JPN-98-007, Forwards Application for Amend to License DPR-59,changing Valve of Allowable Containment Rate to 1.5 Percent Day & Assumed Value of Filter Efficiency for SBGT Used in Calculations to Determine Dose Effects to Onsite

Forwards Application for Amend to License DPR-59,changing Valve of Allowable Containment Rate to 1.5 Percent Day & Assumed Value of Filter Efficiency for SBGT Used in Calculations to Determine Dose Effects to Onsite

ML20247F726
Person / Time
Site:	FitzPatrick
Issue date:	02/26/1998
From:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247F730	List: JPN-98-007, Forwards Application for Amend to License DPR-59,changing Valve of Allowable Containment Rate to 1.5 Percent Day & Assumed Value of Filter Efficiency for SBGT Used in Calculations to Determine Dose Effects to Onsite ML20247F779 ML20247F798 ML20247F910 ML20247F948 ML20247F971 ML20247G028 ML20247G064 ML20247G116
References
JPN-98-007, JPN-98-7, NUDOCS 9805200033
Download: ML20247F726 (2)

Text

F 123 Main Street

• White Plains, New York 10S01 914 681.6950 914 2873309 (Fa4 i

h M I

& Orily s'e$*r*ve"eiIeseent and cniet nuciear ottcer February 26,1998 JPN-98-007 United States Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Changes to the Technical Specifications Regarding the Allowed Containment La=hmae Rate (L;) (JPTS-97-0071

Dear Sir:

The New York Power Authority requests an amendment to the Technical Specifications contained in Appendices A and B of Facility Operating License DPR 59 for the James A. i FitzPatrick Nuclear Power Plant. The proposed TS amendment changes the value of the allowable containment leakage rate (L.) to 1.5 percent per day, and changes the assumed value of tne filter efficiency for the Standby Gas Treatment System (SBGT) used in the calculations to determine dose effects to onsite and offsite receptors during a Design Basis Loss of Coolant Accident. Also, an ancillary change is proposed to correct conflicting information in TS section 4.6.C, " Coolant Chemistry".

The change in the allowed containment leakage rate is necessary to correct an NRC identified discrepancy between the James A. FitzPatrick (JAF) Final Safety Analysis Report M.

(FSAR) and the original NRC Safety Evaluation Report for JAF (NRC inspection report 82- E 04.) The NRC item subsequently was closed based on plans for revising the Technical E i Specifications. The Authority did submit, but then withdrew, the amendment. The E- l Authority also requests this amendment because the misapplication of the ILRT and LLRT l acceptance criterion, design leakage rate of (L.) at 0.5% wt/ day versus the value allowed g-by Appendix J, L., has resulted in additional exposure to plant maintenance personnel and g-expenditure of resources by the Authority during testing and maintenance of marginal LLRT E failures.

l The calculations used to determine dose effects to onsite and offsite receptors during a Design Basis Loss of Coolant Accident (References 20 and 21 of TS) were revised. The revision to these calculations support adoption of an allowed containment leakage rate (L .)

of 1.5 percent / day with an assumed SBGT system charcoa; filter efficiency of 90%. The /

previous revision to these calculations were used to support TS amendment 239 (Power Uprate) and assumed a SBGT filter efficiency of 99E }/

i The Authority requests NRC approval of this proposed amendment prior to July 1,1998 in s order to implement the change prior to the upcoming refueling outage currently scheduled )

for Fall 1998. 9805200033 990226 PDR ADOCK 05000333

)

i P' pm ""

t _ _ _ ___-____________-___A

Tha sign:d origirtl of ths Application for Amendm:nt to Op: rating Licensa is enclosed for

filing. Attachments I and ill to this application contain the proposed TS changes and a f- markup of the current TS pages, respectively. Attachment Il contains the Safety l Evaluation. Attachment IV contains history and background information regarding the l licensing basis of the numerical value of primary containment allowable leakage rate (L ,).

I Attachment V contains the supporting calculations and bases for meteorology.

A copy of this application and the associated attachments are being provided to the designated New York State officialin accordance with 10 CFR 50.91.

If you have any questions, please contact Mr. A. Zaremba at (315) 349-6365.

l Very truly yo rs, J. Knubel Senior Vice President and Chief Nuclear Officer att: as stated cc: U.S. Nuclear Regulatory Commission Regional Administrator 475 Allendale Road King of Prussia, PA 19406 Office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. Daniel Dorman, Project Manager Project Directorate I-1 Division of Reactor Projects - l/11 U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 Mr. F. William Valentino, President New York State Energy, Research and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 l

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