ML20126D325

Rev 9 to Technical Requirements Manual

ML20126D325
Person / Time
Site:	Comanche Peak
Issue date:	12/18/1992
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20126D324	List: ML20126D321 ML20126D325
References
PROC-921218, NUDOCS 9212240141
Download: ML20126D325 (24)

Text

TECHNICAL REQUIREMENTS _ MANUAL-

-Q wi TABLE OF CONTENTS TECHNICAL REQUIREMENT. NUMBER _ SYSTEH/ TITLE (Related Tech Spec if required) 0 Administrative Controls 0.1 (1.0) Definitions 0.2 (3/4.0) Applicability 1.1 (3/4.3.1) Reactor Trip Response Time 1.2 (3/4.3.2) ESF Actuation Response Time i

1.3 Moveable Incore Detection System 1.4 Seismic Instruments 1.5 Loose Parts Detection System 2.1 (3/4.6.3) Containment Isolation Valves' i

-3.1 (3/4.7.9) Snubbers 3.2 Station Service Water System i]

3.3 Feedwater Isolation Valve Temperature 4.1 (3/4.8.4) . Containment Penetration )

Conductor Overcurrent i Protection Devices i

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COMANCHE PEAK - UNITS 1 AND 2 1 9212240141 92121s December 18, 1992 PDR ADOCK 05000445

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PLANT CHANGES THAT MAY EFFECT THE TRM Changes made at CPSES have the potential to affect (or be affected by)-

-(7 the TRM. These include items such as design modifications, procedure A/ - changes, other licensing document changes, etc. -The TRM has been 2 identified as a CPSES licensing basis document by the-10CFR50.59 Program. The 10CFR50.59 Program is based on the latest HUMARC~

Guidelines for.50.59 evaluations. This program requires that.the TRM- 2 be considered-in a manner simila- to the FSAR when screening changes to determine if an unreviewed safety question might be involved.

DISTRIBUTION OF TRM CHANGES / DELETIONS Changes to the TRM will be issued on a replacement page basis to controlled document holders promptly following approval of the change.

REPORT OF TRM CHANGES / DELETIONS TO THE NRC Changes to the TRM will'Le reported to the NRC annually as part of the SAR epdate. Related safety evaluations will be reported as part of the 50.59 annual report.  ;

Proposed TRM changes that are determined to constitute an unreviewed 1 safety question (as defined by 10CFR50.59(a)(2)) will either not be made or will be submitted to the NRC for prior review and approval.

l UNIT 2 APPLICABILITY 8-The requirements for Unit 2 are effective upon issuance of the 8 operation license for Unit 2. 9 i

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l-COMANCHE PEAK - UNITS 1 AND 2 0-2 Revision 9 December 18, 1992 j

TECHNICAL REQUIREMENT 0.1 DEFINITIONS This Technical Requirement contains Section 1.0, DEFINITIONS, of the

-C-(] - Technical Specifications,'which are also applied to'the Technical Requirements, Manual except where otherwise specified. For the purpose of this Technical Requirement, the Technical Requirements Manual terms specified below shall be considered synonymous with the-listed Technical Specification terms:

Technical Recuirements Manual Technical Specifications OPERABILITY CRITERIA LIMITING CONDITION FOR OPERATION COMPENSATORY MEASURE ACTION TESTS / INSPECTIONS SURVEILLANCE REQUIREMENTS TECHNICAL REQUIREMENT SPECIFICATION NOTE: Although the CPSES Technical Specification is repeated here, in part, care must be taken not to overlook Technical Specification requirements.

.c LO COMANCHE PEAK - UNITS 1 AND 2 0-3 December 18, 1992

IECHNICAL'REOUIREMENT 1.2 (continuedl'.

TABLE 1.2.1

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ENGINEERED SAFETY FEATURES RESPONSE TIMES-INITIATION SIGNAL ~AND FUNCTION RESPONSE TIME IN SECONDS-

2. Containment Pressure--High-1

a. Safety Injection (ECCS) 527(1,5a)/27(4,5b) .9_

b. Reactor Trip 52'

c. Feedwater Isolation 56.5 .l

d. Phase "A" Isolation 517(2)/27(1)

e. Containment Ventilation Isolation N.A.

f. Auxiliary Feedwater 560 9

g. Station Service Water N.A.

h. Component Cooling Water N.A.

i. Essential Ventilation Systems -N.A.

j. Emergency Diesel Generator 5 12 Operation O

k. Turbine Trip N.A.

1. Control Room Emergency Recirculation N.A.

m. Containment Spray Pump (7) 5-17/27

>]

COMANCHE PEAK - UNITS 1 AND 2 1-9 Revision 9 December 18, 1992-_ 7

TECHNICAL REOUIREMENT 1.2 (continued)

TABLE 1.2.1-

?. ENGINEERED' SAFETY FEATURES RESPONSE TIMES-INITIATION SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS-

3. Pressurizer Pressure--Low

a. SafetyInjection(ECCS)'- 127(1.Sa)/27(4,5b). 9

b. Reactor Trip 12

-c. Feedwater Isolation s7

d. Phase "A" Isolation 517(2)/27(1) .

e. Containment Ventilation Isolation ~ 5 5(6) g

f. Auxiliary Feedwater 5 60 .9

g. Station Service Water H.A.

h. Component Cooling Water .N.A.

i. Essential Ventilation Systems- N.A.

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, J. Emergency Diesel Generator Operation 5 12

k. Turbine Trip _ N.A.

1. Control Room Emergency Recirculation N.A.

m. Containment Spray Pump H.A. 9 -

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COMANCHE PEA'K --UNITS 1 AND 2 1-10 Revision ~9-  ?

December 18, 1992'

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TECHNICAL REOUIREMENT 1.2 (continuedl~

TABLE- l'. 2.1-ENGINEERED SAFETY FEATURES RESPONSE-TIMES.

INITIATION SIGNAL AND FUNCTION ~ RESPONSE TIME'IN SECONDS

4. Steam Line Pressure--Low

a. Safety Injection (ECCS) 137(3,5b)/27(4,5b)'  ;

b. Reactor Trip. -- $2 -

c. 'Feedwater-Isolation .s 6.5 9

d. Phase "A" Isolation 's17(2)/27(1)

e. Containment Ventilation Isolation N.A.

f. Auxiliary Feedwater- 5 60- 9-

g. Station Service Water N.A.

h. Component Cooling Water N.A.

i. Essential Ventilation Systems N.A.

J. Emergency Diesel Generator Operation $ 12

k. Turbine Trip- N.A.

1. Control Room Emer.gency Recirculation N.A.

m. Containment Spray Pump N.A. 9.

, n. Steam Line Isolation s 6.5 9 10 COMANCHE PEAK --UNITS 1 AND 2 1 Revision 9 '

December.18,f1992..

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1 TECHNICAL REOUIREMENT 1.'2'(continued)-

TABLE 1.2.1-ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATION SIGNAL AND FUNCTION RESPONSE TIME IN-SECONDS

5. Containment Pressure--High-3

a. Containment Spray Pump H.A. l

b. Phase "B" Isolation N.A.

c. Containment Spray Pump Discharge .

Valve 5 119- 9:

6. Containment' Pressure--High-2 Steam Line Isolation 5 6.5

7. Steam Line Pressure - Negative Rate-High

-Steam Line. Isolation 57 9'

8. Steam Generator Water Level - High-High.

a. Turbine Trip H. A. .

b. Feedwater Isolation 5 11-

9. Steam Generator Water Level - Low-Low

} a. Motor-Driven-Auxiliary Feedwater Pumps s 60

b. Turbine-Driven Auxiliary .

Feedwater Pump 5 85 .4

10. Loss-of-Offsite Power Auxiliary Feedwater N.A. 9

11. Trip of All Main Feedwater Pumps All Auxiliary Feedwater Pumps N.A.

04

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L COMANCHE PEAK - UNITS 1 AND 2 1-12 Revision 9 i December 18, 1992;

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TECHNICAL RE0VIREMENT 1.2 (continued)

TABLE 1.2.1 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATION SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

12. RWST Level - Low-Low Coincident with Safety injection Automatic Initiation of ECCS 5 30 Switchover to Containment Sump

13. Loss of Power (6.9 KV and 480V Safeguards System Undervoltage)

a. 6.9 KV Preferred Offsite Source N.A. 9 Undervoltage

b. 6.9 KV Alternate Offsite Source N.A. 9 undervoltage

c. 6.9 KV Bus Undervoltage 5 2(8) 9

d. 6.9 KV and 480V Degraded Voltage with Safety Injection 5 10(8,9) 9 without Safety Injection s 63(8,9) 9

e. 480 V Low Grid Undervoltage s 63(8.9) 9 O

COMANCHE PEAK - UNITS 1 AND 2 1-13 Revision 9 December 18, 1992

TECHNICAL REQUIREMENT 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 SERVICL (Seconds) RE0VIREMENTS

4. Manual Valves (Continued)

SF-011 56 Refueling Water N.A. C 8 Purification to Refueling Cavity SF-012 56 Refueling Water N.A. C 8 Purification to Refueling Cavity SF-021 67 Refueling Cavity N.A. C 8 to Refueling Water Purification Pump SF-022 67 Refueling Cavity H.A. C 8 to Refueling Water Purification Pump iSF-053 71 Refueling Cavity N.A. C 9

() 2SF-0055 Skimmer Pump Discharge 1SF-054 71 Refueling Cavity N.A. C 9 2SF-0056 Skimmer Pump Discharge SI-8961# 83 Accumulator Test N.A. N.A. 8 and Fill 3 HV-23338# 2 MSIV Bypass from N.A. Note 1 8 Steam Generator #1 HV-2334B# 7 MSIV Bypass from N.A. Note 1 8 Steam Generator #2 HV-2335B# 11 MSIV Bypass from N.A. Note 1 8 Steam Generator #3 HV-2336B# 15 MSIV Bypass from N.A. Note 1 8 Steam Generator #4 O

COMANCHE PEAK - UNITS 1 AND 2 2-12 Revision 9 December 18, 1992

TECHNICAL REOUIREMENT 2.1'(continued).

TABLE'2.1.1'(continued) ,

O v

CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION NOTES AND FSAR TABLE- TIME- LEAK TEST VALVE NO. REFERENCE NO.* LINE OR SERVICE (Seconds) BIOUIREMENTS 2BS-0030# 134 Airlock N.A. Notes- 8 Hydraulically 5, 6, 71 '8 Operated Equalization 8 28S-0025# 134 Airlock N.A. Notes 8-Hydraulically 5 , 6 , 7- =8 Operated Equalization 8 2BS-0056# 134a Airlock Manual N.A. Notes 8 Equalization 5, 6 8.

28S-0044# 134a Airlock Manual H.A. Notes 8 Equalization 5, 6 8-2BS-0029# 134a Airlock Manual N.A. Notes 8' Equalization. 5, 6 8 2BS-0015# 134a Airlock Manual N.A. Notes- 8 Equalization 5, 6 8

5. Power-0perated Isolation Valves HV-2452-1 4 Main Steam to Aux. N.A. N.A. 9

FPT From Steam Line #1 PV-2325 5 Atmospheric-Relief N.A. Note 3 8 Steam Generator PV-2326 9 Atmospheric Relief N.A. Note 3- 8 Steam Generator 3 PV-2327 13 Atmospheric Relief N.A.. Note 3 8-Steam Generator 3-HV-2452-2 17 Main Steam to Aux. N.A. N.A. 8 FPT From Steam Line PV-2328 18 Atmospheric Relief N.A. Note 3 8 Steam Generator 3 HV-2491A 20a- Auxiliary Feedwater N.A. N.A. 8 to Steam Generator O

COMANCHE PEAK - UNITS-1 AND 2 2-14 Revision 9 September 1, 1992:

TECHNICAL REOUIREMENT 2.1'(continuedl 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 1

10. Relief Valves (Continued) i MS-061 9b Main Steam Safety N.A. Note 3 8 Valve S.G. #2 MS-062 9b Main Steam Safety N.A. Note 3 8 Valve S.G. #2 _

MS-093 13b Main Steam Safety N.A. Note 3 8 Valve S.G. #3 MS-094 13b Main Steam Safety H.A. Note 3 8 Valve S.G. #3 i MS-095 13b Main Steam Safety N.A. Note 3 8 .,

Valve S.G. #3 3 MS-096 .13b Main Steam' Safety N.A. Note 3 8~

Valve S.G. #3 MS-097 13b Main Steam Safety H.A. Note 3 8 Valve S.G. #3 MS-129 18b Main Steam Safety N.A. Note 3 8 Valve S.G. #4 MS-130 18b Main Steam Safety N.A. Note-3 8 Valve S.G. #4 MS-131 18b Main Steam Safety N.A. Note 3 8 Valve S.G.-#4 MS-132 18b Main Steam Safety N.A. Note 3 8 Valve S.G. #4 MS-133 18b Main Steam Safety- N.A. Note 3 8 Valve S.G. #4 ISI-0182 125 Pressure Relief N.A. N.A. 9 For Bonnet of 9' MOV 8811A 9 O

COMANCHE PEAK - UNITS 1 AND 2 2-25 Revision 9 December 18, 1992 l

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-TECHNICAL REOUIREMENT 2.1 (continued)

TABLE 2.1.1 (continued)-

^i-( CONTAINMENT ISOLATION VALVES-

%).

MAXIMUM ISOLATION NOTES AND FSAR TABLE ' TIME . LEAK TEST VALVE NO. REFERENCE NO.* LD E OR SERVICE -(Seconds)' REOUIREMENTS.

SI-0183 126 Pressure Relief N.A. N.A. 9 for Bonnet of- MOV 8811B 9 CT-0309 127 Pressure Relief. N.A. .N.A. 9 for Bonnet of 9-MOV HV-4782 9 <

,_ CT-0310 128 Pressure Relief N.A. N.A. 9 L for Bonnet of .9-MOV HV-4783 9 l:

l O  !

COMANCHE PEAK - UNITS 1 AND 2 2-26 Revision 9 l December 18, 1992.

TECHNICAL RE0VIREMENT 2.1 (continued)

TABLE 2.1.1 (Continuedl 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

• O 9emeretor etmos9"er4c re'4er ve'ves respect 4ve's- 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 of 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 O

COMANCHE PEAK - UNITS 1 AND 2 2-27 December 18, 1992 r

TECHNICAL RE0VIREMENT 2.1 (continued)-

BASES 2.1 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment 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 within 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.

O

!O COMANCHE PEAK - UNITS 1 AND 2 2-28 December 18, 1992

TECHNICAL RE0VIREMENT 4.1' TABLE 4.1.la 8-UNIT 1 8 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT~ PROTECTIVE DEVICES DEVICE NUMBER SYSTEM --

AND LOCATION POWERED-

1. 6,9 KVAC from Switchgears

a. Switchgear Bus 1A1 RCP fil

1) Primary Breaker IPCPX1 a) Relay 50M1-51 b) Relay 86M ,9 c) Relay 51M2 9

2) Backup Breakers 1Al-1 or 1Al-2 a) Relay 51M3 b)_-Relay 51 for 1Al-1 c) Relay 51 for 1Al-2 d) Relay 86/1A1 O b. Switchgear Bus 1A2 RCP #12

1) Primary Breaker IPCPX2 a) Relay 50M1-51 b) Relay 86M -9 c) Relay 51M2 9

2) Backup Breakers 1A2-1 or 1A2-2 a) Relay 51M3 b) Relay 51 for 1A2-1 c Relay 51 for 1A2-2 d Relay 86/1A2 O

COMANCHE PEAK - UNITS 1 AND 2 4-5 Revision 9 December li 9'

TECHNICAL REOUIREMENT 4.1 (continued)

TABLE 4.1.la (Continued) l8 UNIT 1 8 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES DEVICE NUMBER SYSTEM AND LOCATION P3WERED

1. 6.9KVACfromSwitchgears(Continued)

c. Switchgear Bus 1A3 RCP #13

1) Primary Breaker 1PCPX3

~

a Relay 50M1-51 b Relay 86M 9 c Relay 51M2 9

2) Backup Breakers 1A3-1 or 1A3

a Relay 51M3 b Relay 51 for 1A3-1 c Relay 51 for 1A3-2 d Relay 86/1A3 ,

d. Switchgear Bus 1A4 RCP #14 O 1) Primary Breaker IPCPX4 a) Relay 50M1-51 b) Relay 86M 9

{ c) Relay 51M2 9 21 Backup Breaker 1A4-1 or 1A4-2 a) Relay 51M3 b) Relay 51 for 1A4-1 c) Relay 51 for 1A4-2 d) Re?ay 86/1A4

2. 480 VAC from Switchgears 2.1 Device Location - Containment 480V Switchgears 1EB1, 1EB2, Recire, Fans 1EB3 and IEB4 and CRDM Vent Fans

a. Primary Breakers - 1FNAV1, 1FNAV?, 1FNAV3, 1FNAV4, IFNCB1 and 1FNCB2 O

. COMANCHE' PEAK - UNITS 1-AND 2 4-6 Revision 9 December 18, 1992

IWil 414 51 _ .

TECHNICAL RE001REMENT 4.1 (continued)

TABLE 4.1.la ~(Continued) 8 UNIT 1 8 CONTAI; MENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVLCD DEVICE NUMBER AND LOCATION

9. 118V AC Control Power a.PrimaryDevices-N/A(Fuse)

b. Backup Breakers

~

GENERAL ELECTRIC PANELBOARD NL-- (_KT. NO. BREAKER TYPE 1C2 22 TED 1-1PC1. 10,13 TED 1PC4 6,10 TED 1EC1 7 TED 2 1EC2 7 TED -2 1EC5 8 TED 1EC6 3,8 TED O to. t er9eace tvecuetioa siste wara4a9 '49ats no er

a. Primary Devices - N/A (Fuse)

b. Backup Breakers SQUARE D -

PANELBOARD NO. CKT. NO. BBEAKER . LEE XEC3-3 9, 10 FY-14020 9 1

11. DRPI Data Cabinet Power Supplies

a. Primary Breakers 2 2

SQUARE D 2 EANELBOARD NO. (KI,_F_L BREAKER T'(PE 2 1C14' 1,2 FA-14050A 2

b. Backup Breakers SQUARE PANELBOARD NO. CKT. NO. BREAKER TYPE 1C14 Main Pnl. Bkrs. FS-14070A 2 2

COMANCHE PEAK - UNITS 1 AND 2 4-17 Revision 9 December 18, 1992

TECHNICAL REOUIREMENT 4.1 8 i

TABLE 4.1.lb 8 UNIT 2 8 CONTAINMENT PENETRATION CONDUCTOR 8 OVERCURRENT PROTECTIVE DEVICES  :

8 DEVICE NUMBER SYSTEM 8 AND LOCATIQM EDWERED 8

1. 6.9 KVAC from Switchgears 8

a. Switchgear Bus 2A1 RCP #21 8

1) Primary Breaker 2PCPX1 8 a Relay 50H1-51 8~

b Relay 86M 9 c Relay 51M2 8

2) Backup Breakers 2Al-1 or 2Al-2 8

-e a) Relay 51M3 8 b) Relay 86/2A1 _8

b. Switchgear Bus 2A2 RCP #22 8

1) Primary Breaker 2PCPX2 8 O a) Relay 50M1-51 8 b Relay 86M 9 c Relay 51M2 8

2) Backup Breakers 2A2-1 or 2A2-2 8 i a Relay 51M3 8 b Relay 86/2A2 8- ,

i L:

O COMANCHE PEAK - UNITS 1 AND 2 4-18 Revision 9 December 18, 1992- .

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JLCHNICAL REOUIREMENT 4.1 (continued) 8 TABLE 4.1.lb (Continued 1 8 i UNIT 2 8 ,

CONTAINMENT "ENETRATION CONDUCTOR 8 OVERCURRENf PROTECTIVE D E LCES 8

' & .CE flUMBER SYSTEH' 8 4 LOCATION POWERED 8

1. 6.4KVACfromSwitchgears(Continued) 8 8

c. Switchgear Bus 2A3 RCP #23 8

1) Primary Breaker 2PCPX3 8 a) Relay 50M1-51 8 b) Relay 86M 9 c) Relay 51M2 8

2) Backup Breakers 2A3-1 or 2A3-2 8 a) Relay 51M3 8-b) Relay 86/2A3 8

d. Switchgear Bus 2A4 RCP #24 8

1) Primary Breaker 2PCPX4 8 a) Relay 50M1-51 8 i b) Relay 86M 9 c) Relay 51M2 8

2) Backup Breaker 2A4-1_or 2A4-2 8-a) Relay 51M3 8-b) Relay 86/2A4 8

2. 480 VAC from Switchgears 8 '

2.1 Device Location - Containment 8 480V Switchgears 2EB1, 2EB2, Recirc. Fans 8 2EB3 and 2EB4 and CROM 8 Vent Fans 8

a. _ Primary Breakers - 2FNAV1, -8 2FNAV2, 2FNAV3, 2FNAV4, 8 2FNCB1 and 2FNCB2 8.

O C0MANCHE PEAK - UNITS 1 AND 2 4-19 Revision 9 .

December.18, 1992

i TECHNICAL REOUIREMENT 4.1 (continued) 8

-JAELE 4.1.1b (Continued) 8 I UNIT 2 8

!]

CONTAINMENT PENETRATION CONDUCTOR 8 i OVERCURRENT PROTECTIVE DEVICES 8 DEVICE NUMBER 8 AND LOCATION - 8 l

9. 118V AC Control Power 8

a. Primary Devices - N/A (Fuse) 8

b. Backup Breakers 8 ,

GENERAL ELECTRIC 8 PANELBOARD NO. CKT. NO. BREAKER TYPE 8 2LPC2 22 TED 8 2PC1 10.13 TED 8 2PC4 6,10 TED 8 2EC1 7 TED 8 2EC2 4,7 TED 8 2EC5 8 TED 8 2EC6 3,8 TED 8 8

8 O to c=ersemcx cvecvet4oa s> stem wera4"9 9'4 hts ro er 8

a. Primary Devices - N/A (Fuse) 8

b. Backup Breakers 8 SQUARE D 8 PANELBOARD NO. CKT. NO. BREAKER TYPE 8 XEC4-3 9, 10 FY-14020 9 8

11. DRPI Data C1 binet Power Supplies 8

a. Primary B:eakers 8 8

SQUARE D 8 PANELBOARD NO. CKT. NO. BREAKER TYPE 8 2C14 1,2- FA-14050A 8

b. Backup Breakers 8' SQUARE D 8 PANELBOARD NL CKT. NO. BREAKER TYPE 8 2C14 Main Pn1. Bkrs. FS-14070A 8 l-l CDMANCHE PEAK - UNITS 1 AND 2 4-30 Revision 9 December 18, 1992' ,

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TECHNICAL REQUIREMENTS MANUAL

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EFFECTIVE PAGE LISTING  ;

f BELOW IS A LEGEND FOR THE EFFECTIVE PAGE LISTING:

Original Submitted July 21, 1989 Revision 1 September 15, 1989 Revision 2 January 15, 1990 Revision 3 July 20, 1990 Revision 4 April 24,.1991  :

Revision 5 September 6. 1991 Revision 6 November-22,-1991 Revision 7 March 18, 1992 -t Revision 8 June 30, 1992 Revision 9 December 18, 1992 s

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l . ( )' i L EPL 1 December 18, 1992 y , -,

.m...,, . - , ,.nr. , . +. -, u ,www.....a

TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING TRM-Tab _

Original TRM-Title Page June 30, 1992 Table of Contents-Tab Original i December'18, 1992 Administrative Controis-Tab Original Administrative Controls-Title Page June.30, 1992 0-1 June 30, 1992 0-2 Revision 9 0-3 - December 18. 1992 ,

0-4 June 30, 1992 0-5 June 30. 1992 0-6 June 30. 1992 0-7 June 30, 1992 0-8 June 30,-1992 0-9 June 30.-1992 0-10 June 30, 1992 0-11 Revision'8 0-12 June 30, 1992 0-13 June 30, 1992 0-14 June 30, 1992 A 0-15 June 30, 1992 U 0-16 Revision 8 0-17 June 30,-1992 0-18 June 30, 1992 0-19 Revision 8-0-20 Revision 8 0-21 Revision 8; 0-22 Revision 8 0-23 Revision 8 0-24 Revision 8 0-25 Revision 8 0-26 Revision 8 Tec'inical Requirements-Tab Original Section 1-Tab Original 1-1 June 30, 1992 1-2 Revision 8  ;

1-3 June 30,.1992 1-4 June 30, 1992 1-5 June 30, 1992 1-6 r Revision 8____

1-7 June 30, 1992 1-8 June.'30,-1992 1-9 Revislon 9 1-10 Revision 9 1-11 Revision 9 i-1-12 Revision 9 EPL 2 December 18, 1992

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TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING 1-13 Revision 9

' 1-14 June 30, 1992 1-15 Revision 8 1-16 June 30, 1992 1-17 Revision 8 1-18 Revision 8 1-19 Revision 8 1-20 Revision 8 1-21 June 30, 1992 1-22 -Revision 8 Sec. 2-Tab Original 2-1 June 30, 1992 2-2 Revision 8 2-3 June 30, 1992 2-4 Revision 8 2-5 Revision 8 2-6 Revision 8 2-7 Revision 8 2-8 Revision 8 2-9 Revision 8 2-10 Revision 8 L 2-11 Revision 8 2-12 Revision 9 2-13 Revision 8-2-14 Revision 9 2-15 Revision 8-2-16 Revision _8 2-17 Revision 8 2-18 Revision 8 2-19 Revision 8 2-20 Revision 8 2-21 Revision 8 2-22 Revision 8 2-23 Revision 8 2-24 Revision 8 2-25 Revision 9 2-26 Revision 9 2-27 December 18, 1992 2-28 _

December 18, 1992 Sec. 3-Tab Original 3-1 June 30, 1992 3-2 Revision 8 3-3 . June 30, 1992 3 3-4 June 30, 1992 3-5 June 30,.1992

~3-6 June 30, 1992 EPL 3 December 18, 1992

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(-~g TECHN! CAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTlHG 3-7 June 30,1992 3-8 June 30,1992 3-9 June 30, 1992 3-10 Revision 8 3-11 June 30, 1992 3-12 Revision 8 3-13 Revision 8

-Sec. 4-Tab- _ Original 4-1 June 30, 1992 4-2 Revision 8 4-3 June 30 -1992  !

4-4 June 30, 1992 l 4-5 Revision 9 4-6 Revision 9 4-7 Revision 8 '

4-8 Revision 8 4-9 Revision 8 '

4-10 Revision 8 4-11 Revision 8

• 4-12 Revision 8 1 4-13 Revision 8 O 4-14 4-15 Revision 8

-Revision 8 ,

4-16 Revision 8 17 Revision 9 ,

4-18 Revision 9 4-19 Revision 9 4-20 Revision 8 -

4-21 Revision 8 4-22 Revision 8

• 4-23 Revision 8 4 Revision 8 4-25 Revision 8-4-26 Revision 8 4-27 ReYision 8 4-28 Revision 8 4-29 Revision 8 -

4-30 Revision 9 4-31 June 30, 1992 EPL-Tab' Original-EPL-1 Revision 9 EPL-2 Revision 9 EPL-3 Revision 9 EPL-4 Revision 9' lO l E EPL 4 December 18, 1992 e.

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