ML17037B529

Letter Regarding a Document Entitled Application for Amendment to Operating License.

ML17037B529
Person / Time
Site:	Nine Mile Point
Issue date:	09/02/1975
From:	LeBoeuf, Lamb, Leiby & MacRae
To:	Rusche B Office of Nuclear Reactor Regulation
References
Download: ML17037B529 (22)

Text

NRC DIS RIBUTION FOR PART 50 DOCKET ERIAL (TEMPORARY FORM)

CONTROL NO:

FILE' ROM. LeBoeuf,Lamb,Leiby & MacR DATE OF DOC DATE REC'D LTR TWX RPT OTHER Washingtori, D C LeBoruf Lamb Leib &MacRae 9>>2-75 9-2-75 XXX TO: ORIG CC OTHER SENTNRC PDR Ben C, Rusche 3 Signed SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NOe XXXX 3 50-220 DESCRIPTION: ENCLOSURES N otarized ltr. 8-29-75, ~ ~ trans the follow Propos'ed Amdt. to 0/L change to Tech Spec; con-ingo. ~ .e I sisting of Revisions to ChangeMinimum Critical Ratio, ~ .Attach."B"-Rod Withdrawal Error

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Certificate of Service "Application for Amdt to Opert. Lic." served yupon Mr, Robert P."Jones Supervisor, Town of Scriba,R,D. (f4, Osewege,:N.Y.';>>

PLANT NAME: Nine Mile Point '$ .i et al ~ ~ ~ ~ ~ ~ " .( 40 cys, Rec'd).

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'RaReatqrg LAW orrICES or LEBOEUF, LAMB,LEIBY8 MACRAE l757 N STREET. N. W, WAsHINGTQN, D. C. 20036 ARVIN E. VIaTON I40 BROADWAY LEONARD M. TROSTKN NEW YORK'.Y. IOOO5 WILLIAM O. DOUB September 2, 19.75 EUGENE B. THOMASt JR.

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CABLE ADDRESS HENRY V. NICKEL II LALALU,WAS H IN GTO N D. C, WASHIHOTDH PARTHEHS TELEX: 440274

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Mr. Ben C. Rusche Director Office of Nuclear Reactor SM9II %et~

Regulation U.S; Nuclear Regulatory Commission Nashington, D.C. 20555 Re: Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No, 1 Dock'et No. 50'-'220'ear Mr. Rusche:

Transmitted herewith are three (3) signed originals and nineteen (19) copies of a document entitled "Application for Amendment to Operating License." This Application seeks to amend Section 3.1.7c of the Technical Specifications set forth in Appendix A to Facility Operating License No, DPR-63 to change the Minimum Critical Power Ratio from 1.24 to 1.25.

Forty (40) copies of the proposed, change in Technical Speci-fications and safety evaluation accompany this Application.

A Certificate of Service showing service of these documents upon the persons listed therein is also enclosed.

Very truly yours, LeBoeuf, Lamb, Leiby NacRae Attorneys for Niagara Mohawk Power Corporati.on

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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION

, Xn the Matter of )

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NIAGARA MOHAWK POWER CORPORATION ) Docket No. 50-220 (Nine Mile Point Nuclear Station )

Unit No. 1) )

CERTIFICATE OF SERVICE I hereby certify that X have served. a document entitled "Application for Amendment to Operating License" by mailing a copy thereof first class, postage prepaid, to the following persons this 2nd day of September, 1975.

Mr. Robert P. Jones Dr. William E. Seymour Supervisor Staff Coordinator Town of Scriba New York State Atomic R. D. 54 Energy Council Oswego, New York 13126 New York State Department of Commerce Miss Juanita Kersey 99 Washington Avenue Librarian Albany, New York 12210 Oswego City Library 120 E. Second Street Oswego, New York 13126 Hop M. Babcock LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Applicant

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

)

NIAGARA MOHAWK POWER CORPORATION)

Docket No. 50-220 (Nine Mile Point Nuclear Station)

Unit No. 1) )

J APPLICATION FOR 'AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission, Niagara Mohawk Power Corporation, holder of Facility Operating License No. DPR-63, hereby requests that Section 3.1.7c of the Technical Specifications set forth in Appendix A to that License be amended. This change is provided in response to the August 14, 1975 letter of request from Hr.

George Lear to Mr. G. K. Rhode. This proposed change has been approved by the Site Operations Review Committee and Safety Review and Audit Board.

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The proposed technical specification change is set forth in Attachment A to this application. The Licensee also transmits as Attachment B a document entitled, "Rod Withdrawal Error Transient Analysis." The proposed change would not authorize any change in the types or any increase in the amounts of effluents or any increase in the authorized power level of the facility.

WHEREFORE, Appl icant respectfully requests that Appendix A to Facility Operating License No. DPR-63 be amended in the form attached hereto as Attachment A.

NIAGARA MOHAWK POWER CORPORATION Gera ld K. Rhode Vice President-Engineering Subscribed and sworn to before me on this'-f day of August, 1975.

Nota y Publtc HAZEL 'J. CARRICK, Notary Pohiic in the Stato of Ncw York Qualified in Onon. Co. No. 4524460

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ATTACHMENT A Niagara Mohawk Power Corporation License No. DPR"63 Docket No. 50"220 Proposed Change to Technical Specifications I tern Loca t ion"- Chanche Limiting Condition Page 64a Change Minimum for Operation 3.l.jc Critical Power Ratio (MCPR) value for 8 x 8 fuel to "> 1.25"

<'he June 27, 1975 "Application of General Electric Thermal Analysis Basis (GETAB)"

submittal proposed the addition of page 64a to the Technical Specifications.

ATTACHMENT B Nine Mile Point Unit 1 Nuclear Power Station Rod Mithdrawal Error Transient Analysis (Supplement to "Application of General Electric Thermal Analysis Basis (GETAB)," June'975)

August 1975

I. Introduction This report presents the results of an analysis of the rod withdrawal error transient for Cycle 3. This information is provided in response to Reference 1 and supplements that in Reference 2.

II. Anal sis of Rod Withdrawal Error Transient Discussion of the rod withdrawal error transient analysis, including assumptions, is presented in Sections 6.2.4 and 6.3.3.2 of Reference 3. A description of input to this analysis is presented in Section IV of Attachment B to Reference 2.

With the rod block setting at 1054, the Cycle 3 rod block response is shown'in Figures 24 and 25 of Reference 4. The worst case HCPR at rod block is determined from the attached Figures 1 and 2.

As a result of this analysis, it is necessary that the 8 x 8 HCPR operating limit be increased to 1.25, in order to avoid violating the HCPR Safety Limit during a postulated rod wl thdrawal error transient.

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.05 0.0 Bundle Location (19,34)

-.05

-.10 Bundle Location (11,34)

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-.20

-.25 NOTE: 0.0 corresponds to 8x8 MCPR operating limit

-. 30 12 16 20 24 28 32 NOTCH POSITION OF TRANSIENT ROD (OUT)

Figure 1. NhP-1 Cycle 3 Notch Position of Transient Rod versus ~MCPR for 7x7 Fuel

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.05 0.0 Bundle Location (13,34)

-0.5 CC cl Bundle Location (17,34)

-.15 2

-.25 NOTE: 0.0 corresponds to 8x8 MCPR operating limit

-.30 0 8 12 16 20 24 28 32 NOTCH POSlTION OF TRANSIENT ROD (OUT)

Figure 2. NMP-1 Cycle 3 Notch Position of Transient Rod versus hMCPR for 8x8 Fuel

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REFERENCES

1. Letter from Mr. G. Lear (Nuclear Regulatory Commi ss ion) to Mr. G. K. Rhode (Niagara Mohawk), August 14, 1975.

2. Niagara Mohawk Power Corporation to United States Nuclear Regulatory Commission, "Application for Amendment to Technical Specifications," June 27, 1975.

3. GE/BWR Generic Reload Application for 8 x 8 Fuel, Supplement 2, May, 1975 (NED0-20360).

4. Letter from Mr. P. D. Raymond (Niagara Mohawk) to Mr. A.

Giambusso (Atomic Energy Commission) dated October 15, 1973.

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