ML20086F487

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Submits Rev 6 of Facility Technical Requirements Manual
ML20086F487
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 11/22/1991
From: William Cahill
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-91437, NUDOCS 9112030245
Download: ML20086F487 (21)
v • d • e


Text

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h""""""."f Log # TXX-91437 File #

10 2

Ref. # 10CF 50, 6 itlELECTRIC November 22, 1991 Willlaan J. enhHl. Jr.

Gnwp l'ua henJrni U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) - UNIT 1 DOCKET NO. 50-445 TRANSMITTAL Of TECHNICAL REQUIREMENTS MANUAL, REVISION 6 Gentlemen:

TV Electric herewith submits Revision 6 (enclosed) of the CPSES Technical Reauirements Manual.

Enclosed are the following documents:

Technical Requirements Manual - 1 signed (and sworn) original Revision 6 and 37 copies A page-by-page description of the changes is attached.

The group number assigns a level of significance f or each change made to the Technical Requirements Manual consistent with TU Electric's letter TXX-88467 of June 1, 1988.

Each change was evaluated under the 10CFR50.59 process and it was determined that no unreviewed safety questions exist.

Please insert the revised pages into your controlled copy per the enclomd instruction.

Sincerely,

[

/

William J. Cahill, Jr.

CBC/vid Attachments Enclosure c-Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) ei n

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Attachment I to IXX-91437 Page 1 of 1 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMIS$10N in the Matter of Texas Utilities Electric Company Docket No. 50-445 (Comanche Peak Steam Electric Station, Unit 1)

AIf10Bil William J. Cahill, Jr. being duly sworn, hereby !!cposes and says that he is Group Vice President, Nuclear of TU Electric, the lead Applicant herein; that he is duly authorized to sign and file with the Nuclear Reg {ulatory Commission this transmittal of Revision 6 of the Technical Requiremen 3 tianual for the captioned facility; that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.

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U 1 Tams ya,hi t La Jr.

Group Vice Presi ent, Nuclear STATE OF TEXAS COUNTY OF 5 m vs c)

Subscribed and sworn to before me, on this

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day of s ce n s c.,

1991.

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BILL J. HODGES 0TJ

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.gj March 28.1992

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At t achment 2 to TXX-91417 CPSES TRH REVISION 6 Page 1 of' )

DETAILED DESCRIPTION Pago 1 T RN Page (as estaded)

Group Detttjption Table 2.1.1 3

See Sheet No(s):page 2 13 Adds the personnel and emergency airlock equalizing valves and the personnel airlock hydraulic system valves.

Revision:

These valves are subcomponents of their respective air-locks. The airlocks comply with General Design Criteria 50 and 56.

These valves are relied upon to perform a containment isolation function and comply with the applicable requirements of GDC 56 and GDC 57.

TRH Change Request Number 1R-90-10 Related SER Section: 6.2.3 SER/SSER Impact: No Table 2.1.1 3

See Sheet No(s):page 2 13 Adds the # Note to all the equalizing valves and the hydraulic system vdives to denote that these valves may be opened under administrative control.

Revision:

These valves must be opened as a9propriate to allow containment entry and exit.

This note identifies the valves that may be opened without entering an LC0 (i.e., the valves are still OPERABLE).

TRH Change Request Number: TR 90 10 Related SER Section: 6.2.3 SER/SSER 1mpact: No Table 2.1.1 3

See Sheet No(s):page 2 25 Adds Note 5 to clarify the applicable surveillance requirements to be used for testing the equalization valves to satisfy 10 CFR 50 Appendix J.

Revision:

These valves are required to be Type C tested in accor-dence with 10 CFR 50 Appendix J, paragreph II.H.

This leakage rate requirement is satisfied by Surveillance 4.6.1.3b which is more stringent than 4.6.1.2d.

TRH Change Request Number: TR-90 10 Related SER Section: 6.2.3 SER/SSER Impact: No Table 2.1.1 3

See Shtet No(s):page 2-25 Adds Note 6 to clarify that equalization valves are subject to the controls of Specification 3.6.1.3.

Revision:

These valves are operated in conjuction with their respective airlock door to equalize pressure between the inner and outer boundary during containment entry

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~

" to TXX-91437 CPSES TRH REVISION 6 Page 2 oi 2 DETAILED DESCRIPTION Page ?.

TRM Page (n mended)

Group Ductlation and egress. The equalization valves must be opened and closed in conjunction with their respective dvor to satisfy the Limiting Condition for Operation (LCO) for airlock OPERABILITY.

The opening of an airlock door requires the assistance of an equalizing valve and are thus considered part of the respective door to ensure that a single containment boundary is maintained per the LCO in Specification 3.6.1.3.

This LCO permits a single door and its associated equalizing valve to be opened at a time for normal entry and exit through Containment during H0 DES 1 through 4 Specification 3.6.1.3 Action (a) addresses inoperabili-ty of the airlock door and Action (b) addresses inoper-ability of the airlock, if non compliance to the LCO is determined following investigation permitted per Action (b) to be as a result of an equalizing valve, then Action (a) may be used provided that one isolation boundary can be maintained to ensure containment inte-grity.

TRM Change Request Number: TR 90 10 Related SER Section: 6.2.3 SER/SSER Impact: No Table 2.1.1 3

See Sheet No(s):page 2-25 Adds Note 7 to clarify which equalization valves are interlocked with an airlock door operating mechanism.

Revision:

These equalization valves are secured by hydraulic system valves and interlocks and do not require separate locks.

The interlocks satisfy the locking requirements of G00-56 and T/S 3.6.1.3.

TRH Change Request Number: TR 9010 Related SER Section: 6.2.3 SER/SSER 1mpact: No l

CPSES/TRH COMANCHE PEAK STEAM ELECTRIC STATION TECHNICAL REQUIREMENTS MANUAL (TRM)

INSTRUCTION SHEET The following instructional inf ormation and check list is being f urnished to help insert Revision 6 into the Comanche Peak Steam Electric Station TRM.

A description of this revision is provided in Attachment 2 of TXX-91437, dated November 22,19')1.

Discard the old sheets.and insert the new sheets, as listed below.

Keep these instruction' sheets in the front of the Effective Page Listing to serve as a record of changes.

Egmple 1nsert Section 2 2 13 thru 2+24-2 13 thru 2 26' list of Effective Paaes EPL-1 thru EPL 2 EPL+1 thru EPL 2

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IffHNICAL RE001REMENT 2 1 (continued) i TABLE 2.1.1 (continued)

CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO.

REFERENCE NO.*

LINE OR SERVICE (Seconds) RE0UIREMENTS

4. Manual Valves (Continued) 185-0016#

130 Airlock Hydraulic N.A.

N.A.

6 System 6

185-0017#-

130 Airlock Hydraulic N.A.

N.A.

6 System-6 1B5-0030#

131 Airlock N.A.

Notes 6

Hydraulically 5,6,7 6

Operated Equalization 6

185-0025#

131 Airlock N.A.

Notes 6

Hydraulically 5,6,7 6

Operated Equalization 6

105-0056#

131a Airlock Manual H.A.

Notes 6

Equalization 5, 6 6

185-0044#

131a Airlock Manual N.A.

Notes 6

Equalization 5, 6 6

1B5-0029#

131a Airlock Manual N.A.

Notes 6

Equalization 5, 6 6

'2B5-0015#

131a Airlock Manual N.A.

Notes 6

Equalization 5, 6 6

l --

185-0202#

132 Airlock Manual N.A.

Notes 6

l-Equalization 5,6,7 6

185-0203#

132 Airlock Manual N.A.

Notes 6

Equalization 5,6,7 6

L t

l l

l-COMANCHE PEAK UNIT 1 2-13 Revision 6 November 22, 1991

. :L.

TECHH!{AL REQUIREMENT 2.1 (continued 1 TABLE 2.1.1 (continued 1 CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO.

REFERENCE NO.*

LINE OR SERVICE (Seconds) REOUIREMENTS

5. Power-0perated Isolation Valves 1HV-2452-1 4

Main Steam to Aux.

N.A.

N.A.

FPT From Steam Line #1 1PV-2325 5

Atmospheric Relief N.A.

Note 3 3

Steam Generator 1PV-2326 9

Atmospheric Relief H.A.

Note 3 3

Steam Generator IPV-2327 13-Atmospheric Relief N.A.

Note 3 3

Steam Generator 1HV-2452-2 17 Main Steam to Aux.

N.A.

N.A.

FPT From Steam Line 1PV-2328 18 Atmospheric Relief N.A.

Note 3 3

Steam Generator 1HV-2491A 20a Auxiliary Feedwater N.A.

N.A.

to Steam Generator

  1. 1 1HV-24918 20a Auxiliary Feedwater N.A.

N.A.

to Steam Generator

  1. 1 1HV-2492A 22a Auxiliary Feedwater N.A.

N.A.

to Steam Generator

'92 1HV-2492B 22a Auxiliary Feedwater N.A.

N.A.

to Steam Generator

  1. 2 1HV-2493A 24a Auxiliary feedwater N.A.

N.A.

to Steam Generator

  1. 3 l

1HV-2493B 24a Auxiliary Feedwater N.A.

N.A.

l to Steam Generator

  1. 3 l

COMANCHE PEAK - UNIT 1 2 14 Nov9eber 22, 1991

.-~.- -

1[fHNICAL REOUIREMENT 2.1 (continued)

TABLE 2.1.1 (continued)

CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST YALVE NO.

REFERENCE NO.i*

LINE OR SERVICE (Seconds) REOUIREMENTS

5. Power-0peratedIsciationValves(Continued) 1HV-2494A 26a Auxiliary Feedwater N.A.

H.A.

to Steam Generator 94 1HV-24948 26a Auxiliary Feedwater N.A.

N.A.

to Steam Generator

  1. 4 1-8701B 33 RHR From Hot Leg N.A.

C Loop #4 1-8701A 34 RHR From Hot leg H.A.

C Loop #1 1-8809A 35 RHR to Cold Leg N.A.

Note 4 2

Loops #1 and #2 1-88098 36 RHR to Cold Leg N.A.

Note 4 2

Loops #3 and #4 1-8801A 42 Safety Injection N.A.

N.A.

to Cold Leg Loops

  1. 1, #2, #3, and #4 1-8801B 42 Safety injection N.A.

N.A.

to Cold Leg Loops

  1. 1, #2, #3, and #4 i

1-8802A 43 SI Injection to N.A.

N.A.

RCS Hot Leg Loops

  1. 2 and #3 1

1 1-88028 44 S! Injection to N.A.

N.A.

RCS Hot Leg loops

  1. 1 and #4 L 8835 45 SI Injection to N.A.

.N.A.

RC3 Cold Leg Loops

  1. 1, #2, #3, and #4 i

C0KANCHE PEAK - UNIT 1 2-15 November 22, 1991

f TICHNICAL REOUIREMENT 2.1 (continued)

TABLE 2.1.1 (continued)

CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION N01ES AND FSAR TABLE TIME LEAK TEST VALVE NO.

REFERENCE NO.*

LLEE OR SERVICE (Seconds) REQUIREMENTS

5. Power-Operated Isolation Valves (Continued) 1-8351A 47 Seal Injection to N.A.

N.A.

RC Pump (Loop #1) 1-835.3 48 Seal Injection to N.A.

N.A.

RC Pump (Loop #2) 1-8351C 49 Seal Injection to N.A.

N.A.

RCPump(Loop #3) 1-83510 50 Seal Injection to N.A.

N.A.

RC Pump (Loop #4) 1HV-4777 54 Containment Spray N.A.

Note 4 2

i.o Spray Header (TrainB) 1HV-4776 55 Containment Spray N.A.

Note 4 2

to Spray Header (Train A) 1-8840 63 RHR to Hot Leg N.A.

Note 4 2

Loops #2 and #3 1-8811A 125 Containment N.A.

N.A.

I Recirc. Sump l

to RHR Pumps j

(Train A) l 1-8811B 126 Containment N.A.

N.A.

Recirc. Sump to RHR Pumps (Train B) 1HV-4782 127 Containment N.A.

N.A.

Recirc. to Spray Pumps (TrainA) 1HV-4783 128 Contair, ment N.A.

N.A.

Recirc. to Spray Pumps (Train B)

L l

COMANCHE PEAK - UNIT 1 2-16 November 22, 1991

TECHNICAL RE091REMENT P.1 (continued TABLE 2.1.1 (continug d CONTAINHENT ISOLATION VALVES MAXIMUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO.

.R[FERENCE NO.*

LINE OR SERVICE fSeconds1 REOUIREMENTS

6. Check Valves 1-8818A 35 RHR to Cold leg N.A.

H.A.

Loop #1 1-8818B 35 RHR to Cold Leg N.A.

N.A.

-Loop #2 1-8818C 36 RHR to Cold Leg H.A.

N.A.

Loop #3 1-88180 36 RHR to Cold Leg N.A.

N.A.

Loop #4 l

1-8046 41 Reactor' Makeup H.A.

C Water to Pressu-rizer Relief Tank and RC Pump Stand Pipe 1-8815 42 High Head Safety N.A.

N.A.

l Injection to Cold i

Leg loops #1, #2, I

  1. 3, and #4 151-8905B 43 SI to RC System H.A.

N.A.

l Hot Leg Loop #2 ISI-8905C 43 Si to RC System N.A.

N.A.

Hot Leg Loop #3 ISI-8905A 44 SI to RC System N.A.

N.A.

Hot Leg loop #1 151-89050 44 SI to RC System N.A.

N.A.

Hot Leg loop #4 1SI-8819A 45 SI to RC System N.A.

N.A.

Cold Leg loop #1 l

l-l l

l COMANCHE PEAK - UNIT 1 2-17 November 22, 1991

. -. -. - -,. -......-_. -.. -.. -.~ - -

L. - -..

IffHNICAL REQUIREMENT 2.1 (continue 41 TABLE 2.1.1 (continued)

I

[0NTAINMENT ISOLATION VALVES HAXIMUM ISOLATION NOTES AND FSAR TABLE TlHE LEAK TEST VALVE NO.

REFEREtj(( R

  • LINE OR SERVICE (Seconds 1 Bf00lREMENTS
6. Check Valves (Continued) 151-8819B 45 51 to RC System N.A.

N.A.

Cold Leg Loop #2 151-8819C 45 Si to RC System H.A.

N.A.

Cold Leg Loop #3 151-88190 45 Si to RC System H.A, H.A.

Cold Leg loop #4 1-8381 46 Charging Line to N.A.

C Regenerative Heat Exchanger ICS-8368A 47 Seal Injection to N.A.

N.A.

RCPump(Loop #1)

ICS-8368B 48 Seal Injection to N.A.

N.A.

RCPump(Loop #2) 1CS-8368C 49 Seal Injection to N.A.

N.A.

RC Pump (Loop #3) 1C5-83680 50 Seal injection to N.A.

N.A.

RC Pump (Loop #4) 1CS-8180 51 Seal Water Return N.A.

C and Excess Letdown ICT-145 54 Containment Spray N.A.

Note 4 2

to Spray Header (Tr.B) i l:

I COMANCHE PEAK - UNil 1 2-18 November 22, 1991

.~.

. _.._.. _. _.1..

IECHNICAL REQMIREMENT Pml (continued 1 TABLE 2.1.1 (continued)

CONTAINMENT ISOLATION VALVE 1 MAXIMUM ISOLATION NOTES AND 4

FSAR TABLE TIME LEAK TEST 3

VALVE NO.

REFERENCE NO.*

LINE OR SERVICE {$econds) RE0VIREMENTS

6. Check Valves (Continued) 1CT-142 55 Containment Spray N.A.

Note 4 2

to Spray Header (Tr. A) 101-030 62 Instrument Air N.A.

C to Containment 1-8841A 63 RHR to Hot Leg N.A.

N.A.

Loop #2 1-88418 63 RHR to Hot Leg N.A.

N.A.

Loop #3 151-8968 104.

N2 Supply to N. A.

C Containment 100-629 117 CC Return From N.A.

C

-RCP's Motors 100-713

-118 CC Supply to RCP's N.A:

C Motors 10C-831 119 CC Return From N.A.

C RCP's Thermal Barrier ICH-024 120 Chilled Water N.A.

C Supply to Contain-ment Coolers t

l COMANCHE PEAK - UNIT 1 2-19 November 22, 1991

1 JECHNICALREOUIREMENTPsL_{ continued)

IBLE 2.1.1 (continued)

(DNTAINMENT ISOLATION VALVES MAXIMUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO.

REFERENCE NO.*

LINE OR SERVICE LSeconds) REQUIREMENTS

7. Steam Line Isolation Signal i

1HV-2333A 1

Main Steam from 5

Note 2 & 3 Steam Generator #1 1HV-2409 3

Drain from Main 5

N.A.

Steam Line #1 1HV-2334A 6

Main Steam from 5

Note 2 & 3 Steam Generator #2 1HV-2410 8

Drain from Main 5

N.A.

Steam Line #2 1HV-2335A 10 Main Steam from 5

Note 2 & 3 Steam Generator #3 1HV-2411 12 Drain From Main 5

N.A.

Steam Line #3 1HV-2336A 14 Main Steam from 5

Note 2 & 3 l

Steam Generator #4 1

1HV-2412 16 Drain from Main 5

N.A.

Steam Line #4 i

COMANCHE PEAK - UNIT 1 2-20 November 22, 1991

ILgBNICAL REOUIREMENT 2.1 (continued)

TABLE 2.1.1 (continued)

CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO.

REFERENCE NO.*

LINE OR SERVICE {1grandil REOUIREMENTS

8. Feedwater Line Isolation Signal 1HV-2134 19 feedwater to 5

Note 3 Steam Generator #1 IFV-2193 20c Feedwater Preheat 5

Note 3 Bypass Line S.S. #1 1HV-2185 20d Feedwater Bypass 5

Note 3 Line S.G. #1 1HV-2135 21 feedwater to 5

Note 3 Steam Generator #2 1FV-2194 22c feedwater Preheat 5

Note 3 Bypass Line S.G. #2 1HV-2186 22d Feedwater Bypass 5

Note 3 Line S.G. #2 1HV-2136 23 feedwater to 5

Note 3 Steam Generator #3 1FV-2195 24c Feedwater Preheat 5

Note 3 Bypass Line S.G. #3 1HV-2187 24d Feedwater Bypass 5

Note 3 Line S.G. #3 1HV-2137 25 feedwater to 5

Note 3 Steam Generator #4 1FV-2196 26c Feedwater Preheat 5

Note 3 Bypass Line S.G. #4 1HV-2188 26d Feedwater Bypass 5

Note 3 Line S.G. #4 CDMANCHE PEAK - UNIT 1 2-21 November 22, 1991

e TECHNICAL RE091REMENT 2.1 (continuedi EBLE 2.1.1 (continuedl CONTAlHMENT ISOLATION VALVES MAXIMUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO.

REFERENCE NO.*

LINE OR SERVICE.(leconds) REOUIREMENTS

9. Safety Injection Actuation isolation 1-8105 46 Charging Line 10 C

to Regenerative Heat Exchanger

10. Relief Valves 1-8708B 33 RHR From Hot N.A.

C Leg Loop #4 1-8708A 34 RHR From Hot N.A.

C Leg Loop #1 IMS-021 Sb Main Steam Safety N.A.

Note 3 Valve S.G. #1 1MS-022 Sb Main Steam Safety N.A.

Note 3 Valve S.G. #1 1MS-023 Sb Main Steam Safety N.A.

Note 3 Valve S.G. #1 IMS-024 Sb Main Steam Safety H.A.

Note 3 Valve S.G. #1

(

1MS-025 Sb Main Steam Safety H.A.

Note 3 Valve S.G. #1 IMS-058 9b Main Steam Safety N.A.

Note 3 Valve S.G. #2 1MS-059 9b Main Steam Safety N.A.

Note 3 Valve S.G. #2 1MS-060 9b Main Steam Safety N.A.

Note 3 Valve S.G. #2 l

l COMANCHE PEAK - UNIT 1 2-22 November 22, 1991

IECHNICAL REOUIREMENT 2.1 (continued)

TABLE 2.1.1 (continued)

CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO.

REFERENCE NO

  • LINE OR SERVICE (Seconds)

REOUIREMENTS 10.ReliefValves(Continued) 1MS-061 9b Main Steam Safety N.A.

Note 3 Valve S.G. #2 1MS-062 9b Main Steam Safety N.A.

Note 3 Valve S.G. #2 1MS-093 13b-Main Steam Safety N.A.

Note 3 Valve S.G. #3 1MS-094 13b Main Steam Safety N.A.

Note 3 Valve S.G. #3 1MS-095 13b Main Steam Safety N.A.

Note 3 Valve S.G. #3 1MS-096 13b Main Steam Safety N.A.

Note 3 Valve S.G. #3

.1MS-097 13b Main Steam Safety N.A.

Note 3 Valve S.G. #3 1MS-129 18b Main Steam Safety H.A.

Note 3 Valve S.G. #4 1MS-130 18b Main Steam Safety N.A.

Note 3 Valve S.G. #4 1MS-131 18b Main Steam Safety N.A.

Note 3 Valve S.G. #4 1MS-132 18b Main Steam Safety N.A.

Note 3 Valve S.G. #4 1MS-133 18b Main Steam Safety N.A.

Note 3 Valve S.G. #4 COMANCHE PEAK - UNIT 1 2-23 November 22, 1991

~

lEEHNICALREOUIREMENT2.1(continued)

TABLE 2.1.1 (continued)

CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO.

REFERENCE NO.*

LINE OR SERVICE (Seconds) REOUIREMENTS 10.ReliefValves(Continued) 1RC-036 41a Penetration Ther-N.A.

C nel Relief 1WP-7176 52a Penetration Ther-N.A.

C mal Relief 100-430 60a Penetration Ther-N.A.

C mal Relief IVD-907 61a Penetration Ther-H.A.

C mal Relief 1PS-503 74a Penetration Ther-N.A.

C mal Relief 1PS-50.

77a Penetration Ther-N.A.

C mal Relief 1PS-502 78a Penetration Ther-N.A.

C mal Relief

'a' 500 80a Penetration Ther-N.A.

C mal Relief 1WP-7177 81a Penetration Ther-N.A.

C mal Relief 151-8972 83a Penetration Ther-N.A.

C mal Relief 1C0-1067-114a Penetration Ther-N.A.

C mal Relief ICH-271 120a Penetration Ther-N.A.

C mal Relief ICH-272 121a Penetration Ther-N.A.

C-mal Relief COMANCHE PEAK - UNIT 1 2-24 November 22, 1991

e TECHNICAL REQUIREMENT 2.1 (continued)

TABLE 2.1.1 (Coptinuedl TABLE NOTATIONS

  • Identification code for containment penetration and associated isolation valves in FSAR Tables 6.2.4-1, 6.2.4-2, and 6.2.4-3.
  1. May be opened on an intermittent basis under administrative control.

The table does not list local vent, drain and test connections as they are a special class of containment isolation valves and are locked closed and capped to meet containment isolation criteria when located within the penetration boundary.

Note 1: All four MSIV bypass valves are locked closed in Mode 1.

During Mode 2, 3 and 4 one MSIV bypass valve may be opened provided the other three MSIV bypass valves are locked closed and their associated MSIVs are closed.

Note 2:

These valves require steam to be tested and are thus not required to be tested until the plant is in MODE 3.

Note 3:

These valves are included for table completeness, the requirements of Specification 3.6.3 do not apply.

Instead, the requirements _of Specification 3.7.1.1, 3.7.1.5, 3.7.1.6 3

and 3.7.1.7 apply for main steam safety valves, mainsteam 3

isolation valves, feedwater isolation valves and steam 3

generator atmospheric relief valves, respectively.

3 Note 4:

These valves are leak tested in accordance with Technical Specification Surveillance Requirement 4.6.1.2.

2 Note 5:

10 CFR 50 Appendix J. Type C testing or' these valves is 6

satisfied by the testing of the airlock under Technical 6

Specification Surveillance Requirement 4.6.1.3b.

6 Note 6:

These valves are considered an. integral part of the airlock 6

associated with their respective airlock door.

Therefore, 6

they are subject to the controls of Specification 3.6.1.3.

6 Note 7: These valves are secured in position by hydraulic system 6

. locks and/or interlocks and do not require separate locks.

6 1

~ COMANCHE' PEAK - UNIT 1 2-25 Revision 6 November 22, 1991

O

~

TECHNICAL RE001REMENT 2.1 (continued)

BASES i

2.1 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containmer.t isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of General Design Criteria 54 through 57 of 10CFR50, Appendix A.

Containment isolation witH n the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

i r

COMANCHE PEAK - UNIT 1-2-26.

' November 22,:1991

.... _. -.. _ _ _. _. _ _ _... -.. - _ - -. _... - - _.. _ _,, ~ _,, -. _.. _ -. - _ _ _ _ _. _,. - _..

TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING i

July 20, 1990 0-1 Revision 2 0-2 Revision 2 0-3 Revision 3 0-4 Revision 3 0-5 Revision 3 0-6 Revision 3 0 'I Revision 3 0-8 Revision 3 0-9 Revision 3 0-10 Revision 3 0-11 Revision 3 0-12 Revision 3 0-13 Revision 3 0-14 Revision 3 0-15 Revision 3 0-16 Revision 3 0-17 Revision 3 Sec, 1 Original 1-1 July 21, 1989 1-2 July 21, 1989 1-3 September 15, 1989 1-4 July 21, 1989 1-L July 21, 1989 1-6 July 21, 1989 1-7 July 21, 1989 1-8 July 21, 1989 1-9 July 21, 1989 1-10 July 21, 1989 l

1-11 July 21, 1989 1-12 Revision 4 1-13 July 21, 1989 14 July 21, 1989 1-15 Revision 3 1-16 Revision 3 l

1-17 Revision 1 1-18 Revision 1 1-19 July 21, 1989 1-20 July 21, 1989 1-21 Revision 3 p

l L

EPL-1 November 22, 1991

TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING Sec. 2 Original 2-1 July 21, 1989 2-2 July 20, 1990 2-3 July 21, 1989 2-4 July 21, 1989 2-5 Revision 2 2-6 July 21, 1989 2-7 July 21, 1989 2-8 July 21, 1989 2-9 July 21, 1989 2-10 July 21, 1989 2-11 July 21, 1989 2-12 Revision 3 2-13 Revision 6 2-14 November 22, 1991 2-15 November 22, 1991 2-16 November 22, 1991 2-17 November 22, 1991 2-18 November 22, 1991 2-19 November 22, 1991 2-20 November 22, 1991 2-21 November 22, 1991 2-22 November 22, 1991 2-23 November 22, 1991 2-24 November 22, 1991 2-25 Revision 6 2-26 November 22, 1991 Sec. 3 Original 3-1 July 21, 1989 l

3-2 July 21, 1989 l

3-3 Revision 5 3-4 Revision 5 3-5 September 6, 1991 3-6 Revision 5 3-7 Revision 5 3-8 July 21, 1989 3-9 Revision 5 3-10 July 21, 1989 3-11 July 21, 1989 3-12 Revision 3 3-13 Revision 2 i

EPL-2 November 22, 1991

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