Text

Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads
	ML20202D402
Person / Time
Site:	FitzPatrick
Issue date:	02/06/1998
From:	; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
Shared Package
ML20202D381	List: JPN-98-004, Forwards Application for Amend to License DPR-59,revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads; ML20202D388; ML20202D402;
References
	NUDOCS 9802170074
	Download: ML20202D402 (9)
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Att: chm:nt I to JPN 98 004 i

, REVISED TECHNICAL SPECIFICATION PAGES PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING REACTOR PROTECTION SYSTEM (RPS) NORMAL SUPPLY ELECTRICAL PROTECTION ASSEMBLY (EPA) UNDERVOLTAGE TRIP SETPOINT (JPTS 97-003) l l

9802170074 980236^

PDR ADOCK 05000533 P PDR New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No.'50-333 DPR-59

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JJSFNPP ,

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3.9 (cont'd) 4.9 L (cont'd) !

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'3. From and after the time both power supplies are made or found .-

l

- inoperable the reactor shall be brought to cold condehon withirr 24. -l

' hours. l G. REACTOR PROTECTION SYSTEM ELECTRICAL G. REACTOR PROTECTION SYSTEM ELECTRICAL PROTECTION ASSEMBLIES . PROTECTION ASSEMBLIES -

Two RPS electrical predection assemblies for each inserwce RPS The RPS electncal protection assemblies instrumentahon'shall MG set and inservice attemate source shall be operable except be determi.'ed operable by:

as specified below- -

.1. Performmg a channel funchonal test each time the plant is in

1. ' With one RPSl electrical protection assembly for an - cold shutdown fer a penod of more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , unless inservie RPS MG set or an inservice attemate power performed ir. the previous 6 months.

supply inoperable, resto e the inoperable channel to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or remove the associated 2.1 Once per 24 months, dema.4.inig the operabshty of RPS MG set or attemate power supply from service. over-voltage, under-voltage'and under-frequency protechve instrumentation by performance of a ch.6 ciel calibrahon 2.' With two RPS electrical protection assemblies foi an :includmg simulated automahc actuation of the protective inservice RPS MG set or an inservice attemate power relays, tnppng logic and output cecust breakers and supply inoperable, restore at least one to operable status venfymg the followmg setpomts-within 30 minutes or remove the associated RPS MG set or--

attemate power supply from service. .RPS MG SET SOURCE

)

OVER-VOLTAGE : s132V s4 second Time Delay UNDER-VOLTAGE 2112.5V for "A" Channel 2113.9V for "B" Channel

~s 4 second Time Delay UNDER-FREQUENCY 257Hz-s4 second Tune Delay Amendment No. 41,79,199,233- (contoued on page 222d) -

222c

Attacnment !! to JPN 98 004 SAFETY EVALUATION PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING REACTOR PROTECTION SYSTEM (FiPS) NORMAL SUPPLY ELECTRICAL PROTECTION SYSTEM (EPA) UNDERVOLTAGE TRIP SETPOINT (JPTS-97-003)

New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50 333 o , . -

, Att:chment ll to JPN 98-004 SAEETY EVALUATION

~

i PROPOSED TECHNICAL SPECIFICATION CHANGES

!* REGARDING REACTOR PROTECTION SYSTEM (RPS) l NORMAL SUPPLY ELECTRICAL PROTECTION ASSEMBLY (EPA)

UNDERVOLTAGE TRIP SETPOINT (JPTS 97-003)

1. DESCRIPTION OF THE PROPOSED CHANGES f

The following are proposed changes to the James A. FitzPatrick Technical Specifications.

Paae 222c Specification 4.9.G.2 has been revisec. The undervoltage value for the RPS MG Set source has changed from 1112.3V to 2112.SV for Channel "A" 2113.9V for Channel "B" P. PURPOSE OF THE PROPOSED CHANGES The proposed change revises the RPS-EPA undervoltage trip setpoint as a result of a re".'alysis based on the most limiting voltage requirement of the applied loads.

Ill. SAFETY IMPLICATIONS OF THE PROPOSED CHANGES Char.aes to the RPS Normal Sucolv EPA Undervoltaae Trio Settina in SR 4.9.G.2 A calculation (Reference 1) was performed to determine the total channel uncertainties associated with the Normal RPS EPA trip setpoints over a 24-month operating cycle.

This calculation also considered the results of a voltage drop evaluation performed on the RPG system (Reference 2). Based on the results of this calcu!ation, the RPS MG Set Source Undervoltage (UV) setpoird specified in SF 4.9.G.2 requires revision frr its present value 2112.3V to 2112.5V for the "A" channel and 2113.9V for the "B" channel. The field trip setpoint for the Normal RPS EPA UV trip has been raised to address the issue of voltage drop, however, the setpoint specified in SR 4.9.G.2 requires revision to correct the present Technical Specification limit. The new setpoint was calculated using the methodology of Reference 3. The referenced calculations are included as an Attachment to this submittal.

The RPS instrumentation bus is a 120 VAC power distribution bus which mainly supplies power to instrument power supplies and normally energized relay coils and solenoids.

The EPA trip settings have time delays to prevent transients from de-energizing the bus.

Page 1 of 4 l

Attachm:nt ll ts JPN 98-004

. SAFETY EVALUATION PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING REACTOR PROTECTION SYSTEM (RPS)

NORMAL SUPPLY ELECTRICAL PROTECTION ASSEMBLY (EPA)

UNDERVOLTAGE TRIP SETPOINT (JPTS 97-003)

The Reference 2 calculation analyzed the impact of the voltage drop from the EPAs to the scram pilot valv9 solenods and other relays, based on actual voltage measurements taken at RPS System loads. The calculation concluded that the RPS scram pilot valve solenoids are the components that require the highest minimum voltage to ensure proper operation. Due to the location of the Normal supply EPAs (Turbine Building Electric Bays), the feeder cable run between the supply and the scram pilot valve solenoids results in a significant voltage drop. The voltage drop assessment calculated the "A" and "B" channels separately due to their applicable differences.

The calculation has determined that the minimum UV trip values to assure the Normal '

supply EPAs provide minimum allowable voltage at the scram pilot valve solenoids are 112.5 and 113.9 vo"s for the "A" and "B" side EPAs respectively.

The proposed Normal Supply EPA UV setpoint ensures adequate protection for the RPS, and other essential components, from undervoltage conditions on the RPS power supplies. These changes are necessary to correct the Technical Specification setpoint that did not adequately consider allowances for temperatura effect uncertainty associated with determining the minimum allowabie - age for the RPS instrument buses.

The proposed instrument setpoint changes ensures that plant safety limits are not exceeded for the must limiting voltage requirements. The type of testing and the corrective actions required if the subject surveillances fail remains the same. The proposed changes do not advarsely affect the reliability of these systems or affect the ability of the systems to meet their design obje@es. A historical review of surveillance test results supports these conclusions.

IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATIOM Operation of the FitzPatrick plant in accordance with the proposed Amendment would not involve a significant hazards consideration as defined in 10CFR 50.92, since it would not:

1. involve a significant increase in the probability or consequerces of an accident previously evaluated.

TI e proposed setpoint change evaluated in Section lit does not involve any physical changes to the plant, does not alter the way these systems function, and will not degrade the performance of the plant safety systems. The proposed instrument setpoint changes ensures that plant safety limits are not exceeded for the most limiting voltage requirements. The type of testing and the corrective actions required if the subject surveillances fait remains the same. The proposed changes do not adversely affect the reliability of these systems or affect the Page 2 of 4

Att:chmt nt il t2 JPN 98-004 -

, SAFETY EVALUATION PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING REACTOR PROTECTION SYSTEM (RPS)

NORMAL SUPPLY ELECTRICAL PROTECTION ASSEMBLY (EPA)

UNDERVOLTAGE TRIP SETPOINT (JPTS 97403) ,

ability of the systems to meet their design objectives: A historical review of surveillance test results supports these conclusions.

2. create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed setpoint change evaluated in Section lli does not modify the 0 design or operation of the plant, therefore, no new failure modes are introduced.

The proposed instrument setpoint change ensures that plant safety limits are not exceeded for the most limiting voltage requirements. No changes are proposed to the type and method of testing performed. A historical review of surveillance tc,st results suppoits these conclusions,

3. . Involve a significant reducticn in a margin of safety.

The proposed setpoint change evaiuated in Section lll results in minimal impact l= on system reliability in the interval between surveillance tests. This is based on the redundant design of the evaluated systems. A review of past surveillance history has shown no evidence of failures which would significantly impact the reliability of these systems. Operation of the plant remains unchanged by this proposed setpoint change. The assumptions in the Plant Licensing Basis are not adversely impacted. Therefore, the proposed changes do not result in a I significant reduction in the margin af safety.

- VI. IMPLEMENTATION OF THE PROPOSED CHANGE implementation of the proposed changes will not adversely affect the ALARA or Fire Protection t)rograms at the FitzPatrick plant , nor will the changes affect the environment.

Implementation of this proposed Amendment requires changes to the RPS EPA undervoltage trip setpoir.ts. The affected setpoints have been identified in Section lli of

- the safety evaluation.

Vll. 'CONCLUSlQR The Plan Operating Review Committee (PORC) and ti;e Safety Review Committee (SRC) have reviewed these proposed changes to the Technical Specifications and have concluded that they do not involve an unreviewed safety question, or a significant hazards consideration. and will not endanger the health and safety of the public.

Page 3 of 4 i

Att=hm:nt il to JPN-98-004

. SAFETY EVAf.UATION PROPOSED TECilNICAL SPECIFICATION CHANGES REGARDING REACTOR PROTECTION SvSTEM (RPS)

NORMAL SUPPLY ELECTRICAL PROTECTION ASSEMBLY (EPA)

UNDERVOLTAGE TRIP SETPOINT (JPTS-97-003)

Vill REEERENCES 1.- NYPA Calculation JAF-CALC-ELEC-00757, Revision 8, " EPA for Normal Supply Feeder Channe' Uncertainty and Setpoint Calculation"

2. NYPA Calculation JAF-CALC-RPS-01516, Revblon 2, "RPS Voltage Drop Assessment"

3. NYPA Engineering Standard IES-3A, Revision 1," Instrument Loop Accuracy and Setpoint Calculation Methodology (JAF)"

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a Page 4 of 4

Attzhm:nt lil to JPN 98-004 0

, MARKUP OF TECHNICAL SPECIFICATION PAGE CHANGES PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING REACTOR PROTECTION SYSTEM (RPS) NORMAL SUPPLY ELECTRICAL PROTECTION ASSEMBLY (EPA) UNDERVOLTAGE TRIP SETPOINT (JPTS-97-003)

F k

I New York Power Authority JAMF.S A. FiTZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 ,

l

h- _

JAFNPP 3.9 (cont'd) 4.9 icent'd)

3. From and after the time both power supphes are made or found inoperable the reactor shall be twougl.1 to cold condit:en within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

G. IREACTOft PROTECTION SYSTEM ELECTitiCAL FflOTEC760N G. ftEACTOR PROTECTION SYSTEM ELEC7ftiCAL PftOTECTION ASSEhW.lES m l Two RPS electrice@otection seasaddies for sech inserwce The RPS electrical protection assembios instrumentation WmH RPS MG se end inservice allemste source shed be oporrble be detemuned opers%Io by:

eacept se W below:

1. Performing a dunnel functional test each tier.a the plant is

1. With one RPS electrical prote: tie i assembCy far an in cold shutdown for a period of srere stan 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , inoervice flPS MG set er an insensics alterrate power unless performed in the previous S months.

supply inoperable, testore the inoperal4e channel to operable statue within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or renuw Go aseecleted 2. Once por 24 months, demonstrating the operability of g.. u,*r l R t .ornet. - .uppi, from ser . .go .r urider. .-

protective instrumentation by performance of a chonnel a 2. With two RPS electrical protectien ensembnes for en calilwetka including semdeted automatic actuagion of tiis inservice RPS MG set or an Inserwh:e altomete power protective releys, tripping logic and output circpit supply inoperaldo, restore et least one ta o oerelde status ' tweakers and verifying the following setpoints: 5 within 30 minutes or remove the associates RPS MG set or attemete power supply from sorwice. IIPS MG SET SOURCE OVER-VOLTAGE 5132V s4 second Time Delay

> tt?..Sv Qv

'A UNDER-VOLTA 112.3V[

s4 second Time ossey

,, g. s -

1 11'b.3 V g 'g UNDER-FREOUENCY a:57Hz 54 second Twne Delay

_ ) 1 (conth on page 222dl Amendment No. C, ?S, ?S?,

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ML20202D402

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