ML20204E528

Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function

ML20204E528
Person / Time
Site:	Catawba
Issue date:	03/15/1999
From:	DETROIT EDISON CO.
To:
Shared Package
ML20204E522	List: ML20204E516 ML20204E528
References
NUDOCS 9903250057
Download: ML20204E528 (38)

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l ATTACHMENT 1 REVISED (MARKED COPY) CURRENT TECHNICAL SPECIFICATION PAGES FOR CATAWBA l

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9903250057 990315  ;

PDR ADOCK 05000413 i P PDR l j

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TABLE OF CONTENTS 1.0 US E AN D APPLI CATION ................................. .... ................ . . . ... . ... 1.1 -1 f 1.1 De finition s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . .

1.2 Logical Conn ectors . .... ... . . . ... ..... . ...... .. .. ....... .... .. . .. .. ..... . .. .. ... . . . ... .... ...... 1.2- 1

'1'.3 Comple tion Tim es .. . . ... .... . ... ..... . ...... . .... .. ..... . ..... . .. ... ..... ......... ... . .. ... .. . .... 1.3-1 1.4 Freq ue n cy . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . ... . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . . .. . . 1.4 - 1 l 2.0 SAFETY Li MITS (S Ls) ... ..... ..... ... ... ...... .... . ... .. . ....... ... . . . . . . . . ..... .... . .... . . .. . ........ 2.0-1 2.1 SLs........................................................................................................2.0-1 2.2 S L Viola tio ns . .. . . . . . . . . .. . . . . . .. . . . . .. . .. . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . ... 2.

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY............ .. 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABillW .... ....................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS..................................................... 3.1.1 -1 3.1.1 SH UTDOWN MARG IN (SDM) ...................................................... 3.1.1 -1 3.1.2 Core Reactivity .. . .. ... ...... .. .. ........ ...... .. ....... . .. ... . . ... ... . .... . . .. .. .. . ..... .... 3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC) .................................... 3.1.3-1 3.1.4 Rod G roup Alignme nt Limits ........................................................ . 3.1.4-1 3.1.5 Shutdown Bank Insertion Limits .................................................... 3.1.5-1 3.1.6 Control Bank Inse rtion Um11s ......................................................... 3.1.6-1 3.1.7 Rod Position Indication ........................................................ ..... .... 3.1.7-1 3.1.8 PHYSICS TESTS Exceptions .................................. .................... 3.1.8-1 3.2 POW ER DI STRI BUTION LI MITS .......................................................... 3.2.1 -1 3.2.1 Heat Flux Hot Channel Factor (Fo(X,Y,Z)) ..................................... 3.2.1-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (Fm(X,Y)) ................... 3.2.2-1 3.2.3 AXIAL FLUX DIFFERENCE (AFD) ................................................ 3.2.3-1 3.2.4 OUADRANT POWER TILT RATIO (OPTR)................................... 3.2.4-1 3.3 i N STR U M ENTATIO N ... ........... ... ........ . . ... .......... . . .. ... ... .. ... .............. . .. .... 3.3.1 -1 3.3.1 Reactor Trip System (RTS) Instrumentation .................................. 3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

I nstrum entation . . ... . .... ............. .. .......... ..... . ........ ...... . . ..... .. . ....... 3.3.2- 1 3.3.3 Post Accident Monitoring (PAM) Instrumentation........................... 3.3.3-1 3.3.4 Remote Shutdown System ............................................................ 3.3.4-1 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start I nstru m entation ......... .. ..... .. .... .. .............. .. ... . .... .. . .. .... . ....... ... . ... 3.3.5- 1 3.3.6 Containment Purge and Exhaust Isolation I nstrum e ntation ........... ...... ... .. .. . ....... .. . . ........ ..... ...... . ... . .. ........ 3.3.6- 1 3.3.7 Contr

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oom Ar Ventilatip6 Syste GRAVS) )

uation I rumentatidh ... .. .. ... .. .......... .. ..... .... [....... Sd.7-1 _

3.3.8 uxilipy Building FIlterad Ver)tilation Exh st '

SVstem (ABFX/ES) Actuation Instru ntation .....[.. ... .../.3.3.8-1) 3.3.9 Boron Dilution Mitigation System (BDMS) ..................................... 3.3.9-1 M5 used' l

1 Catawba Units 1 and 2 i Amendment Nos.

TABLE OF CONTENTS B 2.0 SAFETY LIMITS (SLs)

B 2.1.1 Reactor Co re S Ls ... ... .. ............. ... . .. ... ............ .... ... .. ... ... . . ... .......... B 2.1.1 -1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL.................................. B 2.1.2-1

'B'3.0 * ' LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ....... B 3.0-1 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .... ................. B 3.0-9 B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1.1 SHUTDOW N MARGIN (SDM) ........................................................ B 3.1.1 -1 B 3.1.2 Core Reactivity.. ...... .. ........................ . . . .... ..... .... ........ . ........... .......... B 3.1.2-1 B 3.1.3 Moderator Temperature Coefficient (MTC) ..................................... B 3.1.3-1 B 3.1.4 Rod G roup Alignment Limits ........................................................... B 3.1.4-1 B 3.1.5 Shutdown Bank Insertion Limits ...................................................... B 3.1.5-1 B 3.1.6 Control Bank Insertion Limits .......................................................... B 3.1.6-1 B 3.1.7 Rod Poshion Indication ...................... ............................................. B 3.1.7-1 B 3.1.8 PHYSICS TESTS Exceptions ......................................................... B 3.1.8-1 B 3.2 POWER DISTRIBUTION LIMITS B 3.2.1 Heat Flux Hot Channel Factor (FO(X,Y,Z)) ..................................... B 3.2.1-1 B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FAH(X,Y))................... B 3.2.2-1 B 3.2.3 AXI AL FLUX DI FFERENCE (AFD).................................................. B 3.2.3-1 B 3.2.4 OUADRANT POWER TILT RATIO (OPTR).................................... B 3.2.4-1 B 3.3 INSTRUMENTATION B 3.3.1 Reactor Trip System (RTS) Instrumentation ................................... B 3.3.1-1 B 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

! nstrumenta tion .. .. . ........ ...... ..... ...... ... ........... .. ... . .. . ... . ............. . B 3.3.2- 1 B 3.3.3 Post Accident Monitoring (PAM) Instrumentation ............................ B 3.3.3-1 B 3.3.4 Remote Shutdown System .............................................................. B 3.3.4-1 B 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start instrumentation B 3.3.5-1 B 3.3.6 Containment Purge and Exhaust isolation Instrumentation............. B 3.3.6-1 B S.3.7 n hoom ea ven on Syst (CRA Actuat' instru im

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B 3.3.8 Auxil' Buildin sitered ntilation ' ust ystem ( FVES)~ l Actuatio nstrume tion .... . . . . . . . . . . . . . . . . ........... ..... B 3.3 -1 B 3.3.9 Boron Dilution Mitigation System (BDMS) ....................................... B 3.3.9-1 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3A.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ................................................. B 3.4.1 -1 B 3.4.2 RCS Minimum Temperature for Criticality ....................................... B 3.4.2-1 B 3.4.3 RCS Pressure and Temperature (P/T) Limits.................................. B 3.4.3-1 B 3.4.4 RCS Loops-MODES 1 and 2 ........................................................ B 3.4.4-1 B 3.4.5 RCS Loops-MODE 3.............. ............. ... . ... .. .. . . ...... ... ....... . ............ B 3.4.5- 1 8 3.4.6 RCS Loops-MODE 4...... .. ................ . ... .......................... . ... .. ..... .... B 3.4.6-1 B 3.4.7 f RCS Loops--MODE 5, Loops Filled................................................ B 3.4.7-1 B 3.4.8 RCS Loops-MODE 5, Loops Not Filled ......................................... B 3.4.8-1

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Catawba Units 1 and 2 i Revision No.

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CRAVS Actuation Instrumentati )

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3.3 INSTRUMENTATION

' $. 7 'dontrol Room Area Ventilation System (CRAVS) Actuation Instrumentation LCO 3. . The CRAVS actuation instrumentation for each Function ' Table 3.3.7-1 shall be OPERABLE. 1 l

APPLICABILITY: ODES 1,2,3, and 4.

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ACTIONS I NOTE -

Separate Condition entry is allow or each Function. [ . -

CONDITION O ED ACTION COMPLETION TIME A. One or more Functions A.1 --

NOTE with one train face in lorine gas inoperable. protection ode if automatic tr sfer to chlorine gas p tection

/ modeisinopera e.

Place the CRAVS train 7 days with inoperable actuation train in operation.

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l Catawba Units 1 and 2 3.3.7-1 Amendment Nos.173/165 l l

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CRAVS Actuation Instrumentatiop/ f ACTIONS (continued) /3.7 CONDITION REQUIRED ACTION COMPLETI TIME B. ne or more Functions NOTE--

' h two trains Place in the chlorine gas ino rable, protection mode if automatic transfer to chlorine gas protection mode is inoperable.

B.1 Verify one CRAVS train is Im m( m.- <ly

'n operation.

AND B.2 Enter applicable immediately Conditions and R uired Actions for one VS train made ino erable by l inoperable C VS I actuation i trumentation.

1 C. Required Action and C.1 Bein ODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time for Condition A AND or B not met.

C.2 in ODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Delefed' i C awba Units 1 and 2 3.3.7-2 Amendment Nos. 73/165

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CRAVS Actuation Instrume 'tation 3.3.7 SUR - lLLANCE REQUIREMENTS

---NOTE ---

Refer to Ta 3.3.7-1 to determine which SRs apply for each CRAVS Actuatio Function.

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SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform A TUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.7.2 Perform MASTER R Y TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.7.3 Perform SLAVE RELAY TES 92 days Delefed l

Cat wba Units 1 and 2 3.3.7-3 Amendment Nos. 3/165

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CRAVS Actuation Instrum:n ion 3.3.7 Table 3.3.7-1 (page 1 of 1)

, CRAVS ActuationInstrurnentation REQUIRED SURVEll1ANCE FUNCTION CHANNELS REQUIREMENTS iP SETPOINT

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1. Aut tic Actuation Logic and 2 trains SR 3.d.7.1 NA Actuati Relays SR 3.3.7.2 SR 3.3.7.3

2. Safety injecti Refer to LCO 3.3.2, *ESFAS instrumentation Function 1, for all initiation functions and requirements.

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Cat a Units 1 and 2 3.3.7-4 Amendment s.173/165  !

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CRAVS Actuation Instru (tation B 3.3.7

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B 3. INSTRUMENTATION l

B 3.3.7 ntrol Room Area Ventilation System (CRAVS) Actuation Instrume tation l

BASES BACKGROUND

• The CRAVS provides an enclosed control r m environment from which e unit can be operated following an un rolled release of radioactivity.

D *ng normal operation the CRAVS pro ' es filtered ventilation and pre urization of the control room. This ystem is described in the Bases for L 3.7.10, " Control Room Area V ntilation System."

The cont I room operator can initia CRAVS trains by manual switches in the cont I room. The CRAVS i also actuated by a safety injection (SI) signal. e SI Function is di ussed in LCO 3.3.2, " Engineered Safety Featur Actuation Syste (ESFAS) Instrumentation."

APPLICABLE The control room st be pt habitable for the operators stationed SAFETY ANALYSES there during acciden rec ery and post accident operations.

The CRAVS provides supply of filtered and pressurized outside air to the control room to e su the control room is kept habitable for the operators stationed ere ring accident recovery and post accident operations by min' izing th radiation exposure of control room personnel.

The CRAVS ctuation instrumen tion satisfies Criterion 3 of 10 CFR 50.36 (Ref. ).

LCO The L requirements ensure that ins mentation necessary to initiate the C VS is OPERABLE. l Automatic Actuation Loaic and Actuati Relays The LCO requires two trains of Actuation ic and Relays OPERABLE to ensure that no single rando allure can prevent automatic actuation.

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Cata a Units 1 and 2 B 3.3.7-1 Revi n No O l

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CRAVS Actuation instru ntation B 3.3.7 SES LCO tinued)

Automatic Actuation Logic and Actuation Relays nsist of the same features and operate in the same manne as desenbed for ESFAS Function 1.b., SI, in LCO 3.3.2. The ' ied conditions for the CRAVS portion of these functions ar different and less restrictive than those specified for their Si es. If one or more of the Si functions becomes inoperable in ch a manner that only the CRAVS function is affected, the Condi ' ns applicable to their SI

, function need not be entered. The le restrictive Actions specified 4 forinoperability of the CRAVS Fu s specify sufficient  :

pensatory measures for this .

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2. Safe Iniection Refer t CO 3.3.2, Functi n 1, for all initiating Functions and requirem .

APPLICABILITY

\ l The CRAVS Actuatio Ins mentation Functions must be OPERABLE in MODES 1,2,3, and 4 o upport automatic actuation on Si initiation.

Since the only automati actuation function of the CRAVS is due to a SI l initiation, the CRAVS tion Instrumentation Functions must be J OPERABLE whenev Si~ equired to be OPERABLE.

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ACTIONS A Note has bee added to the TIONS indicating that separate i Condition ent s allowed for ea Function. The Conditions of this I Specification ay be entered inde ndently for each Function listed in Table 3.3.7 in the accompanying L O. The Completion Time (s) of the inoperabl nnel(s)/ train (s) of a Fu ion wil! be tracked separately for each Fu starting from the time th Condition was entered for that Funct' .

ition A applies to the actuation logic train notion of the CRAVS.

If one train is inoperable, 7 days are permitted to r store it to OPERABLE status. The 7 day Completion Time is the same as allowed if one train of the mechanical portion of the system is inoperable. The basis for this i Completion Time is the same as provided in LCO 3.7, . If the i Delehd Cata Units 1 and 2 B 3.3.7-2 Revi n No. O

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l CRAVS Actuation Instrum:n ion 3.3.7 BA ES ACTIO (continued) channel / train cannot be restored to OPERABLE status, the RAVS train with an inoperable actuation train must be placed in oper ion. This accomplishes the actuation instrumentation Function a places the unit l in a conservative mode of operation.

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! e Required Action for Condition A is modified by Note that requires i pla 'ng the CRAVS train in the chlorine gas prote ion mode instead of ,

the p ssuri.ted mode of operation if the autom c transfer to chlorine l

gas pr ction mode is inoperable. This ensur s the CRAVS train is placed in most conservative mode of tion relative to the OPERABIL of the associated actuation strumentation.

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B.1 and 8.2 l Condition B applies to he failure of o CRAVS actuation trains. The first  ;

Required Action is to ve 'fy one C VS is in the filtered mode of i operation immediately. 's a mplishes the actuation instrumentation Function that may have be st and ensures the unit is in a  !

conservative mode of opera . The applicable Conditions and Required Actions of LCO 3.7.10 mus al be entered for the other CRAVS train made inoperable by the i ra e actuation instrumentation. This ensures appry>riate lim' are pla d upon train inoperability as -

discussed in the Base for LCO 3. 10.

The Required Acti for Condition B i odified by a Note that requires placing the CRA train in the chlorine as protection mode instead of the pressuriz ode of operation if the utomatic transfer to chlorine gas protecti mode is inoperable. This e sures the CRAVS train is placed in th most conservative mode of ration relative to the OPERABI TY of the associated actuation in trumentation.

C.1 a C.2 dition C applies when the Required Action and ociated mpletion Time for Condition A or B have not been et The unit must e brought to a MODE in which the LCO requirement re not applicable.

To achieve this status, the unit must be brought to MO 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Com letion Times are reasonable, based on operating experience, to reach e required unit conditions from full power conditions in an orderly man er and without challenging unit systems.

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Cata Units 1 and 2 B 3.3.7-3 Revisi No. O

CRAVS Actuation Instrume tion 3 3.3.7 B ES SUR ILLANCE A Note has been added to the SR Table to clarify that Table .3.7-1

, ,REQl)l, MENTS determines which SRs apply to which CRAVS Actuation Fu ctions.

SR 3.3.7.1

SR 3.3.7.1 is the performance of an ACTUATION IC TEST. The train being tested is placed in the bypass conditi , thus preventing inadvertent actuation. Through the semiautom c tester, all possible ogic combinations, with and without applicabl rmissives, are tested

, r each protection function. In addition, the aster relay coilis pulse te ed for continuity. This verifies that the ic modules are OPERABLE a ere is an intact voltage signal path the master relay coils. This test I wrformsd every 31 days on a S- GGERED TEST BASIS. The Freque cy is justified in WCAP-10271 3-A, Supplement 2, Rev.1 (Ref. 2).

SR 3.3.7.2 SR 3.3.7.2 is t performan of a MASTER RELAY TEST. The MASTER RELA TESTIS e energizing of the master relay, verifying contact operation nd a voltage continuity check of the slave relay coil. Upon master lay ntact operation, a low voltage is injected to the slave relay coil. Thi ge is insufficient to pick up the slave relay, but large enough to de strate signal path continuity. This test is performed every 3 da on a STAGGERED TEST BASIS. The Frequencyis a tabl ased on instrument reliability and industry 4 operating expe ' nce.

3R 3.3.7.

SR 3.3 .3 is the performance o SLAVE RELAY TEST. The ELAVE RE TEST is the energizing of e slave relays. Contact op'.tration is ve ' in one of two ways. Actuati equipment that may be operated in th design mitigation MODE is either llowed to function or is placed in a ition where the relay contact oper ion can be verified without ration of the equipment. Actuation uipment that may not be operated in the design mitigation MODE revented from operation by the SLAVE RELAY TEST circuit. For this er case, contact operation is verified by a continuity check of the circuit taining the slave relay.

This test is performed every 92 days. The Fr uencyis acceptable based on instrument reliability and industry ope ting experience.

Detered Ca wba Units 1 and 2 8 3.3.7-4 evision No. O

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1 CRAVS Actuation Instru ntation B 3.3.7 BA S i

REFE NCES 1. 10 CFR 50.36, Technical Specifications, (c)(2)(ii). ,

2. WCAP-10271-P-A, Supplement 2, Rev.1, June 1 0.

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l Cata a Units 1 and 2 B 3.3.7-5 Revisi n No. O

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ABFVES Actuation Instru :ntttion {

3.3.8 j I

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3. INSTRUMENTATION l ' 3.3.B ' ~ uxiliary Building Filtered Ventilation Exhaust System (ABFVES) Act ation nstrumentation l

! LCO 3.3.8 The ABFVES actuation instrumentation for each unction in Table 3.3.8-1 shall be OPERABLE. I l

l APPLICABILITY: A rding to Table 3.3.8-1.

ACTIONS 3 ---NOTE-- - - --

Separate Condition entry is allowed for each Functiof CONDITION RE RED ACTION COMPLETION TIME I

A. One or more Functions A.1 store one ABFVES train 7 days l with one channel or train o PERABLE status.

inoperable.

B. Required Action and . .1 Be in MO E 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time for Condition A not AND met. <

B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Dele /ed I

f Cat a Units 1 and 2 3.3.8-1 Amendment s.173/165

j. ABFVES Actuation instrumsnte '

L 3 .8 S VEILLANCE REQUIREMENTS NOTE Refer to le 3.3.8-1 to determine which SRs apply for each ABFVES Actuation [ unct

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SURVEILLANCE FREQUENCY SR 3.3.8.1 Perfo ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS  !

l SR 3.3.8.2 Perform MAST RELAY TEST. 31 days on a ,

STAGGERED l TEST BASIS i I

i SR 3.3.8.3 Perform SLAVE RELA EST. 92 days l

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Cat Units 1 and 2 3.3.8-2 Amendme Nos.173/165

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ABFVES Actuation instr :ntation 3.3.8

( Table 3.3.8-1 (page 1 of 1)

ABFVES ActuationInstrumentation APPUCABLE MODES OR SPECIFIED REQUIRED SURVElLLANC TRIP NCTION CCNDmONS CHANNELS REQUIREME SETPOINT

1. Automatic uation Logic and 1,2.3.4 2 trains SR 3. .1 NA Actuation SR 3 .C.2 l SR .3.8.3

2. Safety injection Hefer to LCO 3.3.2. 'ESFAS InstnaT.= d -'. Function 1, for all initiation functions i

and requirements.

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Cata a Units 1 and 2 3.3.8-3 Amendment Nos. 3/165

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p l ABFVES Actuation Instr intation B 3.3.8

,B 3 ,1NSTRUMENTATION B 3.3. Auxiliary Building Filtered Ventilation Exhaust System (ABFVE Actuation instrumentation BASES l

l BACKGROUND e ABFVES ensures that radioactive terials in the ECCS pump r s atmosphere following a loss of ant accident (LOCA) are filte and adsorbed prior to exhau ng to the environment. The system i is de ' bed in the Bases for LCO .12, " Auxiliary Building Filtered l

Ventilats Exhaust System." Th ystem initiates filtered ventilation of the ECC ump rooms automat' ily following receipt of a safety injection (S signal.

These actions nction to pr vent exfiltration of contaminated air by initiating filtered ntilatio which imposes a negative pressure on the ECCS pump room APPLICABLE The ABFVES ensur t t radioactive materials in the ECCS SAFETY ANALYSES pump rooms atmo here ollowing a LOCA are filtered and adsort>ed prior to being e usted to he environment. This action reduces the radioactive con nt in the au 'liary building exhaust following a LOCA so that offsite do s remain with the limits specified in 10 CFR 100 (Ref.1).

The ABFV S actuation instrument tion satisfies Criterion 3 of 10 CFR 50.36 ( f.2).

LCO Th CO requirements ensure that inst entation necessary to initiate th ABFVES is OPERABLE.

. Automatic Actuation Loalc and Actuati Relays The LCO requires two trains of Actuation L ic and Relays OPERABLE to ensure that no single rando allure can prevent automatic actuation.

De/ded Cata Units 1 and 2 B 3.3.8-1 Revisi No.O

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ABFVES Actuation Instrums ation  !

3.3.8 BASES

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L (continued)

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Automatic Actuation Logic and Actuation Relays ist of the same features and operate in the same manner a described for ESFAS Function 1.b., Si, in LCO 3.3.2. The ble MODES and specified conditions for the ABFVES port' of these functions {

are different and less restrictive than those ' ied for their Si j roles. if one or more of the Si functions es inoperable in ,

such a manner that only the ABFVES fun n is affected, the  !

Conditions applicable to their Si functio eed not be entered. The  ;

less restrictive Actions specified for i rabilityof the ABFVES l functions specify sufficient compen ory measures for this case, l i

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APPLICABILITY The aut atic ABFVES actuation ins mentation is required in MODES  ;

1,2,3, an 4 to remove fission prod cts caused by post LOCA Emergency ore Cooling Systems akage.

While in MODE S and 6 the A . ES instrumentation need not be OPERABLE si unit temper ure and pressure are very low.

ACTIONS - A Note has been a t the ACTIONS to clarify the application of Completion Time rules. he Conditions of this Specification may be entered independently or ach Function listed in Table 3.3.8-1 in the l accompanying LCO. he pletion Time (s) of the inoperable channel (s)/ train (s) a Functs will be tracked separately for each Function starting om the time Condition was entered for that Function.

Ad Conditi A applies to the failure of an a tion logic train function of the Solid te Protection System (SSPS), if e channel or train is able, a period of 7 days is allowed to store it to OPERABLE sta s. The 7 day Completion Time is the sa e as is allowed if one train of e mechanical portion of the system is i able. The basis for this e is the same as that provided in LCO 3.7.12.

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Cata Units 1 and 2 8 3.3.8-2 Revisio No.O

ABFVES Actuation Instru ntation B 3.3.8 ASEG i

AC IONS (continued)

B.1 and B.2 Condition B applies when the Required Action and sociated Completion Time for Condition A have not been t. The unit must be brought to a MODE in which the LCO requirem ts are not applicable. l To achieve this status, the unit must be broug to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The owed Completion Times are reasonable, based on operating experi ce, to reach the required unit conditions from full power conditions ' an orderly manner and ,

'thout challenging unit systems.

l SURVEILLANCE A No has been added to the SR ble to clarify that Table 3.3.8-1 3 REQUIREMENTS determ es which SRs apply to ich ABFVES Actuation Functions.

1 SR 3.3.8.1 /

SR 3.3.8.1 is t perform ce of an ACTUATION LOGIC TEST. The actuation logic is ested very 31 days on a STAGGERED TEST BASIS.

All possible logic nations, with and without applicable permissives, i are tested for each - tection function. The Frequency is based on the j known reliability of relays and controls and the multichannel redundancy avail le, nd has been shown to be acceptable through operating expe ' nce.

SR 3.3.8.2 SR 3.3. is the performance f a MASTER RELAY TEST. The MAST RELAY TEST is the e rgizing of the master relay, verifying conta operation and a low volta continuity check of the slave relay coil. pon master relay contact ration, a low voltage is injected to the si e relay coil. This voltage is ins cient to pick up the slave relay, but ge enough to demonstrate signal th continuity. This test is rformed every 31 days on a STAGG RED TEST BASIS. The ,

Frequency is acceptable based on inst ent reliability and industry  !

operating experience, l l

Delehd Cat a Units 1 and 2 B 3.3.8-3 Revision No. O

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ABFVES ActuationInstrume ation B 3.3.8 B ES SURV LLANCE REQUIREMENTS (continued)

SR 3.3.8.3 SR 3.3.8.3 is the performance of a SLAVE RELAY T ST. The SLAVE RELAY TEST is the energizing of the slave relays. ntact operation is verified in one of two ways. Actuation equipment at may be operated in the design mitigation MODE is either allowed to unction or is placed in a ndition where the relay contact operation be verified without op ration of the equipment. Actuation equi ent that may not be ope ted in the design mitigation MODE is revented from operation by the S VE RELAY TEST circuit. For thi tter case, contact operation is verified a continuity check of the cir it containing the slave relay. ,

This test performed every 92 days. he Frequencyis acceptable based on i trument reliability and i ustry operating experience.  ;

REFERENCES 1. 10 CFR 1 .11.

2. 10 CFR 50 Techn' i Specifications, (c)(2)(ii).

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Delded I

Cata a Units 1 and 2 B 3.3.8-4 Revi on No.O

CRAVS 3.7.10 3.7 PLANT SYSTEMS .

' 3.7;16 Control Room Area Ventilation System (CRAVS)

. . . - No rf - ~ ~

LCO 3.7.10 Two CRAVS trains shall be OPERABLE. p/aee /n Af4 ch/or/nc pec+te% mos'e }f a afomefk twufer to st A chlonkprotection f APPLICABILITY: MODES 1,2,3, 4,5, and 6,  ?,(afs gofpefd6/f , ]

During movement of irradiated fuel assemblie ,

During CORE ALTERATIONS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

< 1 A. One CRAVS train .1 Restore CRAVS train to 7 days i inoperable. OPERABLE status.

B.- Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met in MODE 1,2,3, or 4. B.2 Be in MODE 5. 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> C. Required Action and C.1 NOTE associated Completion Place in high chlorine Time of Condition A not protection mode if met in MODE 5 or 6, or automatic transfer to high during movement of chlorine protection mode is irradiated fuel inoperable.

assemblies, or during CORE ALTERATIONS.

Place OPERABLE CRAVS Immediately train in operation.  !

06, (continued)

Catawba Units 1 and 2 3.7.10-1 Amendment Nos.

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CRAVS I B 3.7.10 BASES

, ACTIONS (continued)

~

CRAVS function. The 7 day Completion Time is based on the low

, probability of a DBA occurring during this time period, and ability of the Rega//Yd' Ac//t/) 4,//s remaining train to provide the required capability.

McWified bya Jeft &

thh'catly to place YAe systen in the chlorjae/ B.1 and B.2 protedibn Made if l

det /pirw//d. frsAsfer in MODE 1,2,3, or 4, if the inoperable CRAVS train cannot be restored )

to 4/ fh c/>/0/yg to OPERABLE status within the required Completion Time, the unit must profechop1 mow /j be placed in a MODE that minimizes accident risk. To achieve this 4/t. status, the unit must be placed in at least MODE 3 within G hours, and in

(/M MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

C.1. C.2.1. and C.2.2 In MODE 5 or 6, or during movement of irradiated fuel assemblies, or during CORE ALTERATIONS, if the inoperable CRAVS train cannot be restored to OPERABLE status within the required Completion Time, action must be taken to irnmediately place the OPERABLE CRAVS train in operation. This action ensures that the remaining train is OPERABLE, that no failures preventing automatic actuation will occur, and that any active failure would be readily detected.  ;

An attemative to Required Action C.1 is to immediately suspend activities that could result in a release of radioactivity that might require isolation of ,

the control room. This places the unit in a condition that minimizes risk.  ;

This does not preclude the movement of fuel to a safe position.

Required Action C.1 is modified by a Note indicating to place the system in the chlorine protection mode if automatic transfer to high chlorine protection mode is inoperable.

D.1 and D.2 In MODE 5 or 6, or during movement of irradiated fuel assemblies, or ,

during CORE ALTERATIONS, with two CRAVS trains inoperable, action must be taken immediately to suspend activities that could result in a l

l Catawba Units 1 and 2 B 3.7.10-4 Revision

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ATTACHMENT 2 l l

. PROPOSED (REPRINTED) TECHNICAL SPECIFICATION PAGES FOR CATAWBA 1

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TABLE OF CONTENTS 1.0 U S E A N D A P P LI C ATI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1 - 1 1.1 D e fin ition s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1 -

' 1.2 - Logica l Con n ectors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 2- 1 1.3 C om ple tion Tim e s . . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.3- 1 1.4 F req u e n cy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 4- 1 2.0 S A F ETY LI M ITS ( S Ls) . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .. . . . . . . . . .. 2.0- 1 2.1 SLs...................................................................................................2.0-1 2.2 S L Vi ola tio n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 0-3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.............. 3 0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ............................ 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS .................................................. .. 3.1.1 -1 3.1.1 SH UTDOWN MARGIN (SDM) ....... ............................................. 3.1.1-1 3.1.2 Co re R eactivliy . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1.2- 1 3.1.3 Moderator Temperature Coefficient (MTC) .................................... 3.1.3-1 3.1.4 Rod G roup Alig nm ent Limits ........ ................................................. 3.1.4-1 3.1.5 Shutdown Bank insertion Limits .................................................... 3.1.5-1 3.1.6 Control Bank Insertion Limits......................................................... 3.1.6-1 3.1.7 Rod Position Indication ...... . .. . . .. . ...... ... .... . . . ... . . .. .. . . .. . .. ..... .. ... . .... . .. . 3.1.7- 1 3.1.8 PHYSICS TESTS Exceptions ........... ............................................ 3.1.8-1 3.2 POWER DI STRIBUTION LIMITS .......................................................... 3.2.1 -1 3.2.1 Heat Flux Hot Channel Factor (Fo(X,Y,Z))..................................... 3.2.1-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (Fm(X,Y))..... ............. 3.2.2-1 3.2.3 AXI AL FLUX DI FFER ENC E (AFD) ..... .......................................... 3.2.3-1 3.2.4 OUADRANT POWER TILT RATIO (OPTR)................................... 3.2.4-1 3.3 I N ST R U M E NTATI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . 3. 3.1 - 1 3.3.1 Reactor Trip System (RTS) Instrumentation .................................. 3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

I nstru m e nta tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3.2- 1 3.3.3 Post Accident Monitoring (PAM) Instrumentation........................... 3.3.3-1 3.3.4 Re mote Shutdown System . . . . .. . . . . . . . . . .. ... ....... ... . . . . .. .. .. .. . . ... ... . . . . .. .. . 3.3.4- 1 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start I n stru m enta tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3.5- 1 3.3.6 Containment Purge and Exhaust isolation I n stru m e ntation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 3.6- 1 3.3.7 Not Used 3.3.8 Not Used

.3.3.9 Boron Dilution Mitigation System (BDMS) ..................................... 3.3.9-1 Catawba Units 1 and 2 i Amendment Nos.

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TABLE OF CONTENTS B 2.0 SAFETY LIMITS (SLs)

B 2.1.1 R ea cto r Co re S Ls . . . . . . . . . .. . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . B 2.1.1 - 1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL.. ............ .................. B 2.1.2-1 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILIT(. .... 3 3.0-1 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ...................... B 3.0-9 B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1.1 SH UTDOW N MAR GI N (S D M) ............... ......................... ... ........ B 3.1.1 -1 B 3.1.2 Co re R ea ctivity. . . . .. . . . . . . . .. . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . .. . . . .. . . ......... B 3.1.2-1 B 3.1.3 Moderator Temperature Coefficient (MTC) ..................................... B 3.1.3-1 B 3.1.4 Rod G roup Alignment Limits ....... ......... .. ...................... ............... B 3.1.4-1 B 3.1.5 Shutdown Bank Insertion Limits ............................... ...... .. ........ ... B 3.1.5-1 B 3.1.6 Control Bank Insertion Limits ... ............................... . .... . ........... . B 3.1.6-1 B 3.1.7 Rod Position Indicati an ..... .... ... .................. .. .............. .. .......... . B 3.1.7-1 B 3.1.8 PHYSICS TESTS Exceptions . . .... ...........................................B3.1.8-1 B 3.2 POWER DISTRIBUTION LillTS B 3.2.1 Heat Flux Hot Channel Factor (FO(X,Y,Z)) ......... .. ........................ B 3.2.1-1 B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FAH(X,Y))........ ...... .. B 3.2.2-1 B3.23 AXlAL FLUX DIFFERENCE (AFD)............................. . . . . . . . . . . . . . . . . . B 3.2.3- 1 B 3.2.4 OUADRANT POWER TILT RATIO (OPTR)................... . .......... .. B 3.2.4-1 B 3.3 INSTRUMENTATION B 3.3.1 Reactor Trip System (RTS) instrumentation . ................. ............... B 3.3.1-1 B 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

I n st ru m e ntation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . B 3.3.2- 1 B 3.3.3 Fost Accident Monitoring (PAM) Instrumentation ......... ............... . B 3.3.3-1 B 3.3.4 Remote Shutdown System ............. .... ........................... . . ... ...... B 3.3.4-1 B 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation B 3.3.5-1 B 3.3.6 Containment Purge and Exhaust Isolation Instrumentation............. B 3.3.6-1 B 3.3.7 NotUsed ]

B 3.3.8 Not Used B 3.3.9 Boron Dilution Mitigation System (BDMS) . ........................ ... ....... B 3.3.9-1 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ......... .......... .. ..... ..... ... ........ B 3.4.1-1 B 3.4.2 RCS Minimum Temperature for Criticality. ................... ..... . . .. .. . B 3.4.2-1 B 3.4.3 RCS Pressure and Temperature (P/T) Limits..................... .. ... . . B 3.4.3-1 B 3.4.4 RCS Loops-MODES 1 and 2 ..... . .......... ....................... . .......... B 3.4.4-1 ,

B 3.4.5 R C S Loops-MO D E 3. . .. . . . . . .... . . . . . . . . . .. . . . .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .. . . B 3.4. 5- 1 I B 3.4.6 RCS Loops-MODE 4.... ....... ................................................B3.4.6-1 B 3.4.7 RCS Loops-MODE 5, Loops Filled........... ........ ............ .. . ... .. . B 3.4.7-1 B 3.4.8 RCS Loops-MODE 5, Loops Not Filled ........... ... ... ......... ... . . .. B 3.4.8-1 Catawba Units 1 and 2 i Revision No.1 1

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p CRAVS 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Area Ventilation System (CRAVS)

LCO 3.7.10 Two CRAVS trains shall be OPERABLE.

APPLICABILITY: MODES 1,2,3,4,5, and 6, During movement of irradiated fuel assemblies,

- During CORE ALTERATIONS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRAVS train A.1 --- N OTE-----------

inoperable. Place in high chlorine protection mode if automatic transfer to high chlorine protection mode is inoperable.

Restore CRAVS train to 7 days l OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met in MODE 1,2,3, or 4. B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued) 1 i

Catawba Units 1 and 2 3.7.10-1 Amendment Nos.

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l CRAVS 3.7.10 ACTIONS

! . .- CONDITION REQUIRED ACTION COMPLETION TIME i

l C. Required Action and C.1 ----- N OT E -------------

l' associated Completion Place in high chlorine Time of Condition A not protection mode if met in MODE 5 or 6, or automatic transfer to high during movement of chlorine protection mode is irradiated fuel inoperable.

assemblies, or during --------------------------------

CORE ALTERATIONS.

Place OPERABLE CRAVS Immediately train in operation.

C.2.1 Suspend CORE immediately ALTERATIONS.

AND C.2.2 Suspend movement of immediately irradiated fuel assemblies.

D. Two CRAVS trains D.1 Suspend CORE Immediately inoperable in MODE 5 ALTERATIONS.

or 6, or during movement of irradiated AND fuel assemblics, or during CORE D.2 Suspend movement of Immediately ALTERATIONS. irradiated fuel assemblies.

E. Two CRAVS trains E.1 Enter LCO 3.0.3. Immediately

- inoperable in MODE 1, 2, 3, or 4.

F. One or more C6VS F.1 Restore CRAVS train (s) 7 days train (s) heater heater to OPERABLE inoperable. status.

M F.2 Initiate action in 7 days accordance with Specification 5.6.6.

Catawba Units 1 and 2 3.7.10-2 Amendment Nos.

F CRAVS B 3.7.10 SASES

• ACTIONS (continued)

CRAVS function. The 7 day Completion Time is based on the low probability of a DBA occurring during this time period, and ability of the remaining train to provide the required capability.

Required Action A.1 is modified by a Note indicating to place the system in the chlorine protection mode if automatic transfer to high chlorine protection mode is inoperable.

B.1 and E .

In MODE 1,2,3, or 4, if the inoperable CRAVS train cannot be restored ,

to OPERABLE status within the required Corrpletion Time, the unit must I be placed in a MODE inat minimizes accident risk. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, Dased on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

C.1. C.2.1. and C.2.2 j in MODE 5 or 6, or during movement of irradiated fuel assemblies, or during CORE ALTERATIONS, if the inoperable CRAVS train cannot be '

restored to OPERABLE status within the required Completion Time, action must be taken to immediately place the OPERABLE CRAVS train in operation. This action ensures that the remaining train is OPERABLE, that no failures preventing automatic actuation will occur, and that any I active failure would be readily detected.

An alternative to Required Action C.1 is to immediately suspend activities I that could result in a release of radioactivity that might require isolation of the control room. This places the unit in a condition that minimizes risk.

This does not preclude the movement of fuel to a safe position.

Required Action C.1 is modified by a Note indicating to place the system in the chlorine protection mode if automatic transfer to high chlorine protection mode is inoperable.

D.1 and D.2 in MODE 5 or 6, or during movement of irradiated fuel assemblies, or Catawba Units 1 and 2 B 3.7.10-4 Revision No.1

CRAVS B 3.7.10

' BASES

' ACTIONS (continued) during CORE ALTERATIONS, with two CRAVS trains inoperable, action must be taken immediately to suspend activities that could result in a release of radioactivity that might enter the control room. This places the unit in a condition that minimizes acc; dent risk. This, does not preclude the movement of fuel to a safe position.

El if both CRAVS trains are inoperable in MODE 1,2,3, or 4, tht, may not be capable of performing the intended function and the ..ut is in a condition outside the accident analyses. Therefore, LCO 3.0.3 must be entered immediately.

F.1 and F.2 With one or more CRAVS heaters inoperable, the heater must be restored to OPERABLE status within 7 days. Alternatively, a report must be initiated per Specification 5.6.6, which details the reason for the heater's inoperability and the corrective action required to retum the heater to OPERABLE status.

The heaters do not affect OPERABILITY of the CRAVS filter trains because charcoal adsorber efficiency testing is performed at 30oC and 95% relative humidity. The accident analysis shows that site boundary radiation doses are within 10 CFR 100 limits during a DBA LOCA under these conditions.

SURVEILLANCE SR 3.7.10.1 REQUIREMENTS Standby systems should be checked periodically to ensure that they function properly. As the environment and normal operating conditions on this system are not too severe, testing each train once every month provides an adequate check of this system. Monthly heater operations dry out any moisture ' accumulated in the carbon from humidity in the ambient air. Systems with heaters must be operated from the control room for 210 continuous hours with the heaters energized and flow through the HEPA filters and charcoal adsorbers. The 31 day Frequency is based on the reliability of the equipmer,t and the two train redundancy availability.

Catawba Units 1 and 2 B 3.7.10-5 Revision No.1 As-

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• ATTACHMENT 3 DESCRIPTION OF PROPOSED CHANGES AND TECHNICAL JUSTIFICATION FOR CATAWBA I

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Description of Changes and Technical Justification

.'TS 3s3.7 and 3.3.8 govern the CRAVS Actuation Instrumentation and the ABFVES Actuation Instrumentation, respectively. TS 3.3.7, Table 3.3.7-1, CRAVS Actuation Instrumentation, requires two trains of Automatic Actuation Logic and Actuation Relays. TS z

3.3.8, Table 3.3.8-1, ABFVES. Actuation Instrumentation, also requires two trains of Automatic Actuation Logic and Actuation Relays. These requirements are applicable in Modes 1, 2, 3, and

4. TS 3.3.7 and 3.3.8 each has a set of Surveillance Requirements (SR), which consist of an actuation logic test, a master relay' test, and a slave relay test. The actuation logic test and the master relay test have a specified frequency of 31 days on a staggered test basis. The slave relay test has a specified frequency of 92 days. As discussed below, these SRs do not apply to the Catawba CRAVS and ABFVES Actuation Instrumentation design. TS 3.7.10 governs the CRAVS itself and TS 3.7.12 governs the ABFVES itself. This LAR requests deletion of TS 3.3.7 and 3.3.8 and adds a note to Required Action A.1 of TS 3.7.10 concerning placing the CRAVS in the high chlorine protection mode if the automatic transfer to the high chlorine protection mode is inoperable.

The circumstances surrounding this LAR were discussed with the NRC in a request for enforcement discretion which the NRC granted on March 11, 1999. This LAR is the formal amendment request made in follow up to the request for enforcement discretion. i At Catawba, the CRAVS and ABFVES are actuated by the diesel generator load sequencer, which in turn, is actuated by the Solid State Protection System (SSPS) Automatic Actuation Logic and Actuation Relays. The CRAVS and ABFVES are not direv ly actuated by the SSPS. Catawba TS 3.3.7 and 3.3.8 were based on the ,

standard version of these TS contained in NUREG-1431, Revision 1, I

" Standard Technical Specifications, Westinghouse Plants."

The Bases for both NUREG-1431 and the Catawba TS state that the Automatic Actuation Logic and Actuation Relays consist of the same features and operate in the same manner as described for the Safety Injection function. It also states that the specified conditions for the CRAVS and ABFVES portion of these functions are different and less restrictive than those specified for their Safety Injection roles. This Bases discussion is applicable for a plant design that utilizes the SSPS to directly actuate the CRAVS and ABFVES. As indicated above, at Catawba, the CRAVS and ABFVES are actuated by the diesel generator load sequencer, and not directly via the SSPS. Refer to Figure 1 for a simplified depiction of the CRAVS and ABFVES Actuation Instrumentation arrangement.

Fiaure 1 SSPS Cabinet Seauencer input Logic Output Bay Bay Bay N

Slave CRAVS and Relays > > ABFVES

\ / Systems

, ' % 4' % . /

7300 input '

Logic M

• C CD '##

' NIS >C::C Relays Cards Re ays Test etc.

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/ Note: CRAVS and ABFVES actuations tested during outage Tested by Actuation ESF Test.

Logic Test / Master Relay Test 1

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LCatawba has determined that due to'the CRAVS and ABFVES Actuation

• ' Instrumentation design, that these TS should not have been included in'the Improved TS. Catawba'is proposing to delete TS 3.3.7 and 3.3.8.

TS-3.3.2, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation, contains all the necessary requirements that apply to the Automatic Actuation Logic and Actuation Relays

-insofar as SSPS testing is concerned. These requirements are found in Table 3.3.2-1,. Engineered Safety Feature Actuation System Instrumentation under the Safety' Injection function (Function lb in the table, Automatic Actuation Logic and Actuation Relays). As indicated in'the table, an actuation logic test (SR 3.3.2.2), a master relay test (SR 3.3.2.4), and a slave relay test (SR 3.3.2.6) are specified for Function lb. These SRs test SSPS' actuation of the diesel generator load sequencer. As indicated above, at Catawba, the CRAVS and ABFVES are actuated by the load sequencer, and not directly via the SSPS. The automatic start of the CRAVS and ABFVES functions from the load sequencer are performed as part of engineered safeguards testing, which is conducted during refueling outages. SR 3.7.10.3 requires on an 18-month frequency, verification that each CRAVS train actuates on an actual or simulated actuation' signal. SR 3.7.12.3 requires on an 18-month frequency, verification that each ABFVES train actuates on an actual or simulated actuation signal. Therefore, deletion of TS 3.3.7 and 3.3.8 is acceptable, as the EFSAS SSPS testing, in combination with engineered safeguards testing, fully tests all functions from the SSPS, through the load sequencer, and to the CRAVS and ABFVES.

l Deletion of TS 3.3.7~and 3.3.8 will not have any adverse

. consequences insofar as high radiation protection and high'

' chlorine protection requirements are concerned. At Catawba, th.re is no control room automatic isolation function on a high radiation signal. As part of the Improved TS conversion process, operability and testing requirements for the chlorine detectors were relocated from the TS to the Selected Licensee Commitments Manual, which is Chapter 16 of the Updated Final Safety Analysis

-Report. No changes to any operability or testing requirements pertaining to the chlorine detectors will occur as a result of

-this LAR. As part of this LAR, it is necessary to add a note to Required Action A.1 of TS 3.7.10 concerning action to take if the automatic transfer to the high chlorine protection mode is inoperable. Addition of this note is necessary to ensure that it applies,to Modes 1 through 4. An identical note is already present.in Required Action C.1 of TS 3.7.10, which is applicable in Mode 5 or 6, or during movement of irradiated fuel assemblies, or during core alterations. Addition of this note to Required

v-Action'A.1 will ensure that it applies during all modes and conditions of applicability for TS 3.7.10.  !

Finally, LCOs 3.7.10 and 3.7.12 contain all other necessary 4 requirements for the mechanical portions of the CRAVS and ABFVES, l' respectively.

In summary,-the ESFAS and the CRAVS and ABFVES Actuation Instrumentation will remain fully capable of fulfilling their required safety function, consistent with the manner in which they were designed. No decrease in equipment availability or

-reliability'will be incurred as a result of the approval of this ,

LAR. Approval of this LAR will have no impact from a I probabilistic risk standpoint, since there will be no impact on equipment reliability or availability.

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ATTACHMENT 4 NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION I 1

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No Significant Hazards Consideration Determination

..The'following discussion is a summary of the evaluation of the changes contained in.this proposed amendment against the 10 CFR 50.92 (c) requirements to demonstrate that all three standards are satisfied. A-no.significant hazards consideration is indicated if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated, or'

2. Create the possibility of a new or'different kind of accident from any accident previously evaluated,-or

3. Involve a significant reduction in a margin of safety.

First Standard Implementation.of this amendment would not involve a significant  !

increase in the probability or consequences of an accident previously evaluated. Approval of this amendment will have.no effect on accident probabilities or consequences. No physical i changes are being made to the plant design which will result in any increase in accident probabilities. Approval of this 1 amendment will not result in a decrease in system or equipment reliability or availability. Therefore, there will be no impact on'any accident consequences.

Second Standard Implementation of this amendment would not create the possibility of a new or different kind of accident from any' accident

-previously evaluated. No new accident causal mechanisms are created as a result of NRC approval of this amendment request. .

No changes are.being made to the plant that will introduce any l new accident causal mechanisms. j 1

Third Standard  :

Implementation of this amendment would not involve a significant reduction in a margin of safety. Margin of safety is related to the confidence in the ability of the fission product barriers to j perform their design functions during and following an accident l situation'. These barriers include the fuel cladding, the reactor coolant system, and the-containment nystem. The performance of these' fission product barriers will not be degraded by the implementation of this amendment. No safety margins will be impacted.

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F Based.upon the preceding discussion, Duke Energy Corporation has concluded that the proposed amendment does not involve a

. . significant hazards consideration.

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ATTACHMENT 5-ENVIRONMENTAL ASSESSMENT i

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Pursuant to 10'CFR 51.22(b),.an evaluatien of this license

. amendment request has been performed to determine whether or not

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• it meets the criteria' for categorical exclusion set forth in 10 CFR151. 22 (c) (9) of the regulations.

This amendment to the Catawba TS deletes TS 3.3.7 and 3.3.8 concerning the CRAVS and ABFVES Actuation Instrumentation, respectively, and adds a note regarding chlorine protection to TS 3.7.10 concerning the CRAVS itself.

Implementation of this amendment will have no adverse impact upon the Catawba units;.neither will it contribute to any additional 3 quantity or type of effluent being available for adverse environmental impact or personnel exposure.

It has been determined there is:

1. No significant hazards consideration.

2. No significant change in the types, or significant increase in the amounts, of any effluents that-may be released offsite, and

3. No significant_ increase in individual or cumulative occupational radiation exposures involved.

Therefore, this amendment to the Catawba TS meets the criteria of 10 CFR 51.22 (c) (9) for categorical exclusion from an environmental assessment / impact statement.

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