ML20247R779

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Proposed Tech Specs Re Core Spray Sys Surveillance Requirements
ML20247R779
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 05/31/1989
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20247R760 List:
References
NUDOCS 8906070317
Download: ML20247R779 (7)
v • d • e


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I' .

I ATTACHMENT 1 TO JPN-89-036

. PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING CORE SPRAY SYSTEM SURVEILLANCE REQUIREMENTS

New York Power Authority j i

JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 8906070317 890531 PDR ADOCK 05000333 P PDC l

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' ATTACHMENT ll TO JPN-89436 SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING CORE SPRAY SYSTEM SURVEILLANCE REQUIREMENTS (JPTS-86-003) -

New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 l'

L l ;. l.

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Attachment ll to JPN-89-036

~ ' SAFETY EVALUATION Page 1 of 3

1. DESCRIPTION OF THE PROPOSED CHANGES The proposed change to the James A. FitzPatrick Technical Specifications revises Specification 4.5.A.1.b on page 113 and the associated Bases on page 125. The specification is changed from:

" Flow Rate Test - Core Spray pumps shall deliver at least 4,625 gpm against a system head corresponding to a total pump developed head of > 113 psig." _

To read:

" Flow Rate Test - Core spray pumps shall deliver at least 4,625 gpm against a system head corresponding to a reactor vessel pressure of greater than or equal to 113 psi above primary containment pressure."

in the Bases to Specification 3.5.A, "psig" is replaced with " psi above primary containment pressure."

11. PURPOSE OF THE PROPOSED CHANGES The proposed change to the core spray system does not result in any changes to the actual system setpoint or system behavior. The loss-of-coolant accident analysis does not take credit for spray coolant entering the reactor before the internal pressure of the reactor has fallen to 113 psi above primary containment pressure. This is consistent with the change proposed to the core spray pump flow rate test requirements and bases. This change will make the wording of the core spray pump flow rate test requirements consistent with the flow rate test requirements of the other pumps in the Emergency Core Cooling System and does not change the original intent of the Technical Specifications or the FSAR. This change merely corrects the errors which exist in the specifications.

111. IMPACT OF THE PROPOSED CHANGES The loss-of-coolant accident analysis does not take credit for spray coolant entering the reactor before the internal pressure of the reactor has fallen to 113 psi above primary containment pressure. The proposed changes to the core spray pump flow rate test requirements and bases is consistent with the accident analysis and does not change the original intent of the Technical Specifications or the FSAR. This change merely corrects the errors which exist in the specifications.

The acceptence criteria contained in the FitzPatrick inservice Test program for the core spray l pumps assure that the core spray pumps meet the amended Technical Specification requirement. The pumps have always been required to meet the more conservative acceptance criteria as contained in the proposed specification.

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i Attichment 11 to JPN-89-036

,' , SAFETY EVALUATION i Page 2 of 3 IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION I

Operation of the James A. FitzPatrick Nuclear Power Plant in accordance with the proposed amendment would not involve a significant hazards consideration as stated in 10 CFR 50.92, since it would not:

1. involve significant increase in the probability or consequences of an accident previously evaluated. The intent of the proposed change is to clarify and correct the Technical Specifications. The change is purely administrative in nature. There are no setpoint changes, safety limit changes, or changes to limiting conditions for operation. The proposed change assures that the core spray system is tested in accordance with the assumptions contained in the existing accident analyses. This change has no impact on plant safety operations. The change will have no impact on previously evaluated accidents.
2. create the possibility of a new or different kind of accident from those previously evaluated. The proposed change is purely administrative in nature and is intended to clarify and improve the quality of the Technical Specification. The change cannot create the possibility of a new or different kind of accident.
3. involve a significant reduction in the margin of safety. Thc proposed change corrects an error which currenty exists in the Technical Specifications. The change is administrative in nature and will clarify the specifications. This change does not contain any setpoint or safety limit changes regarding isolation or alarms. The proposed change does not affect the environmental monitoring program. This change does not negatively affect the plant's safety systems and does not reduce any safety margins.

In the April 6,1983 Federal Register (48FR14870), NRC published examples of license amendments that are not likely to involve a significant hazards consideration. Example (i) from this Federal Register is applicable to these changes and states:

"A purely administrative change to technical specifications: for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature."

The proposed change can be ciascified as not likely to involve significant hazards considerations, since the change is administrative or editorial in nature and does not involve hardware changes nor any changes to the plant's safety related structures, systems, or components. The proposed change is designed to improve the quality of the Technical Specifications.

V. IMPLEMENTATION OF THE PROPOSED CHANGE implementation of the proposed changes will not impact the AUtRA or Fire Protection Programs at FitzPatrick, nor will the changes impact the environment.

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.* Attachment il to JPN 89-036 SAFETY EVALUATION Page 3 of 3 l

[ VI. CONCLUSION l'

The change, as proposed, does not constitute an unreviewed safety question as defined in 10 CFR 50.59. That is, it:

a. will not change the probability nor the consequences of an accident or malfunction of equipment importald to safety as previously evaluated in the Safety Analysis Report;
b. . will not increase the possibility of an accident or malfunction of a different type from any previously evaluated in the Safety Analysis Report;
c. will not reduce the margin of safety as defined in the basis for any technical specification;
d. does not constitute an unreviewed safety question; and
e. involves no significant hazards consideration, as defined in 10 CFR 50.92.

Vll. REFERENCES

1. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, Sections 6.4.3 and 6.5.2.
2. James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER), dated November 20,1972 and Supplements.

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