ML20070T765

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Forwards 910327 License Amend Request 91-001 Re Addition of Spec 3/4.7.12 & Bases 3/4.7.12 for Safety Chilled Water Sys
ML20070T765
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 04/01/1991
From: William Cahill, Walker R
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To: Locker D
TEXAS, STATE OF
References
TXX-91138, NUDOCS 9104050098
Download: ML20070T765 (1)
v • d • e


Text

9 i-

-9 Log # TKX.91138

-,,, ,,-- File # 916(3/4.7)

= = Ref. # 10CFR50.92 filELECTRIC $fr"gh',f' Wiman J. CsWil Jr.

tmwtw sw am*= April 1, 1991 Mr. D. K. Locker Bureau of Radiation Control Texas Department of Health 1100 West 49th Street Austin, Texas 78704

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50 445 LICENSING AMEN 0HENT REQUEST 91 001 AODITION OF SPECIFICATION 3/4.7.12 AND BASES 3/4.7.12, SAFETY CHILLED WATER SYSTEM Dear Mr. Locker Pursuant to 10CFR 50.91(b), TV Electric is providing the attached copy of the application for the proposed amendment to Facility Operating License No.

NPF 87. The License Amendment Request (LAR) proposes the addition of Technical Specification Section 3/4.7.12 and the Bases to 3/4.7.12. Technical Specification 3/4.7.12 provides a technical specification for the Safety Chilled Water System. This Technical Specification is being added to identify the proper controls and actions for this safety related support systems.

Sincerely, C[f ,m f William J. Cahill, Jr.

sy rk '

!?

R?D. Walker Manager of Nuclear Licensing MCP/vid Attachment O

cSwM,%S?NRC7D'opunenfC"ontrollDesk i 'Mrl R'.!' D Martin," Region IV

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-i u*e. ,yO_

o J Resident inspectors, CPSES (3)

,,3 Hr J. W. Clifford. NRR p?g405 cops 93949, _

p 400 North ouw Strwt LB. 81 Delta Texas 75201 ADOCK 05000445 PDR

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M EE Log # TXX 91082 f?

TilELECTRIC March 27, 1991 w um = J. cehat. h.

tmum en em.*=

0. S. Nuclear Regulatory Commission Attn Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES), UNIT 1 DOCKET NO. 50 445 LICENSING AMENOMENT RE0 VEST 91 001, ADDITION OF SPECIFICATION 3/4.7.12 and BASES 3/4.7.12.

SAFETY CHILLED WATER SYSTEM Gentlemen:

Pursuant to 10CFR 50.90, enclosed is an apr11 cation for amendment to Facility The enclosed License Amendment Request (LAR)

Operating License No. NPF 87.

proposes the addition of Technicai Specification Section 3/4.7.12 and the Bases to 3/4.7.12. Technical Specification 3/4.7.12 This provides a technical Technical specification for t*ie Safety Chilled Water System.

Specification is being added to identify the proper controls and actions for this safety related support system.

While the change proposed in this LAR is not required to address an immediate safety concern, incorporation of this change would greatly aid the operator by providing a consistent ar.proach concerning the operability of the Safety Chilled Water System. Accordingly, TU Electric desires to implement the.

requested change as soon as possible and therefore, requests timely review and approval of this LAR by the NRC. TV Electric requests that the revised Technical Specifications be made effective seven days after approval of the license am?ndment by the NRC.

Sincerely, Mr William J. C hill, Jr.

MCP/grp Attachment Enclosure c Mr. R. D. Martin, Region IV Resident inspectors. CPSES (3)

Mr. J. W. Clifford. NRR (Vf&G[ q 400 North Oh Strwt LS. 81 DeAes.Teus 7$301

Attachment to TXX 91082 Page 1 of 1 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

)

in the matter of )

) Docket No. 50 445 Texas Utilities Electric Company

)

)

(Comanche Peak Steam Electric )

Station, Unit 1)

AFFIDAVII William J. Cahill, Jr. being duly sworn, hereby deposes and says that he is Executive Vice President, Nuclear of TO Electric, that he is duly authorized to sign and file with the Nuclear Regulatory Commission this transmittal of License thereof Amendment Request 91 001; that he is familiar with best of his knowledge, information and belief.

7 2 A dV '

WliliamJ.Catffl.Jr.

Executive Vice President. Nuclear STATE OF TEXAS )

)

COUNTY OF ScenavtLL )

Subscribed and' sworn to before me, a Notary Public, on this 27th day of w eh ., 1991,

t. /2 Y Notary Public J

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.. .. .PATNCLA

, m ames WILSON

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Enclosure to TXX 91082

  • Page 1 of 13 CPSES UNIT 1 NRC DOCKET NO. 50 445 ADDITION OF TECHNICAL SPECIFICATION 3/4.7.12 and BASES 3/4.7.12 TABLE OF CONTENTS
1. SIGNIFICANT HAZARDS CONSIDERATION
2. PROPOSED INSTRUCTIONS FOR INCORPORATION
3. PROPOSED TECHNICAL SPECIFICATION 1

I 1

1

i Enclosure to TXX 91082 Page 2 of 13  !

l 1

CPSES UNIT 1 HRC DOCKET NO. 50 445 ADDITION OF TECHNICAL SPECIFICATION 3/4.7.12 and BASES 3/4.7.12 SIGNIFICANT HAIARDS CONSIDERATION

, Enclosure to ?XK.91082 i

' Page 3 of 13

- SIGNIFICANT HAZARDS CONSIDERATION PROPOSED CPSES UNIT 1 TECHNICAL $PECIFICATION CHANGES SAFETY CHILLED WATER SYSTEM LAR 91 001

1. DESCRIPTION OF TECHNICAL SPECIFICATION CHANGE RE0 VEST This request proposes to add Technical Spe:ification (3/4.7.12) for the Safety Chilled Water System to the Comanche Peak Steam Electric Station (CP5ES) Unit 1 Technical Specifications (NUREG 1399, Reference 1).

The change to the Technical Specification consists of the Safety l Chilled Water System Limiting Condition for Operation (LCO) 3,7.12, including the mode applicability and the required actions, and system surveillance requirements (4.7.12). This request also proposes that the basis for the new technical specification be added to the BASES.

!!. BACKGROUND The CPSES Unit 1 Technical Specifications do not currently include LCO, surveillance requirements or BASES for the Safety Chilled Water System. The purpose of this proposed tecnnical specification change is to provide a technical specification for this safety related support system.

' The Safety Chilled Water System is comprised of two independent 100% capacity trains of safety related equipment. The function of the $afety Chilled Water System is to provide essential cooling to fan coolers for motor driven Engineered Safety Feature (ESF) pump rooms and to the Class IE electrical switchgear areas. The Safety Chilled Water System provides chilled water to the ESF pump room coolers and electrical switchgear area coolers during accident conditions. The ESF pump room coolers are interlocked to start with their respective ESF pumps on a safety injection actuation signal. The safety chilled water system, the electrical switchgear area f an coolers and ESF pumps receive an automatic start signal f rom a safety injection actuation signal. The safety chilled water system provides cooling to the electrical switchgear area during loss of of f site power. The safety chilled water system also provides chilled water to the cooling coils of the ESF pump room coolers during normal operation. Tne ESF pump room areas and electrical switchgear areas are normally cooled by a non safety related heating, ventilating and air conditioning i

(HVAC) system during normal operation. See FSAR Sections 9.4.3.

9.4.5, and 9.4F (Reference 2) for additional details.

! ! ! .' JUST!FICATION The requested technical specification is needed to provide explicit identification of the operational requirements for the Safety Chilled Water System in a manner consistent with the existing technical specifications for other similar plant support and station service systems (e.g.. component cooling water (CCW) water (SSW) systems).

IV. SAFETY EVALOATION The proposed LCO and surveillance requirements are consistent with comparable safety related support systems for CPSES Unit 1 (CCW and SSW Systems) as well as those at similarly designed licensed facilities (Shearon Harris Unit 1. Palo Verde Units 1, 2 and 3, and Vogtle Units 1 and 2. References 3, 4 and 5 respectively).

The requirement for two independent trains of safety chilled water to be OPERABLE is consistent with the assumptions used in the The proposed change is safety analyses for CPSES Unit 1.

consistent with the single failure criteria as required by 10CFR50, Appendix A, General Design Criterion 44, Cooling .hter.

The applicability in MODES 1. f., 3 and 4 ensures the OPERABILITY of safety chtiled water in the event of a design basis accident (OBA).

It ensures that the required support system will be available to supply cooling for the safety related equipment required for safe shutdown and for the mitigation and control of Hence, the reliability of the system will be accident conditions.

improved by the proposed change.

V. OETAILED DISCUS $10N OF PROPOSED TECHNICAL SPE The proposed LCO 3.7.12, requires that two independent trains of 1 safety chilled water be capable of ptrforming their safety functions in plant operating MODES 1, 2, 3 and 4.

/

The ACTION required by LCO 3.7.12 if one train is not operable is  !

to restore the capability of the system within an appropriate time  ;

(72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) or to place the plant in an operational MODE for which '

the LCO no longer applies.

The proposed system surveillance requirement 4.7.12, requires that the position of each valve in the flow path servicing safety related equipment be periodically verified to be in its correct position unless it is secured in its correct position by locks, seals, or other appropriate means.

The proposed system surveillance requirement also requires periodic testing of the automatic start of the saf sty chilled water pump and chiller, and the electrical area fin coil units on a safety injection test signal,

Enclosure to TXX 91082 Page 5 of 13 VI.' PRECEDENTS The principal attributes of the proposed CPSES Unit 1 Technical Specification change have previously been incorporated in Technical Specifications for other licensed facilities (e.g..

Shearon Harris Unit 1. Palo Verde Units 1. 2 and 3. and Vogtle Units 1 and 2). Also, the proposed Technical Specification change will provide consistency with technical specifications for CCW and SSW systems existing in the CPSES Unit 1 Technical Specifications.

Vll. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION PER 10 CFR 50.92 TV Electric has evaluated whether or not a significant hazards consideration is involved with the proposed changes by focusing on the three standards set forth in 10CFR50.92(c) as discussed below:

Does the proposed change:

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

The proposed LCO does not alter any of the assumptions used in the safety analyses for CPSES Unit 1 because the capability of the Safety Chilled Water System to transfer heat from its supported safety systems to the CCW system The under normal and accident conditions is maintained.

LCO ensures suitable redundancy to assure that for onsite electric power system operation (assuming offsite power is not available) the system safety function can be accomplished assuming a single failure.

The proposed surveillance requirements will enhance the reltability of the chillers because they will enforce a periodic inspection of the chiller that is in a standby mode. This surveillance will assure all valves, pumps and components will perform as required and the chiller will perform its sefety function.

4 These surveillance requirements are commensurate with the CCW and SSW system surveillance requirements.

Therefore, the proposed Technical Specification change has no effect on the probability or consequences of any accident previously evaluated for CPSES Unit 1.

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

The proposed LCO. surveillance requirements and BASES do not involve any hardware changes or any revisions in how the system functions. Therefore, no new failure modes are created and no possibility for new or different kinds of accidents i,s created.

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' Enclosure to TXX 91082 Page 6 of 13 3.

Involve a significant reduction in the margin of safety?

The margin of safety for the Safety Chilled Water System relative to Technical Specifications is preservation of the single failure criterion. The proposed LCO with respect to Safety Chilled Water System satisfies the single failure criteria provided General Design Criterion 44, Cooling Water.

Standard Technical Specifications issued for use on cPSES Unit 1 (Reference 6) provide the bases for the limitations placed on cooling water systems with redundant cooling capacity and which, assuming a single failure, are consistent with the assumptions used in the safety analyses, The standard time allowed to restore an inoperable train of such cooling water systems is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Because the proposed Technical Specification invokes this time limit, there is no reduction in the margin of safety which forms the basis for CPSES Technical Specifications.

Yll!, NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The Nuclear Regulatory Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (51 FR 7751, Reference 7) of amendments that are considered not likely to involve significant hazards consideration. Example (i) relates to a change to achieve Example (ii) consistency throughout the Technical Specifications.

relates to a change that constitutes an additional limitation, restriction or control not presently included in the technical specifications.

In this case, the proposed Limiting Condition for Operation in that the Safety described above is similar to example (1)

Chilled Water System specification isThe consistant prop 9 with sed other surveillance similar systems (e.g. SSW and CCW). in that adding the described above is similar to example (ii) technical specification for the Safety Chilled Water System constitutes an additional limitation (e.g. an additional survet11ance) not presently included in the Unit 1 Technical Specifications.

1

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  • Enclosure to TXX 91082 Page 7 of 13 Based on the above evaluations. TV Electric concludes that the activities associated with the above described changes present no significant hazards consideration under the standards set out in 10CFR50.92(c) and, accordingly, a finding by NRC of no significant hazards consideration is just(fied.

IX. ENY1RONMENTAL EVALUATION TV Electric has evaluated the proposed changes and has determined that the changes do not involve (i) a significant hazards consideration (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or Accordingly, the cumulatiYe occupational radiation exposure.

proposed changes meet the eligibility criterion for categorial Therefore, pursuant to exclusion set forth in 10CFR51.22(c).

i 10CFR51.22(b), an environmental assessment of the proposed changes is not reqr X. REFERENCES 1",

1. NUREG 1399, " Technical Specifications, CPSES Unit No April 1990
2. CPSES, FSAR Section 9.4 i
3. NUREG 1240, " Technical Specifications, Shearon Harris.

Unit No 1", No January 1987

(

4, NUREG'S 1133, 1181, 1287, " Technical Specifications, Palo Verde Nuclear Generating Station, Unit Nos 1. 2 and

3. May 85/ April 86/ November 87.
5. NUREG 1359, " Technical Specifications, Vogtle, Unit Nos. 1 and 2", March 1989
6. NRC letter from Mr. C.I. Grimes to Mr. W.G. Counsil, dated August 14, 1987, transmitting current Westinghouse 3

Standard Technical Specification.

7. 51 FR 7751, " Federal Register Vol. $6, No. 44, Rules and Regulations", March 6, 1986 l

-g

.- Enclosure to TXX 91082

  • Page 8 of 13 CPSES UNIT 1 NRC DOCKET NO. 50 445 OPERATING LICENSE NPF 87 ADDITION OF TECHNICAL SPEtfFICATION 3/4.7.12 and BASES 3/4.7.12 1

S AFETY CHILLED W ATER SYSTEM INSTRUCTIONS FOR ILCOP0 RATION The proposed amendment to the Technical Specifications (Appendix A to Operating License NPF 67) would be incorporated as follows:

Remove Pane Insert Paae index vill & xit Index viii & xii

- -3/4 7 26 8 3/4 7 7 8 3/4 7 7

!Nb? O } #[h [ff 1

Enclosure to TXX 91082 Pa9e 9 of 13 CPSES UNIT 1 NRC DOCKET NO. 50 445 ADDITION OF TECHNICAL SPECIFICATION 3/4.7.12 and BASES 3/4.7.12 PROPOSED TECHNICAL SPECIFICATION 1

)

I 1

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~7 *M Enclosuro to TIX-91082 Pags 10 of 13

!NDEX LIMI'YING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS DaGE

$!! TION 3/4.6. OEPRESSURIIAT: N AND COOLING SYSTEMS 3/4 6-;1

ntainmen; S: ray System. .. ...... ........ .. .

5: ray A:01tive System. . . . .. . . . . 3/4 6-12 CONTAINMENT ISOLATION VALVES.. .. ........ ............ 3/4 6 13 3/4.6.3 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors. ........................ .......... ..

3/4 6 15 Electric Hycrogen Recomoiners.................... ....... 3/4 6 16 3/4.7 DLANT Sv5TEMS 3/4.7.1 TURBINE CYCLE Safety valves............................................ 3/4 7 1 TABLE 3.7-1 max! MUM ALLOWABLE power RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVCS OURING FOUR LOOP 0PERATION......................................

3/4 7 2 3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.....................

Auxiliary Feeewater System.................. ............ 3/4 7-3 Condensate Storage Tank.................... ............ 3/4 7 5 Soecific Activity.......................... ............ 3/4 7-6

  • ABLE 4.7-1 SECONDARY CCOLANT SYSTEM SPECIFIC ACTIVI* SANPLE AND ANALYSIS PR0 GRAM..................................... 3/4 7-7 3/4 7 6 Main Ste am Line Isolation Va1ves. . . . . . . . . . . . . . . . . . . . . . . . .

3,4 7-9 Main Feedwtter Isolation Valves..........................

Steam Generator Atmospheric Relief Valves................ 3/4 7-11 3i4 7-12 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........

3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SY ST EM. . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 7-14 3/4.7.4 STAT 10N SERVICE WATER SYSTEM.............................

3/4 7-15 3/4.7.5 ULTERAT E NEAT $ 1 NK . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 7-16 3/4.7.6 FL800 PROTECT 10N.........................................

3/4 7-17 3/4.7.7 CONT RO L ROOM HV AC SY S T EM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 7-20 3/4.7.8 PRIMARY PLANT VENTILATION SYSTEM - ESF FILTRATION UNITS..

3/4 7-22 3/4.7.9 SNUBBERS.................................................

MONITORING.............................. 3/4 7 23 3/4.7.10 AREA TEMPERATURE MONITORING........................... 3. 4 7-24 TABLE 3.7 3 AREA TEMPERATURE

. ......................... 3 a 7 25 3/4.7.11 UPS__NVAC SYSTEM... .

% .7 12. 6 A FFry CHILLO WATDR. SyJTEM JA N ]/ ,

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Enclosuro to TXX 910A2 Page 11 of 13 INDEX BASES PAGE SECTION_

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS................................ B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK.............................. B 3/4 5 2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 P R I MARY CONT A ll#4ENT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS...................... B 3/4 6-3 3/4.6.3 CONTA DETENT I SO LAT I ON V ALV E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-3 3/4.6.4 C006USTIBLE GAS CONTR0L................................... B 3/4 6-4 3/4.7 PLANT SYSTEMS 3/4.7.1 TUR$1NE CYCLE............................................. B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE /TE)fERATURE LIMITATION. . . . . . . . . . . B 3/4 7-3 3/4.7.3 C0f90NENT COOLING WATER SYSTEM............................ B 3/4 7 4 3/4.7.4 STATION SERVICE WATER SYSTEM.............................. B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK........................................ B 3/4 7 4 3/4.7.6 FLD00 PROTECT!0N.......................................... R 3/4 7-4 3/4.7.7 CONTROL R00h ;NAC SYST94. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-5 3/4.7.8 PRIMARY PLANT VENTILATION SYSTEM - ESF FILTRATION UNITS... B 3/4 7-5 3/4.7.9 SE28ERS.................................................. B 3/4 7 5 3/4.7.10 AREA TDFERATURE MONITORING...............................

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B 3/4 7_6

. 7.1 B 3/4 7-7

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3/4.8.1, 3/4.8.2, and 3/4.6.3 A.C. SOURCES. 0.C. SOURCES, and OIts!TE PO E R DISTRIBUTION........ -...................... B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPIENT PA0TECT!YE .' utS. . . . . . . . . . . . . . . . . . . B 3/4 8-3 3/4.9 REPm tua OPERATI0lts 3/4. 9.1 MMI CtBICENTRATI0N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.2 M AT!0N...........................................

B 3/4 9-1 3 /4 . 9 . 3 edw ist . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.4 CONTAlle p T SUILDING PENETRATIONS......................... B 3/4 9 1 3/4.9.5 C0f0 G ICATIONS............................................ B 3/4 9-1 3/4.9.6 REFUELING M4 CHINE......................................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS................... B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOYAL AND C0OLANT CIRCULATION............. B 3/4 9-2 3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL and B ,<4 9-3 IRP4DIATED FUEL STORAGE .................................. i s

CMANCHEPEAK-imIT1 xii

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knclosuro to13Txx-91082 P,ago 12 0.f 4

DRAFT

' PLANT SYSTEM 1 ORAFT 3/4.7.12 SAFETY CHILLED WATER SYSTEM ORAFT LIMITING CONDITION FOR OPERATION _

ORAFT 3.7.12 At least two independent safety chilled water trains shall be OPERABt.E .

DRAFT APPLICABILIII: MODES 1, 2, 3, and 4.

ORAFT t

ACTION: '

DRAFT With only one safety chilled water train OPERABLE, restore at least two trains to OPERABLE status within 72 I,ours or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within ine ,

following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ORAFT SURVEILLANC.LREQtjlREMENTS lORAFT 4.7.12 The safety chilled water trains shall be demonstrated l DRAFT OPERABLE:

ORAFT

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing s.R'v-related equipment that is not locked, sealed or oth -ise secured in position, is in its correct position, ORAFT
b. At least orse per 18 months by demonstrating that each safety '

chiiled water train pump, chiller and electrical switchgear

' area emergency fan coil units start on a Safety Injection test signal, I

COMANCHE PEAK - UNIT 1 3/4 7 26

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Enclosuro to TXX-91080 PCgo 1,3 of 13

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  • Me OPERA 61dTY of the ur5 HVAC System ensures tnat the uninteruottole mpower sucoiv and cistricution rooms ameient air temocratures do not exceee at g t.e i!ow'aole temceratures per Specification 3/4.7.10 for u ntinuous-cuty 4 .aionent.

<ct tne ecu ement anc instrumentation cooled by this i

4

./4.7.12 $AFETY CHILLED WATER SYSTEM i. DRAFT

. ORAFT The OPERABILITY of the Safety Chilled Water System ensures that sufficient cooling capacity is available for continued operation of safety related equir wnt during normal and accident conditions. The redundant cooling capacity of this system, assuming a sigle failure, is consistent with the assumptions used in the safety analyses.

)

B 3/4 7-7 CCMANCHE FIAK - UNIT 1

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