Text

Proposed TS 3/4.7.2 Re CR Emergency Filtration sys,3/4.7.3 Re Flood Protection & 3/4.7.4 Re RCIC Sys
	ML20126K788
Person / Time
Site:	Brunswick
Issue date:	12/31/1992
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20126K787	List: ML20126K782; ML20126K788;
References
	NUDOCS 9301070251
	Download: ML20126K788 (30)
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ENCLOSURE 5 4

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2-NRC DOCKETS 50-325 & 50 324 OPERATING LICENSES DPR-71 & DPR-62

- REQUEST FOR LICENSE AMENDMENTS,

SERVICE WATER SYSTEM TECHNICAL' SPECIFICATION PAGES - UNIT 1 t

4 4

9301070251 92'1231 PDR' ADOCK 05000324-P PDR s

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INDEX BASES SECTION PACE 3/4.4 REACTOR COOLANT SYSTEM (Continued) 3/4.4.4 CH EM I S TR Y........................................... 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 MAIN STEAM LINE ISOLATION VALVES.................... B 3 /4 4-7 3/4.4.8 STRU CTUR AL I NT EC RI TY................................ B 3 / 4 4-7 3/4.5 EMERCENCY CORE COOLING SYSTEM 3/4.5.1 HICH PRESSURE COOLANT INJECTION SYSTEM.............. B 3/4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATTON SYSTEM (ADS)............. B 3/4 5-1 3/4.5.3 LOW PRES SURE COOLING SYSTEMS........................ B 3 /4 5-2 3/4.5.4 SUPPRESSION P00L.................................... B 3/4 5-4 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT................................. B 3/4 6-1 3/4.6.2 DEPRESbURIZATION AND C00LINC SYSTEMS................ B 3/4 6-3 3/4.6.3 PRIMARY CONT AINMENT ISOLATION VALVES................ B 3 /4 6-4 3/4.6.4 VACUUM RELIEF....................................... B 3/4 6-5 3/4.6.5 SECONDARY CONTAINMENT............................... B 3/4 6-5 3/4.6.6 CONT AI NMENT ATMOSPHERE CONTR0L...................... B 3 / 4 6-6 l

3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS............................... B 3/4 7-1 0

3/4.7.2 CONTROL ROOM EMERCENCY FILTRATION SYSTEM............ B 3 /4 7-1/

BRUNSWICK - UNIT 1 XI Amendment No.

149

)l INDEX BASES SECTION PACE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECTION......................................

B 3/4 7-1/

3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM.................

B 3/4 7-1g 3/4.7.5 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 PENETRATIONS.............................

B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS.................................

B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH...................................

B 3/4 9-1 3/4.9.2 I N S TR UM EN TATI O N.......................................

B.3/4 9-1 B 3/4 9-1' 3/4.9.3 CONTROL ROD P0SITION..................................

3/4.9.4 DECAY TIME............................................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................

B 3/4 9 '

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 -

3/4.9.10 C O N TR O L R O D R EM 0V AL................................... -

B 3/4 9-2 4

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.........................

B-3/4.10-1

'3 / 4.10. 2.

ROD SEQUENCE CONTROL SYSTEM (DELETED).................

B 3/4~10-1 3 /4.10.'3 ~

S HUTDOWN MARCIN DEMONSTRATION S........................ B 3/4 10-1 3/4.10.4 R EC I R CU LATI ON - L00 P S................................... B 3/4 10-1 3/4.10.5 PLANT SERVICE WATER...................................

B 3/4 10-1 i

a BRUNSWICK - UNIT 1 XII Amendment No. 146

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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 least:

In OPERATIONAL CONDITIONS 1, 2, and 3:

si e Threche 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:

Three OPERABLE ice nuclear service water pumps, and two operable Unit I 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 ACTION:

In OPERATIONAL CONDITION 1, 2, ory IN s E RT a.

d.

I 1.

Witht[oOPERABLEconventionalservicejaterpumpsanddnlyone f

nuclear service water / pump OPERABLE,,testore the remairning nuclear ser/ ice water pump r'o OPERABLE statys within 7 days Mr be in HOT S)f TDOWN within 12/ hours and COLD HUTDOWN within,the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

/

\\

With no OPERABLE nuclear servi'lce water pumps,/regardless of

/

2 y

conventionaf service water pdmp status, be in at least HOT S)dlTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN withift'the following I hours.

f WithtwoOPERABLEnucl,ea/

/

r service water pumps and only pne 3.

conventional service, Water pump OPERAS E, restore at 1,4a s t one addiiional conventional service wate/ pump to OPERABLt status withipn 7 /ays or be in HOT SHUTDOWN within'12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and CodD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .'

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4./

WithtwoOPERABLEnuclearse7 rice water pumps,and no conventi al

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service watef pump OPERABLE restore at leas / one convention service wat'er pump to OPERABLE status withjf 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and store

/

the remajding conventionp( service water ftSump to OPERABLF status within 7 days from the,gime of the loss /of the first p

.p.

Othe ise, be in at 1past HOT SHUTDOW #within the nex 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and 9 in the following'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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in LD SHUTDOWN wi BRUNSWICK - UNIT 1 3/4 1-2 Amendment No. 146

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PLANT SY3TEMS LIMITING CONDITION FOR OPERATION (Continued)

[ ACTION:

( Cd'n t in ue d )

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3

/

/'-

5,./ With only one

' clear service wa er pump and one c ventional service water mp OPERABLE, r store at least on additional servi e

/

wate r pumpf'nuclea r or convent ional, t o OPERAB(.E' s tatus within

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72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months dnd restore the re$aining service wa(er pump to OPERASr E j

j status,within 7 days f rojr'the time of the J ss of the first d

mp.

Otherp,tse, be in at leplit HOT SHUTDOWN wi, thin the next 12 urs and in OLD SHUTDOWN wit)rfn the following,24' hours.

clear service dter pump and no ~

6[./ithoneOPERABL ERABLE conventional seivice water pumps /be in at least H T SHUTDOWN within

/

the next 12 bdurs and in COLD SHbTDOWN within the following l

,/

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

,/

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l,4;.

In OPERATIONA, CONDITION 4 or,Y:

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1.

With'one less than the required number e~f nuclear servicg/ water ppinp s OP ER AB LE p e r,s i t e, r e s t o re a t 14'a s t one additional' nuclear service water pump to OPERABLE stat)('s within 14 days,d'r declare the

/dieselgeneratorsinoperableandfaketheACTIONrq,uiredby

/

S pec i f i c a t ion /3. 8.1. 2.

With the pe/

/

rvice water syst, gin nuclear header 'noperable, or n 2.

Unit 1 p6 clear service water pumps OPERABL operation may co tinue

'(

provide,d that the servicI. water system c ventional header,,i's OPERABLE with at leas /two conventional service water pumps

~

OPCRABLE. Restore tfIe service water,rfstem nuclear header to

.0PERABLE status wi(hin 14 days or dfclare the Core Sp,r$y System and

/ the LPCI System /i'noperable and taVe the ACTION req'ui' red by Speci f ication/3.5.3.1 and 3.5. (2. Also, declare the diesel

/

generators jdoperable and uk the ACTION requir$d by

./

Speci f ic at4on 3.8.1.2.

,/

With le/ss than two OPERA LE site nuclear pe/

rvice water pump

'/

3.

dec14re the diesel geoirators inoperableand take the ACT N reqYired by Specificftion 3.8.1.2.

,/

/

4.

With only on: Or>It I service wate pump OPERABLE, r tore at least oneadditiona/ Unit 1 pump, eit) r nuclear or con ntional, powere fromasepa[teemergencybus/toOPERABLEstaty within 7 days Core Spray Systyin and the LPCI Sy fem inoperable a f'

declare t ACTIONrequiredpfSpecifications)f.5.3.1and3.5.3.

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(f take th BRUNSWICK - UNIT 1 3/4 7-2a Amendment No. 146

n g.

-g-INSERT A 1.

With one OPERABLE conventional service' water pump, restore at least one additional

conventional service water pump 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 COLD shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

With no conventional service water pumps OPERABLE, restore at least one conventional service water pump to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-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 .

3.

With two OPERABLE site nuclear service water pumps, unless the provisions of._

ACTION b.4 apply for Unit 2, restore one additional site nuclear service water pump within 7 days.or be in at least 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 site nuclear service water pumps and less than two OPERABLE conventional service water pumps, restore at least two conventional service water pumps to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least 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 .

5.

With less than two OPERABLE site nuclear service water pumps, be in at'least 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 .

b.

In OPERATIONAL CONDITIONS 4 or 5:

1.

With one OPERABLE Unit 1 service water pump, restore at least two Unit 1 service-water pumps to OPERABLE status within 7 days or declare the Core Spray and LPCI systems inoperable.

2.

With,o OPERABLE Unit 1 ~vice water pumps, declare the Core Spray and LPCI f

systems inoperable.

3.

With two OPERABLE site nuclear service water pumps, unless the provisions of..

ACTION b.4 apply, restore at least one additional nuclear service water. pump to-OPERABLE status within 7 days or declare the diesel generators inoperable.

i.

4.

With the service water system nuclear header inoperable, operation of both units may continue provided that two Unit 2 nuclear service water pumps are OPERABLE, both units' nuclear service water header valves are administratively controlled as required ~

to ensure cooling water to the diesel generators, at least two Unit 1-conventional service water pumps are OPERABLE on the conventional header, and vital ECCS loads are a.igned to the conventional service water system header. Restore the service water :

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- system nuclear-~ header and at least three site - nuclear service water pumps to

. OPERABLE status within 14 days.' Otherwise, declare the core spray system, the LPCI system, and the diesel generators inoperable.

5.

With less than two OPERABLE site nuclear service water pumps, declare the diesel generators inoperable.

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I t-PLANT SYSTEMS SURVEI LLANCE REQUIREMENTS -

4.7.1.2 The service water system shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying ~that each valve (manual,-

~ power-operated, ~ or_ automatic) servicing safety related equipment -

that-is not locked, scaled, or otherwise secured in position, is in-its. correct position.

b.

'At least. once per 18 months. during shutdown, by veri f ying that _.each r

automatic valve servicing safety-related equipment actuates.to its~

correct ~ position on the appropriate ECCS actuation test signals,.

fin OPER,ATIONAL CONDITION 4 r 5 with service yater system nucte y

--7

-lt c.

headeyinoperable,_verif that the service hter system -convertnonal header is lined up to pply; cooling wate.to..vi tal-_- ECCS loads and tpfIt the Unit 2 nucl r header is line up to-supply _ cool' g water.

,/for the' diesel gen ators by verifyir that_each valve rvicing the dies'el generator that_is not rock open is-'administ tively-e (controlled in e proper positio_.

Deleted. (See ACTION b.4-))

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. BRUNSWICK - UNIT 1 3/4'7-2b

' Amendment N o.- _ _II.6 1.,-.

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SPECIAlf TEST' EXCEPTIONS 3/4 1005-PLANT SERVTCE WATER.

LIMITING CONDITION FOR OPERATION 4

3.10.5.

The service water. conventional header required to be operating per Specification _3.7.1_.2 ACTION b.

may _ be removed - f rom operation by.

stopping the pumps to permit isolating and draining _ the service water nuclear header for maintenance provided that The service water conventional header remains lined up to supply a.

cooling water to the required ECCS-loads.

b.

The draining / maintenance on the service water nuclear header will not affect the service water conventional system or lineup described in a.

above.

c.

Average coolant temperature-is 1100 F -and the heatup rate is.

110 F per hour.

d.

Two dedicated qualified members of the unit operational staff are assigned to initiate _ the service water conventional 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 offsite power occurs.

O PERATloNAL.

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

ACTION: With the requirements of the. sbove specification not satisfied, as soon as practicable, restore the r -

4.

Service water conventional header to operating status per the a.

requirements of Specification 3,7.1.2 ACTION b.

, or b.

Service water nuclear header to OPERABLE status per Specification 3.7.1.2.

SURVEILLANCE REOUIREMENTS 4.10.5 When the service water conventional header is not operating as specified above:

Prior to securing all service water pumps, verify that the a.

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

BRUNSWICK - UNIT I 3/4 10-5 RETYPED TECH.-SPECS.

Updated Thru. Amend. 53

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'I 3/4.7-PLANT SYSTEMS BASES

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-3 /. 7.1 SERVICE WATER SYSTEMS-uring the initial 1 stage of a DBA (0-10 minutes), the service wate syst em provides lube water and service water cooling to the' diesel ~

~

The service water system design allow's either unit's nug ear generat s.:

header t supply diesel generator cooling -water..Two_pumpsLare nec/ssary to supply suf 'cient flow to cool all four diesel generators under wofst-ci.se scenarios wh'le also supplying flow to other saf ety^and non-safely related--

-components.

erefore, any combination of three OPERABLE nucl r 'se rvice'.

water pumps pe site will meet the single failure criteria an assure diesel generator coolin. The requirement for two OPERABLE nuclea service water pumps associated

'th a unit in OPERATIONAL CONDITIONS 1,

, ' or 3.and: at'~ least three OPERABLE.nucibar~ service water pumps per site when ne or both units.are inOPERATIONALCONDIT(ONS4or5ensuresthat emergency tesel generator.

coolang requirements-a y met.

After the. initial te minutes of a DBA, additi nal loads re' quire cooling water.

These loads includ RHR and CS pump room p olers,- RHR service water heat exchangers, and.RHR puma seal heat exchange 7s.-

Evaluations have:

determined that the RHR-pump stals, as well as he equipment fn'roomstservice'd by the RHR and CS room coolers, emain within he manufacturers' temperature'

. limits for the first ten minutes f a DBA.-

o meet the additional loads-t during the post-ten minute stage o a DBA, wo service water pumps on.the -

affected unit must:be in service.

n ord r to assure single failure criteria.

is met, theTechnicalSpecificationrkqfrestwoOPERABLEconventionalservice-water pumps per unit'while in OPERATIO 1; CONDITION:1, 2, or 3.

As discussed above, when in.0P TIO AL CONDITIONS 4 and 5, the reduced core decay heat-load and the acces/ibility \\o the reactor building for manual operator action reduce the requirement for 0 RABLE service-water' pumps lafter an' accident / transient to one.-Jherefore, whe in OPERATIONAL CONDITIONS.4

- or 5, two OPERABLE service wat4r pumps (any com ' nation of; nuclear and/or conventional) capable of-su ying the nuclear he der are-required'provided that-there are at least th e OPERABLE nuclear ser 'ce water pumps' per site.

!Haintaining two OPERABLE ervice water pumps-(nucleag and/or conventional) on-the unit while in OPERA ONAL CONDITIONS 4 or 5 assureg -lon'g-term cooling.can '

be supplied, even af te application of the ' single ' failu\\e criteria.

Stipulating at least hree ' OPERABLE nuclear service watets pumps per site -

assures diesel gene cor cooling will be available followib any-DBA, regardless of whic unit suffers the accident / transient.

3-

.The allowe out-of-service times and compensatory measure established in the ACTION St ements'are conservative.

In particular, ACTION atement a.2.

for OPERATIO - L CONDITIONS 1, 2, and 3 requires the unit to.be in OT. SHUTDOWN within 12 h urs and la COLD SHUTDOWN 'within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ich no OPERABLE clear. service water' pumps. Analyses have been performed khich -

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l' RUNSWICK - UNIT 1 B 3/4 7-1 Amendment No.

46-A

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3/4.'7 PIANT SYSTEMS BASES

-3/4.7.1-SERVICE WATER SYSTEMS The service water system is designed to provide cooling water for the removal of

-heat from equipment such - as - the emergency diesel generators, Residual Heat Removal (RHR) pump ' coolers, and room coolers for Emergency Core Cooling System (ECCS) equipment,-that is required for a safe reactor shutdown following design basis - accident (DBA) or transient.

The service water system also

~

a provides cooling to the Reactor Building Closed Cooling Water (RBCCW): System and the Residual Heat Removal Service Water (RHRSW) System,. as required, -- during -

normal and shutdown operation.

The service water system provides lubricating water for the service water pumps and cooling water for the service' water pump

~

motors. During the initial stage (0 - 10 minutes) of a LOCA or LOOP, the service water system must automatically provide cooling water to the emergency diesel generators. Following the first ten minute period, additional safety-related and shutdown cooling loads must be supplied. The service water system also provides flow to the Turbine Building Closed Cooling - Water System, the Chlorination System, and fill to the Circulating Water System.

The service water system design all is either (or both) unit's nuclear header to-supply diesel generator cooling wa ar when required. The phrase " site nuclear.

service water pump" refers to any nuclear service water pump on either unit.

Other pump designations refer to the specific-unit under discussion. The four-nuclear service water pumps on site, two per unit, are - each 'on. a separate emergency < bus so that a single failure could prevent only one nuclear service water pump from operating.

The OPERABILITY requirements are structured to ensure - that the Service Water System is capable of automatically supplying sufficient cooling water for the Diesel Generators assuming no operator. action for the first 10 minutes following-a -DBA, and that at-least one service water pump per unit is available to supply

[

the safety-related and shutdown cooling. loads after the first ' ten minutes following a DBA. The OPERABILITY requirements for' the service water system are, in general, based on - a LOCA (Loss of Coolant. Accident). and in some ' cases combined with a LOOP (Loss of Offsite Power), since this event or combination would provide the most significant challenge to the system's capabilities.

' The four nuclear. service. water pumps are powered from separate. emergency buses.

The three conventional' service water pumps on each unit are on separate emergency _

buses.

For'each unit, two of the conventional pumps are on the same emergency-buses as the two unit nuclear service water pumps. The loss of one nuclear pump-and one conventional pump on the unit-due to a single failure of one emergency.

bus-has-been accounted for in -the OPERABILITY-requirements.

.However, conventional service water pump OPERABILITY will be more strictly _ defined-in; cases where only one nuclear pump and one conventional-pump are available for operation.

Therefore, with one unit nuclear.^ service water pump and one conventional service water pump available, the' conventional service water pump must be powered from a separate emergency bus to be considered OPERABLE; BRUNSWICK UNIT - 1 B 3/4 7-1 Amendment No, i

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3/4.7-PLANT SYSTEMS BASES 3/4.7.1 SERVICE WATER SYSTEMS (Continued)

In OPERATIONAL CONDITIONS 1, i, and 3, a conventional service water pump must be capable of supplying water to both the nuclear header and the conventionalLheader to be considered OPERABLE.

This will ensure that the vital header and RHR service water heat exchangers can be supplied from either header when a single failure of any header isolation valve is assumed and personnel access is not available for manual valve alignment. In OPERATIONAL CONDITIONS 4 and 5, because of reduced primary pressure, the possibility of a.LOCA is not considered credible and access is considered available to manually position header isolation valves -

if required. Therefore, in OPERATIONAL CONDITIONS 4 and 5, a conventional pump may be considered OPERABLE when only the nuclear header discharge valve is OPERABLE except as specifically identified in the ACTION statement for a nuclear header outage.

This allows. maintenance on the conventional header without reducing service water system OPERABILITY. However, a conventional pump aligned to the nuclear header is not considered to meet the requirements for an OPERABLE nuclear pump since it is not automatically powered and restarted on the-diesel-generators following an accident signal.

For OPERATIONAL CONDITIONS 1, 2,

3, 4,

and 5, and a DBA in either unit, two nuclear service water pumps from one or both units are capable of supplying sufficient flow to cool all four emergency diesel generators under worst-case scenarios while also supplying flow to other potential flow paths (vital header -

loads, cross-header leakage, and lubewater). To prohibit any single failure from preventing the supply of service water to the diesel generators during the first 10 minutes following a DBA, at least three nuclear service water pumps per site are required while in OPERATIONAL CONDITIONS 1, 2, 3, 4, or 5.

Af ter the first ten minutes following a DBA, additional loads may require cooling water on the affected unit. These loads include RHR and CS pump room coolers, RHR service water heat exchangers, ard RHR pump seal -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 manufacturers' temperature limits for at least the first ten minutes of a DBA. Operator action is credited af ter the first 10 minutes following a DBA to make the necessary pump and valve alignments either remotely or manually, except that manual action inside the Reactor Building following a LOCA while in OPERATIONAL CONDITIONS 1, 2, and 3 is not credited because of the potential for unsafe conditions.

In OPERATIONAL CONDITIONS 1, 2,

and 3, one conventional - service water pump supporting the affected unit is capable of supplying the - additional required sa fe ty - rela ted and shutdown equipment.

No ' single failure can prevent the-necessary loads from being aligned to one of the nuclear or conventional headers by manual or remote operator action.

To prohibit any single failure from preventing the supply of service water after the first 10 minutes following a DBA, at least two operable conventional service water pumps are required while in OPERATIONAL CONDITIONS 1, 2, or 3.

BRUNSWICK UNIT - 1 B 3/4 7-la Amendment No, y

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,: t r 3/4.7 PLANT SYSTEMS I BASES 3/4.7.1 SERVICE WATER SYSTEMS (Continued)

In OPERATIONAL CONDITIONS.4 and 5, one unit service. water pump, nuclear or conventional', is capable of supplying the. additional required safety-related and shutdown equipment. Manual action in the Reactor Building is credited-to align equipment to the nuclear header if required. To prohibit any single failure:from preventing _ the supply of service water after the.first 10 minutes following a =

DBA, at least two OPERABLE unit service water pumps, nuclear or conventional,.are required while in OPERATIONAL CONDITIONS 4 and 5.

~

The allowed out of-service times and compensatory measures established in ' the ACTION statements are conservative. Although the probability and consequences.

of a DBA are reduced in OPERATIONAL CONDITIONS 4 and 5, the ACTION' statements for the nuclear service water pumps for a unit in OPERATIONAL CONDITIONS 4-or 5 are based on the assumption that'the other unit.is in OPERATIONAL CONDITIONS l',2, or 3.

Specific ' ACTION statements and LCO time limits-have not been established :

-for both units in OPERATIONAL CONDITIONS 4aor 5 since the ACTION statements for

~

.one unit in OPERATIONAL CONDITIONS 4 or 5 are more conservative.

In OPERATIONAL CONDITIONS 4 and 5, because of reduced core [ decay heat load,s the,

reduced possibility of a U}CA, and the accessibility to tha reactor building for manual operator action, the vital header loads could' be manually aligned to the nuclear header if~a failure prevented remote valve. alignment.

Therefore,'the operability requirements-for the unit service water pumps apply for nuclear or

. conventional pumps.

With one OPERABLE unit service water' pump,' the ' core spray and-LPCI systems remain OPERABLE. ' However, to minimize the possibility of loss of these systems due to loss of the single pump, the out-of-servi ~ e time for one c

OPERABLE unit service water pump is set at 7 days. For no OPERABLE unit service water pumps, the core-spray and LPCI systems must be; declared inoperable. 'This.

is equivalent to' the ACTION statement for core spray;and LPCI systems -inoperable.

ACTION statement '3.7.1.2.b.4' for OPERATIONAL CONDITIONS -4 and 5 allows one unit -

to operate with the nuclear service water: header inoperable for-up to.14 days

~

provided that:

a) two nuclear service water pumps are OPERABLE on the other unit.

-b) both unit's nuclear service water header valves are administrative 1y-controlled as - required to ensure coolingL water : to - the.. diesel generators, c) the service water system conventional header-is-OPERABLE -with two unit conventional service water pumps OPERABLE, and'

~

d) vital : ECCS loads are. aligned to the. conventional service. water -

system header.

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

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3/4.7 PLANT SYSTEMS BASES 3/4.7.1 SERVICE WATER SYSTEMS (Continued)

Considering any additional single failure, this requirement ensures at least one OPERABLE nuclear service water pump to supply the Diesel Generators _during the first 10 minutes af ter a DBA and one OPERABLE conventional service water pump to supply the unit safety-related and shutdown cooling loads following the first 10 minutes after a DBA. By requiring administrative control of both unit's nuclear header valves, the ACTION statement minimizes the risk of inadvertent valve action that could reduce cooling water flow to the diesel generators.

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

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i PLANT SYSTEMS BASES 3777154 JERVICE WATER SYSTEMS (Continued) demons t rat e operat t o.

PERATIONAL CONDITIONS I through 3 wirk tRABLE nuclear service water pumps table provided r"

s teast two nuclear a

is service water pumps are OPERABLE on en e unit and two conventional pump s a r e OP ER AB LE o n t hepe:rTnTt.

Spec CTION statements and LCO time limits for th,3-,trCatton have not been developed a more conserv ' '

v ION Statement has been established in order to -

' mice the of personnel error in administrating ~this situation.

..t 3/4.7.2 CONTROL ROOM EMERCENCY FILTRATION SYSTEM The OPERABILITY of the cont rol room ventilation system ensures that

1) the ambient air tempsrature 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 accidenC 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 5 rem or less, uhole body, or its equivalent. This limitation is consistent with the requirements of Ceneral 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" Mean Sea Level is based on the maximum elevation at which facility flood control measures provide protection to safety-related equipment.

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 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 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 system to be operated.

BRUNSWICK - UNIT 1 B 3/4 7-l/'

Amendment No. [46 j

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ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS ~ 50-325 & 50 324 OPERATING LICENSES DPR-71 & DPR 62 REQUEST FOR LICENSE AMENDMENTS SERVICE WATER SYSTEM TECHNICAL SPECIFICATION PAGES - UNIT 2 pair

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_6 INDEX BASES SECTION PACE 3/4.4 REACTOR COOLANT SYSTEM (Continued) 3/4.4.4 CHEMISTRY...........................................

8 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY.................................... B.3/4 4-2 3/4.4.6.

PRESSURE / TEMPERATURE LIMI TS.......................... B 3 /4 4-3 3/4.4.7 M AI N STEAM LI NE I SOLATI ON V ALVES..................... B 3 /4 4-7 3/4.4.8 S TRUCTU RAL I NTECR I TY.................................. B 3 / 4 4 - 7 3/4.5 EMERCENCY CORE COOLING SYSTEM 3/4.5.1 HICH. PRESSURE COOLANT INJECTION SYSTEM............... B 3/4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS).............. B 3/4 5-1 3/4.5.3 LOW PRESSURE COOLING SYSTEMS......................... B 3/4 5-2 3/4.5.4 S U P PR ES S I ON P00 L..................................... B 3 / 4 5 -4 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY C0NTAINHENT.................................. B 3/4 6-1 3/4.5.2 DEPRESSURIZATION AND COOLING SYSTEMS................. B 3/4 6-3 1

3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES................. B 3/4 6-4 3/4.6.4 VACUUM RELIEF........................................~B 3/4 6 3/4.6.5 SECONDARY CONTAINMENT................................ f. 3/4 6*$

3/4.6.6 CONTAI NHENT ATMOS PHER E CONTR0L....................... B 3 /4 6-6 l

3/4.7 PLANT SYSTEMS 3/4.7.1 S ER V I CE W AT ER S Y S TE MS................................ B 3 / 4 1-l' 3/4.7.2 CONTROL ROOM EMERCENCY FI LTRATION SYSTEM............ 8 -3 /4 7-ly i

BRUNSWICK - UNIT 2 XI Amendment No. 179-

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.l INDEX c

BASES PACE SECTION 3/4.7 PLANT SYSTEMS (Continued) d 3/4.7.3 FLOOD PROTECTION......................................

-B 3/4 7-1/

B3/4-7.la"d I

f 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM.................

B.3/4 7-2 3/4.7.5 SNUBBERS..............................................

3/4.7.6 SEALED SOURCE CONTAMINATION.........................

R'3/4 7-4 3/4.7.7 FIRE SUPPRESSION SYSTEMS..............................

8_3/4 7-4 3/4.7.3 FIRE BARRIER PENETRATIONS.............................

B 3/4 7-5 t

3,/4.8 ELECTRICAL POWER SYSTEMS.................................

8/3/4 8-1 3/4.9 REFUELINC OPERATIONS 1

3/4.9.1 R EA CTOR H OD E SW i T CH...................................

8 3/4 9-1 3/4.9.2 INSTRUMENTATION.......................................

B 3/4 9-1 3/4.9.3 CONTROL ROD POSITION..................................

6 3/4 9-1

.3/4.9.4 DECAY TIME............................................

8 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 STC3 ACE P00L.................

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

B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 P R DtARY CONTA I NMENT I CTECRITY......................... B 3/4'10-1

-3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED)................. 8 3/4-10 3/4.10.3 SHUTDOWN MARCIN DEMONSTRATIONS........................

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

B 3/4 10-1 3/4.10.4 3/4.10.5 PLANT SERVICE WATER...................................

B 3/4 10-1 4

BRUNSWICK - UNIT 2 Xil Amendment No. 177

(

4 PLANT SYSTEMS SERVICE WATER SYSTEM LIMITINC CONDITION FOR OPEPATION 3.7.1.2 The service water system shall be OPERABLE with at least:

In OPERATIONAL CONDITIONS 1, 2, and 3:

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

~

In OPERATIONAL C3NDITIONS 4 and 5:

Three OPERABLE site nuclear service water pumps; and two OPERABLE Unit 2 service water pumps, nuclear and/or conventional, powered f rom separate

,cy buses and capable of supplying the nuclear header.

emer APPLICABILITY:

OPERATIONAL CONDITIONS 1,12, 3, 4, and 5 ACTION:

INSERT 3 a.

In OPERATIONAL CONDITION 1, 2, or F 1.

With two OP$RABLE conver.tionp( service water pumps and only one [

p nuclear service water pump 0PERABLE, restore phe remaining nuclear j

service' water pump to OPF,KABLE status within/7 days or be in HOT SHUTD6WN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 'and CO'LD SHUTDOW1/within the followir$g 24 h'ours.

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2. f/ With no OPERABLE, nuclear service wate'r pumps, regardless of

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conventional ser'vice water pump spatus, be in at least HOT SHUTDOWN

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within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 's and in COLD SHUT 00WN within the foIIowing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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3.

With two,0PERABLE nuclear service water pumps and only one j

conventional service water pump OPERABLE, re# tore at least one addit,ional conventional service water pump /f o OPERABLE statu,p/within

/

7 da'ys or be in HOT SHUTDOWN within 12 c'urs and COLD SHUT 'WN within the f ollowiry( 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

WithtwoOPERABLknuclearservicedaterpumpsandnotonventional 4

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service water / pump OPERABLE, restore at least one pdnventional j

service water pump to OPERABLF/ status within 72 b6urs and restore /

j the remaining conventional y[rvice water pump Jd OPERABLE status within / days f rom the tied of the loss of tM first pump.

OtherM se, be in at leap [ HOT SHU~DOWN witidn the next 12 ho s and

(

in,C6LD SHUTDOWN withjd the following 24 dours.

j/

j BRUNSWICK - UNIT 2 3/4 7-2 Amendment No. 177 l

a. --

4 PLANT SYSTEMS LIMITINC CONDITION FOR OPERATION (Continued)

[ ACTION:

(Contded) l 5.

W only one nuclear ser, ice water pump and one fonventional service water pump OPERABLE, restore at least ope additional service water pump, nuclear o/ conventional, to OPERA LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and restor ( the remaining service ter pump to OPERABLE' status within 7 d[ys from the time of th oss of the first pump.

Otherwise,bej(at least HOT SHUTDOWN tchin the next 12, hours and in COLD SHUTDOWN within the followin - 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

6.

With one RABLE nuclear servic water pump and no OPERAR E

=

conventional service water pum, be ir; at'least HOT SHUTDOWN within the n$xt 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COL SHUTDOWN within the-foll'owing-24 fiours.

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^

b.

In,0PERATIONAL CONDITION 4 51 fl.

With one less thanjt'he required number of clear service water

/

pumps OPERABLE p f site, restore at'less one additional nuclear

/

service. water mp to OPERABLE status w thin 14 days or declar the-diesel gener ors inoperable and tak the ACTION required by Specification 3.8.1.2.

/

2.

With e servi'ce water system clear header-inoperabl, or no Uni nuclear' service water umps OPERABLE, operati may continue.

ppivided that the service pater system conventiona header is:

PERABLE with at least two conventional service yater pumps-OPERABLE.. Restore the/ service' water system nu fear header.to 0PERABLE status within 14 days or declare t ore Spray' System and f

the LPCI System io/

Specifications )d.perable and take.the ACT ON required by

/

3.1 and 3.5.3.2.

Als, declare the diesel

/

I generators inpferable and take.the ACT N required by

/

Specificatfra 3.8.1.2.

3.

With less than two OPERABLE sit nuclear service water ppmps, declar$ the diesel--generators i'noperable and take the CTION

~

f re wired by Specification 3,8.1.2.

4.

ith'only one_ Unit 2.se + ice water pump 0PERABL restore at least.

one additional Unit 2 ump, either_ nuclear or /onventional, powere j

from a separate emeygency bus, to OPERABLE catus within 7 days-o

-declare the Core pray System and the LPC System' inoperable a take the ACTION required by Specificati s 3.5.3.1 and 3.5.3..---

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BRUNSWICK - UNIT 2 3/4 7-2a Amendment No. 177

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1 4

I INSERT B 1.

With one OPERABLE conventional service water pump, restore at least one additional conventional service water pump 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 COLD shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

~

2.

With no conventional service water pumps OPERABLE, restore at least one conventional service water pump to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-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 .

3.

With two OPERABLE site nuclear service water pumps, unless the provisions of ACTION b.4 apply for Unit 1, restore one additional site nuclear service water pump within 7 days or be in at least 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 site nuclear service water pumps and less than two OPERABLF conventional service water pumps, restore at least two conventional service water pumps to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SP'JTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.

With less than two OPERABLE site nuclear service water pumps, be in at least 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 , b.

In OPERATIONAL CONDITIONS 4 or 5:

1.

With one OPERABLE Unit 2 service water pump, restore at least two Unit 2 service water pumps to OPERABLE status within 7 days or declare the Core Spray and LPCI systems inoperable.

2.

With no OPERABLE Unit 2 service water pumps, declare the Core Spray and LPCI systems inoperable.

3.

With two OPERABLE site nuclear servics water pumps, unless the provisions of ACTION b.4 apply, restore at least one additional nuclear service water pump'to -

OPERABLE status within 7 days or declare the diesel generators inoperable.

4.

With the service water system nuclear header inoperable, operation of both units may continue provided that two Unit 1 nuclear service water pumps are OPERABLE, both units' nuclear service water header valves are administratively controlled as required to ensure cooling water to' the diesel generators, at least two Unit 2 conventional service water pumps are OPERABLE on the conventional header, and vital ECCS loads

g ',- g --

l are aligned to the conventional service water system header. Restore the service water system nuclear-header and at least three site nuclear _ service water pumps to OPERABLE status within 14 days. Otherwise, declare the core spray system, the LPCI system, and the diesel generators inoperable.

5.

With less than two OPERABLE site nuclear service water pumps, declare the diesel generators inoperable.

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.1.2

'The service water system shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety related equipment I

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 correct position on the appropriate ECCS actuation test signals.

3 l

On[ der -inoperable, verif y hat the service waterjystem conventio CRATIONAL CONDITION 4 5 with service waterfystem nuclear c.

hea desder is lined up to s ply enoting water to vital ECCS loads and that the Unit 1 nucle, r header is lined up to/ supply cooling water for the diesel gene ators by verifying'tha 'each valve servicing.

e diesel generators hat i s not locked ope as administratively (controlled in t e proper position.

Je,eted (See ACTION b. 4-)'.

4 BRUNSWICK - UNIT 2 3/4 7-2h Amendment No. 177

~

e SPECIAL TEST EXCEPTIONS 3/4 10.5 PLANT SERVICE WATER I.IMITING CORDITION FOR OPERATION 4

3.10.5 The service water conventional eader required to be operating per Specification 3.7.1.2 ACTION b.

may be removed f rom operation by stopping the pumps to permit isolating and draining the service water nuclear header for maintenance provided thatt a.

The service water conventional header remains lined up to j

supply cooling water to the required ECCS loads.

j b.

The draining /pr ~ ?nane. on the service water nuclear header will not affs<Y pX-

'i t water conventional system or lineup described in > ske' c.

Average coolant dn e.u re _ 04 <100*F and the heatup rate is 110*P per hour.

d.

Two dedicated, qualified combers of the unit operational staf f are assigned to inittate etye service water conventional heade~r 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 offsite power occurs.

O PER ATloN AL APPLICABILITY: ACONDITIONS 4 and 5 with the nuclear header inoperable.

ACTION:

With the requirements of the above specification not satisfied, as soon as practicable, restore thet 4

a.

Service water conventional header to operatinghstatus per the requirements of Specification 3.7.1.2 ACTION b.), or b.

Service water nuclear header to OPERABLE status per Specification 3.7.1.2.

SURVEILLANCE REOUIREMENTS 4.10.5 When the service water conventional header is not operating as specified above:

a.

Prior to securing all service water pumps, verify that the service water conventional header is lined up to supply cooling water for ECCS by verifying that each valve servicing safety-related equipment that is not locked _in the proper position is administratively controlled in the proper position.

BRUNSWICK - UNIT 2 3/4 10-5 RETYPED TECH. SPECS.

Updated Thru. Amend. 78

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4. 7 PLANT SYSTEMS BA 3/4.7 L ERVICE WATER SYSTEMS DuriQ the initial stage of a DBA (0-10 minutes), the service water system prow des lube water and service water cooling to the dies generators. The service water system design allows either unit's nuclear header to sup ly diesel generator cooling water. Two pumps ar necessary to supply suffici t flow to cool all four diesel generators un r worst-case scenarios while t so supplying flow to other saf ety and non safety related components. Ther ore, any combination of three OPERABLE uclear service water pumps per sit will meet the single failure criteri and assure diesel generator cooling.

e requirement for two CPERABLE nu ear service water pumps associated with unit in OPERATIONAL CONDITIONS

, 2, or 3 and at least three OPERABLE nuclear ervice water pumps per site w en one or both units are in OPERATIONAL CONDITION \\4 or 5 ensures that emerg cy diesel generator cooling requirements are n. t.

After the initial ten m utes of a DIIA, adp tional loads require cooling These loads include PH and CS purip to coolers, RHR service water exchangers, and RHR pump (se 1 heat excha gers.

water.

Evaluations have heat determined that the RHR pump seal, as well s the equipment in rooms serviced by the RHR and CS room coolers, re in wit n the manufacturers' temperature limits for the first ten minutes of DBA To meet the additional loads during the post-ten minute stage of a

, two service water pumps on the affected unit must be in service. In der to assure single f ailure criteria is met, the Technical Specification r qu'res two OPERABLE conventional service water pumps per unit while in OPERA ONAL. ONDITION 1, 2, or 3.

As discussed above, when in ERATIONAL ONDITIONS 4 and 5, the reduced core decay heat load and the ac ssibility to he reactor building for manual operator action reduce the req rement for OPE BLE service water pumps after an accident / transient to one.

Therefore, when i OPERATIONAL CONDITIONS 4 or 5, two OPERABLE service w ter pumps (any combin tion of nuclear and/or conventional) capable of a plying the nuclear head are required provided that there are at least t ree OPERABLE nuclear servic water pumps per site.

Maintaining two OPERABLE service water pumps (nuclear d/or conventional) on theunitwhileinOPERp10NALCONDITIONS4or5 assures ong-term cooling can be supplied, even af tyr application of the single failure criteria.

Stipulating at least/three OPE.RABLE nuclear service water mps per site assures diesel gen stor cooling will be available following any DBA, regardless of whi unit suffers the accident / transient.

The allow out-ot service times ano compensatory measures stablished in the ACTION St ements are conservative. In particular, ACTION St ement a.2 for OPERATIO AL CONDITIONS 1, 2, and 3 requires the unit to be in I T SHUTDOWN within 12 urs and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months w th no

h OPERABLE clear service water pumps. Analyses have been performed w c

/

P UNSWICK - UNIT 2 B 3/4 7-1 Amendment No. 17

o' s

s 3/4.7 PLANT SYSTEMS BASES 3/4.7.1 SERVICE VATER SYSTEMS The service water systern is designed to provide cooling water for the removal of heat from equipment such as the emergency diesel generators, Residual Heat Removal (RllR) pump coolers, and room coolers for Emergency Core Cooling System (ECCS) equipment, that is required for a safe reactor shutdown following design basis accident (DBA) or transient.

The service water system also a

provides cooling to the Reactor Building Closed Coniing Water (RBCCW) System and the Residual Heat Removal Service Water (RHRSW) System, as required, during normal and shutdown operation.

The service water system provides lubricating water for the service water pumps and cooling water for the service water pump motors. During the initial stage (0 - 10 minutes) of a LOCA or LOOP, the service water system must automatically provide cooling water to the emergency diesel Generators. Following the first ten minute period, additional safety-related and shutdown cooling loads must be supplied. The service water system also provides flow to the Turbine Building Closed Cooling Water System, the Chlorination System, and fill to the Circulating Water System.

The service water system design allows either (or both) unit's nuclear header to supply diesel generator cooling water when required. The phrase " site nuclear service water pump" refers to any nuclear service water pump on either unit.

Other pump designations refer to the specific unit under discussion. The four nuclear service water pumps on site, two per unit, are each on a separate emergency bus so that a single failure could prevent only one nuclear service water pump from operating.

The OPERABILITY requirements are' structured to ensure that the Service Water System is capable of automatically supplytag sufficient cooling water for the Diesel Generators assuming no operator action for the first 10 minutes following a DBA, and that at least one service water pump per unit is available to supply the safety related and shutdown cooling loads after the first ten minutes following a DBA. The OPERABILITY regt.irements for the service water system are, in general, based on a LOCA (Lou. f Coolant Accident), and in some cases combined with a LOOP (Loss of Offslu Power), since this event'or combination would provide the most significant challenge to the system's capabilities.

The four nuclear service water ptunps are powered from separate emergency buses.

The three conventional service water pumps on each unit are on separate emergency buses.

For each unit, two of the conventional pumps are on the same emergency

, buses as the two unit nuclear service water pumps. The loss of one nuclear ptunp and one conventional pump on the unit due to a single -failure of one emergency.

bus -has been accounted--for in the OPERABILITY-requirements.

However, conventional service water pump OPERABILITY will be more strictly defined in cases where only one nuclear pump and one conventional ptunp are available-for I

operation.

Therefore, with one unit nuclear service water ptump and one conventional service water pump available, the conventional service water pump must be powered from a separate emergency bus to be considered-OPL 'BLE.

l l

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

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4 3/4. 7 Pl ANT SYSTEMS i

BASES 3/4.7.1 SERVICE WATER SYSTEMS (Continued)

In OPERATIONAL CONDITIONS 1, 2, and 3, a conventional service water pump must be capable of supplying water to both the nuclear header and the conventional header to be considered OPERABLE.

This will ensure that the vital header and RHR service water heat exchangers can be supplied from either header when a single failure of any header isolation valve is assumed and personnel access is not available for manual valve alignment. In OPERATIONAL CONDITIONS 4 and 5, because of reduced primary pressure, the possibility of a LOCA is not considered credible and access is considered available to manually position header isolation valves if required. Therefore, in OPERATIONAL CONDITIONS 4 and 5, a conventional ptunp may be considered OPERABLE when only the nuclear header discharge valve is OPERABLE except as specifically identified in the ACTION statement for a nuclear header outage This allows maintenance on the conventional header without reducing service water system OPERABILITY. However, a conventional pump aligned to the nuclear header is not considered to meet the requirements for an OPERABLE nuclear pump since it is not automatically powered and restarted on t.he diesel generators following an accident signal.

For OPERATIONAL CONDITIONS 1, 2,

3, 4,

and 5, and a DBA in either unit, two nuclear service water pumps from one or both units are capable of supplying sufficient flow to cool all four emergency diesel generators under worst-case scenarios while also supplying flow to other potential flow paths (vital header loads, cross-header leakage, and lubewate r). To prohibit any single failure from preventing the supply of service water to the diesel generators during the first 10 minutes following a DBA, at least three nuclear service water pumps per site are required while in OPERATIONAL CONDITIONS 1, 2, 3, 4,

or 5.

At ter the first ten minutes following a DBA, additional loads may require cooling

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water on the affected unit.

These loads include RHR and CS pump room coolers,

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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 RHR and CS room coolers, remain within the manufacturers' temperature limits for at least the first ten minutes of a DBA. Operator action is credited af ter the first 10 minutes following a DBA to make the necessary pump and valve alignments either remotely or manually, except that manual action inside the Reactor Building following a LOCA while in OPERATIONAL CONDITIONS 1, 2,

and 3 is not credited because of the potential for unsafe conditions.

In OPERATIONAL CONDITIONS 1, 2,

and 3,

one corrientional service _ water pump supporting the affected unit is capable of supplying the additional required safety-related and shutdown equipment.

No single failure. can prevent the necessary loads from being aligned to one of the nuclear or conventional headers by manual or remote operator action.

To prohibit any single failure from preventing the supply of service water after the first 10 minutes following a DBA, at least two operable conventional service water pumps are required while in OPERATIONAL CONDITIONS 1, 2, or 3.

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

so g 3/4.7 PLANT SYSTEMS BASES 3/4.7.1 SERVICE WATER SYSTEMS (Continued)

In OPERATIONAL CONDITIONS 4 and 5,

one unit service water pump, nuclear or conventional, is capable of supplying the additional required safety-related and shutdown equipment. Manual action in the Reactor Building is credited to align equipment to the nuclear header if required. To prohibit any single failure from preventing the supply of service water af ter the first 10 minutes following a DBA, at least two OPERABLE unit service water pumps, nuclear or conventional, are required while in OPERATIONAL CONDITIONS 4 a*.d 5.

The allowed out-of-service times and compensatory measures established in the ACTION statements are conservative. Although the probability and consequences of a DBA are reduced in OPERATIONAL CONDITIONS 4 and 5, the ACTION statements for i

the nuclear service water pumps for a unit in OPERATIONAL CONDITIONS 4 or 5 are based on the assumption that the other unit is in OPERATIONAL CONDITIONS 1, 2, or 3.

Specific ACTION statements and LCO time limits have not been established for both units in OPERATIONAL CONDITIONS 4 or 5 since the ACTION statements' for one unit in OPERATIONAL CONDITIONS 4 or 5 are more conservative.

In OPERATIONAL CONDITIONS 4 and 5, because of reduced core decay heat load, the reduceu possibility of a LOCA, and the accessibility to the reactor building for manual operator action, the vital header loads could be mant '.lly aligned to the nuclear header if a failure prevented remote valve alignment.

Therefore, the operability requirements for the unit service water pumps apply for nuclear or j

conventional pumps.

With one OPERABLE unit service water pump, the core spray j

and LPCI systems remain OPERABLE. However, to minimize the possibility of loss l

of these systems due to loss of the single pump, the out-of-service' time for one OPERABLE unit service water pump is set at 7 days. For no OPERABLE unit service water pumps, the core spray and LPCI systems must be declared inoperable This is equivalent to the ACTION statement for core spray and LPCI systems inoperable.

ACTION statement 3.7.1.2.b.4 for OPERATIONAL CONDITIONS 4 and 5 allows one unit to operate with the nuclear service water header inoperable for up to -14 days provided that:

a) two nuclear service water pumps are OPERABLE on the other unit, b) both unit's nuclear service water header valves are administratively controlled as required to ensure cooling water to - the diesel l

generators,.

c) the service water system conventir wl header is OPERABLE with two unit conventional service water pt _,a OPERABLE, and-d) vital ECCS loads are aligned to the conventional service water system header.

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

.l

- g I

3/4.7 PLANT SYSTEMS BASES 3/4.7.1 SERVICE VATER SYSTEMS (Continued)

Considering any additional single failure, this requirement ensures at least one OPERABLE nuclear service water pump to supply the Diesel Generators during the first 10 minutes after a DBA and one OPERABLE conventional service water pump to

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supply the unit safety related and shutdown cooling loads following the first 10 minutes af ter a DBA. By requiring administrative control of both unit's nuclear header valves, the ACTION statement minimizes the risk of inadvertent valve f

action that could reduce cooling water flow to the diesel generators.

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BRUNSVICK UNIT - 2 B 3/4 7 lc Amendment No, i

L,

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PLANT SYSTEMS BASES TP&r2.1_ SERVICE WATER SYSTEMS (Continued)

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demonstrate operation'in~QfERATIONAL CONDITIONS 1 through 3 w' P ERABLE nuclear service water pumps Y act,egtable provi g t least two nuclear service water pumps are OPERABLE on the per e untt and two conventional pumps are OPERABLE on the af f untt.

Speci te N statements and LCO time limits for th' uation have not been developed sine e

conserva ION Statement has been established in order to minimi. -chg,,

of personnel error in administrating this situation.

3/4.7.2 CONTROL ROOM EMERCENCY FILTRATION SYSTEM The OPERASILITY 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 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 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 saf ety-related equi pment.

3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM The reactor core isolation cooling system (RCICS) is provided-to assure adequate core cooli*ng in the event of reactor isolation from its primary heat 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 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 system to be operated.

d BRUNSWICK - UNIT 2 B 3/4 7-1,#

Amendment No. 177

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