ML20246F486

Safety Evaluation Re Amend 126 to License DPR-59

ML20246F486
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Site:	FitzPatrick
Issue date:	05/04/1989
From:	Office of Nuclear Reactor Regulation
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Download: ML20246F486 (2)

Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 126 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333 INTRODUCTION By letter dated June 10, 1988, the Power Authority of the State of New York (PASNY or the licensee), requested changes to Facility Operating License No.

DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The changes would revise the crescent area ventilation Limiting Conditions for Operation (LCO) and the Surveillance Testing requirements of the Technical Specifications (TS) to clarify the requirements and eliminate a conflict in the operability and surveillance testing sections.

DESCRIPTION The portion of the reactor building commonly referred to as the crescent area is located in the lower level and has the shape of a half-moon.

It is divided, functionally, into two halves, with each half containing a major portion of the Residual Heat Removal (RHR) subsystem and the Core Spray (CS) subsystem. Also, one of these areas contains a major portion of the High Pressure Coolant Injection (HPCI) system and the other area contains a major portion of the Reactor Core Isolation Cooling (RCIC) system. Since each area is separated somewhat from the other, it may be considered to be a compartment. However, the whole crescent area may also be considered to be a compartment. Hence, the proposed change to Specification 3.11.B.1 would replace the term " compartment" with the nomenclature " half of the crescent area" to remove this ambiguity and ensure that the LCO is properly understood.

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Another proposed change to TS Section 3.11.B.1 would replace the reference to Specification "3.5.D" with "3.5.B" since Specification 3.5.0 refers to the Automatic Depressurization System (which has no equipment located in the crescent areh) and Specification 3.5.B refers to the Containment Cooling subsystem of the RHR system (which does have equipment located in the area).

The effect of the change is to ensure proper application of the LC0 so that the containment cooling subsystem is declared inoperable if more than one cooler in one-half of the' crescent area is declared inoperable; rather 'than i

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the Automatic Depressurization System.

The proposed change to Specification 4.11.B would eliminate the existing conflict between Specifications 3.11.B.1 and 4.11.B.1 in determining the applicability of the 7-day and 24-hour LCOs when more than one cooler in fg512o2638903o4 p

ADOCK 05ooo333

one-half of the crescent area is inoperable. The proposed amendment deletes the 7-day LCO, retains the 24-hour LCO, and moves the specification from the surveillance section to the LCO section of the TS.

Thus, the more conservative limit is retained and the LC0 is consistent with similar LCOs.

These proposed changes do not change any systems or subsystem and will not alter the conclusions of either the FitzPatrick Final Safety Analysis Report or Safety Analysis Report accident analysis. They are therefore, acceptable.

ENVIRONMENTAL CONSIDERATION This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and a change in the surveillance requirements. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Sec 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

CONCLUSION We have concluded, based on the considerations discussed above, that:

(1)there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Dated: May 4, 1989 PRINCIPAL CONTRIBUTOR:

D. LaBarge i

I 1

l' May 4, 1989 Docket No. 50 333 DISTRIBUTION Docket file EJordan NRC & Local PDRs BGrimes PDI-1 Rdg TMeek (4)

SVarga WJones Mr. John C. Brons BBoger EButcher Executive Vice President - Nuclear Generation CVogan ACRS(10)

Power Authority of the State of New York DLaBarge GPA/PA 123 Main Street OGC ARM /LFMB White Plains, New York 10601 DHagan JJohnson RCapra JCraig

SUBJECT:

ISSUANCE OF AMENDMENT (TAC NO. 68457)

The Comission has issued the enclosed Amendment No.126 to Facility Operating License No. DPR.59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications in response to your application transmitted by letter dated June 10, 1988.

The amendment clarifies the sections dealing with the Crescent Area Ventilation and associated Limiting Condition for Operation and Surveillance Testing inconsistencies.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular bi-weekly Federal Register notice.

Sincerely, Original signed by David E. LaBarge, Project Manager Project Directorate I-1 Division of Reactor Projects, I/II

Enclosures:

1.

Amendment No.126 to DPR_59 2.

Safety Evaluation cc: w/ enclosures See next page

[AMENDTAC68457]

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. Mr. John C. Brons -

James A. FitzPatrick Nuclear 1

Pdwar Authority of the. State of New York Power Plant l

cc:

Mr. Gerald C. Goldstein Ms.~ Donna Ross Assistant General Counsel New York State Energy Office

-Power Authority of the State 2 Empire State Plaza of New York 16th Floor 10 Columbus Circle Albany, New York 12223 New York, New York 10019 Resident Inspector's Office Regional Administrator, Region !-

U.. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Consiission Post Office Box 136 475 Allendale Road Lycoming, New York 13093 King of Prussia, Pennsylvania 19406 Mr. William Fernandez Mr. A. Klausman Resident Manager Senior Vice President - Appraisal James A. FitzPatrick Nuclear and Compliance Services Power Plant Power Authority of the State Post Office Box 41 of New York Lycoming, New' York 13093 10 Columbus Circle New York, New York 10019 Mr. J. ' A. Gray, Jr.

Mr. George Wilverding, Manager Director Nuclear Licensing - BWR Nuclear Safety Evaluation Power Authority of the State Power Authority of the State of New York.

of New York 123 Main Street 123 Main Street White Plains, New York 10601 White Plains, New York 10601

-Mr. Robert. P. Jones, Supervisor Mr. R. E. Beedle Town of Scriba Vice President Nuclear Support R. D. #4 Power Authority of the State Oswego, New York 13126 of New York 123 Main Street White Plains, New York 10601 Mr. J. P. Bayne, President Power Authority of the State of New York Mr. S. S. Zulla 10 Columbus Circle Vice President Nuclear Engineering New York, New York 10019 Pcwer Authority of the State of New York 123 Main Street Mr. Richard Patch White Plains, New York 10601 Quality Assurance Superintendent James A. FitzPatrick Nuclear power Plant' Post Office Box 41-Vice President Nuclear Operations Lycoming,.New York 13093 Power Authority of the State of New York 123 Main Street Charlie Donaldson, Esquire White Plains, New York 10601 Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271

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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.126 License No. DPR-59 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated June 10, 1988, complies with the standards and re as amended (the Act)quirements of the Atomic Energy Act of 1954, and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. 09R-59 is hereby amended to read as follows:

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, (2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No.126 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION ROAAQ.

Pobert A. Capra, Director Project Directorate I-1 Division of Reactor Projects. I/II 1

Attachment-l Changes to the Technical t

Specification.s Date of Issuance: May 4, 1989 1

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ATTACWMENT TO LICENSE AMENDNENT NO.126 FACILITY OPERATING-LICENSE NO DPR-59 DOCKET NO 50-333 Revise Appendit: A as follows:

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.... 9 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 126 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK 1

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l

1 DOCKET N0. 50-333 i

j INTRODUCTION By letter dated June 10, 1988, the Power Authority of. the State of New York (PASNY or the licensee), requested changes to Facility Operating License No.

DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The changes would

{

revise the crescent area ventilation Limiting Conditions for Operation (LCO)

{

and the Surveillance Testing requirements of the Technical Specifications (TS) to clarify the requirements and eliminate a conflict in the operability and surveillance testing sections.

DESCRIPTION The portion of the reactor building commonly referred to as the crescent area is located in the lower level and has the shape of a half-moon.

It is divided, functionally, into two halves, with each half containing a major portion of the Residual Heat Removal (RHR) subsystem and the Core Spray (CS) subsystem. Also, one of these areas contains a major portion of the High Pressure Coolant Injection (HPCI) system and the other area contains a major portion of the Reactor Core Isolation Cooling (RCIC) system. Since each area is separated somewhat from the other, it may be considered to be a compartment. However, the whole crescent area may also be considered to be a compartment. Hence, the proposed change to Specification 3.11.B.1 would replace the term " compartment" with the nomenclature " half of the crescent area" to remuve this ambiguity and ensure that the LCO is properly understood.

]

~

Another proposed change to TS Section 3.11.B.1 would replace the reference to l

Specification "3.5.0" with "3.5.B" since Specification 3.5.0 tefers to the l

Automatic Depressurization System (which has no equipment located in the crescent area) and Specification S.S.B refers to the Conti.inment Cooling subsystem of the RHR system (which does have equipment located in the area).

The effect of the change is to ensure proper application of the LC0 so that j

the containment cooling subsystem is d' clared inoperable if more than one i

e cooler in one-half of the~ crescent area is declared inoperable; rather than

~ '

)

the Automatic Depressurization System.

The proposed enange to Specification 4.11.8 would eliminate the existing conflict between Specifications '3.11.B.1 and 4.11.B.1 in determining the applicability of the 7-day and 24-hour LCOs when more than one cooler in l

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.. one-half of the crescent area is inoperable. The proposed amendment deletes the 7-day LCO, retains the 24-hour LCO, and moves the specification from the surveillance section to the LCO section of the TS. Thus, the more conservative limit is retained and the LC0 is consistent with similar LCOs.

These proposed changes do not change any s) stems or subsystem and will not alter the conclusions of either the FitzPatrick Final Safety Analysis Report or Safety Analysis Report accident analysis. They are therefore, acceptable.

ENVIRONMENTAL CONSIDERATION This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and a change in the surveillance requirements. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Sec S1.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

CONCLUSION We have concluded, based on the considerations discussed above, that:

(1)there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Dated: May 4, 1989 PRINCIPAL CONTRIBUTOR:

D. LaBarge

__-__