Text

Proposed Tech Spec 3.7.1.2 Re Svc Water Pump Operability Requirements
	ML20065F203
Person / Time
Site:	Brunswick
Issue date:	09/21/1990
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20065F200	List: ML20065F197; ML20065F203;
References
	TAC-76083, TAC-76084, NUDOCS 9010030290
	Download: ML20065F203 (17)
	v • d • e

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1 ENCLOSURE 1-BRUNSWICK STEAM ELECTRIC PLANT, UNITSc1 AND 2 NRC DOCKETS 50-325 6-50-324 OPERATING LICENSES DPR 71 & DPR-62 REQUEST FOR LICENSE. AMENDMENT-SERVICE WATER SYSTEM (NRC TAC NOS', 76083 AND 76084)

TECHNICAL'SPECIFICATIO'.! PAGES - UNIT 1-i e--

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9010030290 900921 p DR ADOCK 00000324

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SECTION PACE 3/4.4 REACTOR COOLANT SYSTEM (Continued) 3'4.4.4 CHEMISTRY............................................. B 3/4 4-2 3/4.4.5 S P E C I F I C AC T I V I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-2 3/4.4.6 PRESSUR E/ TEMPER ATURE LI MI TS . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-3 3/4.4.1 MAI N STEAM LI NE I SOLATION VALVES. . . . . . . . . . . . . . . . . . . . . B 3/t 447 3/4.4.8 S TR UCTURA L I NTECR I T Y. . . . . . . . . . . . . . . . . . . . . . . . . . . . . e ... B 3/4 441 3/4.5 EMERCENCY CORE CDOLING SYSTEM 3/4.5.1 HICH PR ESSURE COOLANT I NJ ECTION SYSTEM. . . . . . . . . . . . . . . . B )/4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS)............... B 3/4 ;1 3/4.5.3 LOW PRESSURE COOLING SYSTEMS............. 4 ........... B 3/4 5-2 3/4.5.4 SUPPRESSION PO0L...................................... B 3/4 $-4 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 P R I MA RY CON TA !:4 M ENT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-1 3/4.6.2 DEPRES3UR I Z ATION AND COOLING SY STEM S . . . . . . . . . . . . . . . . . . B 3/4 6-3 3/4.6.3 PRI MARY CONTAI NMENT I SOLATI ON VALVES . . . . . . . . . . . . . . . . . . B 3/4 6-4 3/4.6.4 VACUUM RELIEF......................................... B 3/4 b-5 3/4.6.5 SECONDARY CONTAINMENT.............................,...

B 1/4 6-5 3/4.6.6 CONTAINMENT ATMOSPHERE CONTR0L........................ B 3/4 6-5 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS.................,............... B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERCENCY FI LTRATION SYSTEM. . . . . . . . . . . . . . B 3/4 7-la l BRUMSWICK - UNIT 1 X1 Amendment No.

.I.N DEX BASES SECTION PACE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 F LOOD P ROT ECT 10N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-la 3/4.7.4 R EACTOR COR E I SOLATION COOL; NC SYSTEM. . . . . . . . . . . . . . . . . B 3/4 7-la 3/4.7.$ SNUBBERS.............................................. B 3/4 7-2 3/4.7.6 S EALED SOURCE CONTAMI NATI ON. . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-3 3/4.7.7 FIRE SUPPRESSION SYSTEMS.............................. B 3/4 7-3 3/4.7.8 FIRE BARRIER l'ENETRAT10NS.............................- B'3/4 7th 3/4.8 ELECTRICAL POWER SYSTEMS................................. B/3/4 8-1 3/4.9 REFUEL!NC _ OPERATIONS 3/4.4.1 REACTOR MODE SWITCH................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATI :...................................... B 3/4 9-1 3/4.9.3 CONTROL ROD POSIT 10W.................................. B 3/4 9-1 3/4.9.4 DECAY TIME............................................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................ B 3/4 9-1 3/4.9 b C RAWE AND HOI ST O PERABI LI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . B'3/4 9-2 3/4.9.7 CRAhE TRAVEL-SPENT FUEL STORACE P00L.................. B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 WATER LEVEL-REACTOR PUEL STORACE P00L................. 'B 3/4 9-2 3/4.9.10 CC NTRO L ROD R EM0V AL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIKARY CONTAINMENT INTECRITY......................... B 3/4 10-1 3/4.10.2 ROD S EQUENCE CONTROL SY STEM ( DELETED) . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.3 SHUTDOWN HARC IN DEMON STRATION S . . . . . . . . . . . . . . . . . . . . . . . . - B 3/4 10-1 3/4.10.4 R EC I R CU LATI ON L00 PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.5 P LANT S ERV I C E W AT ER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1

. BRUNSWICK - UNIT 1 XII Amendment No.

4 PLANT SYSTEMS SERVICE WATER SYSTEM LIMITINC CONDITION FOR OPERATION 3.7.1.2 The service water system shall be OPERABLE with at leasti in OPERATIONAL CONDITIONS 1, 2, and 38 Two OPERABLE nuclear rervice water pumps, and two OPERABLE conventional service water pumps capable of supplying the nuclear and conventional headers.

In OPERATIONAL CONDITIONS 4 and $1 Three OPERABLE site nuclear service water pumps, and two operable Unit _1 service water pumps, nuclear and/or conventional, powered f rom separate emergency buses and capable of supplying the nuclear header.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5 ACTIONI

a. In OPERAtl0NAL CONDITION 1. 2, or 31

1. With two OPERABLE conventional service water pumps and only one

(

nuclear service water pump OPERABLE, restore the remaining nuclear service water pump to OPERABLE status within 7 days or be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SHUTDOWN within, the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. With no OPERABLE nuclear service water pumps, regardless'of.

conventional service water pump status, be in at- least _ HOT SilVTDOWN-within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the f ollowing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3. With two OPERABLE nuclear service water- pumps and only one -

conventional service water pump OPERABLE, restore at least one additional conventional service water pump to OPERABLE status within 7 days or be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4 With two OPERABLE nuclear service water pumps and no conventional service water pump OPERABLE, restore at least one conventional service water pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and restot s-the remaining conventional sersice water pump to OPERABLE status within 7 days f rom the time of the loss of the first pump. l Otherwise, be in at least . H01 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 . f Il i

I BRUNS 91CK - UNIT 1 3/4 7-2 Amendment No.

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PLANT SYSTEMS LIMITINC CONDITION l'OR OPERATION (Continued)

ACTIONI (Continuedi

5. With only one r.uclear service water pump and one conventional service water pump OPERABLE, restore at least one additional service water pump, nuclear'or conventional, to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ar w re the remaininF service water pump to OPERABLE status wit sn 7 3 f rom the time of the loss of the first pump.

Otherwise >< o ,t 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 Shs i within the following ~4 hours. .)

6. With one OPfmBLE nuclear service water pump and nt. OPERABLE conventional service water pumps, be in at least liOT 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 f ollowing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. In OPERAtl0NAL CONDITION 4 or $8

1. With one less than the required number of nuclear service water pumps OPERABLE per site, restore at -least one additional nuclear service water pump to OPERABLE status within 14 days or declare the diesel generators inoperable and take the ACTION required by Specifications 3.8.1.1 or 3.8.1.2 as appropriate.

2. With the service water system nuclear header inoperable, or no Unit I nuclear service water pumps OPERABLE, operation may continue provided that the service water system conventional header is OPERABLE with at least two conventional service water pumps OPERABLE. Restore the service water system nuclear header to OPERABLE status within 14 days or declare the Core Spray System and the LPCI System inoperable and take the ACTION required by Specifications 2.5.3.1 and 3.5.3.2. Also, declare the diesel generators inoperable and take the ACTION required by Specifications 3.8.1.1 or 3.8.1.2 as appropriate.

3. With less than two OPERABLE site nuclear service water pumps, declare the diesel generators inoperable and take the ACTION required t'y Specifications 3.8.1.1 or 3.8.1.2 as appropriate.

4. With only one Unit I service water pump OPERABLE, restore'at least one additional Unit 1 pump, either nuclear or conventiona), powered from a separate emergency bus, to OPERABLE status within 7 days or declare the Core Spray System and the LpCl System inoperable and take the ACTION required by Specifications 3.5.3.1 and 3.5.3.2.

i BRUNSWICK - UNIT 1 3/4 7-2a Amendment No.

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SURVEILLANCE REQUIREMENTS l t

4.7.1.2 The service water system shall be demonstrated OPERABLE - i i

a. At least once per 31 days by verif ying that each valve (manual, !

power-operated, or automatic) servicing safety related equipment !

that is not locked, sealed, or otherwise secured in position, is in >

its correct position. I

b. At least once 'per 18 months' during shutdown, by verif ying' that each~ ,

automatic valve servicing safety-related equipnent ' actuates to its !

correct position on the appropriate ECCS actuation test signals.- 1 t

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c. In OpCRATIONAL CONDITION 4 or $ with-service water system nuclear l 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 wal.or .

for the diesel generators by verif ying that_ each valve servicing the ,

diesel generators that is not locked open is administratively- 'l controlled in the proper position. ;

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1 BRUNSWICK - UNIT 1 3/4 7-2b Amendment No. ,

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3/4.7 PLANT SYSTEMS BASES 3/4.7.1 SERVICE' WATER SYSTEMS During the initial stage of a DBA (0-10 minutes), the service water system provides tube water and service water cooling to the diesel generators. The service water system design allows either unit's nuclear header to supply diesel generator cooling water. Two pumps are necessary to supply sufficient flow' to cool all f our diesel generators under_ worst-case scenarios while also supplying flow to other safety and non-saf ety related components. Theref ore, any combination of three OPERABLE nuclear service water pumps per site will meet the single failure criteria and assure diesel-generator cooling. The requirement for two OPERABLE nuclear service water pumps associated with a unit in CPERATIONAL CONDITIONS 1, 2, or 3 and at least three OPERABLE nuclear service water pumps per site when one or both units are in OPERATIONAL CONDITIONS 4 or 5 ensures that emergency diesel generator cooling requiremeats are met.

Af ter the initial ten minutes of a DBA, additional loads require cooling water. These loads include RHR and CS pump room coolers, RHR service water heat exchangers, and RHR pump seal heat exchangers. Evaluations have determined that the RHR pump seals, as well as the-equipment in rooms serviced by the RilR and CS room coolers, remain within the n3nufacturers' temperature limits for the first ten minutes of a DBA. To meet the additional loads during the post-ten minute stage of a DBA, two service water pumps on the affected unit must be in service. In order to assure single f ailure criteria is met, the Technical Specification requires two OPERAG'.E conventional service water pumps per unit while in OPERATIONAL CONDITION 1, 2, or 3.

As discussed above, when in OPERATICN AL CONDITIONS 4 and 5, the reduced core decay heat load and the accessibili y to the reactor building for manual operator action reduce the requirement for OPERABLE service water pumps after an accident / transient to one. Therefore, vnen in OPERATIONAL CONDITIONS 4 or 5, two OPERABLE service water pumps (any combination of nuclear and/or conventional) capable of supplying the nuclear header are required-provided that there are at least three OPERABLE nuclear service wat6r pumps per site.

Maintaining two OPERABLE service water pumps (nuclear and/or conventional) on -

the unit while in OPERATIONAL CONDITIONS 4 or 5 assures long-term cooling can be supplied, even af ter app'.ication of the single failure criteria.

Stipulating at least three OPERABLE nuclear service water pumps per site assures diesel generator ooling will be available following any DBA, regardless of which unit suf fers the accident / transient.

The allowed out-of-service times and compensatory measures established in the ACTION Statement s are conservative. In particular, ACTION Statement a.2 for OPERATIONAL CONDITIONS 1, 2, and 3 requires the unit to be in HOT SHUTDOWN within 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 noi OPERABLE nuclear service water pumps. Analyses have been performed which f

BRUNSWICK - UNIT 1 B 3/4 7-1 . Amendment No. =

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PLANT SYSTEMS ;

BASES ,

3/4.7.1 SERVICE' WATER SYSTEMS (Continued) demonstrate operation in OPERATIONAL CONDITIONS 1 through 3 with no OPERABLE nuclear service water pumps is acceptable provided that at least two nuclear service water pumps are OPERABLE on the opposite unit and two conventional ;

pumps are OPERABLE on the affected unit. Specific ACTION statements and LCO time limits for this situation have not been developed since a more connervative ACTION Statement hea been established in order to minimize the.

risk of personnel error in administrating this situation.

1 3/4.7.2 CONTROL ROOM EMERCENCY FI LTRATION P! STEM i

The OPERABILITY of the cont rol room ventilation system ensures that . i

1) the ambient air temperature does not exceed the allowable temperature- f or :

continuous duty rating f or the equipment and instrumentation cooled by this '

system and 2) the cont rol room v'il remain habitable f or -operations personnel '

during and f ollowing all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to .,l 5 rem or less, whole body, or its equivalent. This limitation is consistent-with the' requirements of General Design Criteria 10 of Appendix "A",

10 CFR Part 50.

3/4.7.3 FLOOD PROTECTION The limitation on llood protection ensures that facility protective i actions will be taken and operation will be terminated in the event of flood

conditions. The limit of elevation 17'6" Mean Sea Level is based on the -

maximum elevation at which f acility flood control measures provide protection !

to safety-related equiteent.

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3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM The reactor core isolation cooling-system (RCICS) is provided to assure adequate core cooling in the event of reactor isolation f rom its primary heat '

sink and the loss of f eedwat'er flow to the reactor vessel without requiring ,

,. actuation of any of the' Emergency Core Cooling equipment. RCICS is- '

conservatively required to be OPERABLE whenever reactor pressure exceeds'll3:

psig even though the Residual heat Removal (RHR) system provides-adequate core cooling up to 150 psig.- The condensate storage tank provides sufficient water to reduce the reactor coolant temperature and pressure to permit the RHR "

l system to be operated. ;

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l BRUNSWICK - UNIT 1 B 3/4 7-la : Amendment No.

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ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS $0 325 & $0 324 OPERATINC LICENSES DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT SERVICE WATER SYSTEM (NRC TAC NOS. 76083 AND 76084)

TECHNICAL SPECIFICATION PACES - 11 NIT 2

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BASES v I

SECTION P.^.C E 3/4.4 REACTOR COOLANT SYSTEM (Continued) 3/4.4.4 CllEMISTRY............................................. B 3/4 4-2 f I

3/4.4.$ S PECI FI C ACTI VI TY . . . . . . . . . . . . . . . . . . . . . . . 4 ............ B 3/4 4-2 3/4.4.6 PRESSURE / TEMPERATURE LIMITS........................... B 3/4 4-3 '

3/4.4.1 M AI N STEAM LI NE I SO LATI ON V ALVE S . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-7 !

3/4.4.8 STRUCTURAL INTECRITY.................................. B 3/4 4-7 3/4.5 EMERCENCY CORE COOLING SYSTEM I 3.5.1 111 011 PR ES SURE COOLANT I NJ ECTION SYSTEM. . . . . . . . . . . . . . . . B 3/4 $-1 ,

s/4.5.2 AUTOM ATIC DEPRESSURIZ ATION SYSTEM ( ADS) . . . . . . . . . . . . . . . B 3/4 $-1 -

3/4.5.3 LOW PRESSURE COOLING SYSTEMS.......................... B 3/4 5-2 ;

3/4.5.4 SUPPRESSION P00L...................................... B 3/4 5-4 3/4.6 CONTAINMENT SYSTEMS I 3/4.6.1 PRIMARY CONTAINMENT...................................' B 3/4 6-l' +

3/4.6.2 DEPRESSURIZ ATION AND COOLING SYSTEMS. . . . . . . . . . . . . . . . . . B 3/4 6-3 -

3/4.6.3 PRI MARY CONTAI NMENT I SOLATION VALVES.' . . . . . . . . . . . . . . . . . B 3/4 6-4 l 3/4.6.4 VACUUH RELIEF......................................... B 3/4 6-$

3/4.6.5 SECONDARY CONTAINMENT................................. B 3/4 6-$ ,

3/4.6.6 CONTA I NME NT ATHOS PilER E C0NTROL. . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-5 ,

3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS................................. B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERCENCY FI LTRATION SYSTEM. . . . . . . . . . . . . . B 3/4 7-la l l

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1 BRUNSWICK - UNIT 2 1 XI Anwndment No.-

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4, INDEX t

BASES j i

__SECTION PACE l 3/4.7 PLA'.T SYSTEMS (Continued) l 3/4.'.1 FLOOD PROTECT!0N...................................... B 3/4 7-la $

i 3/4.7.4 REACTOR CORE I SOLATION COOLING SYSTEM. . . . . . . . . . . . . . . . . 6 3/4 7-la 3/4.7.5 SNUBBERS.............................................. B 3/4 7-2 f t

3/4.7.6 SEALED SOURCE CONTAMINATION........................... B 3/4 7-4 [

3/4.7.7 F I R E SU PPRE SS ION SY ST EM S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-4 !

3/4.7.8 F I R E BARR I ER PEL'ETR AT !0NS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-5 f i

3/4.8 ELECTRICAL POWER SYSTEMS................................. B/3/4 2-1 3/4.9 REFUEllNC OPERATIONS 3/4.9.1 REACTOR MODE SWITCH................................... B 3/4 9-1 I 3/4.9.2 INSTRUMENTATION....................................... B 3/4 9-1 3/4.9.3 CONTROL ROD POSIT 10N.................................. B 3/4 9-1 3/4.9.4 DECAY TIME............................................ B 3/4 9-1 ,

3/4.9.5- COMMUNICATIONS...............................'......... B 3/4 9-1 i 3/4.9.6 CRA N E AND Hol ST O PE RA B I LI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE P00LL . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 WATER LEVEL-R EACTOR FUEL STOR ACE P00L. . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL............................'.......- B 3/4 9-2 4

3/4.10 SPECIAL TEST EXCEPTIONS i 3/4.10.1 PRI MARY CONTA I NMENT I NTECRI TY . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-11 ,

3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED)................. B 3/4 10-1 [

3/4.10.3 SHUTDOWN HARCIN DEMONSTRATIONS........................ B 3/4 10-1 -

3/4.10.4 R EC I R CU LAT I ON L00 PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.5 P LA NT S E R V I C E W AT E R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10 l BRUNSWICK - UNIT 2- X11 Amendment No.

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PLANT SYSTEMS SERVICE WATER SYSTEM LIMITINC CONDITION FOR OPEkATION 3.7.1.2 The service water system shall be OPERABLE with at leasti in OPERATIONAL CONDIT!ONS 1, 2, and 38 Two OPERABLE nuclear service water pumps, and sc, OPERABLE ' conventional service water pumps capable of supplying the nuclear and conventional headert.

In OPERATIONAL CONDITIONS 4 and $1 Three OPERABLE vite nuclear service water pumps) and two OPERABLE Unit 2 service water pumps. nuclear and/or conventional, powered f rom separate -

emergency buses and capable of supplying the nuclear header.

APILICABILITY OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5 ACTION

a. In OPERATIONAL CONDITION 1, 2, or 31

1. With two OPERABLE conventional service water pumps and only one nuclear service water pump OPERABLE, restore the remaining nuclear service water pump to OPERABLE status within 7 days or be in 110T SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SilVTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. With no OPERABLE nuclear service water pumps, regardless of conventional service water pump status, be in at least il0T SilVTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SilVTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .-

3. With two OPERABLE nuclear service water pumps and onty one conventional service water pump,0PERABLE, restore at least one ;

additional conventional service water pump to OPERABLE status within l 7 days or be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4. With two OPERABLE nuclear service water pumps and no conventional service water pump OPERABLE, restore at least one conventional service water pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and restore -

the remaining conventional service water pump to OPERABLE status within 7 days from the time of the loss of the first pump.

Otherwise, be in at least il0T SilDTDOWN within' the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and:

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

. BRUNSWICK - UNIT 2 .3/4 7-2 Amendment No.

. l PLANT SYSTEMS LIMITINC CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

5. With only one nuclear Service water pump and one conventional service water pump OPERABLE, restere at least one additional service water pump, nuclear or conventional, to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and restore the remaining service water pump to OPERABLE status within 7 days f rom the time of the loss of the first pump.

Otherwise, 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 .

6. With one >PERABLE nuclear service water pump and no OPERABLE conventional service water pumps, 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 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 6.

b. In OPERATIONAL CONDITION 4 or 5:

1.

With one less than the required number of nuclear service water pumps OPERABLE per site, restore at least one additional nuclear service water pump to OPERABLE status within 14 days or declare the !

diesel generators inoperable and take the ACTION required by specifications 3.8.1.1 or 3.8.1.2 as appropriate.

2.

With Unit the service water system nuclear header inoperable, or no 2 nuclear provided that service water pumps OPERA 3LE, operation may continue the service water system conventional header is OPERABLE with at least two conventional service water pumps OPERABLE.

Restore the service water system nuclear header to OPERABLE status within 14 days or declare the Core Spray System and the LPCI System inoperable and take the ACTION required by Specifications 3.5.3.1 and 3.5.3.2. Also, declare the diesel generators inoperable and take the ACTION required by Specif icat ions 3.8.1.1 or 3.8.1.2 as appropriate.

3.

With less than two OPERABLE site nuclear service water pumps, declare the diesel generators inoperable and take the ACTION required by Specifications 3.8.1.1 or 3.8.1.2 as appropriate.

4.

With only one Unit 2 service water pump OPERABLE, restore. et least one additional Unit 2 pump, either nuclear or conventional, powered from a separate emergency bus, to OPERABLE status within 7 days or declare the Core Spray System and the LPCI System inoperable and take the ACTION required by Specifications 3.5.3.1 and 3.5.3.2.

BRUNSWICK - UNIT 2 3/4 7-2a Amendment No.

PLANT SYSTEMS SURVEILLANCE REQUIRL'MENTS

4. 7.1. 2 - The 6ervice water system shall be demonstrated OPERABLE

a. At least once per 31 days by verif ying that each valve (nanual, power-operat ed, or automatic) . servicing sa f ety relat ed equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety-related ' equipment actuates to !ts correct position on the appropriate ECCS actuation test signals.

c. In OPERATIONAL CONDITION 4 or 5 with ~ service water system nuclear l header inoperable, verif y. that .the _ service water system conventional header is lined up to supply cooling water to vital ECCS loads and that the Unit I nuclear header is lined up to supply cooling weter.

for the diesel' generators by verif ying that each valve servicing the diesel generators that is not locked open is administratively controlled in the proper position.

BRUNSWICK - UNIT 2 3/4-7-2b Amendment No.

I l

b 3/4.7 PLANT SYSTEMS BASES 3/4.7.1 SERVICE. WATER SYSTEMS During the initial stage of a DBA (0-10 minutes), the service water system provides lube water and service water cooling to the diesel generators. The service water system design allows either unit's nuclear header to supply diesel generator cooling water. Two pumps are necessary to supply suf ficient flow to cool ali f our diesel generators under worst-case scenarios while also supplying flow to other saf ety and non-safety. related components. Therefore, any combination of three OPERABLE nuclear service water pumps per site will meet the single failure criteria and assure diesel generator cooling. The requirement for two OPERABLE nuclear service water pumps associated with a unit in OPERATIONAL CONJITIONS 1, 2, or 3 and at least three OPERABLE nuclear service water pumps per site when one or both units are in OPERATIONAL CONDITIONS 4 or 5 ensures that emergency diesel generator conting requiretaents are met.

At;er the initial 'en minutes of a DBA, additional loads require' cooling water. Tt.'se loads include RHR and CS pump room coolers,' RHR service water heat exchangces, and RHH pump seal heat exchangers. Evaluations have determined that the RHR pump seals, as well as the' equipment in rooms serviced by- the RHR and Cb room coolers, remain within the manuf acturers' temperature limits for the f irst ten minutes of a DBA. To meet the additional loads during the post-ten minute stage of a DBA, two service water pumps on the affected unit must be in service. In order to assure single failure criteria is met, the Technical Specification requires two OPERABLE conventional service' water pumps per unit while in OPERATIONAL CONDITION 1, 2, or 3.

As discussed above, when in OPERATIONAL CONDITIONS 4 and ,5, the reduced core decay heat load and the accessibility to the reactor building for manual operator action reduce the requirement for OPERABLE service water pumps af ter an accident / transient to one. Therefore, when in OPERATIONAL CONDITIONS 4 or 5, two OPERABLE service water pumps (any combination of nuclear and/or conventional) capable of supplying the nuclear header are required provided that there are at least three OPERABLE nuclear service water pumps = per site.

Maintaining two OPERABLE service water pumps (nuclear and/or conventional) on the unit while in OPERATIONAL CONDITIONS 4 or 5 assures long-term cooling- can be supplied, even af ter application of the single failure criteria.

Stipulating at least three OPERABLE nuclear service water pumps per site

)

assures diesel generator cooling will be available following any DBA, regardless of which unit suf fers the accident / transient.

l The allowed out-of-service times and compensatory measures established in ,

the ACTION Statement s are conservative. in particular, ACTION Statement a.2 3 f or OPERATIONAL CONDITIONS 1, 2, and 3 requi res the unit t o be in HOT SHUTDOWN I within 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 no OPERABLE nuclear service water pumps. Analyses have been performed which l

BRUNSWICK - UNIT 2 B 3/4 7-1 Amendment No.

' l,

e.

PLANT SYSTEMS BASES 3/4.7.1 SERVICE WATER' SYSTEMS (Continued) demonstrate operation in OPERATIONAL CONDITIONS _1 through 3 with no OPERABLE nuclear service <ater pumps is acceptable provided that at least two nuclear service water pumps are OPERABLE on the opposite unit and two conventional pumps are OPERABLE on the affected unit. Specific. ACTION statements and LCO time limit s for this situatior. have not been developed since a more conservative ACTION Statement has been established in order to minimize the

~

risk of personnel error in administrating this situation.

3/4.7.2 CONTROL ROOM EMERCENCY FILTRATION SYSTEM The OPERABILITY of the control room ventilation system ensures that

1) the ambient air temperature does not exceed the allowable temperature f or continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel' during and f ollowing all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limitinf the radiation exposure to personnel occupying the control room to

$ rem or less, whole body, or its equivalent. This limitation is consistent wi h the requirements of General Design Criteria 10.of Appendix "A",

10 CFR Part 50.

3/4.7.3 FLOOD PROTECTION The limitatiun on flood protection ensures that facility-protective actions will be taken and operation will be terminated in the event of flood ~

conditions. The limit of elevation 17'6" Mean Sea Level is based en the maximum elevat ion at which f acility flood cont rol measures provide protection-to saf et y-related equi pment .

3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM The reactor core isoletion cooling system (RCICS) is provided'to assure-adequate core cooling in ,2.e event of reactor isolation f rom its. primary heat sink and the loss 01 feedwater flow to the reactor vessel without requiring actuation of any of the Emergency Core Cooling equ'ipment. .RCICS is; conservatively required.to be OPERABLE whenever reactor pressure exceeds 113 psig even though the Residual llent Removal (RilR) system provides adequate core cooling up to 150 psig. The condensate storage tank-provides-sufficient water-

~

to reduce the reactor coolant temperature'and pressure to permit the RilR system to be operated.

4

,)

BRUNSWICK - UNIT 2 B 3/4 7-la -Amendment No.-

4

,+

e b*

ENCLOSURE 3 BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 NRC DOCKETS $0 325 & $0 324 OPERATINC LICENSES DPR 71 & DPR 62 REQUEST TOR LICENSE AMENDMENT SERVICE WATER SYSTEM (NRC TAC NOS. 76083 AND 76084)

INSTRUCTIONS FOR INCORPORATION The proposed changes to the Technical Specifications (Appendix A to Operating Licenses DPR-71 and DPR 62) would be incorporated as follows:

UNIT 1 Remove Page Insert Pare XI XI '

XII XII 3/4 7 2 3// 7 2 0 3/4 7 2a 3/4 7 2b B 3/4 7 1 B 3/4 7 1 B 3/4 7 la UNIT 2 Remove.Eggt Insert Page XI XI XII XII 3/4 7 2 3/4 7 2 3/4 7 2a-3/4 7 2b B-3/4 7 1 B 3/4 7 1 j B 3/4 7-la a

E3 1

-

v t e Letter Sequence Other
TAC:76083, (Open) TAC:76084, (Open)
Initiation Request Acceptance... Supplement Administration Questions Answers Results Approval... Other: ML20059N054, ML20065F203
MONTHYEAR1990-09-21 [Table View]

ML20065F203

Text

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