ML20140H104

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Proposed Tech Specs Incorporating Administrative Update Resulting from Issuance on 970418 of Amends 184 & 215 to Units 1 & 2,respectively
ML20140H104
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 05/09/1997
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20140H093 List:
References
NUDOCS 9705120333
Download: ML20140H104 (4)
v • d • e


Text

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. 82/83/8994 02:18 9104573014 PAGE 05

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i ENCL OSLJRE 1 BRUNSW1CK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS, DPR-71 AND DPR-62 4

CONDENSER VACUUM PUMP ! SOLATION l

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! REPLACEMENT TECHNICAL SPECIFICATION PAGES 1

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9705120333 970509 PDR ADOCK 05000324 P PDR

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fe2/e3/1994 e2:le 91e4573e14 PAGE e6 l

.. L@LL

BASES ..__"_...,

.. I I SECTION _P.1(t[ ..

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-3/4 0 APPLICABILITY. .. .. . .... .. B 3/4 0 1 l 3/4.1 REACTIVITY CONTR01 SYSTFMS

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3/4 1.1 SHUT 00WN MARGIN..... .. . . ... ....., . .. .. . B 3/4 1-1

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3/4.1.2 REACTIVITY ANOMALIES.. .. . .... . . ... .. B 3/4 1 1 i 3/4.1.3 CONTROL R005... .... . .... .... .... . . .. B 3/4 1-1 i

3/4.'. 4 CONTROL R00 PROGRAM CONTROLS...... . . .. . . .. .. B 3/4 1-3 '

3/4.1.5 STANDBY LIQUID CONTROL SYSTEM. . . .. . . B 3/4 1 4 3/4 ? POWER DISTRIB'" ION LIMITS 3/4.2.1 AVERAGE PLANAR I INFAR HFAT GENERATION RATE. . .. B 3/4 2 1 3/4 2 ? MININUM CRITICAL POWER RATIO. . . . .. B 3/4 2-2 3/4.3 INSTRUMENTATION 3/4.3.1 HliACTOR PROTECTION SYSTEM INSTP.UMENTATION.. . .. .. G 3/4 3 1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION. ... ..... . . B 3/4 3-2 3/4.3.3 CMCRGENCY CORE COOLING SYSTEM AC'UATION INSTRUMENTATION. B 'J/4 3 2 3/4.3.4 CONTROL R03 WITHDRAWAL BLOCK IhSTRUMENTATION. R 3/4 3 ?a 3/4.3.5 MONITORING INSTRUMENTATION. . . . ... B 3/4 3 23 3/4.3 6 ATWS RFCIRCULATION PUMP TRIP SYSTEM INSTRLMEN~ATION. B 3/4 3 6 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENIAllON. .. . ....... ,,.. . .. . B 3/4 3 6 3/4.3.8 CONDENSER VACQUN PUMP ISOLATION INSTRUMENTATION. . G 3/4 3 6 I 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM.. . ..... . . .. . B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES, .. .. ... ... R 3/4 4 1 3/4.4.3 REACTOR C00lANT SYSTFM IFAKAGE.. .. .. . . B 3/4 4 1 BRUNSWICK UNIT 1 X Amerdnent No.

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22/03/1994 02:18 9104573014 PAGE 07 um

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BASES i SECTION EAG[ .

3/4.0 APPLICABILITY . . . .......... .. ...... . ..... .. .. 8 3/4 0 1  ;

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-3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN.. ... ..... . ...... .. . ... . B 3/4 1 1 3/4.1.2 REACTIVITY ANOMALIES. ... .. . .... . .. ... 8 3/4 1 1

. 3/4.1.3 CONTROL R005.. ......... ..... . .. ... .. .. . . B 3/4 1 1 3/4.1.4 CONTROL R00 PROGRAM CONTROLS. ..... ..... .... .. . B 3/4 1 3 3/4.1.5 STANOBY LIQUID CONTROL SYSTEM... . . .. .. . . .. B 3/4 1 4

3/4.2 POWER DISTRIBUTION LIMITS
  • 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE..... .. B 3/4 2 1 3/4.2.2 MINIMUM CRITICAL POWER RATIO. . . .. . . B 3/4 2 2 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION....... ., B 3/4 3-1 l 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION..... ..... . ..... B 3/4 3-2 ,

3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.. B 3/4 3 2 3/4.3.4 CONTROL R00 WITH0RAWAL BLOCK INSTRUMENTATION.. . B 3/4 3-2a l 3/4.3.5 MONITORING INSTRUMENTATION. ...... .. . . .. ... B 3/4 3 2a l i-3/4.3.6 RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION. . B 3/4 3 6 bRUM TA . .. . ...... B 3/4 3 7 3/4.3.8 CONDENSER VACUUM PUMP ISCLATION INSTRUMENTATION. . B 3/4 3 7 l

! 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM. . .. .... .... .. .... . ... .... B 3/4 4-1 -

3/4.4.2 SAFETY / RELIEF VALVES. .. .. ... .......... . . B 3/4 4 1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE... ... . ... B 3/4 4 1 i

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. BRUNSWICK - UNIT 2 X Amendt.ent No

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I02/e3/1994 82:18 9104573814 1 .

! .INSTRLiMENTATION a

[ BASES 3/4.3 7 REACTOR CORE ISOLATION COCLING SYSTEM ACTUATION INSTR'JMENTATION .

The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core coo ~ing in the event, or reactor isolation from its primary heat sink and the loss OT feedwater flow to the reactor vessel without prov1 ding actuation of any ur the energency core cooling equipment. .

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.SDecified surveillance intervals andanalysos allowed out-of-service l

! established based on the reliability docurented in times were GE recort  ;

GENE-770 06-2P-A, " Bases for Chances to Surveillance Test Intervals and Allowed Out-of Scevice Times for Selected Instrumentatinr. Technical Specifications." December 1992.

al.13.8 CONDENSE *4 VACulM PUMP ISOLATION INSTRLNENTATION f I Backaround i

The condenser vacuum pump 1solat10n InstrumentoLion 'nitiates a trio of the respective condenser vacuum pumo ano the common 1 solation valve following i events 1n which the main steam line radiation moritor(s) exceed a

. predetermined value. The condenser vacuum pump 1 solation instrunentation .

Initiates an isolation of the conderser vacuum pump (s) to limit main control 1

room doses resultino fron fuel Cladding failure in the event of a controf rod l - drop accident (CRDA) .. The isolation lo ic r.cnsists of two indeoendent trip

! systems, with two channels of the Main ! team Line Radiation H1gh function in tach tri Each trip system is a one out of two loo 1C ,or this

-runctior.p system.Thus, either channel of the Main Steam line Radiation-H1gn Function

, in each trip system are needed to trio a trio system. The outputs of the l 1 channels are,arrar,19ed in a logic so that both trip system must trip to result 1 in an 1 solation signal i

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1 4

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i BRUNSWICK - UNIT 2 B 3/4 3 7 Amen @ent No. I i

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