ML19350A344

Proposed Tech Spec Changes Re Core Exposure,Affecting Figures 3.5-1 & 3.5-2.Safety Evaluation of Changes Encl

ML19350A344
Person / Time
Site:	FitzPatrick
Issue date:	03/09/1981
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML19350A338	List: ML19350A337 ML19350A341 ML19350A344
References
NUDOCS 8103130560
Download: ML19350A344 (9)

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ATTACHMENT I PROPOSED TECHNICAL SPECIFICATIONS CHANGES RELATED TO CORE EXPOSURE POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 MARCH 9, 1981 81031305(o09 '

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P ATTACHMENT II SAFETY EVALUATION OF CHANGES RELATED TO CORE EXPOSURE POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 MARCH 9, 1981

d Section I - Description of Modification The proposed modification extends MPLHGR limits of 7x7 fuel to 36 GWD/t, thus extending the present limits of 30 GWD/t.

The affected Technical Specification figures are Figures 3.5-1 and 3.5-2 and data for extending them were calculated and supplied

!- by General Electric by letter dated October 21, 1980 (attached).

These new data constitute a revision to the MAPLHGR Tables SA and SB in General E ectric Report NEDO-21662-2. The General Electric data was modified for this application to incorporate penalties of 10% at 30 GWD/t and 20% at 36 GWD/t, as agreed in a telephone conversation with NRC on March 9, 1981.

Section II - Purpose of the Modification During the present operating cycle (Cycle 4) the peak nodal exposure for 7x7 fuel is expected to surpass 30 GWD/t. This modification provides MAPLGHR limits consistent with presently accepted ECCS analysis, which allot operation beyond the present limit of 30 GWD/t.

Section III - Impact of the Change

' The revised extension in MAPLHGR limits are more conservative than the-attached amendment to General Electric report NEDO-21662-2,

" Loss-of-Coolant Accident Analysis Report for James A. FitzPatrick Nuclear Power Plant" (lead plant) which was submitted to the Commission in a letter from George T. Berry to Robert W. Reid, Chief-of Operating Reactors Branch, on July 29, 1977. This report forms the basis of the presently accepted ECCS analysis for the FitzPatrick plant; an SER issued by the Commission on September 16, 1977 references the Power Authority submittal. Thus the proposed modifications will not alter the conclusions reached in the FSAR and SER accident analysis.

Section IV - Implementation of the Modification The modification as proposed will not impact the ALARA or Fire Protection Program at JAF.

Section V - Conclusion r

- The incorporation of these modifications: a) will not increase l the probability nor the consequences of an accident or mal-

' function of equipment important to' safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility for an . accident or malfunction of a dif ferent type than any evaluated previously_in the Safety Analysis Report; and c) will l not reduce the margin of safety as defined in the basis for any Technical Specification, and d) does not constitute an unroviewed safety. question.

Section VI - References L

l (a) JAF FSAR

, (b) JAF SER (c). GE report NEDO-21662-2, " Loss-of-Coolant Accident Analysis

-ReportL for James A. FitzPatrick Nuclear Power Plant"

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GENER AL h ELECTRIC

( AND SERVICES GENERAL ELECTRIC COMPANY.175 CURTNER AVE., SAN JOSE. CALIFORNIA 95125 DIVIS1ON October 21, 1980 NEX: 80-217 Mr. J. M. Clabby Power Authority State of New York 10 Columbus Circle New York, NY 10019

Subject:

Errata and Addenda Sheet No. 2 - LOCA Analysis Report for James A. FitzPatrick Nuclear Power Plant (Lead Plant)

Dear Jim:

Enclosed for your information and use are sixty-five (65) copies of the subject Errata and Addenda Sheet. The purpose of this change is the addition of MAPLHGR limits at 35,000 and 40,000 ped /ST for FitzPatrick Initial Core Fuel types 2 and 3.

Very truly yours,

$$ b C. M. Richards, Manager Fuel Prcjects - Northeast Region M/C 193 - (408) 925-6509 mq Enclosures

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NUCLE AR ENERGY sustNEss GROUP + GE NER AL E LECTRIC COMPANY

• f SAN JOSE, CALIFORNI A 95125 G EN ER AL h ELECTRIC APPLICABLE TO:

NEDO-21662-2 PUBLICATION NO T. i. E NO - SHEET LOCA ANALYSIS REPORT FOR 2 TITLE JAMES A. FITZPATRICK NUCLEAR October 1980 g,7, PO'a'ER PLANT (LEAD PLANT)

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July 1977 publicat:On as specsfor:below.

tSSul O ATE REFERENCES INST RUCTIONS IT E M pjsaacba"pd b Et (coRRECTsoNS AND AcoiTioNS) 01 Page 4-7 Replace with new page 4-7.

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NED0-21662- 2

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Table SA MAPLHCR VERSUS AVERAGE PLANAR EXPOSURE Plant: Fit: Patrick Fuel Type: Initial Core Tvoe 2 Average Planar Exposure MAPLEGR PCT 0xidation OKWd/t) (kW/ft) (OF) Fraction 200 14.9 2198 0.032 1000 14.9 2196 0.031 5000 14.9 2198 0.030 10000 14.6 2199 0.031 15000 14.1 2197 0.075

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20000 13.9 2197 0.075 25000 13.8 2198 0.071 30000 13.3 2189 0.075 35000 12.4 2065 0.050 40000 11.1 1870 0.025 _

Table SB MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Fuel Tree: Initial Core 1N;e 3 P13nt: Fit: Patrick

, I j Average Planar l Exposure MAPLEGR PCT 0xidation l OTWd/t) (kW/ft) (CF) Fraction

..n 200 14.7 2197 0.032 l

l 1000 14.8 2197 0.032 5000 15.0 2197 0.032 l 10000 14.6 2198 0.030 15000 14.1 2199 0.077 20000 13.9 2196 0.077 25000 13.7 2199 0.079 30000 13.1 2198 0.050 35000 11.8 2111 0.068

(,; 40000 10.5 1933 0.035 ,

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