Text

Proposed Tech Specs 3.7.1.2,clarifying & Expanding Svc Water Pump Operability
	ML20059N054
Person / Time
Site:	Brunswick
Issue date:	09/27/1990
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20059N053	List: ML20059N052; ML20059N054;
References
	TAC-76083, TAC-76084, NUDOCS 9010090215
	Download: ML20059N054 (17)
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, g. ENCLOSURE 1

.g a. . : BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 ANDl2 <

"3 NRC DOCKETS 50 325 & 50 324,

v OPERATING LICENSES DPR 71'& DPR-62 REQUEST FOR LICENSE' AMENDMENT SERVICE WATER SYSTEM- .!.

,; (NRC TAC NOS. 76083'AND 76084)-

TECHNICAL SPECIFICATION PAGES - UNIT 1 ,

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INDEX Y h-A4 BASES: 4 SECTION PACE 3/4.4 REACTOR COOLANT SYSTEM (Conti'ued) n

3/4.4.4 CHEMISTRY............................................. B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY..................................... B 3/4 4-2 !

3/4.4.6. -PRESSURE / TEMPERATURE LIMITS........................... B-3/4 4-3 3

3/4.4.7 MAI N STEAM LI NE I SOLATI ON VALVE S. . . . . . . . . . . . . . . . . . . . . . B 3/4 4-7

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'3/4.4.8 STRUCTURAliINTEGRITY......................'............ B 3/4 4 ,.

23/4.5 ~ EMERCENCY CORE' C00 LING SYSTEM ,

I 3 / 4 '. 5.1 H ICH PRESSURE COOLANT I NJECTION SYSTEM. . . . . . . . . . . . . . . . B'3/4'.5-1 r.

3/4 f.2 AUTOMATIC DEPRESSURIZ ATION SYSTEM ( ADS) . . . . . . . . . . . . . . . B 3/4.5-1 3/4.5.3 LOW P RE S S UR E C00LI NC SY ST EM S . . . . . . . . . . . . . . . . . . . . . . . . . . - 'B 3/4 5-2 n

s :3/4.5.4 S U P PR ES S I ON P00 L . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 5-4

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3/4.6' CONTAINMENT SYSTEMS .)

"t 3/4.6.1 PRIMARY CONTAINMENT................................... B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.................. BD3/4 6-3

=3/4.6.3 PRIKARY CONTAINMENT ISOLATION VALVES.................. B 3/4 6-4

- 3 / 4. 6.'4 V AC UU M R E LI E F . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4'6-5 ;

3/4.6.5 SECONDARY CONTAINMENT................................. B 3/4 6-5

?- > 3/4.6.6 CONTAINMENT ATMOS PH ER E- CONTR0L. . . . . . . . . . . . . . . . . . . . . . . . - B J/4 6-5' $

3/4.7 PLANT SYSTEMS !

L 1-3/4.7.1 ' SERVICE WATER SYSTEMS................................. B.3/4 7-1 ~

3/4.7.2 CONTROL ROOM EMERCENCY FILTRATION SYSTEM. . . . . . . . . . . . . . B 3/4 7-la l t

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3 INDEX BASES SECTION PACEL 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECTION...................................... .B-3/4 7-la 3/4.7.4 REACTOR CORE I SOLATION -COOLING SYSTEM.'. . . . . . . . . . . . . . . . B 3/4 7-la!

3/4.7.5 SNUBBL. .............................................~ 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 BARRIER PENETRATIONS............................. B 3/4L7-4 3/4.8 ELECTRICAL POWER SYSTEMS................................. B'3/4 8-1 3/4.9 REFUELINC OPERATIONS

.3/4.9,1 REACTOR MODE SWITCH................................... B'3/4 9-1=

3/4.V.2 I N STRUM ENTATI ON . . . . . . . . . . . . . . . . ...................... B=-3/4 9-1. Y 3/4.9.3 CONTROL ROD P0SITION.................................. 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 3/4.9.6 CRANE AND HOIST OPERABILITY...........................- >B 3/4 9-2 3/4.9.7 CRANE 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 FUEL STORACE P00L................. B 3/4.9-2.

3/4.9.10 ~ CON TR OL ROD R EM 0V AL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY' CONTAINMENT INTECRITY......................... B 3/4'10 3/4.10.2- ROD SEQUENCE CONTROL SYSTEM (DELETED)................. B 3/4 10-l' 3/4.10.3 SHUTDOWN MARCIN DEMONSTRATIONS........................ B 3/4 10 3/4.10.4 RECIRCULATION L00PS................................... B 3/4 10-1 3/4.10.5 P LANT S ERV I C E W AT ER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10 BRUNSWICK - UNIT 1 XII Amendment No.

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SERVICE WATER SYSTEM' l

_ LlHITING CONDITION FOR OPERATION l t

~- 3. 7.1. 2 - The service water system shall be OPERABLE with at.least: .

. in'0PERATIONAL CONDITIONS 1, 2, and 3:

Two OPERABLE nuclear service water pumps, and two OPERABLE conventional service water pumps capable of supplying the nuclear and' conventional-headers..

l In OPERATIONAL CONDITIONS 4 and 5:

0! Three OPERABLE site nuclear service water pumps, and two operable Unit 'l

, service water pumps, nuclear and/or conventional, powered from separate emergency buses and capable of supplying the nuclear header. ;

APPLICABILITY: 0PERATIONAL CONDITIONS 1, 2, - 3, 4, and 5 ACTION:

a. -In OPERATIONAL CONDITION 1, 2, or 3: t

, 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 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s- and COLD SHUTDOWN within- the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

. conventional service water pump status, be in at least 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 .

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

,r conventional service water. pump::0PERABLE, restore at:least-one . j additional conventional service water pump to OPERABLE status within -

7: days for 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. hours.

o .4. Withitwo-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' 0PERABLE status withinL7 days from the time of the loss of the first pump.

.0therwise,-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 .

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

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y LIMITINC CONDI, TION FOR OPERATION (Cont inued) '

-ACTION ~ (Continued)

5. With only on'e nuclear service water pump and;one conventional service water pump OPERABLE, restore at' least one: additional . service +

water. pump,. nuclear or. conventional, to.0PERABLE status within

.g '2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and restore the remaining service water pump to OPERABLE st'atus= 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:

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

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'6. With one OPERABLE nuclear' service water pump and no. 0PERABLE. ,

conventionaliservice water pumps,.be'in at least' HOT SHUTDOWN within.

t , 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. 'In OPERATIONAL CONDITION 4 or 5: J.

1. With one less than the required number of nuclear. service water - l pumps OPERABLE per site, restore'at least one additional nuclear 4 a

l service water pump to OPERABLE status within 14 ' days or declare > the Li

- diesel ogenerators; inoperable and take the ACTION requi red by-Specification 3.8.1.2. , J

2. With the service water system nuclear header inoperable, or no Unit 1 nuclear service water pumps OPERABLE, operation may continu~e.

provided that the service water system' conventional header is -I

.0PERABLE with at least two conventional service water pumps I 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 byL Specification 3.8.1.2. _

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3. With less than two OPERABLE site nuclear service: water pumps,- Il declare the diesel generators inoperable and-take the ACTION j required by Specification 3.8.1.2. >

4. With only one Unit I service water pump OPERABLE, restore at l'eas': t one additional Unit 1 pump, 'either nuclear or conventional, powered ,

from a separate emergency bus, to OPERABLE status within 7Edays-or ?

declare the' Core Spray System and the LPCI System inoperable and' '3 take the ACTION required by Specifications 3.5.3.1 and '3.5.3.2.'

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'PI' ANT SYSTEMS 1 'i SURVEILLANCE REQUIREMENTS- :l

l. ' 4. 7.1. 2 L The service water system shall be demonstrated OPERABLEt .,

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a.- 'At least' once per 31 days by verifying that each valve (manual,--

power-operated, or automatic) servicin,t: safety ' elated r equipment that lls' not locked, sealed, or otherwit e' secured in post tion, _ is in .

its correct position.

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<g b. At _ least once per- 18 months during shutdown',' by veri f ying thatj each automatic. valve servicing safety-related equipment' actuates _to its correct._ position on the appropriate ECCS actuation test signels. , .

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c. In -OPERATIONAL CONDITION 4 or 5. with service water system _ nuclear ~ 'lL"' ,.

, . header inoperable, verify that the; service water system convention'al

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header 'i s_' lined up' to supply cooling water- to vital ECCS > loads 'and:-

that the_ Unit 2 nuclear header is lined-up to supply _ cooling 1 water 4

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for the diesel generators' by verifying that each. valve servicing-the- ,

diesel generators that is not locked open-is administrativelyj controlled in the proper _ position.

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3/4.7 PLfAT SYSTEMS BASES 3/4.7.1 SERVICE WATER ,SJSTEMS 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 suf ficient flow to cool all f our diesel generators under worst-case scenarios while also supplying flow to other saf ety .nd non-saf ety related components. Therefore, any combination of three OPERABLE nuclear service water pumps per site will meet the single f ailure criteria and assure diesel generator cooling. The requirement for two OPERABLE nuclear service water pumps associated with a unit in OPERATIONAL COWDITIONS 1, 2, or 3 and at least three OPERABLE nuclear service water pumps per site wten one or both units are in OPERATIONAL CONDITIONS 4 or $ ensures that emergency diesel generator J cooling requirements are met.

Af tc.' the initial ten minutes of a DBA, additional loads require cooling water. These loads include RHR and CS pump roon. coolers, RHR service water heat exchangers, and RHR pump seat heat exchangers. Evaluations have determined that the RHR pump seals, as well as the equipment in' rooms serviced by the RHR and CS room coolers, remain within the manuf acturers' 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 OPERABLE conventional service water pumps per unit while in OPERATIONAL CONDITION 1, 2, or 3.

e, As discussed above, when in OPERATIONAL CONDITIONS 4 and 5,1the reduced core decay heat load and the accessibility to the reactor building for manual operator act oni reduce the requirement for OPERABLE service water pumps after

-an acaident/ transient to one. Therefore, when in OPERATIONAL CONDITIONS 4 or.5, two GPERABLE service water pumps (any combination of nuclear and/or conventional) capable of supplying the nuclear heac'er are required provided that there are at least three OPERABLE nuclear strvice 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 f ailure cri eria. t Stipulating at least three OPERABLE nuclear service water pumps per site.

assures diesel generator cooling will be available following any DBA, regarditas of which unit suffers the accident / transient.

The allowed out-of-service times and ccmpensatory measurns 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 no OPERABLE nuclear service water pumpe . Analyses have been performed which BRUNSWICK - UNIT 1 B 3/4 7-1 Amendment No.

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PLANT SYSTEMS

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BASES 3/4.7.1 SERVICE WATER SYSTEMS (Continued) !

demonstrate operation in JPERATIONAL CONDITIONS 1 through 3 with.no OPERABLE -

nuclear service water pumps is acceptable provided that at least two nuclear service watet pumps are OPERABLE on the opposite unit and two conventional !

pumps are OPERABLE on the affected unit. Speclite A.CTION statements and LCO !

time limits for this situation have not been developed since a more I 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 EMERGENCY FILTRATION SY9 TEM The OPERABILITY of the control room ventilation system ensures that

1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating f or the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident condit ons. The OPERABILITY of 8

this system in conjunction with control room design provisions is based on limiting the radiation exposure tu personnel occupying the control room to !

5 rem or lei.s, 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 flood protection ensures that facility protective "ticns will be taken and operation will be terminated in the ev1nt of flood ccnditions. The limit of elevation 17'6" Mean Sea Level is based on the ma'4imum elevation at which f acility flood control measures provide protection tf safety-ralated equipmenc.

'J / 4. 7. 4 REACTOR CORE ISOLATION COOLING SYSTEM

.i The' reactor core isolation cooling system (kCICS) is provided to assure adequate. core cooling in the event of reactor isolation f rom its primary heat ,

sink'and the loss of feedwater flow to the reactor vessel without requiring i actuation of any of the Emergency Core Cooling equipment. RCICS.is conservatively required to be OPERABLE whenever t sactor pressure exceeds 113 psig even though the Residual Heat Removal (RHR) system provides adequate core cooling i. to 150 psig. The condensate storage tank provides sufficient water to reduce the reactor coolant temperature and pressure to permit the RHR system to be operated.

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

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ENCLOSURE 2 l

BRUNSWICK STEAi1 ELECTRIC PIANT, UNITS 1 AND 2 i NRC DOCKETS 50 325 & 50-324 l OPERATING LICENSES DPR-71 & DPR 62 )

REQUEST FOR LICENSE AMENDMENT ;

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~ SERVICE WATER SYFTEM ;

(NRC TAC NOS. 76083 !.fD 76084) l k

i TECHNICAL SPECIFICATION PAGES - UNIT 2 .!

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INDEX BASES

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SECTION PACE 3/4.4 REACTOR COOLANT SYSTEM (Cont inued) 3/4.4.4 CHEMISTRY............................................. B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY..................................... B 3/4 4-2' 3/4.4.6~ PRESSURE / TEMPERATURE LIMITS................ .......... B 3/4 4-3 +

3/4.4.7 M AI N STEAM .! NE I SOI.ATI ON V ALVES . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-7 3/4.4.8 S TR UC TU RA L I N TECR I T Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-7 -

3/4.5 EMERCENCY CORE COOLINC SYSTEM l

3/4.5.1 HICH PRESSURE COOLANT I NJECTION SYSTEM . . . . . . . . . . . . . . . . B 3/4 5-1 3/4.5.2 AUTOM ATIC DEPRESSURIZ ATION SYSTEM ( ADS) . . . . . . . . . . . . . . . B 3/4 5-1 3/4.5.3 LOW P RE S S UR E COOLI NG S Y ST EM S . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 5-2 3/4.5.4 SUPPRESSION P00L...................................... B 3/4 5 ,

3/4.6~ CONTAIMMENT SYSTEMS 3/4.6.1 PRlhARY CONTAINMENT................................... B 3/6 6-1 3/4.6.2 DEPRESL ORIZ ATION AND COOLING SYSTEMS. . . . . . . . . . . . . . . . . . B 3/4 6-3 s 3/4.6.3 PRI MARY CONTAINMENT I SO LATION VALVES. . . . . . . . . . . . . . . . . . - B 3/4 6-4 3/4.6.4 VACUUM REL1E."...-- ................................... B 3/4 6-5 3/4.6.5 SECONDARY CONTAINMENT................................. B 3/4 6-5 3/4.6.6 CONTAINMENT ATMOSPHERE CONTR0L........'................ B 3/4 6 [

3/4.7 PLANT SYS"F.MS 1

3/4.7.1 SERVICE WATER SYSTEMS................................. B 3/4 7-1 ?

l- 3/4.7.2 . CONTROL ROOM EMERCENCY FI LTRATION SYSTEM. . . . . . . . . . . . . . B 3/4.7-la -l 3 a

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BRUNSWICK - UNIT 2 XI Amendment No.

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.SECTION PACE.

3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECT 10N...................................... B 3/4 7-la 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM. . . . . . . . . . . . . . . . . B 3/4 7-la.

3/4.7.$ SNUBBERS.............................................. B 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION........................... B 3/4 7-4 3/4.7.1 F I R E SU PP R E S S I O N SY ST EM S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-4 a 3/4.7.8 FIRE BARRIER PENEfR'T10NS............................. B 3/4 7-5 3/4.8 ELECTid C AL POW ER S Y STEM S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B/3/4 8-1 3/4.9 kEFUELINC OPERATIONS 3/4.9.1 R EA CTOR MOD E SW I TCH . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 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 3/4.9.6 CRANE AND HOI ST O PERABI LI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9 3/4.9.7 CRANE TRAV1 L-SPENT FUEL STORACE PD0L. . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 W ATER t.EVEL-REACTOR FUEL STORACE P00L. . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL................................... B 3/4-?-2 3/4.10 SPECIAL, TEST EXCEPTIONS

'3/4.10.1 PRIKARY CONTAINHENT INTECRITY......................... B 3/4 10-1 3/4.10.2 ROD S EQUENCE COHTROL SY STEM ( DELETED) . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.3 S HUTDOWN KARCI N D EMON STRATI ON 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 LA NT S ERV I C E W AT ER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 '

i BRUNSWICK - UNIT 2 XII Amendment No.

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PLANT SYSTEMS SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 The service water system shall be OPERABLE with at leasts-In OPERATIONAL CONDITIONS 1, 2, and 3:

Two OPERABLE nuclear service water pumps, and two OPERABLE conventional service water pumps capable of supplying the nuclear and conventional headers.

In OPERATIONAL CONDITIONS 4 and 5 s

Three OPERABLE site nuclear service water pumpst and two OPERABLE Unit 2 service water pumps, nuclear and/or conventional, powered _from separate emergency buses and capable of supplying the nuclear header.

APPLICABILITY 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 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 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 .

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 rnd 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 e 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 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 .

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

3 ', ,

L _

~43' l I I I

PLANT SYSTEMS {

LIMITING CONDITION FOR OPERATION (Continued)

ACTIONI (Continued) 5.

With only one nuclear 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 and restore the remaining service water pump to OPERABLE status within Otherwise, be7indays at f rom the time of the loss of the first pump.

1 in COLD SHUTDOWNleast withinHOT SHUTDOWN the following within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

6.

With one OPERABLE nuclear service water pump and no OPERABLE.

conventional service water pumps, be in at h the next least HOT SHUTDOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following b.

In OPERATIONAL CONDITION 4 or $t 1.

With one less than the required number of nuclear service water pumps OPERABLE per site, restore at least one additional nuclear I

service water pump to OPERABLE status within 14 days or declare the diesel generators Specitication inoperable and take the ACTION required by 3.8.1.2.

2 With the service water system nuclear header inoperable, or nc Unit 2 nuclene provided that service water pumps OPERABLE, operation may continue the servita water system conventional header is OPERABLE'with at OPERABLE. least two conventional service water pumps Restore the service water system nuclear header to OPERABLE status within 14 days or declare the Core Spray System and F 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 Specification 3.8.1.2.and take the ACTION required by 3.

With less than two OPERABLE site nuclear service water pumps, declare the diesel generators inoperable and take the ACTION required by Specification 3.8.1.2.

4.

With only one Unit 2 service water pump OPERABLE, restore.at least one additional Unit 2 pump. either nuclear or cot.ventional, 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.

i b

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

a-..

-24: - */

,4..

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4

4.7.1.2 The service water system shall be demonstrate ( 'jPERABLE

a. At least once per 31 days by verif ying.that eacr. valve (manual, power-operated, or automatic) servicing safety reteted 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 its carrect 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'l nuclear header is lined up to supply cooling water for the diesel generators by verifying that each valvo servicing the diesel generators that is not locked open is administratively.

controlled in the proper position.

BRUNSWICK - UNIT 2 3/4 7-2b Amc.)dment No.

e .

, .. a-o, -

3/4.7 PLANT SYSTEMS BASES .

3/4.7.1 GERVICE WATER SYSTEMS I Ouring 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 l header to supply diesel generator cooling water. Two pumps are necessary to

. supply sufficient flow to cool all four diesel generators under worst-case scenarios while also supplying flow to other safety and non-safety related j components. Therefore, any combination of three OPERABLE nuclear service . i water' pumps per site will meet the single failure criteria and assure diesel 'l generator cooling. The requirement for two OPERABLE nuclear service water i pumps associated with a unit in OPEP'TIONAL CONDITIONS 1, 2, or 3 and at least i three OPERABLE nuclear service water pumps per site when one or both units are .!

in OPERATIONAL CONDITIONS 4 or $ ensures that emergency diesel generator !

cooling requirements are met. i Af ter the initial ten minutes of a DBA, additional loads require cooling ;

water. These loads include RilR and CS pump room coolers, RilR service w3ter heat exchangers, and RHR pump seal heat exchangers. Evaluations have i determined that the RllR pump seals, as well as the equipment in rooms; serviced-by the RilR and CS room coolers, remain within the manufacturers' 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 failure criterla~.

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 CONDITIONE 4 cod 5, the reduced 1 core decay heat load and the accessibility to the reactor building for manual operator gg.,lon reduce the requirement for OPERABLE service water pumps af ter 2 an accident / transient tu 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 i be supplied, even af ter application of the single f ailure 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.

Tne allowed out-ot-service times and compensatory measures established in ;

the ACTIf N Statements are conservative. In particular, ACTION Statement a.2 for OPERAsTONAL CONDITIONS 1, 2, and 3 requires the unit to be in ll0T SitVTDOWN 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 ,

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

W. -

it E.

3 i a . .

..n, PLANT SYSTEMS BASES 3/4.7.1 SERVICf; WATER SYSTEMS (Continued) demonst rate operation in OPERATIONAL CONDITIONS l' through 3 wi th no OPERABLE nuclear service water pumps is acceptable. provided that at least two nuclear service wate' pumps are OPERABl.E 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 ,

conservative ACTION Statemen'. has been' established in order to minimize the risk of personnel error in administrating this situation.

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

1) the ambient air temperature does not exceed the allowable temperature for >

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 following all credible accident cenditions. 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 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" Hean Sea Level is based on the maximum elevation at which facility flood control measures provide protection to safaty-relcted equipment.

3/4.7.4 REACTOR CORE ISOLATION C00LINC SYSTEM The reactor core isolation cooling systen. (RCICS) is provided to assure adequate core cooling in the event of reactor isolation from its primary heet

sink and.the' loss of feedwater 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 113 i psig even though the Residual Heat Removal (RHR) system provides 3dequate 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 system to be operated. ,

?

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

1

%p l;;7

.<; a

'.i"p-g\.aa.,.

g g> \

1 l-a ENCLOSURE 3

, . BRUNSWICK STEAM ELECTRIC. PLANT,'. UNITS 1 AND 2 NRC DOCKETS 50 325 & 50 324. >

OPERATING LICENSES DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT.

2 '

SERVICE WATER SYSTEM

} (NRC TAC NOS. 76083 AND 76084)

INSTRUCTIONS FOR INCORPQRATION :

r The proposed changes co the Technical'SpecificationsL(Appendix A to' Operating '

Licenses DPR 71 and DPR 62) would be incorporated as follows: !

UNIT 1 f Remove Pagg Insert Para XI XI !

XII XII ;

3/4.7 2 3/4 7 2 l 3/4 7 2a '

3/4.7-2b B 3/4 7 1 B 3/4 7 1 ;

B 3/4 7 la l

, i l

UNIT 2 l Ermove Pane Insert Pare ;

.XI XI ,

XII '

XII

~I 3/4 7 2 3/4 7 2 3/4 7e2a :

3/4 7-2b

.B 3/4 7 1 B 3/4 7 1 B 3/4'7 la ,

i i

a f

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]

ML20059N054

Text

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