Plant,"

Novembe 1977;

2. XN-NF-77-58, "ECCS Analysis for the R. E.

Ginna Reactor with ENC WREM-2 PWR Evaluation Model," December 1977;

3. XN-NF-77-52(P), "R. E. Ginna Reload Fuel De-sign," December 1977.

Forty (40) copies of each of these reports are also trans-mitted with this letter. XN-NF-77-52(P), listed above as item (3), contains information of a proprietary and confi-dential nature to Exxon Nuclear Company, Inc. Accordingly, the Applicant requests that XN-NF-77-52(P) be withheld from public disclosure in accordance with Sections 2.790 and 9.5 of the Commission's regulations. The basis for our request for confidential treatment is set forth in detail in the enclosed affidavit of Roy Nilson, sworn to on December 22, 1977.

Finally, a Certificate of Service is also enclosed.

LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation

BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION

)

)

ROCHESTER GAS AND ELECTRIC )

CORPORATION ) Docket. No. 50-244 (R. E. Ginna Nuclear Power ).

Station, Unit. No. 1) )

CERTIFICATE OF SERVICE I hereby certify that I have served a document entitled, "Application for Amendment to Operating License" together with copies of the following documents transmitted with that Application:

1. Attachment A (Proposed Technical Specifications Changes);

2. Attachment B (Safety Evaluation);

3. XN-NF-77-53, "R. E. Ginna Nuclear Plant Cycle 8 Safety Analysis Report," December 1977;

4. XN-NF-77-40, "Plant Transient Analysis for the R. E. Ginna Unit 1 Nuclear Power Plant,"

November 1977;

5. XN-NF-77-58, "ECCS Analysis for the R. E.

Ginna Reactor with ENC WREN-2 PWR Evaluation Model," December 1977;

6. Affidavit of Roy Nilson, December 22, 1977, by mailing copies thereof first, class, postage prepaid to each of the following persons this 6th day of January, 1977:

Mr. Michael L. Slade Dr. Emmeth A. Luebke 1250 Crown Point Drive Atomic Safety and Licensing Webster, New York 14580 Board U.S. Nuclear Regulatory .

Warren B. Rosenbaum,, Esq. Commission One Main Street East Washington, D.C. 20555 707 Wilder Building Rochester, New York 14614 Dr. A. Dixon Callihan Union Carbide Corporation Auburn L. Mitchell, Esq. P. O. Box Y Office of the Executive Oak Ridge, Tennessee 37830 Legal Director U.S. Nuclear Regulatory Mr. Robert N. Pinkney Commission Supervisor Washington, D.C. 20555 Town of Ontario 107 Ridge Road West, Edward Luton, Esq. Ontario, New York 14519 Atomic Safety and Licensing Board Jeffrey L. Cohen, Esq.

U.S. Nuclear Regulatory New York State Energy Office Commission Swan Street Building Washington, D.C. 20555 Core 1, Second Floor Empire State Plaza Albany, New York 12223 Le K. Larson LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and. Electric Corporation

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )

)

Rochester Gas and Electric Corporation ) Docket No. 50-244 (R. E. Ginna Nuclear Power Plant, )

Unit No. 1) )

APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.

Nuclear Regulatory Commission (the "Commission" ), Rochester Gas 6 Electric Corporation ("RGGE"), holder of Provisional Operating License No. DPR-18, hereby requests that the Technical Specifications set forth in Appendix A to that license be amended. This request for a change in the technical specifications is submitted as a result of analysis performed in designing Ginna fuel Cycle 8.

The proposed technical specifications change is set forth in Attachment A to this Application. A safety evaluation is set forth in Attachment B. This evaluation also demonstrates that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level.

4 WHEREFORE, Applicant respectfully requests that. Appendix A to Provisional Operating License No. DPR-18 be amended in the form attached hereto as Attachment A.

Rochester Gas and Electric Corporation By L. D. Whi e, Jr.

Vice President, Electric and Steam Production Subscribed and sworn to before me this +'ay of January, 1978.

SHARON G. CAVALERI NOTARY PUBLIC, State of N.Y., Monroe County c

gy Commission Expires htarch 30, 19~+

ATTACHMENT A Replace Technical Specification pages 3.10-4 and 3.10-8c with the enclosed pages:

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lf the quadrant to average 1.02 but is less than 1.12 power for a tilt ratio exceeds sustained period of 16 without known cause, or if such a I

more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> tilt recurs intermittently reactor power level shall be without known cause, the restricted so as not to exceed 50% of rated power. If the cause of the tilt is determined, continued operation at a power level consistent with 3.10.2.2 above, shall be permitted.

Except for physics test, if the quadrant to average power tilt ratio is 1.12 or greater, the reactor shall be put in the hot, shutdown condition utilizing normal operating procedures. Subsequent operation for the purpose of measuring and correcting the tilt is permitted provided the power level does not exceed 50% of rated power and the Nuclear Overpower Trip "set point is reduced by 50%".

Following any refueling and at least every effective full power month thereafter, flux. maps, using the movable detector system, shall be made to confirm that the hot channel factor limits of Specification 3.10.2.2 are met.

The reference equilibrium indicated axial flux difference as a function of power level (called the target flux difference) shall be measured at least once per equivalent full power quarter. The target flux difference must be updated at least each equiv-alent full power month using a measured value or by interpolation using the most recent measured value and the predicted value at the end of the cycle life.

The target flux difference shall be between +5.0 and

-7.5% at the beginning of cycle life and between +2.0 and -7.5% at the end of cycle life. Linear interpola-tion shall be used to determine values at other times in cycle life.

Except during physics tests, control rod excercises, excore detector calibration, and except as modified by 3.10.2.9 through 3.10.2.12, the indicated axial flux difference shall be maintained within + 5% of the target flux difference (defines the target band '6 on axial flux difference). Axial flux difference for power distribution control is defined as the average value for the four excore detectors. If one excore detector is out of service, the remaining three shall be used to derive the average.

3.-1-0-4 Proposed

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different from those resulting from operation within the target band. The instantaneous consequence of being out'side the band, provided rod insertion limits are observed, is not worse than a 10 percent increment in peaking factor for flux difference in the range

+14 percent to -14 percent (+ll percent to -ll indicated) increasing by +1 percent of each 2 percent percent decrease in rated power. Therefore, while the deviation exists the power level is limited to 90 percent or lower depending on the indicated flux difference.

If, for any reason, flux difference is not, controlled within the + 5 percent band for as long a period as one hour, then xenon distributions may be significantly changed and operation at 50 percent is required to pro-tect against potentially more severe consequences of some accidents.

As discussed above, the essence of the limits is to maintain the xenon distribution in the core as close to the equilibrium full power condition as possible.

This is accomplished, without part length rods, by using the chemical volume control system to position the full length control rods to produce the required indication flux difference.

The effect of exceeding the flux difference band at or below half power is approximately half as great as would be at 90% of rated power, where the effect of it deviation has been evaluated.

The reason fox requiring hourly logging is to provide continued surveillance of the flux difference if the normal alarm functions are out of service. It is intended that this surveillance would be temporary until the alarm functions are restored.

The quadrant power radial power tilt ratio limit assures that the distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during startup testing and periodically during power operation.

The limit of 1.02 at which corrective action is required provides DNB and linear heat generation rate protection with x-y plane power tilts. A limiting can be tolerated before the margin for tilt of 1.025 uncertainity in Fq is depleted. Therefore, the limiting tilt has been 3,.10-8c Proposed

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ATTACHlANT B The R.E. Ginna Nuclear Plant will be refueled in March 1978. The reload will consist of 32 new fuel assemblies supplied by Exxon nuclear Corporation and 89 previously exposed Westinghouse fuel assemblies. Detailed discussions of the safety analysis performed by Exxon Nuclear for reload (Cycle 8) operation are presented in or referenced in the enclosed report, "Cycle 8 Reload Safety Analysis Report", fiN-NF-77-53.

The change to Technical Specification 3.10.2.7 is required to meet the conditions of Power Distribution Control (PDC 1) as described in, "Exxon Nuclear Power Distribution Control for Pressurized Water Reactors", XiV-76-40 and Addendum.

The change to the bases of the Technical Specifications on pages 3.10-8c is required for clarity and to reflect a different methology used by Exxon Nuclear in the nuclear design. The revised basis is consistant with the Nuclear Regulatory Commission's Standard Technical Specifications.

Prior to operation of Cycle 8 a Startup Physics Test Program will be completed. This program will consist of the following:

1. Boron endpoints at all rods out (ARO), D bank in, and D + C bank in.

2. Isothermal temperature coefficient at ARO and D bank in.

3. Differential and integral bank worths for bank D and bank C with D bank in.

4. Zero power flux maps at ARO and D bank in.

5. Full core flux map prior to operation at 50% of rated power.

The results of this test program will be reviewed prior to power operation by the Ginna Station Nuclear Engineer.

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