ML17037B575

Letter Regarding a Preliminary Review of Application for License Amendment and a Request for Additional Information on Core Cycle 4 Analysis

ML17037B575
Person / Time
Site:	Nine Mile Point
Issue date:	09/17/1975
From:	Lear G Office of Nuclear Reactor Regulation
To:	Rhode G Niagara Mohawk Power Corp
References
Download: ML17037B575 (6)

Text

DISTRIBUTION:

NRC PDR TBAbernathy Local PDR ACRS (16)

SEP 1 c (975 Docket Gray file Docket No. 50-220 ORBN3 Rdg

,KRGoller TJCarter OELD Niagara mohawk Powor Corporation 016E (3)

ATTN: Mr. Gerald K. Rhode . GLear Vice president - Engineering JGuibert 300 Brio Boulevard lUest SATeets Syracuse, New York 13202 RiUoods DFieno Gentlemen: SVarga DEisenhut A preliminary review of your application for license amendmont dated August 18, 1975 indicated that we will require additional information.

Tho requested information is contained in the enclosure.

In order. that we may completo our review on a timely basis and accommodate your earliest anticipated Cycle 4 startup date of November 1, 1975, please submit your written response to the items contained in the enclosure within 14 days following roceipt of this letter.

If you have any questions regarding the requested information, we would be pleased to meet with you.

Sincorely,

/o( 1 Georgo Lear, Chief Operating Reactors Branch 83 Division of Reactor Licensing

Enclosure:

Requested Information on Core Cyclo 4 Analysis Sor Nine hfile Point Unit 1 cc: Soe next page OPPIC2~ ORB( ORB83 SURKAME % JGuibertX f DFieno RIUood s GLear OATS W 9/ /7 /75 9/ /'P /75 9/ f /75 9/ /P /75 FOrm AEC.318 (Rer. 9.$ 5) hZCM 0240 ,4 V 4, OOVCRHM2HT PIIIHTIHO OI'PICRI 107A 424 140

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Niagara Mohawk Power Corporation 2 SEP 1 c gyp CC:

Arvin E. Upton, Esquire LeBoeuf, Lamb, Leiby $ MacRae 1757 N Street, N. W.

Washington, D. C. 20036 Anthony Z. Roisman, Esquire Berlin, Roisman 5 Kessler 1712 N Street, N. W.

Washington, D. C. 20036 Dr. William Seymour, Staff Coordinator New York State Atomic Energy Council New York State Department of Commerce 112 State Street Albany, New York 12207 Oswego City Library 120 E. Second Street Oswego,. New York 13126

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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION CORE CYCLE 4 ANALYSIS FOR NINE MILE POINT UNIT 1

1. Provide the value for the delayed neutron fraction applicable to the beginning and the end of Cycle 4.

2. Provide the design conservatism factors for scram reactivity, Doppler coefficient, and void coefficient (include both values used in Table 6-1).

3. Provide. a statement verifying that the Neutron Effective Void model was used in the calculation of the void coefficient used for Cycle 4.

4. Provide the control rod location used in the development of Figures 6-12 and 6-13 of NED0-20772, "GE-NPR Reload-5 Licensing Submittal for NMP-1 Nuclear Power Station, Unit 1'!, for tho Rod lfithdrawal Error transient analysis.

5. Provide the time in Cycle 4 to which the curves in Figures 6-2 through 6-5, NED0-20772, correspond.

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6, The analysis of the fuel loading error accident (page 6-7 of NEDO-20772) shows"that a localized MCPR of 1.05 would occur in a. misplaced bundle.

Provide an explanation of the consequences of operating with a MCPR less than the Safety Limit of 1.06. Include the radiological consequences, if any.

7. The GETAB transient analysis initial condition parameters, Table 4-4 of NED0-20772, indicate that the initial condition MCPR values used in the transient analyses are lower than the operating limits derived from the analyses. Provide a discussion of how this affects the conservatism of the analyses. Include an explanation of the relationship botween initial MCPR and hMCPR.

8. Provide an explanation of the difference in the GETAB transient analysis initial condition parameters .as prqsenged in Table 4 of your Juno 30, 1975 submittal and Table 4'-..4 of NED0-20772.

9. For the Rod Withdrawal Error transient analysis, provide a curve of APRM channel reading ('-'f initial level) versus control rod position (ft. withdrawn) for the case where no LPIN's are bypassed.

10. Pxovide an explanation for the difference in the void fraction values in Tables 5-1 and 6-1, NED0-20772.