ML20112D272

Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements

ML20112D272
Person / Time
Site:	FitzPatrick
Issue date:	05/30/1996
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20112D262	List: JPN-96-026, Forwards Application for Amend to License DPR-59,revising ATWS Recirculation Pump Trip Reactor Pressure for High Setpoint,Either Zero or Safety Relief Valves Out of Svc ML20112D267 ML20112D272
References
NUDOCS 9606040186
Download: ML20112D272 (14)

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l Attachm:nt I to JPN-96-026 i REVISED TECHNICAL SPECIFICATION PAGES PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING AIWS RECIRCULATION PUMP TRIP INSTRUMENTATION REQUIREMENTS i l

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l New York Power Authority  ;

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 l

9606040186 960530  :

PDR ADOCK 05000333 f P PDR

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TABLE 32-7 ATWS RECIRCULATION PUMP TRIP INSTRUMENTATION REQUIREMENTS Minimum Number of Operable Instrument Channels Per Trip System (Notes 1 & 2) Trip Function Trip Level Setting Applicable Modes 2 Reactor Pressure - High s 1120 psig, or Run s 1155 psig (Note 3) 2 Reactor Water Level - Low Low 2126.5 in. Run above TAF Amendment No.-997-76a

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' TABLE 3.2-7 (cont'd) ,

ATWS RECIRCULATION PUMP TRIP INSTRUMENTATION REQUIREMENTS ,

l NOTES FOR TABLE 3.2-7 -

1. There shall be two operable or tripped trip systems for each Trip Function, except as_ provided for below: i I

a. For each Trip Function with one less than the required minimum number of operable instrument channels, place the inoperable instrument channel and/or its associated trip system in the tripped condition

• within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Otherwise, place the reactor in the start- ,

up/ hot standby mode within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. For each Trip Function with two or more channels less than the required minimum number of operable instrument channels:

1) Within one hour, verify sufficient instrument channels remain operable or tripped

• to maintain trip capability in the Trip Function, and -

2) Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, place the inoperable instrument channel (s) in one trip system and/or that trip system" in the tripped condition *, and j

3) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, restore the inoperable instrument channel in the other trip system to an operable status. i If any of these three conditions cannot be satisfied, place the reactor in the start-up/ hot standby mode within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

An inoperable instrument channel or trip system need not be placed in the tripped condition where this would cause the Trip Function  !

to occur. In these cases, if the inoperable instrument channel is not restored to operable status within the required time, place the reactor in the start-up/ hot standby mode within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

• • This action applies to that trip system with the greatest number of inoperable instrument channels. If both systems have the same number of inoperable instrument channels, the ACTION can be applied to either trip system. ,

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2. When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Limiting ,

Conditions for Operation and required actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Trip Function maintains ATWS RPT initiation capability.

Amendment No.

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TABLE 3.2-7 (cont'd)

ATWS RECIRCULATION PUMP TRIP INS _IRUMENTAILQN_BEQU1BEMENIS NOTES FOR TABLE 3.2-7 (cont.)

3. The ATWS Reactor Pressure High Recirculation Pump Trip setpoint shall be s 1155 psig when either zero or one SRVs are out of service. The setpoint shall be s 1120 psig when two or more SRVs are out of service.

Amendment No.

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Attachment ll to JPN-96-026 l 1

i SAFETY EVALUATION FOR j PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING ATWS RECIRCULATION PUMP TRIP. INSTRUMENTATION REQUIREMENTS  !

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

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. Attachm*.nt 11 to JPN-96-026 SAFETY EVALUATION PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING ATWS RECIRCULATION PUMP TRIP INSTRUMENTATION REQUIREMENTS

1. DESCRIPTION OF THE PROPOSED CHANGES The following proposed changes to the James A. FitzPatrick Technical Specifications l establish a revised ATWS Recirculation Pump Trip Reactor Pressure - High setpoint {

when either zero or one Safety Relief Valves (SRVs) are out of service. l Page 76a Change Trip Level Setting for Reactor Pressure - High to "s 1155 psig, or s 1120 psig (Note 3)" in Table 3.2-7. Delete lines stating, " NOTES FOR TABLE 3.2-7 See next page for Notes 1 and 2."

Eage 76b l l

Add a new page 76b which contains the text presently on page 77.

l Page 76c Add a new page 76c which contains the headings of present page 77 along with new note 3. Text for note 3 is, "The ATWS Reactor Pressure High Recirculation Pump Trip l setpoint shall be s 1155 psig when either zero or one SRVs are out of service. The '

setpoint shall be s 1120 psig when two or more SRVs are out of service."  !

Page 77 Replace text on page 77 with "This page intentionally blank."

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II. P_URPJSE OF THE PROPOSED CHANGES i

The purpose of the proposed changes is to limit the potential for reactor water  !

recirculation (RWR) pump trips on high reactor pressure vessel (RPV) pressure. This will limit the potential for rapid RPV lower head cooldown associated with loss of forced circulation.

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, Att:chment 11 to JPN-96-026 J

SAFETY EVALUATION

PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING ATWS RECIRCULATION PUMP TRIP INSTRUMENTATION REQUIREMENTS 1

111. SAFETY IMPLICATIONS OF THE PROPOSED CHANGES

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The proposed changes make the ATWS Recirculation Pump Trip Reactor Pressure -

{ High setpoint dependent on the number of SRVs out of service. The peak RPV pressure resulting from an ATWS with Main Steam isolation Valve (MSlV) closure (the

, limiting transient) is dependent on the power produced during the transient (which is sensitive to the RWR pump trip setpoint) and the capability to remove heat from the RPV (which is sensitive to the number of SRVs out of service). The reference 1

, analysis for ATWS RWR pump trip setpoint assumed 2 SRVs were out of service.

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When fewer SRVs were assumed to be out of service, the capability to remove heat I

- from the RPV increased, which allowed raising the high RPV pressure setpoint. i

j. l Reference 2 reports the results of an analysis which demonstrates that for a high RPV l

_ pressure setpoint of 1155 psig, with one or zero SRVs out of service, the peak RPV l pressure for the worst case MSIV closure ATWS is 1430 psig. The allowable RPV i pressure for this event is 1500 psig, therefore adequate margin exists with the revised l setpoint. Reference 1 documents the acceptability of the 1120 psig RPV pressure

• setpoint for the case of MSIV closure with 2 SRVs out of service (peak RPV bottom l pressure for this case is 1495.3 psig). l i i The analyses reported in references 1 and 2 are applicable to operation at power uprate conditions. Implementation of an ATWS high RPV pressure RWR trip setpoint which is dependent on the number of SRVs out of service provides a Technical  :

Specification setpoint value which is above the Technical Specification SRV lifting _  !

setpoint when zero or one SRVs are out of service. This will limit the potential for

RWR pump trips during transients which result in high RPV pressure. l 1 IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION i l

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( Operation of the FitzPatrick plant in accordance with the proposed Amendment would i not involve a significant hazards consideration as defined in 10 CFR 50.92, since it j would not:

i 1. involve a significant increase in the probability,or consequences of an accident  !

previously evaluated because:  ;

A change in the ATWS Recirculation Pump Trip Reactor Pressure - High ,

[- setpoint does not affect initiation of any accident. Operation in accordance with i i the revised setpoints ensures the consequences of previously analyzed accidents are not changed.

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. Att chm:nt ll to JPN-96-026 f SAFETY EVALUATION

PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING ATWS RECIRCULATION PUMP TRIP INSTRUMENTATION REQUIREMENTS i

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

, RPV pressure following an ATWS with MSIV closure event (worst case

, transient for RPV pressurization) remains within acceptable limits with the revised setpoint. Therefore changing the setpoint will not lead to a new type of accident.

3. Involve a significant reduction in a margin of safety because:

l The analyses performed to determine the revised ATWS Recirculation Pump

Trip Reactor Pressure - High setpoint assure maintenance of the same margin of safety as presently exists for limiting RPV pressure following an ATWS with

] MSIV closure (limiting transient).

i V. IMPLEMENTATION OF THE PROPOSED CHANGES l Implementation of the proposed changes will not adversely affect the ALARA or Fire

Protection Program at the FitzPatrick plant, nor will the changes impact the '

environment.

VI. CONCLUSION l ,

Based on the discussions above, implementation of an ATWS Recirculation Pump Trip i Reactor Pressure - High setpoint of s 1155 psig for zero or one SRVs out of service i does not involve a significant hazards consideration, or an unreviewed safety question, and will not endanger the health and safety of the public. The Plant Operating Review Committee and Safety Review Committee have reviewed this proposed Technical j Specification change and agree with this conclusion.

Vll. REFERENCES (1) FitzPatrick Power Uprate Impact Study, Engineering Report

Section 9.3.1, ]

t ATWS Analyses for the James A. FitzPatr;ck Nuclear Power Plant, GE-NE-187- i j' 59-1191, November 1991.  ;

I GE letter, C. H. Stoll to Robert Penny (CHS-96-05), "FitzPatrick Nuclear Power (2)

Piant ATWS Analysis for Recirculation Pump Trip Setpoint Changes High Pressure Trip Setpoint Evaluation," dated May 23,1996.

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Attachment til to JPN-96-026 4

MARKUP OF TECHNICAL SPECIFICATION PAGE CHANGES i

PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING ATWS REC.lRCULAllON PUMP TRIP INSTR 11 MENTATION REQUIREMENTS 4

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New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 1 i

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TARi5 3.2 7 fconfj$ f c'

%i AYWS (ECIRCLA.ATION PURE TMP MSTIWAENTATION REQtERERAENTS -

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s NOTES FOft TABLE 3.2-7 l

1. There shaB be two operatale or tnpped hip systems for each Trip Funcemn, except as prowded for bekner.

a. For each Tnp Function isWn one less than the requesd rninimum number of operable instrument channets, place the inoperable l makument channet anWor ils W isip system in the 14l ped contStion untun 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Olhonsese, place the reactor in the  !

stast-eghot stan@y modo sumiin Sie nestl 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. For each Trip Function teidt huo or mose channels less than the serpired frunenum number.of operable instrument channets t) Wisiin one hour, weafy mariarit instrument channats sommin operaMe or Inpped* to mainlam trip ragnhiky in Ihe Tnp Function.

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2) Willan 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, place tie inoperable instrument channel (s) in one inp system anWor that Inp systern" in the tripped condition *, g o

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3) Withm 24 houts, restore the inoperable instrument channel in the osier trip system to an operable status. $l l

if any al these tuee con Stons cannot be sabshed, place the reactor in the start-uptiot stan&y mode usthm the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />  !

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An IrW instrument channel or trip system need not be placed in the hipped condsten where this would cause the Trip 4, Function to occur. In these cases, if tie ',noperatile instrument channel is not sessored to operatile statu:; withm the required <> i time, place Die reador in Wie slashpthat stan@y mode w3hm Wie next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

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" This acton apphes to that trip system with the greatest number of inoperable instrument channels li both systems have the 8<

same number of inoperable instrument &nnnels, the ACTION can be applied to either trip system.

2. When a channel is placed in an inoperable status solely for performance of required surveipances entry into associated Luniung g Condtions for Operabon and requered actons may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> prowded the assocsated Trip Function maartans

• ATWS RPTiruhahnn capel10Ily. ,

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TABLE 3.2-7 teont'd)

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ATWS RECIRCULATION PUMP TRIP INSTRUMENTATION IEQUIREMENTS g l NOTES FOR TABLE 3.2-7 (cont.)

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% 3. The ATWS Reactor Pressure High Recirculation Pump Trip setpoint shaN be s 1155 psig when either zero or one SRVs are out

( of service. The setpoint shan be s 1120 psig when two or more SRVs are out of service.

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i stOTES FOR Tama F 3 2-7

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1. There shes be two W or telepad hip systems for each Tiip Funcemn, except as prowded for channels, place the moperable l

a. For see Trip P.m. cPstieth one less then the roepsed mmanum niunber of operable ins Ottennse, place the reactor in the l Instrument dennel andor its aseodeced tsip systern be to tripped conebon' witun 72 stast-upRiot ,stanttey made uWiin Sie next S houss number.of operableinstnament channels

b. For endi Trip Function wWe tumo or more diennels less then sie regsired 1 or tripped

• 10 mamtam tnp rap =May in the Trip Funcien, w t) Wilhin one hour, wenty sullument instrument channels remain g;l and w i

" _, in one trip system and/or inet tsip system ** In tie tapped conditiorf, S!

2) Witun 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, piece she inoperable instrument - <3 and . g

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^_^: inst channel in sie other trip system to an operable status.

3) Wiltan 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, restore tie i+-

, place the reactor in tie startW stamby mode witam the nemt 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. g it any of enese three coruitens cannot be M

h An inoperable instument or tsip system need not be placed in sie inpped condibon where this would cause the Tnp cases, if tie Inoposable instrument diennelis not restored to operable status within the regared g Funtson to occur. In time, place the See elast-up4 tot stantRuy mode within Wie nemt 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> l

- This achon to that tdp system with Ihe pestest number of inoperable instnwnent channe6s f( toth systems have the same of inoperable instrument deannels, sie ACTION can be appled to eilher trip system.

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2. W rhennel is placed in an inoperable status solely tor performance of required surveillances, entry into associated Um "

for Operabon and respined actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> prowded the wwuned Tnp Function snain 3 1WS RPTinieleton cap hmmy. Y M

Amenenent No.[I,[,1[ t/4, t[,-2H- n

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