Text

Amends 36 & 57 to Licenses DPR-71 & DPR-62,respectively, Changing Tech Specs to Incorporate Conditions Under Which Either Unit Svc Water Sys Nuclear Header May Be Secured for Maint & Mod
	ML19347E845
Person / Time
Site:	Brunswick
Issue date:	05/06/1981
From:	Ippolito T; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML19347E844	List: ML19347E843; ML19347E845; ML19347E850;
References
	NUDOCS 8105140027
	Download: ML19347E845 (26)
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,gv..... f CAROLINA POWER & LIGHT COMPANY, DOCKET f0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 AMENCMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. DPR-71 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Carolina Power & Light Company dated March 13, 1981, as supplemented by letter dated April 22, 1981, 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 of the Comission; C.

There is reasonable ' assurance (i) that' the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

Tie issuance of this amendment is in accordarce with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:

2.C.(2) Technical Soecifications l

The Technical Specifications contained in Appendices A and j

B, as revised through Amendment No. 36, are hereby ' incorporated in the license. The licensee shall operate the facility in j

accordance with the Technical Specifications.

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This' license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION W

Thomas Iopolito, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical i

Specifications Date of Issuance: May 6,1981

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ATTACHMENT TO LICENSE AMENOMENT NO. 36 FACILITY OPERATING LICENSE NO. OPR-71 DOCKET NO. 50-325 Remove the following pages and replace witn identically numbered pages.

IX/X TI/XII 3/4 T 1/3/4 7-2 Add 3/4 7-2a Add 3/4 10-5 Add:3/4.10-6 B3/4 10-1 The underlined pages are changed.

Overleaf pages are provided for. convenience.

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RECUIREMENTS PAGE SECTION 3/4.9 REFUELING OPERATIONS (Continued) 3/4.9.3 CONTROL ROD P0SITION...............................

3/4 9-5 DECAY TIME............................'.............

3/4 9-6 3/4 9.4 3/4.9.5 COMMUNICATIONS.....................................

3/4 9-7 3/4.9.6 CRANE AND HOIST OPERABILITY........................

3/4 9-8 CRANE TRAVEL-SPENT FUEL STORAGE P00L...............' 3/4 9-9 3/4.9.7 3/4.9.8 WATER LEVEL-REACTOR VESSEL.........................

3/4 9-10 3/4.9.9 WATER LEVEL-SPENT FUEL STORAGE P00L................

3/4 9-11 3/4.9.10 CONTROL R00 REMOVAL Single Control Rod Remova1.........................

3/4 9-12 Mul ti ple Con trol Rod Removal....................... 3/4 9-14 3/4.10 SPECIAL TEST EXCEPT!0'iS 3/4.10.1 P RIMAR Y CONTAI NMEN* INTEGRIT Y...................... 3/4 10-1 3/4.10.2 ROD !EQUENCE CONTRCL SY5iEM........................ 3/4 10-2 3/4.10.3 SHUT 00WN MARGI N DEMCN STRATI ON S..................... 3/4 10-3 3/4.10.4 RE CI R CU LATI ON L OCP S................................ 3/4 10-4 3/4.10.5 PLANT SERVICE WATER...............

3/4 10-5 l

E:UNS4!CK - UNIT 1 IX Amentent NO. 22. 25, 36

IN P00R ORIGINAL B AMS PAGE SECTI O'.4 B 3/4 0-1 APPLICA3fLITY......................................

3/4.0 3.[4.1 REACTIVITY CONTROL SYSTEMS B 3/4 1-1 3/4.1.1 SHUTDOWN MARGI N............................

B 3/4 1-1 3/4.1.2 REACTIV I1Y ANDMALIES.......................

B 3/4 1-1 3/4.1.3 CONTROL R005...............................

B 3/41-3 CONTROL R00 PROGRAM CONTROLS...............

3/4.1.4

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B 3/4 1-4 ST ANDBY LIQUID CONTROL SYSTEM..............

3/4.1.5 3/4.2 POWER DISTRIFUTION LIMITS i

B 3/4 2-1 AVERAGE PLANAR LINEAR HEAT GENERATING RATE.

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B 3/4 2-3 3/4.2.2 AP RM S ETP0 I NT S.............................

MINIHLH CRITICAL POWER RATIO................ B 3/4.2.3 B 3/4 2-5 3/4.2.4 LINEAR HEAT GENERATIONRATE................

3/4.3 INSTR MENTATION _

B 3/4 3-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION..

3/4.3.1 B 3/4 3-2 ISOLATION ACTUATION INSTRUMENTATION.........

3/4.3.2 EMERGENCY CORE COOLING SYSTEM ACTUATION B 3/4 3-2 3/4.3.3 INSTRUMENTATION.........................

CONTROL ROD WITHCRAWAL BLOCK INSTRUMENTATION.........................

B 3/4 3-2 3/4.3.4 B 3/4 3-2 3/4.3.5 MONITORING INSTRUMENTATICN.................

ATVS RECIRCULATION PUMP TRIP SYSTEMB 3/4 3-4 l

3/4.3.6 IHfTRUMENTAT10N..........................

3/4.4 REACTOR COOLANT SYSTEM B 3/4 4-1 j

3/4.4.1 RECIRCULATION SYSTEM.......................

i B 3/4 4-1

.3/4.4.2 SAFETY / RELIEF YALVES.......................

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B 3/4 4-1 REACTOR COOLANT SYSTEM LEAKAGE.............

3/4.4.3 1

ic.eninent Ho, 24 X.

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PAGE SECTION 3/4.4 REACTOR C00LUiT SYSTEM (Continued) 3/4.4.4 CH EMI STRY........................................ B 3 / 4 4 - 2 3/4.4.5

,5PECIFIC ACTIVITY..........'..................... B 3/4 4-2 3/4.4.5 PRESSURE /TP.P ERATURE LIMIT 5...................... B 3/4 4-3 3/4.4.7 MAIN STEAM LINE ISOLATION VALVE 5................. B 3/4 4-7 STRL'CTURAL INTEGRITY...........

1' B 3/4 4-7 3/4.4.3

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3/4.5 EMERGENCY CCRE COOLING SYSTEMS e-3/4.5.1 HIGH PRESSURE COOLANT INJECTION SYSTEM........... B 3/4 5-1 e

AUTCMATIC DEPRESSURIZATION SYSTEM.......$........ B 3/

3/4.5.2

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3/4.5.3 LOW PRESSURE COOLING SYSTEM 5..................... B 3/4 5-2 P*

3/4.5.4 SU PPRESSION P00L................................. B 3/4 5-4 3/4.5 CONTAINMENT SYSTEMS 3/4.5.1 PRIMARY C0NTAiNMEKT.............................. B 3/4 6-1 3/4.5.2 DEPRESSURIZATION AND COOLING SYSTP.5............. B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISCLATION VALVE.5............. B 3/4 6-4 o

3/4.6.4 YA CULM RELI'.J.................................... B 3 / 4 6-5 3/4.6.5 SdCONDARYCONTAINMENT............................B3/46-5 3/4.6.6 CONTAINMENT ATMCSPHERE CONTR0L................... B 3/4 6-5 s a t *- C V. C. ""'.* q a

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,m 3ASES PAGE SECTION 3/4.7 PLANT SYSTEUS (Continued) 3/4.7.3 FLCCD PROTECTION...........................

B 3/4 7-1 3/4.7.4 REACTOR CORE ISOLATICN COOLING SYSTEM...... B 3/4 7-1 3/4.7.5 HYDRAULI C SNUE B ERS.........................

B 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION................ B 3/4 7-3 3/4.7.7 FIRE SUPPRESSION SYSTEMS................... B 3/4 7-3 3/4.7.8 FIRE BARRI ER PENETRATIONS.................. B 3/4 7-4 l

3/4.8 ELECTRICAL POWER SYSTEMS........................... B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 R EACTOR MOD E SWITCH........................ B 3/4 9-1 3/4.9.2 INSTRUMENTATION............................

B 3/4 9-1 3/4.9.3 CONTR0L ROD P0SITION.......................

B 3/4 9-1 3/4.9.4 D E CA Y T I M E................................. B 3/4 9-1 3/4.9.5 C0 M INICATIONS.............................

B 3/4 9-1 3/4.9.5 CRANE AND HOIST OPERABILITY................ B 3/4 9-1

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3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L....... B 3/4 9 'I 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 WATER LEVEL-SPENT FUEL STORAGE PCOL........ B 3/4 9-2 3/4.9.10 CO NTRO L RO D R EM0 VAL........................ B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.............. S 3/4 10-1 3/4.10.2 RCD SEQU ENCE CONTROL SYSTEM................ B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS.............

B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS........................

B 3/4 70-1 S/J.10.5 PLANT SERVICE WATER.....

B 3/a 10-E ERJNSWICK - UNIT 1 XII Amendment No. 22, /26', 36 l

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3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.1 Two independent Residual Heat Removal Service Water (RHR$W)

System subsystems shall be OPERABLE with each subsystem comprised of:

a.

Two pumps, and b.

An OPERASLE flow path for heat removal capable of taking suction from the intake canal via the service water system and transferring the water through an RHR heat exchanger.'

APPLICABILITY: CONDITIONS 1, 2 and 3.

ACTION:

With one RHRSW pump inoperable, operation may continue and the a.

provisions of Specification 3.0.4 are not applicable; restore the inoperable pump to OPERABLE status within 31 days or be in at least EDT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD e

SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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With one XHR$W subsystem inoperable, operation may continue b.

and the provisions of Specification 3.0.a are not applicable; restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With both RHRSW subsystems inoperable, restore at least one c.

subsystem to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN vithin the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REGUIREVENTS 4.7.1.1 Each residual heat removal service water subsystem shall be demenstrated OPERA 3LE:

At least once per 31 days by verifying that each valve in I

a.

the flow path that is net locked, sealed or otherwise secured in position, is in its correct position, and b.

At least once per 92 days by verifying that each pumo develops a cump :P of at least 232 psi at a flow of 4000 opm measured through the heat exchanger with a minimum suction pressure of 20 psig.

'5RL'NSWICK - UNIT 1 3/* 7-1 Amentent No. 2E s

:LANT SYSTEu,3 P00R ORIGINAL.

L*MIT*NG CCIC! TION FOR CFIP.: TION 2. 7.1. 2 The service water system nuclear header shall be CFERABLE with at least three GFERABLE service water pumps.

A?:LIC*3ILIN : CONDITIONS 1, 2, 3, 4 and 5.

AC ICN:

a.

In CCNDITION 1, 2. Or 3:

1.

With only tw: service water pu= s G?ERABLE, rest:re at least CPI. *.3LE status within 7 days or be in at least L

three Ou=:s ::

HOT SHUTDCWN within the next 12 h urs and in COLD SHL'TOCWN-within the f:llcwing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

With Only One se-vice water pu=p 0? ERA 5LE, rest:re at least two pu=:s :: CFERABLE s.atus within 72 hcurs and restere at least three pu=;:s :: OPERA 5LE status within 7 days fr:= the time of the initial icss er be in at least HOT SHUTCCWN withia the next 12 h:urs and in COLD SHUTDCWN within the fo11cwing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In Condition 4 or 5:

1.

With only one service water pump OPERABLE, restore at least two service water pumps to OPERABLE status within 7 days or declare the Core Spray System, the LPCI System, and the diesel generators i

inoperable and take the ACTION recuired by Specifict.tions

3. 5. 3.1, 3. 5. 3. 2, and 3. 8.1. 2.

2.

With the service water system nuclear header inoperable, operation may continue provided that the Unit No. 2 service water nuclear header is OPERABLE with at least three OPERABLE Unit No. 2 service water pumps; restore the service water system nuclear header to OPERABLE status within 14 days or declare the diesel generators inoperable and take the ACTION required by Specification 3.8.1.2.

3.

With the service water system nuclear header incperable, operation may continue provided that the service water system conventional header is in operation with at least two service water pumps OPERABLE.* Restore the service water system nuclear header to j

OPERABLE status within la days or declare the Core Spray System i

and LPCI System inoperable and take the ACTION required by j

Specifications 3.5.3.1 and 3.5.3.2.

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See Special Test Exception 3.10.5 i

EEUi:SWICK-UNIT 1 3/* 7-2 Arendnent,o.

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P00R ORIGINAL i

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'E"EILLI.f'CE REOUIREMENTS (continued)

SL 4.7.i.2 Tne service water system shall be demen:: rated OPERA 3LE:

a.

At lets en:e per 31 days by verifying that each valve (:ar.ual; p:wer Operatad er aut:r2 tic) se-vi:ing safaty related equip-ment that is not ic ked, sealed, Or Othenvise secured in position, is in its Orre:: position.

b.

A: least n=e per 13 =enths during shutdown, by verifying that each aut::2:i: valve se vicing safety related equip:nent a::uates :: its ::r e:: ; sition :n the appropriate EC05 a::ua.icn test signals.

c.

In CONDITION 4 or 5 with service water system nuclear header inoperable, verify that the service water system conventional..

header is lined up to supply cooling water to vital ECCS loads and that the Unit 2 nuclear header is lined up to supply cooling water for the diese'. generators by verifying that each valve servicing the diesel generators that is not locked cpen is administratively controlled in the proper position.

l 3K:ssu::I - i; NIT 1 3 / J-7":a Amendment "o.

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! l SPECIAL TEST EXCEPT'ONS I_3/4 10.5 PLANT SERVICE WATER l

lLIMITIf4GCONDITIONFOROPERATION I

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i 3.10.5 The service water conventional header required to be operating per i

Specification 3.7.1.2 ACTION b.3 may be removed from operation by l

l stopping the pumps to pere isolating and draining the service water nuclear header for maintenance provided that:

a.

The service water conventional header remains lined up to r~~% cooling water to the required ECCS loads.

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b.

uraining/ maintenance on the service water nuclear header will l

not affect the service water conventional system or, lineup described in a. above.

c.

Average coolant temperature is 1100*F and the heat up rate is i

110 F per hcur.

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Two dedicated qualified members of the unit operational staff g

are assigned to initiate the service water conventional header pumps should any ~of the followin.g occur:

1.

Any event occurs which requires ECCS actuation.

j 2.

Primary coolant temperature exceeds 180*F.

}l 3.

A loss of off-site power occurs.

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! APPLICABILITY: CONDITIONS 4 and 5 with the nuclear header inoperable.

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ijACTION:

With the requirements of the above specification not satisfied, I;

as soon as practicable, restore the:

lI a.

Service water conventional header to operating status per the l.

requirements of Specification 3.7.1.2 ACTION b.3, or it b.

Service water nuclear header to OPERABLE status per Specification 3.7.1.2.

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SURVEILLANCE REOUIREMENTS i

4.10.6 When the service water conventional headc' is not operating as specified above:

1 Prior to securing all service water pumps, verify that the j

a.

service water conventional header is lined up to supoly cooling water for ECCS by verifying that each valve servicing safety related equipment that is not locked in the preper position is administratively controlled in the proper position.

BRUNSWICK-UNIT 1 3/a 10-5 Amendment No. M

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, SURVEILLANCE RE0VIREMENTS 1

b.

Every four hours, verify that the primary coolant temperature is less than or equal to 180*F.

c.

Prior to securing the service water pumps and at least once per eight hours, verify two-way comunications between the Control Rocm and the Service Nater Building.

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BRUNSWICK-UNIT 1 3/4 10-6 Amendment No. 36 i

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3/4.10 SPECIAL TEST EXCEPTIONS l

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BASES 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY _

The requirement for PRIMARY CONTAINMENT INTEGRITY is removed during the period when open vessel tests are being performed during low power PHYSICS TESTS.

3/4.10.2 ROD SE00ENCE CONTROL SYST94 In order to perform the tests required in the Technical Specifica-tiens it is necessary to bypass the sequence restraints on control red The additional surveillance requirements ensure that the movement.

specifications on heat generation rates and shutdown margin requirements are not exceeded during the period when these' tests are being performed.

3/4.10.3 SHUT 00WN MARGIN DEMONSTRATIONS Performance of shutdown margin demonstrations with the vessel head removed requires additional restrictions in order to ensure that These additienal restrictions are specified

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criticality does not occur.

in this LCO.

N, 3/4.10.4 RECIRCULATION LOOPS T;11s special test exception permits reacter criticality under no flow conditions and is required to perform certain startup and PHYSICS TESTS while at low THERMAL PCWER levels.

3/4.10.5 PLANT SERVICE WATER This Special Test Exception permits securing the Service Water System conventional header when the nuclear header is out of service and is required to permit flange installation in service water system header cross-connect piping.

BRUNSWICX - UNIT 1 S 3/4 10-1 AmendmentNo.22,)MI36

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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. DPR-62 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Carolina Power & Light Company da't'ed March 13,1981, as supplemented by letter dated April 22, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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, anf the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment 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 ragulations; D.

The issuance of this amendment will not be inimical to the comcn defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirewnts have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment, and paragraph 2.C (2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:

2.C.(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 57, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

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2-3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Thomas / ippolito, Chief.

Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 6,1981 e

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ATTACHMENT TO LICENSE ANENCMENT NO. 57 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Remove the following pages and replace..with identically numbered pages.

TX/X YT/XII I

3/4 7 1/3/4 7-2 Add 3/4 7-2a Add 3/4.10-5 Add 3/4.10-6 B3 / 4 10-1 l

Underlined pages are changed. Overleaf pages are provided for convenience.

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I_NDEX

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BASE 5 PAGE SECTION APPLICABILITY _..........................................

B 3/4 0-1 3/4.0 3/4.1 REACTiVITYCONfROLSYSTEMS 3/4.1.1 SHUTDOWN MARGIN................................

B 3/4 1-1 3/4.1. 2 REACTIVITY AN0MALIES...........................

B 3/4 1-1 3/4.1.3 CONTROL R0DS...................................

S. 3/4 1-1 3/4.1.4 CONTROL ROD TA0 GRAM CONTROLS...................

B 3/4 1-3 3/4.1.5 STAl:0BY -LIQUID CONTROL SYSTEM..................

B 3/4 1-4 3/4.2 POWER DISTRIBUTION ' LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATING RATE.....

B 3/4 2-1 3/4.2.2 AP RM S ET P01 NTS.................................

B 3/4 2-3

3/4.2.3 MINIMUM CRITICAL POWER RATIO...................

B 3/4 2-3 '

3/4.2.4 LINEAR HEAT GENERATION RATE....................

B 3/4 2-E 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION......

B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION............

B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.............................

B 3/4 3-2 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION...

B 3/4 3-2 3/4.3.5 MONITORING INSTRUMENTATION.....................

B 3/4 3-2 3/4.3.6 RECIRCULATION PUMP TRIP. ACTUATION IN ST RUME NTAT I O N..............................

B 3/a 3-4 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM...........................

B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES......'.....................

5 3/a 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE....................

B 3/4 4-1

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LIMI-TING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREME

'SECTION-JAGE 3/4.9 REFUELINGOPERATIONS_(Continued) 3/4 9-3 3/4.9.2 INSTRUMENTATION......................................

3/4 9-5 3/4.9.3 CONTROL ROD P0SITION.................................

3/4 9-6 3/4.9.4 DECAY TIME...........................................

3/4 9-7 3/4.9.5 COMMUNICATIONS.......................................

3/4 9-8 3/4.9.6 CRANE AND HOIST OPERABILITY..........................

^

3/4 9-9 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L.................

WATER LEVEL +REAETOR VESSEL...........................

3/4 9-10 3/4.9.8 3/4.9.9 WATER LEVEL-SPENT FUEL STORAGE P00L..................

3/4 9-11

['

~3/4.9.10 CONTROL ROD REMOVAL s_

3/4 9-12

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Singl e Control Red Remova1............................

3/4 9-14 Mul tipl e Centrol Rod Remova1.........................

3/4.10 SPECIAL TEST EX EFTICNS 3/4.10.1 PRIMARY CONTA:':ME!iT INTEGRITY.......................

3/4 10-1 3/4 10-2 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM..........................

3/4 10 3 3/4.10.3 SHUTDC'n'N MARGIN DEMONSTRATIONS.....................

RECIRCULATION L00PS.................'.....;...........

3/4 10 4 3/4.10.4 3/4 10-5 l 3/4.10.5 PLAtlT SERVICE WATER'......................................

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i:

d INDEX

(

BASES pg r.

SECTION 3/4.4 REACTOR COOLANT SYSTEM (Continued)

CH EMI S TRY........................................ B 3/ 4 4 3/4.4.4 3/4.4.5 SPECIFIC ACT I V ITY............................... B 3/ 4 4-2

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PRESSURE / TEMPERATURE LIMITS...................... B 3/4.4.6 MAIN STEAM LINE ISOLATION VALVES.,................ B 3/4 4-7 3/4.4.7 STRUCTURAL INTEGRITY...........,.................. B 3/4 4-7 3/4.4.8 l'

3/4.5 EMERGENCY CORE COOLING SYSTEMS HIGH PRESSURE COOLANT INJECTION SYSTEM.......... B 3/4 5-1

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3/4.5.1 AUTOMATIC OEPRESSURIZATION SYSTEM................

3/4.5.2 LOW PRESSURE C00 LING SYSTEMS.....................

3/4.5.3 SU P PRESS ION P00L.................................. B 3 3/4.5.4 3/4.6 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT.............................. B 3/4 6-1 3/4. 6.1 DEPRESSURIZATION AND COOLING SYSTEMS............

3/4.6.2 PRIMARY CONTAINMENT ISOLATION VALVES............

3/4.6.3 V ACUUM RELIEF...................................

4 3/4.6.4 SECONDARY CONTAINMENT..........................

3/4.5.5 CONTAINMENT ATMOSPHERE CONTR0L................

3/4.6.6 3/4.7 PLANT SYSTEMS --

S ERV IC E WATER SYSTEMS........................

3 / 3.7.1

(

t' CCNTROL ROOM EMERGENCY FILTRATION SYSTEM.....

l_

3/4.7.2 s-.

XI ll 9R'!NSU!CK

'PUT 2 l

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INDEX EASES PAGE SECTION 3/4.7 P8. ANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROT ECT I ON...............................

B 3/4 7-1 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM..........

B 3/4 7-1 3/4.7.5 HYDRAULIC SNUBBERS.............................

B 3/4 7-2 3/4.7.6 SEALED SOURC E CONTAMINATION....................

B 3/4 7-3 3/4.7.7 FIRE SUPPRESSION SYSTEMS.......................

B 3/4 7-3 FIRE B ARRI ER PEN ETRATIONS.....................'.

B 3/4 7-4 3/4.7.8 3/4.8 EL ECTRICAL POW ER S YSTEMS...............................

B 3/4 8-1 3/4.9 REFUELING GPERATIONS 3/4.9.1 REACTOR MOD E SWITC H............................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION................................

B 3/4 9-1 3/4.9.3 C0hTROL R00 P0S ITION...........................

B 3/4 9-1 3/4.9.4 D ECA Y T I M E.....................................

B 3/4 9-1 3/4.9.5 C0mu,N ICAT I ON S............T... !:................

B 3/4 9-1 3/4.9.6 CRAN E AND HOI ST O P ERABILITY....................

B 3/4 9-1 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L...........

B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 WATER LEVEL-S PENT FU EL STORAGE P00L............

B 3/4 9-2 3/4.9.10 CONTROL R00 REM 0 VAL............................

B 3/4 9-2 6/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY..................

B 3/410-1 3/4.10.2 R00 SEQUENCE CONTROL SYSTEM....................

B 3/4 10-1

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3/a.10.3 SHUTDOWN PARGIN DEMONSTRATI0NS.................

B 3/4 10 3/4.10.4 RECIRCULATION L00PS............................

B 3/4 10-1 3/4.10-5 PLANT SERVICE WATER..............................

B 3/4 10-5 L

AmendmentNo.,M57 SRUNSWICK - UNIT 2 XII

3/a.7 PLANT SYSTEMS 3 /4. 7.1 SET.VICE VATER SYSTiMS RESIDUAL HEAT REMOVAL SERVICE WATER SYSTEM LIMITINGCONDITIONFdROpERATION 3.7.1.1 Two independent Residual. Heat Removal Service Water (RHRSW)

System subsystems shall be OPERABLE with each subsystem comprised of:

a.

Two pumps, and b.

An OPERABLE flow path for heat removal capable of taking suction from the intake canal via the service water system and transferring the water through an RHR heat exchanger.

APPLICABILITY: CONDITIONS 1, 2 and 3.

ACTION:

,s a.

With one'RHR5W pump inoperable, operation may continue and the p'rovisions of Specification 3.0.4 are not apolicable; restore the inoperable pump to OPERABLE status within 31 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ..

[~

b.

With one RHRSW subsystem inoperable, operation may continue t.,

and the provisions of Specification 3.0.4 are not applicable; restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD' SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

With both RHRSW subsystems inoperable, restore at least one subsystem to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ' and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REOUIREMENTS 4.7.1.1 Each residual heat removal service water subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve in the flow path that is not locked, sealed or otherdise secured in position, is in its correct position, and b.

At least-once per 92 days by verifying that each cump develops a pump sP of at least 232 psi at a flow of 4000 gpm measured th~ rough the heat exchanger with a minimum suction pressure cf 20 psig.

Amen menc NO. El BRUNSWICK - UNIT 2 2/4 7_1

LANT SYSTEMS SER'/ ICE *a'ATER SYSTEM L*MITING CCN0! TION 20R OPERATION 2. 7.1. 2 The servi:e water systa= nuclear header shall be CFERAELE witn at least three CFERABLE service water pumps.

A?:LICA!!LITY:

CCNCITICMS 1, 2, 3, 4 and 5.

ACTICN:

a.

In CONDITICN 1, 2, er 2:

1.

With :nly tw: service water pu=;s 0? ERA 3LE, rest:re at least three pu=:s :: CPERA3LE status within 7 days Or be in at least HCT SHUTOC'4N.within the next 12 h:urs and in COLD SHUTOCWN within the f:llcwing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

With Only one service watzr pu=; CPERAELE, rest:re at least two pu=:s t: CFERA3LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and rest:re at least three pc=ps t 0? ERA 3LE status within 7 days fr:= the time of the initial 1:ss er be in at least HCT SHUTCCWN within the next 12 h urs tnd in CCL3 SHUTOCWN within the f=11cwing 24 hcurs.

b.

In Condition 4 or 5:

1.

With only one service water pump OPERABLE, restore at least two service water pumps to OPERABLE status within 7 days or declare the Core Spray System, the LPCI System, and the diesel generators inoperable and take the ACTION required by Specifications 3.5.3.1, 7.5.3.2, and 3.8.1.2.

2.

With the service water system nuclear header inoperable, operation may continue provided that the Unit No.1 service water nuclear heauar is OPERABLE with at least three OPERABLE Unit No. I service water pumps; restore the service water system nuclear header to OPERABLE status within 14 days or declare the diesel generators inoperable and take the ACTION required by Specification 3.8.1.2.

3.

With the service water system nuclear header inoperable, operation may continue prcvided that the service water system conventional header is in operation with at least two service water pumps OPERABLE.* Restore the service water system nuclear header to OPERABLE status within 14 days or declare the Core Spray System and LPCI System inoperable and take the ACTION required by Specifications 3.5.3.1 and 3.5.3.2.

1

See Special Test Exception 3.10.5 ERU"Su!CM-UI'IT 2 3/4 7-2 Amendment.';:. 37 l

i

i T 3Y3:IMS I l ?;A::

SL'RVIILLA.':CE p.E00iREMENTS (continued) i

".7.1.2 The service water system shall be dem:nstrated OPERA 3LE:

a.

A: least ence per 31 days by verifying that each valve (=anual; p:wer cperated er act::stic) servi:ing safety related equip-

=ent that is not ic ked, sealed, er otherwi:e see: red in position, is in its ::rre:: positien.

b.

A: leas: er.:e per 13 : nths during shutdown, by verifying that each aut:=atic valve servicing safety related equipment a:::ates :: its ::rre:: pesitien en the appr:priate ECOS actuatien test sigr.als.

c.

In CONDITION 4 or 5 with service water system nuclear header inoperable, verify that the service water system conventional header is lined up to supply cooling water to vital ECCS loads and that the Uniti nuclear neader is lined up to supply cooling water for the diesel generators by verifying that each valve servicing the diesel generators that is not locked open is administratively controlled in the proper position.

Ear::s;;cI - UN : 2 3/' 72:a Amendment No. 57

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SPECIAL TEST EXCEPTIONS 3/4 10.5 PLANT SERVICE WATER LIMITING CONDITION FOR OPERATION 3.10.5 The service water ccnventional header required to be operating per Specification 3.7.1.2 ACTION b.3 may be removed from operation by stopping tne pumps to permit isolating and draining the service water nuclear header for maintenance provided that:

a.

The service water conventional header remains lined up to supply cooling water to the required ECCS loads.

I b.

The draining / maintenance on the service water nuclear header will l

not affect the service water conventional system or lineup described in a. above.

r c.

Average coolant temperature is <100*F and the heat up rate is

~

j

<10 F per hour.

d.

Two dedicated qualified members of the unit operational staff are assigned to initiate the service water conventio.1al header pumps should any of the following occur:

1.

Any event occurs which requires ECCS actuation.

2.

Primary coolant temperature exceeds 180*F.

3.

A loss of cff-site power occurs.

APPLICABILITY: CONDITIONS 4 and 5 with the nuclear header inoperable.

ACTION:

With the requirements of the above specification not satisfied, as soon as practicable, restore the:

a.

Service water conventional header to operating status per the requirements of Specification 3.7.1.2 ACTION b.3, or b.

Service water nuclear header to OPERABLE status per Specification 3.7.1.2.

SURVEILLANCE REOUIREMENTS I;4210.6 When the service water conventional header is not operating as j

specified above:

a.

Prior to securing all service water pumps, verify that the l

service water conventional header is lined up to supply cooling water for ECCS by verifying that each valve servicing i

i i

safety related equipment that is not locked in the proper I'

position is admini-tratively controlled in the proper position.

l BRUNSWICX-UNIT 2 3/4 10-5 Amendment No. 57

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SURVEILLANCE REQUIREf1ENTS b.

Every four stours, verify that the primary coolant temperature is less than or equal to 180*F.

c.

Prior to securing the service water pumps and at least once per eight hours, verify two-way connunications between the Control Room and the Service Water Building.

9 f

I l

BRUNSWICK-UNIT 2 3//. 10-6 Amendment No. 57

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3/4.10 SPECIAL TEST EXCFPTIONS

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BASES 3/4.10.1 PRIMARY CONTAlfMENT INTEGRITY The requirement for PRIMARY CONTAINMENT INTEGRITY is removed during the period when open vessel tests are being perfomed during low power PHYSICS TESTS.

3/4.10.2 ROD SE00ENCE CONTROL SYSTEM _

In order to perfor n the tests required in the Technical Specifica-tions it is necessary to bypass the sequence restraints on control tod The additional surveillance requirements ensure that the movement.

specifications on heat generation rates and shutdown margin requirements are not exceeded during the period when these' tests are being perfomed.

3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS Performance of shutdown margin demonstrations with the vessel head removed requires additional restrictions in order to ensure that These additional restrictions are specified criticality does not occur.

/(^7 in this LCO.

3/4.10.4 RECIRCULAT10N LOOPS This special test exceptica pemits reactor criticality under no flow conditions and is required to perfom certain startup and PHYSICS TESTS while at low THERMAL PCWER levels.

3/4.10.5 PLANT SERVICE WATER _

This Special Test Exception permits securing the Service Watar System conventional header when the nuclear header is out of service and is recuired to permit flange installation.in service water system header cross-connect piping.

t I

SRUNSWICK - UNIT 2 B 3/4101

~ Amendment No. 57

_ _ _,,,,

ML19347E845

Text

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