ML20217M073

Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively, Revising LGS Units 1 & 2 TS Section 4.0.5 & Bases Sections B 3/4.4.8 Re Surveillance Requirements Associated W/Isi & IST

ML20217M073
Person / Time
Site:	Limerick
Issue date:	03/31/1998
From:	Stloz J NRC (Affiliation Not Assigned)
To:
Shared Package
ML20217M069	List: ML20217M064 ML20217M073 ML20217M079
References
NUDOCS 9804080002
Download: ML20217M073 (14)

Text

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a C84g I y t UNITED STATES g

j NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 3086H001 s...../

PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l

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Amendment No.125 Ucense No. NPF-39

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Philadelphia Electric Company (the licensee) dated September 2,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and j 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 Commission; I C. There is reasonable assurance (i) that the activities ainthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) l that such activities will be conducted in compliance with the Commission's I regulations; l

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 i

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the l Commission's regulations and all applicable requirements have been satisfied. i 9804080002 980331 9' PDR ADOCK 05000352 M P PDR {

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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 Ucense No. NPF-3g is hereby amended to read as follows:

Technical Boecificationg The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.125 , are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. ' This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 8

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n F. Stolz, Directo J Project Directorate 1-2 l l Division of Reactor Projects-1/11 ,

Office of Nuclear Reactor Regulation j i

Attachment:

Changes to the l Technical Specifications l

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..Date of issuance: March 31, 1998 l L

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e ATTACHMENT TO LICENSE AMENDMENT NO.1g l FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 1

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Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert l 3/4 0-2 3/4 0-2  !

3/4 0-3 3/4 0-3 l

l B 3/4 0-5 B 3/4 0-5 i

B 3/4 4-6 B 3/4 4-6 e

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'APPLI'CABILITY SURVEILLANCE REQUIREMENTS l~

4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified i

surveillance time interval with a maximum allowable extension not to exceed 25%

of the surveillance' interval.

4.0.3 Failure to perform a Surveillance Requirement.within the allowed surveillance interval ~ defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition' fo'r Operation. The time limits of the ACTION requirements are applicable at the time-it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time.

limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condi-tion shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the. applicable surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply

with ACTION requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:

a. . Inservice inspection of ASME Code Class 1,~2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3-pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a.

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as l 'follows in these Technical Specifications:

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LIMERICK - UNIT l- 3/4 0-2 Amendment No ff,38,125 L

APPLICABILITY SURVEILLANCE RE0VIREMENTS (Continued)

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice. inspection and testing inspection and testino activities activities Weekly At least once per 7 days Monthly At least once per 31 days

-Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months _ At least once per 276 days Yearly or annually. At least once per 366 days Biennially or every 2 years At least once per 731 days l

c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

e. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification,

f. The Inservice Inspection (ISI) Program for piping identified in NRC Generic Letter 88-01 shall-be performed in accordance with the staff positions on schedule, methods and personnel, and sample expansion ,

included in the Generic Letter. Details for implementation of these requirements are included as augmented inspection requirements in the ISI Program.

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l LIMERICK - UNIT 1 3/4 0-3 Amendment No. ff,(9,125 ,

1 3/4.0 APPLICABILITY

. BASES If-the allowable outage time limits of the ACTION requireuents are less than 24 'I hoursorashutdownisrequiredtocomplywithACTIONrequirements~e.

Specification 3.0.3'~ a 24-hour allowance is provided to permit a delay gin, I

implementing:theACi10Nrequirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of-

-this allowance is to permit the completion of a surveillance before a shutdown '

would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance.

' ' The basis for this allowance includes consideration for plant conditions, adequate plannina,: availability of personnel the time required to perform the surveillance and the.. safety.. significance of the delay in completing the required surveillance, . This provision also provides a time limit foi the completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed. If a surveillance is not completed within the'24-

' hour allowance, the time limits of the ACTION requirements are applicable at that'

' time. When a surveillance is performed within the 24-hour allowance and the-

- Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

. Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply. However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

ication 4.0.4 establishes the requirement th'at all applicable surveillances mus e met before entry into an OPERATIONAL CONDITION or other condition of statement. The purpose of this operation specificationspecified in thethat is to ensure Applicability system an d component GPERABILITY requirements or

' parameter limits are met before entry into an OPERATIONAL CON 3ITION or other specified condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL CONDITIONS or other specified conditions associated with plant shutdown as well-as startup.

Under the provisions of this specification the applicable Surveillance

. Requirements must be performed within the s,pecified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower CONDITION of operation.

Snecif cation 4.0.5 establishes the requirement that inservice inspection of ASME Code-C' ass 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with a periodically updated version;of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as

. required by 10 CFR'50.55a. Additionally the Inservice Inspection Program conforms to theNRCstaffpositionsidentifiedinNREGenericLetter88-01 "NRC Position on IGSCC

-in BWR Austinatic Stainless Steel Piping,"asapprovedinNRC$afetyEvaluationsdated March 6, 1990 and October 22, 1990.

LIMERICK.- UNIT'1, B 3/4 0-5 Amendment No. ff,# ,125

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REACTOR COOLANT SYSTEM BASES 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES Double isolation valves are provided on each of the main steam lines to

- minimize the potential-leakage paths from tise containment in case of a line break.

Only one valve in each line is required to maintain the integrity of the containment however single failure considerations require that two valves be {

0PERABLE. the surveillance requirements are based on the operating history of 1

-this type valve. The maximum closure time has been selected to contain fission i produc;s and to ensure the core is not uncovered following line breaks. The J minimum closure time is consistent with the assumptions in the safety analyses to prevent pressure surges..

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3/4.4.8 STRUCTURAL INTEGRITY The inspection ograms for ASME Code Class 1, 2 and 3 components ensure that

~ he structural integr y of these components will be ma,intained at an acceptable t

level throughout the fe of. the plant.

Components of the reactor coolant system were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1971 Edition and Addenda through Winter 1972.

The inservice inspection program for ASME Code Class 1 2 and 3 components will be performed in accordance with Section XI of the ASME boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a. Additionally the Inservice Inspection Program conforms to the NRC staff positions identified in,NRC Generic as approved Letter 88-01,fety in NRC Sa Eveluations dated March 6, 1990 and October"NRC22,.1990. Position on 3/4.4.9 RESIDUAL HEAT REMOVAL The RHR system is required to remove decay heat and sensible heat in order to maintain the. temperature of the reactor coolant. RHR shutdown cooling is comprised of four Each loop consists of two (2) motor driven (4) subsystems pumps, a heat which make and exchanger two associated (2) loops. pi

. common suction from the same re, circulation loop.Two ping(2).

and valves.- Both redundant, loops have a manually controlled shutdown coolina subsystems of the RHR System can provide.the required decay heat removal capability. Each > ump discharges the reactor coolant after it has been cooled by circulation through tle respective heat exchangers, to tbe reactor via the.

associated recirculation loop or. to the reactor via the low pressure coolant injection pathway. The RHR heat exchangers transfer heat to the RHR Service Water System. The RHR shutdown cooling mode is manually controlled.

An OPERABLE RHR shutdown cooling subsyste:r. consists of an RHR um -a' teat exchanger, valves, piping, instruments, and controls to ensure an OP! RAKE flow path.

-In HOT SHUTDOWN condition, the requirement to maintain OPERABLE two (2) independent RHR shutdown cooling subsystems means that each subsystem considered OPERABLE must be- u associated with a different heat exhanger loop i the "A" RHR heat exchanger with  !

the g".e.kheatexchancerwiththe"B"RHR B RH the"A"RHRguyorthe"C"RHRpump,ignependentRHRshutdowncoolingsubsystems.

RHR Only one pump 1)(or'the of the two D (pump

2) RHRarepumps two (2) associated with each RHR heat exchanger loop is LIMERICK . UNIT 1 B 3/4 4-6 AmendmgntNo.(9,97,fff,125

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Kf0 UNITED STATES s-j- NUCLEAR REGULATORY COMMISSION

,, g WASHINGTON. D.C. 200864001 PHILADFI pHIA Fi FCTRIC COMPANY DOCKET NO. 50 353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No.89 License No. NPF-85

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Philadelphia Electric Company (the licensee) dated SeptemberI 19g7, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 nf the Commission;

! C. There is reasonable assurance (i) that the activities authorized by this amendment l can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's f regulations; t

i. D. The issuance of this amendment will not be inimical to the common defense and i-security or to the health and safety of the public; and E. The issuance of this amendment is in accordanbe with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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, 2. Accordingly, the license is amended by changes to the Technical Specifications as i indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility

) Operating License No. NPF-85 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 89 , are hereby incorporated in the license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

l 3. This license amendment is effective as of its date of issuance FOR THE NUCLEAR REGULATORY COMMISSION

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j J hn F. Stolz, Direct roject Directorate l-l Division of Reactor Projects- t/ll Omco of Nuclear Reactor Regulation i

Attachmenti Changes to the l

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Technical Specifications l Date of lasuance: March 31, 1998 l

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I ATTACHMENT TO LICENSE AMENDMENT NO. 89 l

l FACILITY OPERATING LICENSE NO. NPF-85 l

i DOCKET NO. 50-353 l

l l Replace the following pages of the Appendix A Technical Specifications with the attached pages.

j The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

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1 Remove InEAd 1

3/4 0-2 3/4 0-2 3/4 0-3 3/4 0-3 B 3/4 0-5 B 3/4 0-5  !

B 3/4 4-6 B 3/4 4-6 i

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l l APPLICABILITY SURVEILLANCE REQUIREMENTS

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~4.0.I' Surveillance Requirements shall be met during the OPERATIONAL l CONDITIONS or other conditions'specified for individual Limiting Conditions i

for Operation unless otherwise stated in an individual Surveillance Requirement.

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' 4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance time interval with a maximum allowable extension not to exceed 25% of the' surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed u surveillance. interval defined by Specification 4.0.2, shall constitute l noncompliance with the OPERABILITY requirements. for a' Limiting Condition- for l' Operation. The time limits of the ACTION requirements are applicable.at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements .nay be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to l permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance requirements do not-have to be performed on inoperable equipment.

( 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condi-l tion shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified. This provision shall not

~ prevent passage through or to OPERATIONAL CONDITIONS as required to comply

-with ACTION requirements.

i 4.0.5' Surveillance Requirements for inservice inspection and testing of ASME i L -Code Class 1, 2, & 3 components shall be applicable-as follows: '

.a. Inservice inspection of ASME Code Class I, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section-XI of the ASME Boiler-and Pressure Vessel. Code' and applicable Addenda 'as required by 10 CFR  !

Part'50, Section 50.55a.

E b. Surveillance intervals'specified in Se'ction-XI of the ASME Boiler and Pressure Vessel Code.and applicable Addenda for the inservice

,' inspection and testing activities' required by the ASME Boiler and ,

Pressure Vessel Code and applicable Addenda shall be ' applicable as l

follows in these Technical Specifications: '

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o OMERICK-UNIT 2 3/4.0-2 Amendment No. f,89 t

i APPLICABILITY l

j SURVEILLANCE REQUIREMENTS (Continued) i ,

l ASME Boiler and Pressure Vessel Required frequencies I

Code.and applicable Addenda for performing inservice l

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terminology for. inservice inspection and testing insnection and testino activities activities l

l Weekly- At least once per 7-days Monthly -

- At least once per 31 days l- Quarterly or every 3 months At least once per 92 days L Semiannually or every 6 months At least once per 184 days L ,

Every 9 months At least once. per 276 days-L Ye'arly'or annually At.least once per 366 days Biennially or every 2 years At least once per 731 days l

c. -The provisions of Specification 4.0.2 are applicable to the above L required frequencies for performing inservice inspection and testing activities.

d. Performance of the above inservice inspection and testing activities-shall be in addition to other specified Surveillance Requirements.

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e. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to l supersede the requirenients- of any Technical Specification.

l f. The Inservice Inspection-(ISI) Program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods and personnel, and sample expansion included in the Generic Letter. Details for implementation of these -

requirements are included as augmented inspection requirements in the ISI Program.

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Amendment No. 12,89 LIMERICK - UNIT 2 - 3/4 0-3 l

I APPLICABILITY BASES If the allowable outage time limits of the ACTION re uirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTIO requirements e.g S cification 3.0.3 a24-hourallowanceisprovidedtopermitadelayin, i lesentingtheACil0Nrequirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the completion of a-surveillance before a shutdown would be required to comp y with ACTION requirements or before other remedial  !

measures would be require that may preclude the completion of a surveillance.  ;

! The basis for this allowance includes consideration for plant conditions, adequate i

planning, availability of personnel the time required to perform the i surveillance surveillance,andthesafetysinificanceofthedela in completing the required 1

. This provision a so provides a time li it-for the completion of - -

i Surveillance Requirements that become applicable as a consequence of CONDITION l changes imposed by ACTION requirements and for completing Surveillance 1 Re uirements that are applicable when an exception to the requirements' of '

S cification 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour a lowance the time limits of the ACTION requirements are applicable at that time.

When a sur,veillance is performed within the 24-hour allowance and the Surveillance Requirements are not met the time limits of the ACTION requirements are applicable at the time t$at the surveillance is terminated. '

Surveillance Re uirements do not have to be performed on inoperable e ui j because the ACTf0N requirements define the remedial measures that appfy.pment However,  !

the Surveillance Requirements have to be met to demonstrate that inoperable

equipment has been restored to OPERABLE status. i l

Snecification 4.0.4 establishes the requirement that all' applicable surveillances  :

must be met before entry into an OPERATIONAL CONDITION or other condition of-  !

operation specified in the Applicability statement. The pur>ose of.this l specification is to ensure that system and component OPERABI.ITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systems and components ensure safe operation of the facility. This provision applies to changes-in OPERATIONAL CONDITIONS or other specified conditions associated with plant shutdown as well as startup. l Under the provisions of this specification, the applicable Surveillance

l. Requirements must be performed within the specified surveillance interval to '

ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.  ;

l When a Gutdown is required to comply with ACTION requirements the provisions of L Specification 4.0.4donotapplybecausethis'woulddelayplaclngthefac~ilityin L a lower CONDITION of operation.

Snecif' cation 4.0.5 establishes the requirement that inservice inspection of ASME Code C' ass 1 2 and 3 com onents and inservice testin of ASME Code Class 1 2 and

3 pumps and alves shall e performed in-accordance w th a periodically upd ted ,

eversion of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as  !

-required by 10 CFR 50.55a. Additionally the-NRCstaffpositionsidentifiedinNRdtheInserviceInspectionProgramconforms-to Generic Letter 88-01 "NRC Position on IGSCC in BWR Austinetic Stainless Steel Piping," as approved in NRC $afety Evaluations dated -

March 6, 1990 and October 22, 1990.

LIMERICK - UNIT 2- B 3/4 0-5 Amendment No. f2,89 l

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REACTOR COOLANT SYSTEM BASES 3/4.4.7 MAIN' STEAM LINE ISOLATION VALVES Double' isolation valves are provided on each of the main ' steam lines to

minimize the' potential leakage path; from the containment in case of a line break.

'On1;r one valve in each line is reg ired to maintain the integrity of the con"ainment however single failure i:onsiderations require that two valves:be

, OPERABLE. ihe survel11ance requirements are based on the operating history of this tr produc;".pe s andvalve. The maximum to ensure the core closure timeLhas been is not uncovered selected following line to contain breaks. fission

'The

' minimum closure time.is consistent with the assumptions in the safety analyses to prevent pressure surges.

3/4.4.8 STRUCTURAL INTEGRITY

'The inspection ograms'for ASME Code Class 1,-2 and 3' components ensure that the structural integr y.of these components will be ma,intained at an acceptable-level throughout.the fe of the plant.

Components of the reactor-coolant system were designed to provide access to permit-inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel' Code 1971 Edition and Addenda through Winter 1972.

The inservice inspection program for ASME Code-Class 1 - 2 and 3 components will be performed in accordance with Section XI of the ASME Eoiler and' Pressure

-Vessel Code and applicable addenda as required by 10 CFR 50.55a. Additionally the Inservice Inspection Program conforms to the NRC staff positions identified in,NRC Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping,"

as approved in NRC Safety Evaluations dated March 6, 1990 and October 22, 1990.

3/4.4.9 RESIDUAL HEAT REMOVAL The RHR' system is required to remove decay heat and sensible heat in order to maintain the temperature of the reactor coolant. RHR shutdown cooling is comprised of

.four (4) subsystems which make two (2) loops. Each loop consists of two driven pumps,. a heat exchanger, and associated piping and valves. : Both lo(2) opsmotor have a common suction from the same recirculation loop. Two (2) redundant, manually controlled shutdown cooling subs t f the RHR S heat removal capabilit Each )ys ump ems o discharges thereactor ystem can provide coolant theit required e'ter has beendecay

' cooled by circulation y. through tie res)ective heat exchangers, to th,e reactor via.the associated recirculation loop or to tie reactor via the low pressure coolant injection pathway..-The RHR heat exchangers. transfer heat to the RHR Service Water System. The-

.RHR shutdown cooling mode is manually controlled.

. 'An OPERABLE RHR shutdown cooling subsystem consists of an RHR pump a heat

' exchanger, valves, piping, instruments, and controls to ensure an OPERAB[E flow path.

-In HOT SHUTDOWN shutdown condition, cooling subsystems meansthethat.each requirement to maintain subsystem OPERABLE considered OPERABtwo (2)LE.must beinde associated with a different heat exhanger loop 1 the "A" RHR heat exchanger with the B RH Ethe"A"RHRgumpcrthe"C"RHRpump,ignependentRHRshutdownco D RHR- ms. Only

' one pump1):of (orthe the'two (pump are two (2)2) RHR pumps associated with each RHR heat exchan LIMERICK - UNIT 2' Appndment No. f2,6f,82,89 B 3/4 4-6