ML20093E260

Proposed Tech Spec Changes Re Instrumentation That Initiates Recirculation Pump Trip

ML20093E260
Person / Time
Site:	FitzPatrick
Issue date:	10/09/1984
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20093E236	List: ML20093E233 ML20093E247 ML20093E260
References
JPN-84-65, NUDOCS 8410120033
Download: ML20093E260 (6)

Text

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ATTACHMENT I to JPN-84-65 PROPOSED TECHNICAL SPECIFICATION CHANGES

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INSTRUMENTATION THAT INITIATES ,

RECIRCULATION PUMP TRIP [

(PTS-84-17) i i

I NEW YORK POWER AUTHORITY JAMES A. FIT 1 PATRICK NUCLEAR POWER PLANT t DOCKET NO. 50-333 t ., i l

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JAFNPP TABLE 3.2 INSFfRUMENTATION 'IHAT INITIATES RECIRCULATION PUMP TRIP

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Minimum Number of Total Nunber of Instrument Operable Instrument. Channels Provided by Channels-per trip Design for Both System (1) Instrument' Trip Level Setting Channels . Action 1 Reactor High Pressure < 1120 psig 4 (2) l 1 Reactor Low-I m - >-38 in indicated 4 (2)

Water Level level ( 2 126.5 in, above the top of active fuel)-

Notes for Table 3.2-7

1. Whenever the reactor is in the run mode, there shall be,one '

operable trip system fo'r each paramater for each operating _ . ,

recirculation pump. From and aftep the time it is found that '

this cannot be met, the indicated action shall be~taken.

2. Reduce power and place the lede 3 elector-Switch in a Mode other than the Run Mode within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. _

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ATTACHMENT II to JPN-84 -65 SAFETY EVALUATION ~

t RELATED TO INSTRUMENTATION THAT INITIATES RECIRCULATION PUMP TRIP (PTS-84-17) u 3

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. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 4

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Section I - Description of the Change The change: proposed revises Table 3.2-7 (" Instrumentation That  !

Initiates Recirculation Pump Trip") on Page 77 of Appendix A to the FitzPatrick Operating: License. The trip. level setting associated with the reactor high pressure' instrument is changed from " > 1120

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psig" to " $ 1120 psig".

Section II - Purpose of the Chance The purpose of.this change is to correct an error on Table 3.2-7

'that was apparently introduced in the initial issuance of the Technical Specification-(Appendix A).

In NEDO-10349 (Reference a), the General Electric Company Analyzed the potential consequences of an' anticipated transient without scram (ATWS) event.. This report specifically addresses the shutdown effects' inherently associated with a reduction in-reactor coolant flow.(recirculation pump. trip). NEDO-10349 analyzed the most severe transients at various ATWS. conditions with "...the additional function;of automatically. tripping (shutting off) the recirculation pumps whenever there was a conincidential occurance of: a. Neutron Flux' Trip-Level and, b.- Vessel Pressure 1150 psig." This. report concluded that the recirculation pump trip function is "quite effective in keeping reactor power, pressures and temperatures well

-below appropriate safety limits."

Section 3.2.G (" Recirculation Pump. Trip") on Page 54 and the ,

associated bases on Page 60 both state that the purpose of this recirculation pump trip is to limit the potential' consequences of a failure to scram during an anticipated transient (ATWS).

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? As-the'. existing Technical Specifications are written, this table requires'that=the instruments used to detect high reactor-pressure '

forethe purpose of initiating a recirculation pump trip have a setpoint. greater than or equal to 1120 psig. This incorrectly 1 1 establishes a : lower limit for this setpoint. The intent of.the recirculation pump-tripLi,s to provide.a means of reducing reactor power in the event of a failure-to-scram. This table should

correctly' establish an upper reactor. pressure limit;. exceeding this nsetpoint will trip the recirculation pumps thereby reducing reactor

. power and consequently, reactor pressure.  !

, This error was discovered in August, 1984 during routine review-of  ;

-plant modification documents. Before the error was' discovered, a ,

setpoint of ll35'psig was used; soon after>the error'was.-discovered,.

1the setpoint was readjusted to approximately 1112 psig.

NoEsignificant safety hazard existed prior to the discovery and-subsequent correction of this setpoint because plant procedures assure that'atono time was the 1150 psig value used in NEDO-10349

< exceeded, while setting the high reactor pressure recirculation pump-trip;.setpoint.

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It appears that this error was introduced during the preparation of the original issuance of the FitzPatrick Technical Specifications because no amendments have been issued by the NRC for Page 77.

Calibration procedures for this setpoint were prepared from the approved Technical Specifications; this resulted in the establishment of the incorrect setpoint.

The Authority discussed this error with the FitzPatrick NRC Project Manager on August 1, 1984. During these telephone conversations, we were informed that the NRC staff agreed that Table 3.2-7 was incorrect and that " 2, 1120 psig" should be changed to read I 1120 psig".

Section III - Impact of the Changes The proposed changes to the Technical Specifications do not change any system or subsystem and will not alter the conclusions of either the FSAR or SER accident analysis. The Authority considers that-this proposed amendment can be classified as not likely to involve significant hazards considerations since the change constitutes a correction to the Technical Specifications. This is clearly in keeping with example (i) included in Federal Register, Vol. 43 No.

67 dated April 6, 1983 Page 14870, (examples of amendments that are considered not likely to involve significant hazards consideration which states: "(i) A purely administrative change to technical specifications: for example, ... correction of an error, ... ")

Section IV - Implementation of the Changes The proposed changes will not impact the Fire Protection Program at the JAF plant nor will the changes impact the environment.

Section V - Conclusion The incorporation of these changes: a) will not change the probability nor the consequences of an accident or malfunction 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 different type than any evaluated previously in the safety Analysis Report; c) will not reduce the margin of safety as defined in the Bases for any Technical Specification; d) does not constitute an unreviewed safety question; and, 3 ) involves no signification hazards considerations, as defined in 10 CFR 50.92.

Section VI - References

a. General Electric Licensing Topical Report " Analysis of Anticipated Transients without SCRAM", NEDO-10349 dated March 1971.

b. James A. FitzPatrick Nuclear Power Plant Updated Final Safety AnLlysis Report (PSAR), Revision 2 dated July 1984.

c. -James A. Fitzpatrick Nuclear Power Plant Safety Evaluation dated March 3, 1970, AEC~ Division of Reactor Licensing.

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