ML20247F779

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

ML20247F779
Person / Time
Site:	FitzPatrick
Issue date:	02/26/1998
From:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
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
NUDOCS 9805200046
Download: ML20247F779 (1)

Text

' ~ BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION in the matter of )

NEW YORK POWER AUTHORITY ) Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant )

APPLICATION FOR AMENDMENT TO OPERATING LICENSE The New York Power Authority requests an amendment tc the Technical Specifications contained in Appendices A and B to Facility Operating License DPR-59 for the James A.

FitzPatrick Nuclear Power Plant. This application is filed in accordance with Section 10 CFR 50.90 of the Nuclear Regulatory Commission's regulations.

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 the 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 leckage rate is necessary to correct an NRC identified discrepancy between the James A. FitzPatrick (JAF) Final Safety Analysis Report (FSAR) and the original NRC Safety Evaluation Report for JAF (NRC inspection report 82-04.) in addition, the Authority requests this amendment because the misapplication of the ILRT and LLRT acceptance criterion, design leakage rate of (L,) at 0.5% wt/ day versus the value allowed by Appendix J, L., has resulted in unnecessary exposure to plant personnel and expenditure of resources by the Authority.

The calculations used to determine dose effects to onsite and offsite receptors during a Design Basis Loss of Coolant Accident (Referer ces 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 charcoal filter efficiency of 90E The previous revision to these calculations were used to support TS amendment 239 (Power Uprate) and assumed a SBGT filter efficiency of 99E Attachments I and ll1 to this application contain the proposed TS changes and a markup of the current TS pages, respectively. Attachment il contains the Safety Evaluation.

Attachment IV contains history and background information regarding the licensing basis of the numerical value of primary containment allowable leakage rate (L ). Attachment V contains the supporting calculations and bases for meteorology.

New York Power Autho ity STATE OF NEW YORK COUNTY OF WESTCHESTER

/ Subscribed and swor o before me thiscM day o ru e 1998.

J/Kn6 bel /

/ Senior Vice President and ,

Chief Nuclear Officer w,- ,[

MLMIN E. O'CONNO Notaryfu~blic U Notary Ptets, State of New Yort  !

No.4991062 QueNHed hhchester Co Commiesten Rigbos January 21, 9805200046 980226 PDR ADOCK 05000333 P PDR