ML20151M855
| ML20151M855 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/29/1988 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML19292J200 | List: |
| References | |
| JPN-88-037, JPN-88-37, NUDOCS 8808080023 | |
| Download: ML20151M855 (2) | |
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-o-July 29,1988 JPN-88-037 U.S. Nuclear Regulatory Commission Mai! Station PI-137 Washington, D.C. 20555 ATTENTION: Document Control Desk
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Change to the Technical Specifications Regarding Reload 8/C3cle 9 (JPTS-88-016) i
Reference:
NYPA letter, J. C. Brons to D. R. Muller (NRC), JPN-86-63, dated Decernber 23, 1986, regarding Reload 7/ Cycle 8 Technical Specifications.
Dear Sir:
)
This application for an amendment to the James A.
FitzPatrick Technical Specifications proposes changes necessary to support plant operation after the Reloed 8/ Cycle 9 refueling outage. During this outage,184 fuel bundles are to be removed from the reactor core and replaced by new fuel. This represents approximately 1/3 of the fuel bundles now in the FitzPatrick core.
The changes to the Technical Specifications involve deleting specifications associated with the discharged fuel and with Cycle 8 specific analyses. Specifications appropriate for the new fuel and which are based on Cycle 9 specific analyses are added incorporating a reduction to the fuel cladding integrity safety limit. The NRC has previously approved this change on a generic basis for GE fueled BWR plants.
The four Westinghouse QUAD + lead test assemblies inserted as part of Relead 7 will remain in the FitzPatrick Cycle 9 core. They will be operated in accordance with the same constraints that applied during the last operating cycle with the exception that adjacent control rods may be inserted at power for some portion of the operating cycle.
This does not represent a deviation from the NRC approvt use of the QUAD +
assemblies, since the rod insertion constraint was only applicable during the first cycle of irradiation.
These changes to the Technical Specifications are required for the start-up following the 1988 refueling outage currently scheduled to begin August 28, 1988.
Therefore, the Authority requests that this application be approved by October 31, 1988.
Enclosed for filing is the signed original of a document entitled "Application for Amendment to Operating License," with Attachments I,11,111, and IV thereto, comprising a statement of the proposed changes to the Technical Specifications, the 8808080023 880729 d Mf g gp gDR ADOCK 0500 3
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Enclosed for filing is the signed original of a document entitled "Application for Amendment to Operating License," with Attachments I,11, III, and IV thereto, comprising a statement of the proposed changes to the Technical Specifications, the associated Safety Evaluation, and two (2) reports from the General Electric Company.
The two reports are entitled: "Supplemental Reload Licensing Report for James A.
FitzPatrick Nuclear Power Plant - Reload 8 (Cycle 9)," and "James A. FitzPatrick Nuclear Power Plant SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis -
Errata and Addenda No. 2."
The General Electric Report, "James A.
FitzPatrick Nuclear Power Plant SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis - Errata and Addenda No.
2," included as Attachment IV to this application contains information which General Electric customarily maintains in confidence and withholds from public disclosure.
This information has been handled and classified as proprietary to General Electric as indicated in the affidavit previously submitted to the NRC as Attachment V to Reference 1, and the Authority hereby requests that this report be withheld from public disclosure in accordance with the provisions of 10 CFR 2.790.
In accordance with 10 CFR 170.12, a check in the amount of $150.00 is enclosed as payment of the application fee for the review of the proposed changes to the Technical Specifications, in accordance with 10 CFR 50.91, a copy of this application and the associated attachments are being provided to the designated New York State official.
Should you or your staff have any questions regarding the proposed changes, please contact Mr. J. A. Gray, Jr. cf my staff.
Very truly yours, tw ohn rons Executive Vice President Nuclear Generation l
CC; U.S. Nuclear Regulatory Commission Mr. liarvey Abelson 475 Allendale Road Project Directorate I I l
King of Prussia, PA 19406 Division of Reactor Projects - 1/11 U.S. Nuclear Regulatory Commission Office of the Resident inspector Mail Stop 14 B2 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 P.O. Box 136 I
Lycoming, NY 13093 Ms. Donna Ross i
Division of Policy Analysis and Planning i
Empire State Plaza Building Number 2 - 16* Floor 3
Albany, New York 12223 i
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