ML20035H356
| ML20035H356 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/28/1993 |
| From: | TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20035H354 | List: |
| References | |
| PROC-930428, NUDOCS 9305040290 | |
| Download: ML20035H356 (79) | |
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{{#Wiki_filter:> i e i COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES i FIRST INTERVAL t ? REVISION 2 i f i Prepared By: Date: ,2893 .y j Approved By: ( _ (Al A., Date: t4-28 'i3 Ranager. T.aat Engineering i Approved By: k ~ Date: I[95 Vich President, Nuclear Operations 9305040290 930429 PDR ADOCK 05000445 p PDR
. = 1 g l i COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 i INSERVICE TESTING PLAN FOR PUMPS AND VALVES - i FIRST INTERVAL -TABLE OF CONTENTS SECTION 1.0 - GENERAL INFORMATION 1-1 ] 1.1 - Introduction 1-1 1.2 - Code Edition and Addenda 1-1 6 1.3 - Dates of Test Interval 1-2 i 1.4 - Approval Status 1-2 1.5 - References 1-3 SECTION 2.0 - INSERVICE PUMP TESTING PLAN 2-1 2.1 - Pump Testing Code 2-l' 2.2 - Scope 2-1 2.3 - Pump Testing Table Format 2-2 Table 0 - Inservice Pump Testing Plan SECTION 3.0 - INSERVICE VALVE TESTING PLAN .3-1 -3.1 - Valve Testing Code 3-1 3.2 - Scope-3-2 = 3-1 3.3 - Valve Testing Table Format Table 1 - Auxiliary Feedwater Table 2 - Component Cooling Water ^ Table 3 - Chilled Water'(Safety) Table 4 - Chemical and Volume Control Table 5 - Containment Spray Table 6 - Demineralized and Reactor Makeup Water Table 7 - Diesel Generator Auxiliaries Table 8 - Feedwater l Table 9 - Main Steam Table 10 - Reactor Coolant Li Table 11 - Residual Heat Removal Table 12 - Spent Fuel _ Pool Cooling Table 13 -_ Safety Injection 4 Table 14 - Service Water Li Table 15 - Ventilation (Control Room Air Conditioning) Table 16 - Vents and Drains l Table 17 - Misc. Containment Isolation Valves APPENDIX A - RELIEF REQUESTS FOR PUMPS AND VALVES A-1 l !') i i COMANCHE. PEAK - UNITS 1 AND 2 i April'30,_1993-y
=- l i i CPSES/IST Plan t i. t COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 l 1 INSERVICE TESTING PLAN FOR PUMPS AND VALVES 'l FIRST INTERVAL '{ i 1.0 GENERAL INFORMATION lq 1.1 Introduction The Inservice Testing Plan for Pumps and Valves, hereafter referred to as the IST Plan, has been prepared to summarize the test program for certain pumps and valves pursuant to the requirements of the Code of Federal Regulations, 10CFR50.55a(f)(4). This testing plan is applicable to CPSES' Units 1 & 2. The content and distribution of the-IST Plan are controlled and users are cautioned to verify the control 3 status of their copy prior to use. To obtain a copy of this-document, contact Distribution Control-at the Main Document l Control Center, Extension 8387. l [ 1.2 Code Edition and Addenda j t This IST_ Plan meets the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, 1989 Edition (no addenda), _ i Subsections IWA (as applicable),-lWP (as modified by 10CFR50.55a(f)(4)), and IWV (as modified by 10CFR50.55a(f)(4) and (b)(2)(vii)), except in specifically 4 identified instances where an alternative to the Code requirements is proposed or where it has been determined ] t. that conformance with certain Code requirements is i impractical. In these instances, a request for relief from the Code requirement (s), including proposed alternatives to { the requirement (s), has been prepared for Nuclear Regulatory l Commission review and approval pursuant to.10CFR50.55a(a)(3) or(f)(5). 2_ a
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See Section 2.0, " Inservice Pump Testing Plan", and Section 3.0, " Inservice Valve Testing Plan" for a more detailed discussion of Code edition. l:: i I y COMANCHE PEAK - UNITS l'AND_2. 1-1 Rev. 2 l April 30, 1993 { -t
i g- .i i CPSES/IST Plan f 1.3 Dates of Test Interval , Implementation of this 1989 Edition IST Plan will be .I completed on CPSES Unit 1 before that unit is returned to power following the third refueling outage and at that time will supercede in its entirety the original Unit 1 Inservice. j Testing Plan for Pumps and Valves developed for the first i inspection interval. The original Unit 1 IST Plan was implemented per the requirements of the 1986' Edition of-Section XI. This 1989 Edition IST Plan constitutes an. f update of the original Unit l'IST Plan to a later approved Code edition as allowed by 10CFR50.55a(f)(4)(iv) and as approved by the NRC staff. This IST Plan will remain in 2 effect for Unit 1 for the 120 month interval following the date of issuance of the. Unit 1 operating license (February I 8,1990). i This IST Plan was' implemented on CPSES Unit 2 upon issuance '2 of that unit's operating license and will remain in effect. for Unit 2 for the 120 month interval following the date of I issuance of the Unit 2 operating license (February 2, 1993). 9 If, in the future, it is determined to be advantageous to 2 l place both Unit 1 and Unit 2 on the same schedule for -l periodic 120 month IST Plan updates, then the Unit 2 IST. 'j program may-be updated coincident with the required update i to the Unit 1 program. Alternatively, the Unit 1 IST program may be updated coincident with the required update to the Unit 2 program. This would effectively extend the i first test interval for Unit 1 beyond the required 120 i months and would therefore require a NRC staff approved j exemption from regulation 10CFR50.55a(f)(4)(ii) prior to 120 i months from the date of issuance of'the Unit 1 operating j license. i 1.4 Approval Status This IST Plan was submitted to-the NRC staff on July 2, 1992 2-l via TXX-92302 requesting-1 i 1. Approval to update the Unit 1 IST program to the 2 i ~ requirements of the 1989 Edition of ASME Section XI as i described in this IST Plan; ~i 2. Approval of a proposed schedule for phasing in the-2 -) implementation of this IST Plan for Unit.1; and, j l 3. Approval of the Relief Requests contained in Appendix 2-A of this IST Plan for use in the testing of Unit 1 -] and Unit 2. COMANCHE. PEAK - UNITS 1 AND 2 1-2 Rev. 2 April 30, 1993
1 I CPSES/IST Plan l By safety evaluation dated January 29, 1993 for Unit 1 and 2 NUREG-0797, Supplemental Safety Evaluation Report (SSER) No. 26 dated February, 1993 for Unit 2, the NRC staff granted i the following approvals. 1 1. Approval to update the Unit 1 IST program to the 2 requirements of the 1989 Edition of ASME Section XI and approval to test Unit 2 to the requirements of the Code. (Approval had not specifically been requested to test Unit 2 to the requirements of the 1989 Code since regulation 10CFR50.55a already seemed to permit it; approval was granted nonetheless.) 2. Approval of the schedule described in Section 1.3 2 t above for phasing in the implementation of this IST Plan for Unit 1. i 3. Approval of the Relief Requests contained in Appendix 2 l A of this IST Plan for use in the testing of Unit I and Unit 2 with the exception of Relief Request V5 l which was denied. (See Appendix A for specific information.) l As pointed out in the safety evaluation and SSER, the NRC 2 staff review of this IST Plan did not include verification that all pumps and valves within the scope of 10CFR50.55a j and ASME Section XI are contained in the IST program. t Additionally, for the components included in the IST program, all applicable testing requirements were not q verified. l 1.5 References )' J 1. Code of Federal Regulations, 10CFR50.55a, " Codes and 'l Standards". 2. ASME Boiler and Pressure Vessel Code, Section XI, 1989 l l Edition. (Subsections IWA, 1WP, IWV and Appendix F) 3. ASME/ ANSI OM-1987, Part 1 " Requirements for Inservice 1 Performance Testing of Nuclear Power Plant Pressure Relief Devices". I i 4. ASME/ ANSI OMa-1988 and OMb-1989, Part 6, " Inservice l Testing of Pumps in Light-Water Reactor Power Plants". (Addenda to ASME/ ANSI OM-1987) .l, 5. ASME/ ANSI OMa-1988, Part 10. " Inservice Testing of I Valves in Light-Water Reactor Power Plants". (Addenda i to ASME/ ANSI OM-1987) i i COMANCHE PEAK - UNITS 1 AND 2 1-3 Rev. 2 i April 30, 1993 j
.. ~. l l CPSES/IST Plan l 6. USNRC Generic Letter No. 89-04, " Guidance on Developing Acceptable Inservice Testing Programs", l April 3, 1989. 1 i 7. USNRC, " Minutes of the Public Meetings on Generic j Letter 89-04", October 25, 1989. i 8. USNRC Staff Guidance Letter, "NRC Staff Guidance for Complying with Certain Provisions of 10CFR50.55a(g), Inservice Inspection Requirements", November 1976. [ i 9. USNRC Staff Guidance Letter, "NRC Staff Guidance for Preparing Pump and Valve Testing Program Descriptions i and Associated Relief Requests Pursuant to l 10CFR50.55a(g)", January 1978. 10. NUREG-0800, "USNRC Standard Review Plan", July 1981. (Section 3.9.6, Inservice Testing of Pumps and Valves) 11. Karassik, Igor J., et al. Puno Handbook, second f edition. New York: McGraw-Hill Book Company, 1986. l l i I t i t i l i I L i i !d il I t i i l i 1 1 COMANCHE PEAK - UNITS 1 AND 2 1-4 April 30, 1993 i i i
C P ANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE PUMP TESTING PLAN TABLE O PAGE 3 0F 4 1 l Test Parawters Dif f er-Pump Driver Flow. Code Pump Discharge ential Flow Bearing Bearing Test j. Pune Identificat101 Diaaram Class T .Sg g[ Pressure Pressure R,1tg Vib. Vib. Schedule m e Reactor Makeup Water CPI-DDAPRM-01 M1-0241-01 3 C/DC N/A N/A X X X N/A 3 MO. CPX-DDAPRM-01 M1-0241-01 3 C/DC N/A N/A X X X N/A 3 MO. .CP2-DDAPRM-01 -M2-0241 3 C/DC N/A N/A X X X N/A 3 MO. i Fuel Oil Transfer-CPI-DO4PFT-01 M1-0215-F (2) PD/ ROT N/A X(1) N/A X(1) X(1) N/A 3 MO. 2 CPI-00FFT-02 M1-0215-F (2) PD/ ROT-N/A X(1 N/A X(1) X(1) N/A 3 MO. CPI-00APFT-03 M1-0215-G (2) PD/ ROT N/A X(1 N/A X(1) X(1) N/A 3 M0. CPI-DOAPFT-04 M1-0215-G' (2) PD/ ROT N/A X(1 N/A X(1) X(1) N/A-3 MO. .CP2-DO4PFT-01. M2-0215-F (2) PD/ ROT N/A X(1 N/A X(1) X(1) N/A 3 MO. CP2-D04PFT-02 M2-0215-F (2) PD/ ROT N/A X(1) N/A X(1) X(1) X N/A 3 MO. CP2-00APFT-03 M2-0215-G (2) PD/ ROT N/A X(1) N/A X(1) (1) N/A 3 M0. CP2-DOAPFT-04 M2-0215-G (2) PD/ROI N/A X(1) N/A X(1) X(1) N/A 3 MO. Residual Heat Revval TBX-RMPRH-01 M1-0260 2. C/CC N/A N/A X X N/A X 3 MD. i TBX-RHAPRH-02 M1-0260 2 C/CC N/A N/A X X N/A X 3 MO. I TCX-RHAPRH-01 M2-0200 2 C/CC N/A N/A X X N/A X 3 MD. TCX-RHAPRH-02 M2-0260 2 C/CC. N/A N/A X X N/A X-3 MO. Spent Fuel Fool Coolina CPX-5FAP5F-01 M1-0235 3 C/DC N/A N/A X X X N/A 3 MD. CPX-5FAP5F-02 M1-0235 3 C/DC N/A N/A X X X .N/A 3 MO. Rev. 2 April 30. 1993
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. y _. _. _. _ - .---.m. m l-l i e i, ~ Y COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 f INSERVICE PUMP TESTING PLAN i: TABl.E O L E 1 NOTES -t t 1. See Reflef Request P1 for substitute ranges for test parameters for Fuel Oil Transfer Punps. l t ? l 2. The Fuel Oil Transfer Pumps were not cornercially available as A5ME BPV Code, $cction lil, Class 3; however, the normal tornercial design 2' L -r was upgraded to " equivalent
- ASME 5ection Ill, Class 3 quality requirtwnts through seismic testing, qualification, and documentatlon.
i t k i i l' t a l l l i-i i + E s t I t i. i i i l Rev. 2 j April 30, 1993 s 1
COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN VALVE TABLE INDEX (Page 1 of 3) VALVE TYPES ACTUATOR TYPES VALVE FUNCTIONS AN - Angle AO - Air Operator A - Active BA - Ball HO - Hydraulic Operator P - Passive BF - Butterfly MA - Manual Operator CK - Check MO - Motor Operator SAFETY FUNCTION POSITIONS DA - Diaphram SA - Self Actuated i GA - Gate 50 - Solenoid Operator 0 - Open GL - Globe C - Closed PL - Plug RE - Relief SCK - Stop Check l SF - Safety VB - Vacuum Breaker VALVE CATEGORIES Catecory A - Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required safety function (s). Catecory B - Valves for which seat leakage in the closed position is inconsequential for fulfillment of their required safety function (s). Catecory C - Valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves), for fulfillment of their required safety function (s). Catecory D - Valves which'are actuated by an energy source capable of only one operation, such as rupture disks or explosively actuated valves, for fulfillment of their required safety function (s). (There are no Category 0 valves or pressure relief devices in the CPSES IST Plan.) Note: Seat tightness determination is performed as part of the performance test for Category C pressure 2 relief devices (SRV) and may be performed as a method of close exercise test for check valves (CV). However, pressure relief devices and check valves are further classified as Category A only if some safety analysis criteria exist for valve seat leakage such as for pressure relief devices or check valves performing containment isolation functions or reactor coolant system pressure isolation functions. Rev. 2 April 30,1993
i t COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN j VALVE TABLE INDEX (Page 2 of 3) l TEST PARAMETECS Leak Test LT - Leak test Category A valve (other than containment isolation valves) per the requirements of OM Part 10, para. 4.2.2.3. LTJ - Leak test Category A containment isolation valve per the requirements of OM Part 10, para. 4.2.2.2 (i.e., 10CFR50, Appendix J) and additional requirements of OM Part 10, paras. 4.2.2.3(e) and (f) as required by 10CFR50.55a(b)(2)(vii). Exercise Test MT - Exercise power operated Category A or B valve full-stroke to its safety function position (s) and 1 measure stroke time per the requirements of OM Part 10 para. 4.2.1. ET - Exercise manual Category A or B valve full-stroke to its safety function position (s) per the requirements of OM Part 10, para. 4.2.1. CV - Exercise Category C check valve full-stroke to its safety function position (s) per the requirements of OM Part 10, para. 4.3.2. CVD - Disassemble Category C check valve to verify operability per the requirements of OM Part 10, para. 4.3.2.4(c). PS - Exercise Category A or B valve or Category C check valve part-stroke towards its safety function position (s) per the requirements of OM Part 10, paras. 4.2.1 or 4.3.2, as applicable. Part-stroke close exercising is not applicable to check valves. SRV - Performance test Category C safety, relief or vacuum breaker valve per the requirements of OM Part 10, para. 4.3.1 (i.e., applicable portions of OM Part 1). DT - Test Category D valve per the requirements of OM Part 10, para. 4.4. April 30,1993
O COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN VALVE TABLE INDEX (Page 3 of 3) TEST PARAMETERS (Continued) Fail Safe Test F0 - Fail safe test Category A or B valve in the open direction per the requirements of OM Part 10, para. 4.2.1.6. FC - Fail safe test Category A or B valve in the closed direction per the requirements of OM Part 10. para. 4.2.1.6. Position Indicator Test PIT - Test Category A, B, C or D valve position indication per OM Part 10, para. 4.1. TEST SCHEDULES Q-Perform exercise test (and fail safe test, if applicable) nominally every three months. CS - Perform exercise test (and fail safe test, if applicable) during each cold shutdown. Such exercise is not required if the time period since the previous full-stroke exercise is less than three months. Valve exerci>;ing during cold shutdown shall. commence within 48 hours of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power. For extended outages, testing need not be commenced in 48 hours provided all valves required to be tested during cold shutdown will be tested prior to plant startup. RF - Perform exercise test (and fail. safe test, if applicable) during each refueling outage. l TS - Perform test at the applicable Technical Specification frequency. NYR - Perform test at least;once every N years. For leak tests (LT) and position indicator tests (PIT), N equals twol years. For pressure relief device performance tests (SRV), N nominally ~ equals five years or ten years.for Class 1 or Class 2 & 3 devices respectively. However, other test frequencies may apply _for. pressure relief devices. See OM Part 1, paras. 1.3.3 and l'3.4. April 30,1993 . a.. . ~
~ ~ COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 1 - AUXILIARY FEEDWATER PAGE 9 0F 11 i Test Parameters / Schedule j-Flow Valve / Safety Fall Position Valve Diagrani Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator j Nuter (Coord] Type 5j;c Class gg.ry_ tien Pos. Tei! Test .T_ cit Teit Rmarks HV-2462 M1-0200 GL/A0 3 3 B A O/C N/A MT/Q F0/Q PIT / ATW to SG Flowpath/ATW to (B-5) 2YR Faulted SG Flow Isolation M2-0206 (B-5) LV-2478 M1-0206-2 GL/A0 3 3 B P C N/A N/A N/A PIT / Non-Safety Makeup Line (E-1) 2YR isolation M2-D206-2 (E-1) HV-2480 M1-0?06-1 GA/MO 6 3 B A 0 N/A MT/Q N/A PIT / AFW Pump Emergency Supply 2 (B-2) 2YR Flowpath M2-0206-1 (B-2) HV-2481 M1-0206-1 GA/M0 6 3 B A 0 N/A MT/Q N/A PIT / AFW Pumo Emergency Supply 2 (B-4) 2YR Flowpath M2-0206-1 (B-4) HV-2402 M1-0206-1 GA/MO 8 3 8 A 0 N/A MT/Q N/A PIT / AFW Pump Emergency Supply 2 (B-4) ZYR Flowpath M2-0206 1 (B-4) HV-2484 Mi-0206-2 BF/MO 12 3 B A C N/A M1/Q N/A PIT / Condensate System to (D-4) 2YR Condensate Storage Tank M2-0206-2 Isolation to Preclude Tank (D-4) Overpressurization i l i Rev. 2 -April 30, 1993
.~ COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 1 - AUXILIARY FEE 0 WATER NOTES i 1. AF-0075, AF-0078, AF-0083, AF-0080, AF-0093, AF-0098, AF-0101, AF-0106, AFW to Steam Generator Header Check Valves, are full-stroke exercised at cold shutdowns. These valves cannot be full or part-stroke open exercised during plant operation because such testing would unnecessarily subject the steam generator nozzles to thermal transients from the cool auxiliary feedwater for which they are not designed and could result in steam generator level transients. The valves cannot be exercised closed during plant operation for the same reasons. Fivwer, the valves are verified to be closed periodically during plant operation through UDstream te'iperature monitoring of the piping and pumps. 2 1 4 i Rev. 2 April. 30, 1993 .....~--.. -..a ..~--
..=. COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 2 - COMPONENT COOLING WATER PAGC 4 0F 10 Test Parameters / Schedule . Flow Valve / Safety Fail Position Valve Diagram Actuator Code Cate-Func~ Func. Leak Exercise Safe Indicator Number (Coord.) TVDe Site Class glyy_ tion. os. Tysl Test Test Test Rrmarks P .100-1080 M1-0216-1 CK/5A 1/2 3 A/C A C CT/2YR CV/Q N/A N/A $afety-Related Air Accumu-(F-4) RR V3 RR V2 lator to Non-Safety Air Supply isolation i ICC-1081 M1-0216-1 CK/5A 1/2 3 A/C A C LT/2YR CV/Q N/A N/A Safety-Related Air Accumu-(F-4) RR V3 RR V2 lator to Non-Safety Air Supply Isolation 10C-1082 M1-0216-1 CK/5A 1/2 3 A/C A C LT/2YR CV/0 N/A N/A Safety-Related Air Accumu-(F-4) RR V3 RR V2 lator to Non-Safety Air Supply isolation 1 20C-1090 M2-0231-A RE/5A 3/4 2 A/C A 0/C LTJ/T5 SRV/ N/A N/A Containment Penetration (F-2) X 10YR Themal Relief /Contaiment 1 Isolation ^ 2CC-1091 .M2-0216-B CK/SA 1/2 3 A/C A C LT/2YR CV/Q N/A N/A Safety-Related Air Accumu-(D*1) RR V3 RR V2 lator to Non-Safety Air Supply isolation 2CC-1092 _M2-0216-B CK/SA 1/2 3 A/C A C LT/2YR CV/Q N/A N/A Safety-Related Air Accumu-(0-1) RR V3 RR V2 lator to Non-Safety Air . Supply isolation 20C-1093 M2-0216-B CK/SA 1/2 - 3 A/C A C LT/2VR CV/Q N/A N/A Safety-Related Air Accumu-(D-1). RR V3 RR V2 lator to Non-Safety Air Supply Isolation 200-1094 M2-0216-8 CK/5A 1/2 3 A/C A 'C LT/2VR CV/Q N/A N/A Safety-Related Air Accumu-(0-1) RR V3 RR V2 lator to Non-Safety Air Supply isolation X-PV-3583 .M1-0229-A PL/MO 3 3 B A N/A N/A N/A N/A N/A Control Room A/C Condenser (E-5) -(5) Cooling Flow Control X-PV-3584 M1-0229-A PL/MO 3 3 B 'A N/A N/A N/A N/A N/A Control Room A/C Condenser '(D-6) (5) Cooling Flow Control April 30, 1993
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COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVC TESTING PLAN TABLE 2 - COMPONENT COOLING WATER PAGE 6 0F.10 Test Parameters / Schedule F low Valve / Safety Fail Position Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator Number (Coord.) Type 5_ite. Class goly tion Pos. Jeg.t Test Ins _t Tes_.t Rmarks HV-4515 M1-0229-B BF/MG 24 3 B A C N/A MT/Q N/A PIT / Train A to Train B Crosstie (A-4) 2YR Isolation M2-0229 (D-6) HV-4524 M1-0229-A BF/MO 24 3 B A C N/A MT/C5 N/A PIT / Non-Saf ety Loop flowpath (F-1) (6) 2YR Isolation M2-0229 (D-4) HV-4525 M1-0229-A BF/MO 24 3 B A C N/A -MT/CS N/A PIT / Non-Safety Loop Flowpath (F-1) (6) 2YR isolation M2-0229 (D-4) HV-4526 M1-0229-B BF/MO 24 3 8 A C N/A MT/C5 N/A PIT / Non-Safety Loop Flowpath (A-5) (6). 2VR isolation M2-0229 (0-6) HV-4527 M1-0229-B BF/MO 24 3 B A C N/A MT/C5 N/A PIT / Non-Safety Loop Flowpath. '(A-5) (6) ZYR Isolation M2-0229 (D-6)- FV-4536 M1-0229-A BF/A0 10 3 8 A C N/A MT/Q FC/Q PIT / CCW Flowpath Boundary 2 (F-2) 2YR M2-0229 (A-1) FV-4537 M1-0229-B Br/A0 10 3 B A C N/A MT/Q FC/Q PIT / CCW Flowpath Boundary 2 (B-2) 2YR M2-0229 (G-1) Rev. 2 April 30, 1993
COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 3 - CHILLED WATER (SAFETY) PAGE 1 0F 1 Test Parameters /Schafule Flow Valve / Safety Fail Position Valve Diagram Actuator Code Cate-Func - Func. Leak Exercise safe Indicator Number (Coord,) Type Size Class cory. tion _Pos. Test Test. Test Int R(marks CH-0300 0311 CK/SA 1 3 C A 0 N/A CV/Q N/A N/A Surge Tank Emergency Makeup (D-3)' Flowpath CH-0301 0311 CK/SA 1 3 C A C N/A CV/Q N/A N/A Surge Tank Emergency Makeup 4 (F-3) Flowpath Bourdary - CH-0302 0311 GL/MA 1 3 B A 0/C N/A ET/Q N/A N/A Surge Tank Emergency Makeup (D-3) Flowpath/ Isolation CH-0305 0311 GL/MA 1 3 B A 0/C N/A E1/Q N/A N/A Surge Tank Emergency Makeup (E-3) Flowpath/Isolat ion HV-6720 0311 GL/A0 1 3 B A 0 N/A MT/Q F0/Q PIT / Surge Tank Emergency Makeup 2 (D-3) 2YR Flowpath i l l l 1 l Rev. 2-l l April 30, 1993 1 i 1 ... _ _ _... ~.., _.. _ _. _. - _. _ _,....... _. -.. -
COMANCHE PEAK STEM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TEST [NG PLAN TABLE 4 - CHEMICAL and VOLUME CONTROL PAGE 6 0F 12 ' Test Parameters / Schedule Flow Valve / Safety Fail Position r Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator Ntrter (Coord.) Type She Class ggat tion-Pos. Test Test Trit Test - Remarks HV-8220 M1-0255 GA/50 1 2 B A C N/A MT/C5 FC/C5 PIT / ECCS Flowpath Boundary & l 2. (E-2) (1) 2VR isolation of VCT Cover Gas M2-0254 from Charging Pinps' (0-2) Suction Header (uoan low VCT level) HV-8221 M1-0255 GA/50 1 2 8 A C N/A MT/C5 FC/C5 P1T/ ECCS Flowpath Boundary & l2 (E-2) (1) 2YR 1 solation of VCT Cover Gas M2-0254 from Chargino Pumps' l (0-2) Suction Header (upon low VCT level) C5-8350A M1-0253 CK/SA 2 1 C A C N/A CV/C5 N/A N/A Reactor Coolant Pressure (D-4) (3) Boundary - M2-0255-1 RR V5 (C-6) 05-83508 M1-0253 CK/SA 2 1 C A C N/A CV/C5 N/A N/A Reactor Coolant Pressure (D-4) (3) Boundary M2-0255-1 RR V5 i (G-6) i C5-8350C M1-0253 CK/SA 2 1 C A C N/A CV/C$ N/A N/A ' Reactor Coolant Pressure (0-4). (3) Boundary M2-0255-1 RR V5 l (G-3) CS-83500 M1-0253 CK/5A 2-1 C A C N/A CV/C5 ' N/A N/A Reactor Coolant Pressure (D-4) (3) Boundary M2-0255-1 RR V5 l-(C-3) 8351A M1-0253 GL/MD 2 2 B A C N/A MT/C5 N/A PIT / Contaiment Isolation (D-5) (3) 2YR - M2-0255 (0-5) Rev. 2 April 30, 1993 l l t -w..w,.g-=-marwo-*ew.-m es s r-i m- -=e =w v w-n-e ar e msw e---+w =m+- -m meen-,+-wee,,+-,.+ -=--e--i-msww revw y e-a'-+= we+-=+-34,w**d,+--4 -*---**w'ven*-*w-e-se v- ' + - * = n e r =vw e
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_== : i COMANCHE FEAK STEAM ELECTRIC STATION UNIT 1 & 2 l INSERVICE VALVE TESTING PLAN TABLE 4 - CHEMICAL and VOLUME CONTROL PAGE 9 0F 12 Test Parameters / Schedule Flow Valve / Safety fail Position t Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator ' NPtor (Coord.) Type 5ijzg Class cory tion
- Pos, les_t Test Lest Lagt Remarks 8378A M1-0253-A CK/5A 3
1 C A 0 N/A CV/Q N/A N/A Boration F1twpath (B-5) (8) f2 M2-0255 (G-3) C N/A CV/C5 N/A N/A Reactor Coolant Pressure -(2) Boundary i RR V5 83788 M1-0253-A CK/5A 3 1 C A 0 N/A CV/Q N/A N/A Boration Flowpath (B-5) (8) l2-M2-0255 (G-3) C N/A CV/C5 N/A N/A Reactor Ccolant Pressure (2) Boundary RR V5 8370A M1-0253-A CK/5A 3 1 C A 0 N/A CV/Q N/A N/A Baration Flowpath M2-0255. (8) l2 (B-5) (G-3) C N/A CV/C5 N/A N/A Reattor Coolant Pressure (2) Boundary RR V5 83796 M1-0253 A CK/SA 3 1 C A 0 N/A CV/Q N/A N/A Boration Flowpath i .(B-5) (8) l2 H2-0255 (G-3) C N/A CV/C5 N/A N/A Reactor Ecolant Pressure (2) Boundary 3 RR V5 a l 8381 M1-0253-A CK/5A 3 2 A/C A 0 N/A CV/Q N/A N/A Boration Flowpath (E-3) M2-0255 C LTJ/T5 CV/C5 N/A N/A Contalment isolation '.i (E-2) (2) .t Rev. 2 April 30, 1993 2 z.---.-...,---......-....-..-.-..---..,.....,,;...-...-..:.-.~:....-., =. - - -.. -. -. -.. -
COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 4 - OEMICAL and VOLUME CONTROL PAGE 11 0F 12 Test Parameters / Schedule Flow Valve / Safety Fail Position Valve Diagram Actuator Code Cate-FL d func. Leak Exercise Safe Indicator ___ Number (Coord,} Type ,$_ jig Class aory tion .Pos. Test Test Igs_t Trit Remarks C5-8487 M1-0257 CK/5A 2 3 C A O/C N/A CV/0 N/A N/A Boration Flowpath/Boration l (C-4) Flowpath Boundary Mi-0257 i (C-6) .8497 M1-0255-1 CK/5A 3 2 C A C N/A CV/0 N/A N/A ECCS Flowpath Boundary (D-2) M2-0254 (F-4) 8510A M1-0255-1 RE/SA 1-1/2 2 C A 0/C N/A SRV N/A N/A High Head Safety injection (D-4) X (9) Pmip Miniflow Path /ECCS l2 M2-0254 2 Recirculation Flowpath (F-5) . Boundary 8510B M1-0255-1 RE/SA 1-1/2 2 C A O/C. N/A SRV N/A N/A HighHeadSafetyinjection (D-4) x (9) Pump Miniflow Path /ECCS l2 M2-0254 2 Recirculation Flowpath (F-6) Boundary 3 85114 M1-0255-1 GL/MO 2 2 B' 0/C N/A MT/Q N/A PIT / High Head Safety injection A (D-4) 2VR Pump Miniflow Path /ECCS M2-0254 Recirculation Flowpath (E-5) Boundary i 85118 M1-0255-1 GL/MO 2 2' B A. 0/C N/A -MT/Q N/A PIT / . High. Head Safety injection (D-4) 2VR Pump Miniflow Path /ECCS M2-0254 Recirculation Flowpath (E-6)' Boundary 8512A M1-0255-1 GL/M0 2 2 B A C N/A MT/Q N/A PIT / ECCS Recirculation Flowpath (D-4) 2VR Boundary M2-0254 (F-6) t Rev. 2 April 30, 1993 ... a _,._ __...__...~ _.. _ _..-___. __._ _ _ _ _._.. _.._ _. n
_ = =. - =, -. r i .[ COMANCHE PEAK 51EAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE a - CHEMICAL and VOLUME CONTROL fqTj5 5. 05-8442 Emergency Boration Line Check Valve, is full-stroke exercised at cold shutdowns. This valve cannot be full or part-stroke opan exercised during plant operation because initiating flow through this valve introduces high concentration boric acid to the RCS via the charging syst m resulting in a reactivity transient and possibly a reactor shutdown. 6. 8481A & B, Charging /High Head Safety injection Pumps Discharge Check Valves, are part-stroke open exercised every three months and are full-stroke open exercised at refueling outages. These valves cannot be full-stroke open exercised during plant operation or during cold shutdowns because the full flow path discharges into the RC5. During plant operation, the high RCS pressure will not allow the maximum required injection-flowrate to be achieved. The valves cannot be full-stroke exercised at cold shutdowns because the high flowrates required could challenge the s RCS Cold Overpressure Mitigation Systs as well as impose hydraulic transients on the charging system and on the Reactor Coolant Pump seals which can cause th m to cock. ,7. 8546, Charging /Hioh Head Safety injection Pumps $uction from the RWST Check Valve, is part-stroke open exercised at cold shutdowns, full-stroke open exercised at refueling outages and f ull-stroke tiose exercised at cold snutdowns. (Part-stroke close exercising is not applicable.) This valve cannot be full or part-stroke exercised during plant operation because initiating flow through this valve introduces high concentration boric acid to the RCS via the charging system resulting in a reactivity transient and possibly a reactor shutdown. Further, during plant operation the high RCS pressure will not allow the maximum required injection flowrate to be achieved. The valves cannot be full-stroke exercised at cold shutdowns because the high flowrates required could challenge the RCS Cold Overpressure Mitigation Systs as well as impose hydraulic transients on the charging systs and on the Reacter Coolant Pump seals which can cause thm to cock. l 8. Charging service is alternated approximately every refueling outage between the nomal charging line (containing check valves 8378A and 83788) 2 and the alternate charging line (containing check valves 8379A and 8379B) such that neither flowpath will be exposed to more than 60% of the themal transients associated with stoppage and restart of charging flow, in accordance with OM Part 10, para. 4.3.2.5, the pair of check valves in the charging line which is out of service need not be open exercise tested quarterly as they are only relied on to perfom their open l boration path function when they are designated to be in service. However, they must be open exercise tested within 3 months prior to placing. l the charging line back in service, l' l-1 i l' 'Rev. 2 l April 30, 1993 _,.__.____..au..,--._.. -,. _ _.-_m.u__,__-._.-..-_
- a k . 3 CCNANCHE PEAiC STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PtAN TABl.E 4 - CHEMICAL and VOLUME CONTROL NOTES The check valves in both the normal and alternate charging lines are relied on to perfom their CICsed reactor cooiant pressure boureary 2-function at all times when this function is required. Therefore, the close exercise test schedule must be maintained for all four check valves, regardless of which charging line is designated to be in service. 4 9. Under the provisions of 10CFR50.55a(f)(6)(li), the NRC staff has imposed augented inservice test requirments for relief valves 1-8510A,1-- -2 85108, 2-8510A, 2-8510B. As directed by the safety evaluation dated January 29, 1993 for Unit I and NUREG-079/, SER Supplement 26 for Unit 2, the following frequency requirments shall apply (in lieu of the OM Part 1, para.1.3.4 f rmuency requirerrents) for perfomance testing tne subject valves. A. One valve from each unit shall be perfomance tested each fuel cycle. Both valves frtrn each unit shall be perfomance tested within any 2 two fuel cycles. l B. If the tested valve from a given unit fails the set pressure detemination portion of the perfomance test, then the other ' valve frtn g that unit shall be perfomance tested. If the tested valve from a given unit fails one of the other triteria of the perfomance test (i.e., visual examination, seat tightriess detemination or balancing device integrity verification), then the cause shall be evaluated and the need to test the other valve from that unit shall be detemined. C. Both valves frm a given unit shall be perfomance tested following any systm actuation which results in the valves discharging. This 2 perfomance test shall be perfomed at the next cold shutdown of sufficient duration to perfom these attivities, i i t Rev. 2 ' April 30 1993 L .ns ow www.e-m..e-ee.-- ---we t ra e -ewre - w t-.*=>--arw - m a e---ee.we---..w.-,...d a 4e w, +.. ma gm .+--e-mene es+ wre - w w. es.nd ews--s==---e-.w.me--w m e www
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CrHANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 7 - DIESEL GENERATOR AUXILIARIES PAGE 3 0F 4 Test Parameters /Schodule Flow - Valve / Safety Fail Position Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator . Number (Coord.} Tvoe 5_i2g Class cory tion Pos. Test Test Tgst Test Renarks i i 200-0074 M2-0215-O CK/SA 1-1/2 3 C A C N/A CV/Q N/A N/A Safety-Related Air Receiver - (E-1) RR V2 to Non-Safety Air Supply Isolation 200-0075 M2-0215-0 CK/SA 1-1/2 3 C 'A C N/A CV/Q N/A N/A Safety-Related Air Receiver (F-5) RR V2 to Non-Safety Air Supply Isolation 200-0076 M2-0215-E CK/5A 1-1/2 3 C A C N/A CV/Q N/A N/A Safety-Related Air Receiver (E-1) RR V2 to Non-Safety Air Supply Isolation 200-0077 M2-0215-E CK/SA 1-1/2 3 C A C N/A CV/Q N/A N/A Safety-Related Air Receiver (F-5) RR V2 to Non-Safety Air Supply isolation 00-0104 .M1-0215.H CK/5A 1 3 C A C N/A CV/Q N/A N/A Jacket Water Flowpath (F-3) Boundary M2-0215-H (F-3) 00-0107 M1 -0215-H (1) 8 3 B A N/A N/A. N/A. N/A N/A Jacket Water Temperature (E-4) (1) Control M2-0215-H (E-4) 00-0157 M1-0215-B CK/SA 6 3 C A 0 N/A CV/Q N/A N/A . Lube Oil Flowpath -l .(C-6) M2-0215-B (C-6) DO-0158 M1-0215-B CK/SA 6 3 C A C N/A CV/Q N/A N/A Lube Oil Flowpath Boundary (C-6) M2-0215-B (C-6) April 30,'1993 .~.... ....u. ..__.,s, .2.,.__--...__._......a.__.._.-.___....._.__..-,..-.,._
-._________.._______w. 1: -]- +- l COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 l INSERVICE VALVE TESTING PLAN TABLE 7 - DIESEL GENERATOR AUXILIARIES PAGE 4 0F 4 j Test Parameters / Schedule Flow Valve / Safety fail Position Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator Number (Coord.) Tyne Site Class cory tion .Pos. les_t Test Test Test Remarks 00-0204 M1-0215-J CK/$A 1 3 C A C N/A CV/Q N/A N/A Jacket Water Flowpath (F-3) Boundary c M2-0215-J (F-3) 00-0207 M1-0215-J (1) 8 3 B A N/A N/A N/A N/A N/A Jacket Water TeTpprature (E-4) (1) Control .l M2 0215-J .l (E-4) 00-0257 M1-0215-C CK/5A 6 3 C A 0 N/A CV/Q N/A N/A Lube Oil Flowpath-1 (C-6) M2-0215-0 (C-6) a DO-0258 M1-0215-0 CK/5A 6 3 C A C N/A CV/Q N/A N/A Lube Oil Flowpath Boundary 4 (C-6). M2-0215-0 3 (C-6) .I i I t r I Lf 'Iq April 30, 1993 i t l- { [ -iev r w-mw -rwr,ever>+4--+- e www w me,,wwww wwywwwww w v e w4 h %WWw sw h e&m-dw swdp e wwe--wg+1mypwdwJgw hw-gw vm ww Seem m greem wh qup wkwetew 1e+*we wm deedersmium Np -heWwdumd 'M *pmeiaW e wasn5* Emm4*T'h w w ww s#w e en we*M hw
l i I l COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 8 - FEEDWATER NOTES 1. FW-0070, FW-0076 FW-0082, FW-0088, Main feedwater Header Check Valves, are full-stroke exercised at cold shutdowns. These valves cannot be-full-stroke exercised during plant operation because close testing the valves requires isolating feedwater flow. This would result in severe F l steam generator level transients and, most likely, a turbine and reactor trip. Part-stroke close testing is not applicable. l l 2. FW-0191, FW-0192, FW-0193, FW-0194, Feedwater Preheater Bypass Check Valves, are full-stroke exercised at cold shutdowns. These valves cannot I be full-stroke exercised during plant operation because running the AFM pumps to close test the valves imoses-an excessive number of themal transients on the steam generator nozzles for which they were not designed. Part-stroke close exercising is not applicable. i t 3. FW-0195, FW-0100, FW-0197, FW-0198, Feedwater Preheater Bypass Check Valves, are full-stroke eiercised at cold shutdowns. These valves cannot j te full-stroke exercised during plant operation because running the AFW pumps to open test the valves imposes an excessive number of thermal j I transients on the steam generator doi 21es for which they were not designed. i-4 HV-2134, HV-2135, HV-2136. HV-2137, Feedwater Isolation Valves, are part-stroke exercised quarterly and are full-stroke exercised at cold. shutdowns. These valves cannot be full-stroke exercised during plant operation because closing the valves interrupts feedwater flow resulting . t in severe steam generator level transients and, most likely, a turbine and reactor trip. I 5. FV-2181, FV-2182, FV-2183 FV-2184, Feedwater Split Flow Bypass Valves, are part stroke exercised quarterly and are full-stroke exercised at cold shutdowns. These valves cannot be full-stroke exercised during plant operation because cycling the valves imposes an excessive number of themal transients on the steam generator auxiliary nozzles for which they were not designed. Also, isolating flow to the steam generator auxiliary nozzles causes flow to the steam generator main. nozzles to exceed design specifications resulting in preheater tube vibration and possibly premature tube failure. The fail-safe test for these valves is performed in conjunction with the full-stroke exercise test at told shutdowns because the part-stroke exercise test during plant coeration does not remove valve actuating power from the actuators. 6. HV-2185, HV-2186, HV-2187, HV-2188. Feedwater Isolation Bypass Valves, are full-stroke exercised at cold shutdowns. These valves cannot be full . t-or part-stroke exercised during plant operation because they are interlocked to remain closed while the Feedwater Isolation Valves are open. L April 30, 1993 t mes-e e w- -+, ewe,v-e-v~=+ --r-t-w 2 ame-**e--r% - wr a- -=.-4-ww--.-+e-= -es.*:-3,s =, ..-m-r.+- an--tu.-=-- -e mwm - --e n-.e-.=- ,, we m-w,e-r-w-e ai m e mn w -r---m,=-,si--=~,- - w e i-wn.ewwwgr e-w e .vw mmo e.wem-w,--
COMNCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSCRVICE VALVE TESTING PLAN TABLE 9 - MAIN STEAM f PAGE 1 0F 12 Test Parameters / Schedule Flow Valve Diagram _ Valve / Safety Fail Position Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator Number (Coord.) Tvre 5jte Class cory tion Pos. Tgst . Test .yeT st Test Remarks j MS-0021 M1-0202 SF/5A 6 2 C A O/C N/A SRV/ N/A PIT / Overpressure Protection & (C-4) X SYR 2YR Steam Vent Flowpath (for M2-0202 8 (1) residualheatremoval)/ (C-4) Steam Line Isolation & Containment isolation MS-0022' M1-0202 SF/5A 6 2 C-A O/C N/A $RV/ N/A PIT / Overpressure Protection & (C-4) X SYR 2VR SteamVentFlowpath(for M2-0202-8 (1) residual heat removal)/ (C-4) Steam Line Isolation & Contairrnent isolation MS-0023 M1-0202 SF/SA 6 2 C A O/C N/A SRV/ N/A PIT / Overpressure Protection & (D-4) X SYR 2YR Steam Vent Flowpath (for M2-0202 8 (1) residual heat removal)/ (0-4) Steam Line Isolation & Containment isolation MS-0024 M1-0202 . SF/SA 6 2 C A 0/C N/A SRV/ N/A PIT / Overpressure Protection & (0-4) X SYR 2YR Steam Vent Flowpath (for M2-0202 8 (1) residual heat rmoval)/ (D-4) Steam Line isolation &' Contaiment isolation - MS-0025 M1-0202 SF/SA 6 2 -C A O/C N/A SRV/ N/A PIT / Overpressure Protection & (E-4) X SYR 2YR Steam Vent Flowpath (for M2-0202 8 (1) residual heat renoval)/ l .(E+4) Steam Line Isolation & Containment isolation MS-0026 M1-0202 GA/MA 8 2 B A C N/A ET/Q N/A N/A ' Steam Generator Tube 2 [ (B-3) Rupture Isolation M2-0202 (Isolates PORV) (B-3) L t l t Rev. 2 April 30, 1993 i , 9--=-r-emw.- h= e-
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-aw-- w w w wa y w - sm+'-w ww w w w +w wa -r-s v v-car,. o w we + +r = w e ' s e-s.k-~ e - E +e-y w e +-'--e "te-%=e+v' N-ew-+m,- r us w-w s ww c-m c e m e-s w "wr e me-r- w - v e+ -we % - esw prewwww- -ca.m E w. +s m - rwe :=+1en Nwe r-r+.r en ---we,.. e,/
- s COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 9 - MAIN STEAM PAGE 2 0F 12 Test Parameters /SchMule Flow Valve / Safety fail Position Valve Diagram Actuator Code Lite-Func-Func. Leak Exercise Safe Indicator Ntrbg (Coord.) Type Size Class gg,y_ tion Pos. Test Test Test Test Ranarks MS-0058 M1-0202 SF/5A 6 2 C A 0/C N/A SRV/ N/A PIT / Overpressure Protection & (C-2) X SYR 2VR Steam Vent Flowpath (for M2-0202 8 (1) residual heat rtmval)/ t (C-2) Steam Line Isolation & Containment Isolation MS-0059 M1-0202 SF/SA 6 2 C A 0/C N/A 5RV/ N/A PIT / Overpressure Protection & (C-2) X SYR 2YR Steam Vent Flowpath (for M2-0202 8 (1) residual heat remval)/ (C-2) Steam Line Isolation &- Contaiment Isolation MS-0060 M1-0202 SF/5A 6 2 C A 0/C N/A SRV/ N/A PIT /- Overpressure Protection & (0-2) X sir 2VR Steam Vent Flowpath (for M2-0202 8 (1) residual heat removal)/ (D-2) Steam.Line Isolation & Contaiment Isolation MS-0061 'M1-0202 SF/5A 6 2 C A 0/C N/A $RV/ N/A PJT/ Overpressure Protection & (D-2) X SYR 2YR SteamVentF10wpath(for H2-0202 8 (1) residual heat remval)/ (D-2) Steam Line Isolation & Contaiment Isolation MS-0002 M1-0202 SF/5A 6 2 C A O/C N/A SRV/ - N/A PIT / Overpressure Protection & (E-2) X SYR 2YR Steam Vent Flowpath (for M2-0202 8 (1) residualheatremoval)/ (E-2) Steam Line isolation & Contaiment Isolation MS-C063 M1-0202 GA/MA 8 2 B A C N/A ET/Q N/A N/A Steam Generator Tube 2 (B-2) Rupture isolation i M2-0202 (Isolates PORV) (B-2) [ Rev. 2 April 30, 1993 m -. m m .m --....... m..~5 ++,~~_-_4.e. v.,.. m ...s+...,s. _a ,%_.r. w v.w,m s%.. y vw,, ....w..w_%y
A C0HANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 9 - MIN STEAM PAGE 3 0F 12 Test Para t ters/Sched'.ile Flow Valve / Safety Fail Position Valve ' Diagram Actuator Cooe Cate-Func-Func. Leak Exercise Safe Indicator Nacher fCoord.) Tvre 5.j&e Class cory tion Pos. Test Test Test Tut Rmarks MS-0093 M1-0202 SF/5A 6 2 C A 0/C N/A SRV/ N/A PIT / Overpressure Protection & (C-1) X SYR 2YR Steam Vent Flowpath (for M2-0202 8 (1) residual heat removal)/ (C-1) Steam Line Isolation & Contalment Isolation MS-0094 . M1-0202 SF/SA 6 2 C A 0/C N/A SRV/ N/A PIT / Overpressure Protection & (C-1) x SYR 2VR 5 team Vent Flowpath (for M2-0202 8 (1) residual heat renoval)/ (C-1) Steam Line Isolation & Contalment Isolation MS-0095 M1-0202 - SF/5A 6 2 C A 0/C N/A SRV/ N/A PIT / Overpressure Protection & f (0-1) X SYR 2YR Steam vent Flowpath (for +- M2-0202 8 (1) residual heat rmoval)/ (D-1) Steam Line Isolation & ~! Contaiment isolation MS-0096 M1-0202 $F/5A 6 2 C 'A 0/C N/A SRV/ N/A PIT / Overpressure Protection & (D-1) X SYR 2YR Steam Vent Flowpath (for M2-0202 8 '(1) residual heat reeval)/ (D-1) . Steam Line Isolation & T Containment Isolation - t MS-0097 M1-0202 SF/SA 6 2 C A 0/C N/A SRV/ N/A PIT / CNerpressure Protection & (E-1) X SYR 2YR Steam Vent Flowpath (for M2-0202 8 (1) residual heat removal)/ (E-1) Steam Line Isolation & Containment Isolation MS-0098 M1-0202 GA/m B 2 B A C N/A ET/Q N/A N/A Steam Generator tube 2, (B-1) Rupture isolation ' M2-0202 (Isolates PORV) ~ (B-1). ~ i Rev. 2 April 30,.1993 b w r, %-.we'~w..*v%, .re..,,w-,v..w,+,. o.. r e-w. vm 6 w<- v-e,ee. --e.= ~ rk w www-,.,, r. <-ew..,r--- .,-ve.w..ww+..+ww.-w~- ,w-mwi s-,-v v e,r t.+.,-v--$-+ -v.-*w,me w i.-ww e-w 3 m ryc ww-.-ee-==v,e Y e - +. ic-ev w.- +,w iv w ,*.re 4. .-1
1 6 i' ,tr .?[ .:Il l [ M 2" &r 3 r r r r 9 no/ no/ no/ no/ no/ 9 of)&n o f )& n of)&n o f )& of)& 1 i(l i(l i(l n i(l n i(l t ano t ano t ano t ano t ano e ch v oi c h v oi ch voi ch v oi chvoi b 0 et oit et oit et oit et oi t et oit u 3 opmt opmt t ant a t a a t ant a t amt a Tn 2 t a a opeal al al opeal opeal o l rwrl o rwrl o rwrl o rwrl o rwrl o ri) .i Po os Po os Po os Po os Po os otV vr it sI l tsI l tsi l t sI ltsI t aR ep eF aI eF aI eF aI eF aI e F aI alO RA r e t r e t r e t r e t r e t rop uthen uthen uthen uth en uth en es sn ne sn ne sn ne sn ne sn ne nI s seli m seli seli m e e s eVaLn eV a L m s elieV aC m eV aL m s eli r u i r u i r u i r u i Get eVaLn k r u i pmdma pmdma pmdma pmdma mulra r pmdma a raiat r ai a t raiat raiat raiat at o m eesen eesen eesen eesen eesen eps vt et o vt et o vt et o vt et o vt et e t uI R OSr5C OSrSC OSr$C OSrSC OSrSC SR( r no ot t / / / / / i a s TR TR TR TR TR A iitc e IY IY IY IY IY / T P2 P2 P2 P2 P2 N sd on EPI l u d l et e h if s A A A A A A c a a e_ / / / / / / e SFSJ N N N N N N / s 2 re t e e s 1 m ict a T r rs / / / / / Q I a ee VR) VR) VR) VR) VR) / N P xT RY1 RY1 RY1 RY1 Rt1 T U N E SS( SS( S5( 5S( S5( E A t N L s OIP e M T T GA A NE kt T IT as A A A A A A S TS2 ee / / / / / / S 1 LT N N N N N N C EN I TIF RT A0 CEM V 4 E L - y. L A E t c. / / / / / C C C C C E V9G ens M A f uo 0 O O 0 O C EEP aFP ACL S E B TIVA S RT E K S A cn N PI no E ui A A A Ft A A A E H CN A ey M .t r O ao C C C C C B C Co s es da ol 2 2 2 CC 2 2 2 e J t ] 6X8 6X8 B 1 6X8 6X8 6X8 ro /teae A A A A A A vup 5 S S S S M t y / / / / / / lact F F F F F A VA S S S S S G m1 - 2 2 2 2 2 2 2 2 2 2 2 2 ad 0)0) 0)0) 0)0) 0)0) 0)0) 0)0) wrr 2525 2525 2525 2525 2525 2524 go 0 0-00 - 0 0-0 0 0-0 - .ao - C C - C - C - D D 0 D - E E B B C 1(2( 1(2( 1(2( 1(2( 1(2( 1(2( iD( M M M M M M M M M H M M ew 9 0 1 2 3 4 2 3 3 3 3 3 1 1 ht 0 0 10 0 0 0 m 1 1 1 au VN S 5 S S S S M M M M M M l lll:lI l
i. COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 9 - MAIN STEAM PAGE 5 0F 12 ' Test Parameters /Sch Nule Flow Valve / Safety Fail Position Valve Diaoram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator i Number (Coord.1 Type Size Clasp ggDL tion _ .. Pos. Test Test Test Test Ro w ks i MS-0142 M1-0202 CK/SA 4 3 C A 0/C N/A CV/Q N/A N/A TDAFW Pump Steam Supply (B-5) Flowpath/TDAFW Pump M2-0202 Steam Supply Flowpath (B-5) Boundary l MS-0143 M1-0202 CK/SA 4 3 C A 0/C N/A CV/Q N/A N/A TDAFW Pump Steam Supply (B-0) - Flowpath/TDAFW Pump 1 M2-0202 Steam Supply Flowpath (8-6) Boundary i 2MS-0063 M2-0218-1 CK/SA 1/2 3 A/C - A C LT/2YR CV/Q N/A N/A Safety-Related Air Accumu-(F-2) RR V3 RR V2 lator to Non-Safety Air Supply Isolation 2MS-0604 M2-0218-1 CK/5A 1/2 3 A/C A C LT/2YR CV/Q N/A N/A Safety-Related Air Accumu-(F-2) RR V3 RR V2 lator to Non-Safety Air 1 i Supply isolation l EMS-0065 M2-0218-1 CK/SA 1/2 3 A/C A C LT/2YR CV/Q N/A N/A Safety-Related Air Accumu-(F-1) RR V3 RR V2 lator to Non-Safety Air Supply Isolation 2MS-0606 . M2-0218-1 CK/SA 1/2 3 A/C A' .C LT/2VR CV/Q N/A N/A Safety-Related Air Accumu-(F-1) RR V3 RR V2 lator tc Non-Safety Air Supply isolation EMS-0667 M2-0218-1 CK/SA 1/2 3 A/C A C LT/2VR CV/Q N/A N/A Safety-Related Air Accumu-(F-1) RR V3 RR V2 lator to Non-Safety Air Supply Isolation 2MS-0C48 M2-0218-1 CK/SA 1/2 3 A/C A C' LT/2YR CV/Q N/A N/A Safety-Related Air Accumu-(F-1) RR V3 RR V2 lator to Non-Safety Air Supply Isolation 2MS-0669 M2-0218-1 CK/5A 1/2 - 3 A/C A. C LT/2VR CV/Q N/A N/A Safety-Related Air Accumu. (F-2) RR V3 RR V2 lator to Non-Safety Air Supply Isolation April 30, 1993 -.am-- -*w-- u am w a u.+e. u'.3%i,l_-rw a-s m+-- qe + -es erendr-ww-%.se e s e a y g-%<g-pe e-wgrs gu-e
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COMANCHE PEAK STEM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 9 - MAIN STEM PAGE 6 0F 12 Test Para neters/ Schedule Flow Valve / Safety Fail Position Valve Diagram Actuator Code Cate. Func-Func. . Leak Exercise Safe Indicator Number (Coord.) Type Size Class cory tion Pos. Test Test Test Test Remarks 2MS-0670 M2-0210-1 CK/5A 1/2 3 A/C A C LT/2YR CV/Q' N/A N/A Safety-N 1ated Air Accumu-(F-2) RR V3 RR V2 .lator to Non-Safety Air Supply isolation IMS-0080 M1-0218-1 CK/5A 1/2 3 A/C A C LT/2YR CV/Q N/A N/A Safety-Related Air. Accumu-(F-3) RR V3 RR V2 lator to Non-Safety Air -Supply isolation IMS-0681 <M1-0219-1 CK/SA 1/2 3 A/C A C LT/2YR' CV/Q N/A N/A Safety-Related Air AO umu - (F-3) RR V3 RR V2 lator tr Non-Safety Air Supply isolation IMS-0682 M1-0218-1 CK/SA 1/2 3 A/C A C LT/2YR CV/Q N/A N/A Safety-Related Air Accumu-I (F-3) RR V3 RR V2 lator to Non-Safety Air. 4 Supply Isolation IMS-0683 M1-0218-1 CK/SA 1/2 3 A/C A .C LT/2YR CV/Q N/A N/A Safety-Related Air Accumu (F-3) RR V3 RR V2 lator to Non-Safety Air Supply Isolation IMS-0684 M1-0216-1 CK/5A 1/2 3 A/C .A C LT/2YR CV/0 N/A N/A Safety-Related Air Accumu-(F-4) RR V3 RR V2 lator to Non-Safety Air-Supply Isolation IMS-0685 M1-0218-1 CK/5A 1/2 3 A/C A C LT/2YR CV/Q N/A N/A. Safety-Related Air Accumu-(F-4) RR V3 RR V2 lator to Non-Safety Air Supply isolation IMS-0666 M1-0218-1 CK/SA 1/2 3 A/C A C LT/2VR CV/Q N/A N/A Safety-Related Air Accumu - '(F-4) RR V3 RR V2 lator to Non-Safety Air - Supply Isolation 1MS-0687-M1-0218-1 CK/5A 1/2 '3 A/C -A C LT/2YR CV/Q N/A N/A Safety-Related Air Accumu-- ~(F-4) RR V3 RR V2 lator to Non-Safety Air Supply isolation April 30, 1993 b . _... _... -... _..... -. _..... -. - -..., _.. ~..,.. __...-_..~..,_..._....-..,_.._..---,-._:...._,......~...____..,....__._,_.,.
q J [ COMANC11E PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 9 - MAIN STEAM PAGE 7 0F 12
- j Test Parameters / Schedule Flow Valve /
Safety fail Position Va he Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator .Nunbar (Coord.) Type Site Class oory tion Pos. Test Test Test Te:it Remarks i. g FV-2325 M1-0202 GL/A0 8 2 B A O/C N/A MT/Q FC/Q PIT / SteamVentflowpath(for r (B-3) 2YR residual heat removal)/ M2-0202 Contalment isolation (B-3) PV-2326 Mi-0202 GL/A0 8 2 B A O/C N/A MT/Q FC/Q PIT / Steam Vent Flowpath (for '{ (B-2) 2VR residual heat rmoval)/ t M2-0202 Contalment.lsolation (B-2) PV-2327-M1-0202 GL/A0 8 2 B A O/C N/A MT/Q FC/Q PIT / Steam Vent Flowpath (for I (B-1) 2YR residual heat removal)/ I M2-0202 . Contaiment isolation (B-1) l . PV-2328 M)-0202 GL/A0 8 2 B A 0/0 N/A MT/Q FC/Q PIT / Steam Vent Flowpath (for (B-4) 2YR residualheatremoval)/
- 2-0202 Contalment isolation t
(B-4) { j tN-2333A M1-0202 GL/HO 32 2 B A C N/A P5/Q FC/Q PIT / Steam Line isolation & f i (F-4) X .MT/C5 2VR Contaiment 1 solation ' M2-0202 34 (2) i (F-4) FN-2333B ~M1-0202 GL/MA 4 2 8 .P .C N/A N/A N/A PIT / . Steam Line Isolation & [ (F-4) 2YR Containment isolation M2-0202 l-(F-4) .} 32 2 B . A C N/A PS/Q FC/Q PIT / Steam Line isolation & t HV-2334A - M1-0202-GL/HO l (F-2) X MT/C5 2VR Contaiment Isolation i M2-0202 34 (2) I j.. (F-2) 1 9 f ' April 30, 1993 l Y Y I I ___--__-._m_..,___.____
i', i P. m A 4 w i e m e r t, r e w s g o e m e = 3 r. 9 + 9 e + &n &n &n &n n n 'w 1 no no no no no oW W oi oi oi oi ioi iF A 3 4 e F 0 it it it a it a ta a y y W t t t tA t a t a al al al al al l&r &r l l o l o o l o o o a a w l os os os os los snd nd t i r r y isi sI sI sI isI ion ito a on p t I I i iu u A w t t t t t tt o s en en en en en nab aB t im im iml Ln ine el l w ne ne ne ne im m mst oh oh e s Ln i k i Ln l i Lni iI a l a s st v r ma ma ma ma ma a p p w a at at at at at tBw Bw b m en en en en en nLo Lo W m e t o t o t e t o t o oEl El 1 R SC SC SC SC SC CHF ' HF W e N w S e es r no ot iat_ / / / / / / / s TR TR TR TR TR TR TR e tci i Le. IV IY IY I Y IY IY IY sd P2 P2 P2 P2 P2 P2 P2 N on EPI l e u v d e e ifn A e Q 0 0 Q W l h / A / A / / W c aae / C / C / C C e SfST N F N F N F F / s 2 r 'M e 4 t e E e s e 1 m i n a ct 5 5 r rs QC) QC) Q Q 5 T I a ee A //2 A //2 A / / e N P xT / ST( / ST( / T T U N E N PM N PM N M M A t ar N L s OP e TI M T GA A e NE kt T IT as A A A A A A A e S TS2 ee / / / / / / / t S 1 LT N N N N N N N EN r C ITIF 8' R A0 T EM w C V 8 E en L - y. L A E t c. w E V9G ens r p M A f uo C C 'C C C C C 4 = EEF aFP A CL S E IB TSVA RT E K 5 w A cn w N PI no f E i ui P A P A P A A ~ Ft w E e H w C N A ev 9-- e M t r O ao B B B B B B B w w C Cc tv t e T s es da ol 2 2 2 2 2 2 2-CC + u f i_ 2 4 2 4 i_ 4 3X3 4 3X3 4 3 3
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CCNANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 IN$ERVICE VALVE TESTING PLAN. TABLE 9 - MAIN STEAM PAGE 10 0F 12 ' Test Parameters / Schedule Flow Valve / Safety Fail Position Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator Ntrnber (Coord.) Type Site Class cory.. tion Pos. Trd Test Int Test Rearks W-2401B M1-0202-2 GL/A0 3/4 2 8 A C N/A MT/0 FC/Q PIT / AFW Flowpath Boundary (C-3) 2YR M2-0202-2 (C-3) 5 W-2402A M1-0202-2 GL/A0 3/4 2 B A C N/A MT/Q FC/Q PIT / AFW Flowpath boundary (C-2) 2YR M2-0202-2 (C-2) W 2402B M1-0202-2 GL/A0 3/4 2 B A C N/A MT/0 FC/Q PIT / AFW Flewpath Boundary (C-3) 2VR M2-0202-2 (C-3) W-2403A M1-0202-2 GL/m3 3/4 2 B A C N/A MT/Q FC/Q PIT / AFW Flowpath Boundary (B-5) 2VR M2-0?o2-2 (B-5) HV-2403B M1-0202-2 GL/A0 3/4 2 B A C N/A MT/0 FC/Q PIT / AFW Flowpath Boundary (B-6) 2VR M2-0202-2 (B-6). W-2404A M1-0202-2 GL/A0. 3/4 2 B A C N/A MT/Q FC/Q PIT / AFW Flowpath Boundary -(C-5) 2YR M2-0202-2 (C-5) 1 W-2404B M1-0202-2 GL/A0 3/4 2 B A C N/A MT/0 FC/Q PIT / AFW F 10wpath Boundary (C-6) 2VR M2-0202-2 ~ C-6) ( r ( April 30, 1993 I w....ww.-,-+e+~ --ee>~=%-+nm-e,v e %~ wr+n+ ,rv v-ew.c.,,.--i-tm iw-.- Sw*- ,+ ' w w + w e w w-+ m
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COMANCHE PEAK STCAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 9 - MAIN STEAM PAGE 11 0F 12 Test Parameters / Schedule Flow Valve / Safety fail Position Valve Diagram Actuator Code Cate. Func-Func. Leak Exercise Safe Indicator a Number (Coord.) Type Sjig (lass cory tion Pos. M Test Test Test R marks HV-2405 M1-0202-2 GL/A0 3/4 2 B A C N/A MT/Q FC/Q PIT / Containment isolation & AFW (F-2) 2YR Flowpath Boundary. M2-0202-2 (F-2) HV-2400 M1-0202-2 GL/A0 3/4 2 8 . A C N/A MT/Q FC/Q PIT / Contaiment Isolation & AFW (F-3) 2VR Flowpath Boundary H2-0202-2 (F-3) HV-2407 M1-0202-2 GL/A0 3/4 2 B A C N/A MT/Q FC/Q PIT / Contalment isolation & AFW (F-4) 2YR Flowpath Boundary M2-0202-2 (F-4) HV-2408-M1-0202-2 GL/A0 3/4 2 B A C N/A MT/Q FC/Q PIT / ~ Containment Isolation & AFW (F-5) 2YR Flowpath Boundary M2-0202-2 (F-5) HV-2409 M1-0202 GL/A0 2 2 B' A E N/A MT/Q FC/Q PIT / Steam Line Isolation & (E-4) 2YR Contaiment isolation M2-0202 (E-4) HV-2410 M1-0202 GL/A0 2 2 B A C N/A MT/Q FC/0 PIT / Steam Line isolation & (E-3) 2VR Contalment isolation M2-0202 (E-3) April 30, 1993 =c ec- [--,--wee-, -,=-w..m3e -me + e,r e w,-,-=,-ev-en m w m e, --w i ,*-ry c: easew.,w,-~-www.w . w,v e v r e-. wc-y+.-wr. =,4,e* w ee%m w.-s - n---o-- -w-q u e.v e ew wn,-- .aw==,+rme w ww , <w ye wea.y e w,e n - weer a.e----,,= es-,s.w oe, e w e=es w e e % = -ms,-- w # ,,ww._
_ _ _ _ = _. _. _. _ _ _.. _.. _ -. _ _, _ _. _. -... _.. _ _. -.. .,.___s__. a: -I q .j COMANCHE PEAK STEN 4 ELECTRIC STATION UNIT 1 & 2 j INSERVICE VALVE TESTING PLAN ' i TABLE 9 - MAIN STEAM L PAGE 12 0F 12 .j Test Parameters / Schedule =! Flow Valve / Safety fail Position i Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise safe Indicator Nfter (Coord.) Type $_j;g Class oory tion .Pos. Test Test Test Test Remarks 1 HV-2411 M1-0202 GL/A0 2 2 B A C N/A MT/Q FC/Q PIT / Steam Line Isolation & ' (E-2) 2YR Containrnent Isolation l M2-0202 (E-2) i l HV-2412 M1-0202 GL/A0 2 2 B A C N/A MT/Q FC/Q PIT / Steam Line isolation & (E-5) 2VR Contairvrent Isolation M2-0202 (E-5) { i HV-2452-1 M1-0202 GL/A0 4 2 B A O/C N/A MT/Q F0/Q PIT / TDAFW Pump Steam Supply i (A-6) 2VR F lowpath/Contaiment .l l M2-0202 Isolat ion j -(A-6) t ' r2452-2 MI*0202 GL/A0 4 2 -B A 0/C N/A MT/Q F0/Q PIT / TDAfW Pump Steam Supply l (A-5) 2YR Flowpath/ Containment M2-0202 Isolation l (A-5) .l I 1 i 3 t l I l' ' I l i t t J ? t April 30, 1993-l 6 i a .k t .c. .-...... 2 .. 2.- I
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COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 IN5ERVICE VALVE TESTING PLAN TABLE 11 - RESIDUAL HEAT REMOVAL PAGE 3 0F 3 Test Paramters/Schad91e Flow Valve / Safety fail Position Valve Diagram Actuator. Code Cate-Func-Func. Leak Exercise Safe Indicator Ntrw (Coord ) 'Twe 5.ite Class aory. tion Pos. Test Test Test Test R earks 8108A M1-0260 RE/SA 3 2 A/C P O/C LTJ/T5 SRV/ N/A N/A RCS Overpressure (E-2) X 10YR Protection /RHR Flowpath M2-02CO 4 (4) Boundary & Contalment (E-2) Isolation 8709B M1-0260 RE/SA 3 2 A/C P O/C LTJ/T5 SRV/ N/A N/A RCS Overpressure (E-5) X 10YR Protection /RHR Flowpath' F2-0260 4 (4) Boundary & Containment (E-5) Isolation 8716A 'M1-0200 GA/MO 10 2 8 A O/C N/A-MT/C5 N/A PIT / ECCS Injection 2 (B-3) (6) 2VR Flowpath/ECC5 Recirculation M2-02fC Flowpath Boundary (B-3)- 8/16B M1-0260 GA/MO 10 2 B A O/C N/A MT/C5 N/A PIT / ECCS Injection 2 (B-4) (6) 2VR Flowpath/ECCS Recirculation M2-0200' flowpath Boundary (B-4) 8717 M1-02CO GA/MA B 2 B P C N/A N/A N/A PIT / ECCS Flowpath Boundary (A-4). 2VR M2-02CO (A-4) 8730A M1-0200 CK/SA 10 2 C A 0/C N/A CV/05 N/A N/A ECCS & RHR Flowpath/ECCS (B-3) (5) Injection Flowpath Boundary l M2-0260 (B-3) a l 8730B M1-02(O CK/5A 10 2 C A O/C N/A CV/C5 N/A N/A ECCS & RHR Flowpath/ECCS (B-5) (5) injection Flowpath Boundary M2-0260 (B-5) t l i Rev. 2 + April 30,1993 - ( i.,_J,----...~--.~,.- -n ~ ~ - - - + -,. ~.6,- .,--<..----,--.,.~.,n.i2--.---.-l.~- -..-,L.-.n. . 6 -,, -~.--...-------A..~ . + - - - -, - -,
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...______.____._..___...________.._._________.____..._...m. l .s i COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN 3 TABLE 13 - SAFETY INJECTION 1 PAGE 2 0F 17 l Test Parameters / Schedule Flow Valve / Safety fail Position Valve Diagrarn Actuator Code Cate-Func-Func. Leak Euercise safe Indicator Ntrter (Coord.) Type Li e Class cory tion Pos. Test Test Test Test R marks il 8802A M1-0263-A GA/MO 4 2 B A 0/C N/A MT/C5 N/A PIT / ECCS to Hot Legs Flowpath/ (A-2) (3) 2YR ECCS to Cold legs Flowpath M2-0262 Boundary & Containment (F-2) Isolation & Passive Pipe Break Isolation 8802B M1-0263-A GA/MO 4-2 B A 0/C N/A MT/C5 N/A PIT / ECCS to Hot Legs Flowpath/ (A-3) (3) 2VR ECCS to Cold legs Flowpath - M2-0262 Boundary & Contairrnent (F-5) 1 solation & Passive Pipe Break Isolation 880aA N1-0201 GA/MG 8 2 B A O/C N/A MT/C5 N/A PIT / ECCS Recirculation (F-5) (4) 2YR Flowpath/ Passive Pipe M2-0261 Break Isolation (A-6) 88048 M1-0263 A GA/MO 8 2 B A O/C N/A MT/C$ N/A PIT / ECCS Recirculation (F-3) (4) 2YR Flowpath/ Passive Pipe M2-0262 Break Isolation 2 (B-4) 8806 M1-0263-A GA/MO 8 2 B A C N/A HT/C5 N/A PIT / ECCS Flowpath Boundary (G-2) (3) 2VR -(duringRecirculation) M2-0262 (A-2) 8807A M1-0201 GA/MG 6 2 B A O/C N/A MT/Q N/A PIT / ECCS Recirculation (E-5) 2YR Flowpath/ Passive Pipe Break M2-0261 Isolation. (B-6) Rev. 2 April 30, 1993.
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COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 i IN5ERVICE VALVE TESTING PLAN i TARLE 13 - SAFETY INJECTION l-PAGE 6 0F 17 Test Pararw=ters/SchMule Flow Valve / Safety i Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise. Fail Position -i Safe Indicator N rter (Coord.) . Type ' Size Class gory tion Pos. M -Test Igit Test Renark s t j 51-8810B M1-0263. CK/$A 2 1 A/C A 0/C LT/T5 CV/RF N/A N/A ECC5 to Cold legs (C-4) (!) (6) Flowpath/ Reactor Coolant j M2-0263 Pressure Boundary & t (D-4) Contalment isolation j 51-8810C 'M1-0263 'CK/5A 2 1 A/C A O/C LT/15 CV/RT N/A N/A ECCS to Cold legs l (B-4) (1) (6) Flowpath/ Reactor Coolant M2-0?63 Pressure Boundary &~ (E-4) Contalment isolation l 51-88190 -M1-0263 CK/5A 2 1 A/C A 0/C LT/T5 CV/RF N/A N/A ECCS to Cold legs (B-4) (1) (6) Flowpath/ Reactor Coolant M2-0263 Pressure. Boundary & (F-4) Containment Isolation 8821A M1-0263-A GA/MO 4 2 B A O/C N/A MT/Q N/A PIT / ECCS to Cold Legs Flowpath/ j (C-3) 2YR ECCS to Hot Legs Flowpath M2-0262 Boundary & Passive Pipe (E-3) Break isolation i 5821B Mi 0263-A EA/MO a 2' B A O/C N/A MT/Q N/A PIT / ECCS to Cold legs Flowpath/ ^ (C-4) 2YR ECCS to Hot Legs Flowpath i M2-0262 Boundary & Passive Pipe [ (E-4) Break isolation ? 8823 M1-0263 GL/A0 3/4 2 -B A-C N/A-MT/Q FC/Q PIT / Containment Isolation & 2 i (E-3) 2YR ECCS Flowpath Boundary -l H2-0263 (B-3) [ l l eI L [ Rey, 2 -i . April 30, 1993 i g ? I I o ? . ~..
e CCl%NCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 13 - SAFETY INJECTION PAGE 7 0F 17 Test Parameters /Schmjule Flow . Valve / Safety fail Position Valve Diagram Actuator Code Cate-Func-Func. Lea': Exercise Safe Indicator . Number (Coord.) Type 5.i g CRs.s cory tion
- Pos, lelt Test Its.t Test Remarks l
8824 M1-0263 GL/A0 3/4 2 B A C N/A-MT/Q FC/Q PIT / Containment Isolation & 2 (E-2) 2VR ECC5 Flowpath Boundary M2-0263 (B-2) 8825 M1-0263 GL/A0 3/4 2 A A C LTJ/TS MT/Q FC/Q PIT / Contairrient isolation & 2 (E-1) 2YR ECC5 Flowpath Boundary M2-0263 (B-2) 4 8835 M1-0203-A GA/MO 4 2 B A 0/C N/A MT/C5 N/A PIT / (CES to Cold Legs Flowpath/ (A-5) (3) 2VR ECCS to Hot Legs Flowpath M2-02f2 Boundary & Contairrient (F 3) Isolation & Passive Pipe Break Isolation 8840 M1-0263-B GA/MO 10 2 A A 0/C LTJ/T5 M1/C5 N/A PIT / [CCS to Hot Legs Flowpath/ (A-3) l3) 2VR ECCS to Cold Legs Flowpath .M2-0263-A Boundary & Contairrnent (F-2) Isolation & Passive Pipe Break Isolation 8841A M1-0263 CK/SA 6 1 A/C A 0/C LT/T5 CV/RF N/A N/A ECC5 to Hut Legs Flowpath/ j (C-1) (1) (6) Reactor Coolant Pressure M2-0263 Boundary & Containment (E-1) Isolation BS41B M1-0263 CK/SA 6 1 A/C A O/C LT/T5 CV/RF N/A N/A ECCS to Hot Legs Flowpath/ 1 (C-2) (1) -(6) Reactor Coolant Pressure M2-0263 ' Boundary & Contairrent -(E-2) Isolation 8843 M1-0201 GL/A0 3/a-2. B A C N/A MT/Q FC/Q ' PIT / Contalrinent Isolation & 2 (B-2) 2YR ECCS Flowpath Boundary M2-0261 '(E-4) Rev. 2 Apr*1 30, 1993
. c [.- t. COMANCHE PEAK STEAM ELECTRIC STATION llNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 13 - SAFETY INJECTION PAGE 10 0F 17 Test Parameters / Schedule Flow Valve / Safety Fail Position Valve . Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator Nyber (Coord.) Type 51/g Class cory tion Pos. .Tgst Test
- Telt, Test Remarks 8879A M1-0263 GL/AD 3/4 2
B P C N/A N/A N/A PIT / ECCS Flowpath Boundary (D-4) 2YR M2-0263 (C-4) 8879B M1-0263 GL/A0 3/4 2 B P C N/A N/A N/A PIT / ECCS Flowpath Boundary -(C-5) 2VR y M2-0263 (E-5) 8879C M1-0263 GL/A0 3/4 2 G P C N/A N/A N/A PIT / ECC3 Flowpath Boundary (B-5) 2YR M2-0263 (F-5) 88790 M1-0263-GL/A0 3/4 2 8 P C N/A N/A N/A PIT / ECC5 Flowpath Boundary (S-6) 2YR M2-0263 (E-6). 4 8880 M1-0262 GL/A0 1. 2 A A C LTJ/T5 MT/Q FC/Q PIT / Containment isolation (G-1) M2-0263-B .2YR (A-1). 8881-M1-0263 Gt/A0 ~3/4 ~ B A C N/A MT/Q FC/0 PIT / Containment Isolation & 2 (E-1) 2VR ECC5 Flowpath Boundary M2-0263 (B-1) Rev. 2 April 30, 1993 .I _________.;_m -m..m .m.-w...
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CO %NCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 13 - SAFETY INJECTION PAGE 11 0F 17 Test Parameters / Schedule Flow Valve / Safety fail-Position Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator Number (Coord.) Type .Sigg Class rJory. tion .Pos. M Test Tgs_t M Rmarks 8882 M1-0261 GL/A0 3/4 ? B P C N/A N/A N/A plt / ECCS Flowpath Boundary (B-3) 2VR M2-0261 (F-3) 8888 M1-0263-A GL/40 3/4 2 A A C LTJ/TS MT/Q FC/Q PIT / Contalment Isolation & 2 (B-2). 2YR ECCS Flowpath Boundary M2-0262 (E-2) 8889A M1-0203 GL/A0 3/4 2 B P C N/A N/A N/A PIT / ECCS Flowpath Boundary (3-2 L 2YR M2-0203 (F-2) 88898 M1-0263 GL/A0 3/4 2 B P C N/A N/A N/A PIT / ECCS Flowpath Boundary (B-1) 2VR M2-0263 (E-1) 8889C M1-0263 GL/A0 3/4 2 B P C N/A N/A N/A PIT / ECC5 Flowpath Bourdary (B-1) 2VR M2'0263 (F41) l 88890 M1-0263 GL/A0 3/4 2 B P C N/A N/A N/A PIT / ECCS Flowpath Boundary (B-3) 2YR M2-0263 (F-3) 8890A M1-0263 GL/A0 3/4 2 A A C LTJ/TS MT/Q FC/Q PIT / Containment isolation & 2 (E-4) 2YR ECCS Flowpath Boundary M2-0263 (B-4)' Rev. 2 April 30, 1993 _,...-,_-..___-._,-,_.a.-,_..__...,,__.,_..___.,-,-.._.__.___,.~.-.. .._.;___._.,__.__u_..._.
COMANCHE PCAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 13 - SAFETY INJECTION PAGE 12 0F 17 Test Parameters / Schedule 3 Flow . Valve / Safety fail Position Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator j _ Number (Coord.1 Tyca Size Class aory tion Pos. Igst Test Test Test ReMrks 8890B M1-0203 GL/A0-3/4 2 A A C LTJ/T5 MT/Q FC/Q PIT / Containment Isolation & 2 (E-5) 2YR ECCS Flowpath Boundary M2-0263 (C-5) SI-8900A M1-0?61 CK/5A 1-1/2 1 A/C A O/C LT/T5 CV/RF N/A N/A ECCS to Cold legs Flowpath (A-2) (1) (6) & Boration Flowpath/ Reactor M2-0261 Coolant Pressure Boundary (G-4) 51-89006 M1-0261 CK/SA 1-1/2 1 A/C A O/C LT/T5 CV/RF N/A N/A ECCS to Cold Legs F1 wpath 0 (A-1) (1) (6) & Boration Flowpath/ Reactor M2-0261 Coolant Pressure Boundary (G-4) 51-89X)C M1-0261 CK/5A 1-1/2 1 A/C A 0/C LT/T5 CV/RF N/A N/A ECCS to Cold Legs Flowpath (A-3) (1) (6) & Boration Flowpath/ Reactor M2-0261 Coolant Pressure Boundary (G-5) 5!-89000 M1-0261 CK/SA 1-1/2 1 A/C-A 0/C LT/T5 CV/RF N/A N/A ECC5 to Cold legs Flowpath (A-2) (1) (6) & Boration Flowpath/ Reactor -M2-0261 Coolant Pressure Boundary (G-5)- SI-8905A M1-0263 Ex/SA 2 1 A/C A 0/C LT/T5 CV/RF N/A N/A ECCS to Hot Legs Flowpath/ (C-2) (1) (6) Reactor Coolant Pressure M2-0263 Boundary & Contaitunent i-(D-2) Isolation Rev. 2 Apri1 30, 1993 u__..._-._.,-,_.. . _ -,,-_-_. - -. _.,. - -... _. - _. _,. ~ _ ~ -..
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i y o v A C ; l e a s ei lu e r t u e p u e r t c e e d n a s s O 1 v q d a a e r - s e 0 l g e e h l l f r p s e 1 it . a l t g s d 8 B a n N t f s g c C A, V i s v a y o b p y l s D p l l TI e u u in u l 8 n V e is a e o s b m a o r o h r r e t a s t e a h ( el s u C n r p ,t h ia C 0 e r e 8 g d ( UN OLI e B, 1 e r a b S k. 0 e e e e, o N k n t A O c r h C c 8 l d s g s v n v N A E r A, P s, e n c. l is e. o a a b i s o ia r a t a s c s R o 8 e r n u o e t P I T l r d v r o GC a v e w e l t h c a d l et f t T l h o h o d e o c b a c e e a u o N T J o 6 e a t d t t e v SIN f 5 M lv v t t o l C r a u x b 3 r V d R s n s e r t E e H e T 9 G n u e q a o x e c n e d. n eR m e SI y 8 a e o h g e l v t e p a t r C R T S p ; o t s e t 1 s e r e io t n io lb e i a E Y l f V h s n h c o a o e t IT T E E p D n t ld l y 5 p k in ie r i b lo t ci ic t N r t a v H a a E A O , t n e o a s l R u r d h R e ic i e h E F T a s o g n l e l W m o n e t c C V L S N 2 C n it i is c a f m 1 t d t et t t p e s s L c h u u P t e t H p s c e v h A e a n s r R o d o i a p r w E V 2 . m l e n t c o - e o e t r s e B o p a a M E r is o r ld r r 5 A 3 5 n o f r n h n a s n r - h C t d u a a e r t a t et f t TI1 E V 4 A iu e e o c n n 5, p r e l s t mno e o a 9 q t s S E R 4 4 e a u it s c e o 3 w m p s h p L h p 8 r e o o s y t. K B 9 r t a l ic d t w A A n 8 m c u r n ic o it 8 o b p r gA s ia s E u o S E T it 0; c ia d eh l v u it n i b t i f ol c f n N o y n e a e a h y u
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n o f I P b r x w l S e l t r. s o n g n o n n h H mw io u t C it io o g E a e t n y t s u s l f d n $ / C ic , u n io h e a l f p a t eE n l u C q o k p a mV e t s c d A ic B, r / a e r o s e P w y io S s t io a t o N f e C t s o w e r u b s n u e id C E r r d r t e o n h M f n r s t l h o t s t t a p p a t O e io e o s f p it 1 f n u it s ic a a lmt l o b o C p , t p p - m 5 in a o u x s I n j s i p r - h r e g S A s t o i l o P m l n u e n s s m e t t ot n 8 e a l 4 t l t u i e 6 i c S p P e o f a 9 o n d f t t r 0 M C p o s la a a w m w o ic 8 e i l a e e a 8 s eE f a k d s m a a f s a n c n a 8 s C e d e p p d l h n N u g r h D; t p b j l s o v a e o e ia i g d n d n o e ml n s H r t P n c n o la v f ie ia t l C h io g e t i v s u a a t a n t t - o t H u i id n e, a i g n y n n o C e P v r e s l r-R r a n u ,t c r is a e o a S s h r h a i m n t r v l I e o o B e j d e c f t e V e s t d a is R d i q p e u f t o s r l u v n d a c h , h n e p n 5 c y v e R t e 8 r i mr is o t e d p t A t i d s S a t s 3 T i n s ,i b v f et e e g 1 a s l s oR m 9 r e is o l c a l 8 . t e t n e m v v s R e o e s p a e H e 0 i t n a n e h s b I l l u S e o o e Ke n l i s u l n e 8 t f v a h t t ; n h - s a e r t t o s r I e S x a e wt o u a s v l h iu S r e h is h H e o t d f w c n e n l t n c v d b n r D; e a e e e s t a u s a b i io-io h i g g q d y T s o u ol t ) a e le a n t e f t s . in r e k h r s V h e( d a f e f H o t t e s s s 2 a t n t l o v o n m y r k w n r p s u e o i a u l n n e g s c ol ie a m g ld a c C h t h c o 5 h n m r c g a s u u e c n e r n v d r e, r iH l h y n - i c s s P l o 4 h a s p i e e, s . u t e r t $ ld n n ig c p o c is e r y u B a m 1 t o H s u t-R ic e n. t s q l w ol a m e s d b r A t B f r v t s o a io it , eP n r h u d f 0 n o mi y ,C t v a e t h e 0 e d ef t ic s B d i a B l n l B x t m t 9 n b h a o e s c a e - r t e e u o is oi & v io p e r g a s 8 a s t l l l t o in i t p f t g e f A ol e r a r A s c t I iu 1 n z s r t 2 p r e i A e c n A e q 0 n z u e d n 0 m e f e 0 ej i 1 k t l S c 4 s e 1 r s e i o t a r c h ; e 8 a o a h y o 8 u x a p 8 h n u 8 t e r a T B r 8 c n c t h c 8 P e s S 8 T i d 8 s t c f 1 2 3 4. 5 [ fl ll1lil1Il!I1l:
m. A e COMANCHE PEAK STEAM [LECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 13 - SAFETY INJECTION NOTES i G. 8815, 51-8900A, B, C, D, 89 % A, High Head Safety injection Flowpath Check Valves; 51-8819A, B, C D, SI-8905A, B, C, D, 8922A & B, 8920, 89494, I B, C & D and 8%98, Intermediate Head Safety Injection Flowpath Check Valves; 8841A & B, low Head Safety injection Flowpath (to the Hot Legs) Check Valves are full-stroke exercised at refueling outages. These valves cannot be full or part-stroke open exercised during plant operation or during cold shutdowns because the flowpaths discharge into the RCS, In the case of the High Head subsystem, the valves cannot be full-stroke exercised during plant operation because the high RC5 pressure will not l allow the maximum required injection flowrate to be achieved. Part-stroke exercising during plant operation is not practicable because any flow through the valves results in unnecessary themal transients on the RC5 cold leg nozzles for which they are not designed and imposes hydraulic transients on the charging system and on the Reactor Coolant Pump seals which can cause thm to cock. The check valves in the high head injection path cannot be full-stroke exercised at cold shutdowns because the high flowrates could challenge the RCS Cold Overpressure Mitigation System as well as irpose hydraulic transients on the charging systm and on the Reactor Coolant Pump seals which can cause the to cock. Part-stroke exercising at cold shutdowns is not practicable because the high head injection flowpath is not designed for throttled operation. In the case of the Intemediate Head and Low Head subsystems, the valves cannot be full or part-stroke exercised during plant operation because j the relatively higher pressure of the Reactor Coolant Systm will not allow forward flow through these paths. (An exception to this is valve 8926 which lies in the $1 Pumps' miniflow path and thus is part-stroke open exercised quarterly during pump tests.) Part-stroke exercising -certain check valves during plant operation via the 51 test header is not practicable because this path yields flowrates too small (approx. 5 gpm) to be meaningful for assessing the operational readiness of these valves. The check valves in the intermediate head injection paths cannot be full-stroke exercised at cold shutdowns using the Safety injection Pumos because the resulting high flowrates and pressures could challenge j the RC5 Cold Overpressure Mitigation System. The check valves in the low head injection paths to the hot legs and the check valves in the combined low head and intemediate head injection paths to the hot legs (8949B & C) are not practicable to test at cold shutdowns because forward flow will disturb these Reactor Coolant Pressure Boundary Isolation Valves. Doing so requires leak tecting the valves per the Technical Specification requirements identified in Note 1 above. This leak testing is not practicable to perfom at cold shutdowns due to its complexity and critical path nature. Such testing would prevent the irmediate return of a shutdown unit to power operation which is contrary to the intent of OM Part 10, paragraph 4.3.2.2.g. Part-stroke exercising these valves at cold shutdowns is not practicable because the flowpaths are not [ designed for throttled operation. i-l Apri1 30. 1993 i l w e-. w v .r -.-w-e ...m ..es,.r-e-e.or=.-e+- +~e,-,-m-v.w-u-w-- -we n ee w-e -+ i. .vu-v,=,ce,w.v.w-*. .-owm= r-e- ,.o .-n. +=-r-.--.---...,em.-.,,--e....%% --w+m-%m-e.#-- m-me +,---w, w-- re, -
M -m 4 r* g g l n e + -y -y y q t e l e s e is s is y d n e m m, y e h 3 u d e t c v l h w c T y e a I t g 9 n e oi h s r l 9 m i e s n 1 t n S x v w s e it e m o y a oi e e e u v t s r s o , t yl h e mc 0 a l o c s n e t b t s a a f 3 f o n a k e a. et e v gd a d s w l of c s r h s b i e S l p e e o o r a i e o T y k i T a t C s c l l e it l i s o g d ot S t v f S e c t e w r M t h p c t u - e a a e . t b h ot A ee g r u h r l r r v ic e u t o e w s y n a c e r e . o s o l u p a n is g ld c f s t s r it lo ic r h f d W x e t u s e e l t h s n n a e o e e i o c T s r n g e ci o e o r n h x b C a e o wi e r l c R t P t e a r o x u t e s w is r r p . r f o s p e e p d e e f n e o s r d w d v e f a h e o o e p t t e e e o o e e t mL r p o c o v v n lb o a u t b k n r d e s o a n l O g i o e e f t e d s y e a n P r p t s o h a e e f R s v d is s c e a h o r e e od id d t o a i t t e id r eh r s C a a it e n k i i l e e e e p r - ed r r f e l k e e u d o t a t v t e e t r r n l o is x s e s e s d h o Gno y c s u r e s s s e r of a t e e s e n l t o e R s h e ey f t c e u i t la u s e o e r a T s r e r l h f e u t d W e - e k p e a i h t x o b r S n f e r t h a c h s t r e r r t o g u s s t e ih s 5' 3 c n a t e n ei e a s e s s b o + s p e s h a h h t h t s t e e h a s ig c t t a t u e 1 id e p b r r 'r n g t e w a y o l o r o r n a l e M y l l l h eb a e s p 5 c r c u n i p a g a l w a o D* n e f y i s v o n e t e l l t y i r e e l o S 2 e u r a it u e t u f io l h f ic f e e h r a l h u r k e e a n e c l n t t s t q a o r v n e io h n e c c r r f t e u h ia a e a o r t r q t n d h r t o f s , a t d a g n e v o l t p a f t' s - s l e r n e r y u l 1 e t l e e r e ei r l n it o e t u s W mil v n p s f t e I s gf l r T a u T i o s a iv io a c s o m n r u n u w a eS l e e t e s a c o N n V h W t s m d t a p e c s c d NAO t o l c e o is n s a lh la r ot e i a t + U ei o t R e N N h w s k a a s e a b u T h l e p e r s e h L l a e s t t p r e O mr o h w e e h s F I TIP t l h u o h T t ol g t GC a o A E f is C a R g g f t s e t l b a ld c H n n s h n gf a t f N T J s h e R i i l t a t a n 4 2 a e e u f e p is g ic u o o I T g le 6 t b N e S n r u a s l h o c M =- t e 1 SI a b 9 p n h p d g s id s s ih a n a o C c g c r Y t a 8 w o t o n n u g e E IT R T S u s w e a n s r i o T E E o ic o it h e e i o r c i s g p l s n e l n T E C F T t v F a g c v a d a e r a n e o e V E A O g c l r u n l e t b u it o f a t m t u s i L S N n a a n e oi a m u d r L A i r v M e e io p r s v h s n ol n e g a E V l p oh e s e s TI1 f o o e n h io c d lv io gf u r r t t n k b n s s e e w E A 3 u t r c t t is u r n + l ei g h p C E e o l a a ic g e n i t o e n f j a t t h t o V r f s V n l a a c c e r n S E r e i p p r ) k p r n h w u i t R A A a is r n L E K B t e w e e m t c o ei t o d a e S e h y g o p s a a e x n d r l N E T 6 T t n l o e g h t e a et w u p = d-I P d 2 e i f h d C n e s u o c 4 C e 9 f r t t 5 e a e m u h l c g E is 8 S d h lp o r p g t b l t t u a u e n k a s f o n H m a f is h lp o e c t C c e e T o x. c a r b e d h o i r N r v t d d ( A e l s a e n r e w n s o oi d M x a y e s g p x oi t s c w t O e v s H i. n ia p e l r t n n d 3 C b c s i t a F u r ) w t s e e N e f u w r h r r ( e d a m o a ei s s o s o et u e s s P p d v s i 'n o L x a d c l o r d g t s l n c u o e u e a a r s g d e p l lc t s. 5 h v v r e m l c n a . n e e n m a s s l t x e d g a e e B e is h e s s i s e l ic e. a e e a & p e u s k u r v x d v s g k ic e oh o i o o m e l ol e n e r r t A t e c o r u x a r o e h i s u t e ia ) 8 e b r t t c e v p c s t l o e = s x 5 k h e s c p e o l m - ed e 9 o g t x s A n e a t h g o c e l e s 8 r u o e e l e h ( a t in c l e mi f o e r D, t o n t lu it e g a s i c s m n p t t h u s c s r n e a o o l d g s a o e e - h a k r f h l e n i n s l t e t t c o w eC n x_ , r r o e c k u mi s .h e B, p o t s f a j r r r is r e e r ( i e C a w h t l r e o o s c e s r M a c x u a m e n l a - n u e e t p o r d e e i t h o e r e a e r f p t s s s t o x e c s u s t e x e e v v o d is a l v v y t w e k s v u l of A l r P e l o t r o s e o r l + a b o e 8 l a h iy v a f p f t o k t t v a b e a l e k e r o a = 2 v a k a u wt s o 9 f r ) a a r o s a k d n r 8 o r. h k d S r d r t r - l k t_ c e a c ei t ef e mta eb , o r w s t l u c h ib a s ,b v e D l a o - s l m e m r - D w et p h i wl l - u u h e c r t l t o w s c r r ,l r f l t F c c
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c l , ol o y s c t s h u C n l h S ih c e .A t s C f f s f a t c e t f n a c m j b s B, a B n t e d , b o ld P a e d o e w e n n e c t o j B e b o io j b s s o a it o& it s u n , t l y t e b s l i . i b u n t , s n mt t u A e A c u s o A o a o a c s s eh 8 v l 8 e a s 6 n h n t r e e edi a t 1 l l 5 jc e a 5 n t t n s ej e h 8 a i 9 n e h e 9 a o a a y p n h T r d w 8 v w8 I b T r 8 c n p c S oI T 7. 8 m 4 1
COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 IN5ERVICE VALVE TESTING PLAN TABLE 17 - MISC. CONTAINMENT ISOLATION VALVES (1) PAGE 1 0F 12 Test Parameters / Schedule Flow Valve / Safety fail Position Valve Diagram Actuator Code Cate-Func-Func. Leak Esercise Safe Indicator Number (Coord.) Type S L?g [_las.1 aory tion
- Pos, Tgit Test Test Tost R marks Buildinos and Structures 185-0015 M1-0245
'BA/MA 3/4 N/A A P C LTJ/15 N/A N/A N/A Contairper.t Isolation (D-3) (2) 2BS-0015 M2-0245 RE/MA 3/4 2 A P C LTJ/T5' N/A N/A N/A Containment isolation l g (E-4) X (3) I 1 - 2B5-0016 M2-0245 GL/MA 3/8 2 A P C LTJ/T5 N/A N/A N/A Containment isolation (C-4) 2B5-0017 M2-0245-GL/MA 3/8 2 A P C LTJ/T5 N/A N/A N/A Contaiteent Isolation (C-4) i-l B5-0025 M1-0245 BA/HO 3 2 A P C LTJ/T5 N/A N/A N/A Contaircent isolation l (0-1) 'M2-0245 (D-2) l2~ 1B5-0029 N1-0245 BA/MA 3/4 N/A A P C LTJ/T5 N/A N/A N/A-Contairment isolation (E-2) (2) 2B5-0029 'M2-0245 RE/MA 3/4 2 A P C LTJ/T5 N/A N/A N/A Contairment isolation (D-3). X (3) -l 2 1 B5-0030 M1-0245 BA/HO 3 2 A P C LTJ/T5 N/A N/A N/A Containment Isolation (C-1) M2-0245 l2 (C-2) 285-0039 K-0245 -. GL/MA' '3/8 '2 'A P C LTJ/T5 N/A N/A N/A Containment isolation (D-4) l2 Rev. 2 April 30. 1993
L l f ~ 1 f-COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 17 - MISC. CONTAINMENT ISOLATION VALVES (1) PAGE 2 0F 12 Test Parameters /Schehle e Flow Valve / Safety Faii Position . j Valve Diagram Actuator Code Cate-Func. Func ' Leak Exercise Safe Indicator Number (Coord.) Type S Class acry tion Pos. Test Test list Test Remarks A l l. 285-0040 M2-0245 GL/MA 3/8 2 A P C LTJ/TS N/A N/A N/A Contalment isolation . l2 l (D-4) I' 1B5-0044 M1-0245 BA/MA 3/4 N/A A P C LTJ/T5 N/A N/A-N/A Containment isolation l (B-2) (2) l 285-0044 M2-0245 RE/MA 3/4 2 A P C LTJ/T5 N/A N/A N/A Contairrnent isolation F (C-3) X (3) I IB5-0056 M1-0245 BA/MA 3/4 N/A A P C LTJ/T5 N/A N/A N/A Contairrnent isolation (B-3) (2) 285-0056 M2-0245 RE/MA 3/4 2 A P C LTJ/T5 N/A N/A N/A Containment Isolation -(B-4) X (3) 1 B5-0202 M1-0245' BA/MA 2 2 A P C LTJ/T5 N/A N/A N/A Contairrent Isolation 2-(A-5) M2-0245-A (B-3) 85-0203 M1-0245- - BA/MA .2 2-A P C LTJ/T5 N/A N/A .N/A Contalanent Isolation - 2 (C-5) P2-0245-A .(E-3) i RW. 2 Apr11 30, 1993 .= r k* e.-is a',. wee-- +-ema eeg* a'wa .y um g it.99tett99 e heurr+ t it 's-= m*9 truer 4 ein 'P*'nate eh h--1Nwa-Ww Ws4W sma* uh -en "Eh+emeewtre 'e 9 Dirv"W-sus 4-as - e W'l4 p n ednot mi.w e si=b Meheets.-weegw..swn.,pe Tyeyeenga hpe er 1re he temmem1-r & wer m
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] .i COMANCHE PEAK STEN 4 ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 17 - MISC. CONTAINMENT ISOLATION VALVES (1) PAGE 9 0F 12 Test Paraw ters/Schadule Flow Valve / Safety Fail Position Valve . Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator Number (Coord.) Type Site Class cory tion Pos. Test Test Tes.t Test Remarks HV-4176 M1-0228 AN/A0 3/4 2 A A C LTJ/T5 MT/Q FC/Q PIT / Containment isolation I. (C-1) 2VR l-M2-0228 -(C-1) f I Radiation Monitorino I HV-5544 M1-0301-A GL/50 1 2. A A C LTJ/I5 MT/Q FC/Q PIT / Containment Isolation l (C-1) -. 2VR M2-0301-A 'l (C-1) } FN-5515 M1-0301-A GL/50 1 2 A A C LTJ/T5 MI/Q FC/Q PIT / Contaiment Isolation i (0-1) ZYR i M2-0301-A (C-1) FN-5546 M1-0301-A GL/50 1 2 A A C LTJ/T5 MT/Q FC/Q PIT / Containment isolation i (C-2) 2VR M2-0301 A I (C-2) ') i. HV-5547 M1-0301-A GL/50 'l 2 4 A C LTJ/T5 MT/Q FC/Q PIT / Contaiment Isolation '(D-2) 2VR M2-0301-A (D 2) Contalment HVAC i j HV-5530 M1-0301 '8F/A0 48 2 A A C LfJ/IS MT/C5 FC/C5 PIT / Contalment Isolation 2- -(F-2).. (8) 2VR .p i M2-0301 ) _(f-2) l i I i l l Rev. 2 .l April 30, 1993 i . =,. - - -..:.-.. -..=.--...........-..
F" -9 C(PANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 17 - MISC. CONTAINMENT ISCLATION VALVES (1) PAGE 10 0F 12 Test parameters / Schedule Flow Valve / Safety fail Position Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator Number (Coord.) Type $jigg Class cory tion Pos. Tgst - Test Tgit Tgst R marks HV-5537 M1-0301 BF/A0 48 2 A A C LTJ/T5 MT/C5 FC/C5 PIT / Contaiment Isolation 2 (E-2) (8) 2VR M2-0301 (0-2) HV-5538 M1-0301 SF/A0 48 2 A A C LTJ/T5 MT/C5 FC/C5 PIT / Containment Isolation 2 (F-3) (8) 2VR M2-0301 (E-3) HV-5539 M1-0301 BF/A0 48 2 A A C LTJ/T5 MT/C5 FC/C5 PIT / Containment isolation 2 (E-3) (8) 2YR M2-0301 (D-3) HV-5548 M1-0301 Br/A0 18 2 A A C LTJ/T5 MT/Q FC/Q PIT / Contaiment Isolation (F-3) 2VR M2-0301 .(E-4) HV-5549 M1-0301 Br/A0 18 2 A A C LTJ/T5 MT/Q FC/Q PIT / Contaiment isolation (E-3) 2YR M2-0301 (0-4) Containnelt Hydrocen Purce HV-5540 M1-0301-BF/MO 12 2 A A C LTJ/T5 MT/C5 N/A PIT / Contaiment isolation 2 (C-2) (8) 2VR M2-0301 (B-2) 1: 1 Rev. 2 April 30, 1993 - _. _ _ -.. _ _. -. _ _. _ _... - - - -. -. ~. _. _. _. _ -.. - - - - - _ _..,. -- s...- .. _.., - - -. -. _ - - - - - ~ _
COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 17 - MISC. CONTAINMENT ISOLATION VALVES (1) PAGE 11 OF 12 Test Parameters / Schedule Flow . Valve / Safety Fail Position Valve Diagram Actuator Code Cate-Func-Func. Leak Exercise Safe Indicator Nifnber (Coord.) Type SA Class aory tion _ Pos. ' Test Test J_egl Test Rcmarks 'HV-5541 M1-0301-BF/MO 12 2 A A C LTJ/T5 MT/CS N/A plt / Containment Isolation 2 (D-2) (8) 2VR M2-0301 (C-2) HV-5542 M1-0301 BF/MO 12 2 A A C LTJ/T5 MT/CS N/A PIT / Contaiment Isolation 2 .(C-4) (8) 2VR M2-0301 -(B-4) HV-5543 M1-0301 BF/MO 12 2 A A C LTJ/TS MT/CS N/A PIT / Containment isolation 2-(D-4) (8) 2YR M2-0301 (C-4) HV-5562 M1-0301 BF/MO 12 2 A A C LTJ/T5 MT/CS N/A PIT / Containment Isolation 2 (D-2) (8) 2YR M2-0301 (C-2) HV-5563 M1-0301 BF/MO '12 2 A A C LTJ/TS MT/C5 N/A PIT / Containment Isolation 2 (D-4). (8) 2YR M2-0301 (E-4) Liavid Waste Processina i LCV-1003 M1-0264 GL/A0 3 2 A A C LTJ/IS MT/Q FC/Q PIT / Contaiment Isolation (G-2) 2VR M2-0264 (G-2) L t Rev. 2 ~ April 30, 1993 t , - ~.. _,. ~, -. -.. - - - -,.,. ~.. ~..,,. - ~.... ...-.,,.,,--.~-.-,,-mr-,~,,--n-,-,~,-- ,,.. ---,., n -n .. - -. ~,. -,.,, -;, a -,,, - -,,. -.,,, -. - -, - -. ~
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CO MNCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 17 - MISC. CONTAINMENT ISOLATION VALVES NOTES 8. HV-5536, -5537, -5538. -5539, Contaitinent Purge Isolation Valves and HV-5540, -5541, -5542, -5543, -5562, -5563, Hydrogen Purge isolation Valves 2, are full-stroke exercised at cold shutdowns. These valves canrot be full or part-stroke exercised during plant operation because they have not been denonstrated tapable of closing during a LOCA or steam line break accident. Consequently, Technical Specification 3.6.1.7 requires these valves to be locked closed during plant operation to ensure that excessive quantities of radioactive materials will not be released via the Contairenent Ventilation Syste=n. i f I-l l l l l: Rev. 2 Apri1 30, 1993 ,-,__..-_.___...--.:...,.-..-....-...-,..._.--..._._,,...-..,_.___..,_2__.._..
CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A RELIEF REQUEST NO. P1 SYSTEM Diesel Generator Auxiliaries PUMP NUMBER CPI-DOAPFT-01 CP1-DOAPFT-02 CP1-00APFT-03 CP1-DOAPFT-04 CP2-DOAPFT-01 CP2-00APFT-02 CP2-DOAPFT-03 CP2-DOAPFT-04 CLASS 3 DESCRIPTION Diesel Generator Fuel Oil Transfer TEST REQUIREMENT -0M Part 6, para. 6.1, " Acceptance Criteria" -0M Part 6, Table 3b, " Ranges for Test Parameters" REFERENCES 1. Zudans, John J. " Introduction to ASME/ ANSI OMa-1988, Part 6: Inservice Testing of Pumps in Light-Water Reactor Power Plants and Technical Differences Between Part 6 and ASME Section XI, Subsection IWP." Proceedinas of the Symposium on Inservice Testino of Pumps and Valves. Washington, DC, August 1-3, 1989, pp. 25-58. 2. Sage, Lawrence. " Introduction to ASME/ ANSI OMa-1988, Part 6: Basis of the New Vibration Measurement Criteria and Requirements of Part 6." Proceedinas of the Symposium on Inservice Testina of Pumps and Valves. Washington, DC, August 1-3, 1989, pp. 59-74. 3. International Standards Organization Standard: " Mechanical Vibration of Machines with Operating Speeds from 10 to 200 rev/s - Basis for Specifying Evaluation Standards," 150 2372, First Edition - 1974-11-01. BASIS FOR RELIEF Unlike earlier editions of ASME Section XI, OM Part 6 emphasizes the use of bearing vibration measurements as the primary indicator of pump degradation and places less emphasis on hydraulic measurements. Further, OM Part 6 introduces the classification of pumps by type. According to References 1 and 2, pump classification is introduced in recognition of the fact that the quality of vibration measurements varies among pump types. By classifying pumps, different test requirements and acceptance criteria can be specified depending on type. For example, vertical line shaft pump bearings are generally inaccessible A-2 April 30, 1993 L
t CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A BASIS FOR RELIEF for vibration monitoring. So to compensate, OM i (continued) Part 6 imposes more stringent hydraulic acceptance criteria for these pumps and additionally requires i that vibration monitoring be done on the driver i bearings. Another pump type which incurs a " penalty" in hydraulic acceptance criteria in OM Part 6 is reciprocating positive displacement pumps. Reciprocating pumps are characterized by pulsating flow and high, oscillating inertia forces due to i the back and forth motion.of the pressure producing members. Therefore, diagnosing the mechanical condition of reciprocating pumps using vibration measurements is somewhat difficult and to compensate, OM Part 6 specifies a reduced range of hydraulic acceptance criteria for these pumps. Throughout OM Part 6 the terms " positive displacement pump" and " reciprocating pump" are used interchangeably. However, from Reference 2 it is clear that the pump type being addressed is the reciprocating variety of positive displacement pumps. Unfortunately, OM Part 6 ignores the other variety of positive displacement pumps, rotary pumps, and in doing so seems to apply the test requirements and acceptance criteria intended for reciprocating pumps to all positive displacement pumps. The Fuel Oil Transfer Pumps are rotary positive displacement pumps which do not share the inherent difficulties and limitations of bearing l vibration diagnostics which reciprocating pumps 4 experience. On the contrary, these low inertia, j untimed multiple-rotor screw pumps are characterized by low mechanical vibration, pulsation-free axial flow and bearing loadings 4 which do not vary through the pumping cycle. The bearings are quite accessible as the pump bores themselves effectively form continuous hydrodynamic fluid film bearings along the. entire length of-the j rotors. The mechanical condition of screw pumps r can be well understood through vibration monitoring. Reference 2 discusses the pump classification methodology used by the O&M Task Group on Vibration 1 Monitoring in preparing OM Part 6. That task group drew heavily.on guidance from Reference 3 in classifying pump types. Of the six classes of pumps recognized in the ISO standard, the group' determined that most pumps in nuclear power plant 'l applications fell into one of two 150 classes: Class'lll or Class V. The primary difference i A-3 April 30,'1993
i CPSES UNIT 1 f, 2 INSERVICE TESTING PLAN APPENDIX A BASIS FOR RELIEF between these classes'is that Class III comprises (continued) rotating machines whereas Class V comprises reciprocating machines. These ISO classifications were translated into DM Part 6 as two major pump F types: centrifugal and reciprocating positive displacement. (Note that vertical line shaft pumps are a special case of centrifugal pumps.) The subject screw type pumps were not specifically considered for classification by the task group. Nonetheless, they are inadvertently classified with reciprocating pumps in OM Part 6 due to the use of the general term " positive displacement". The Fuel 011 Transfer Pumps are most closely 150 Class III pumps and should therefore be subject to the applicable requirements and criteria for centrifugal pumps in OM Part 6. SUBSTITUTE TEST For the purpose of determining the Acceptable Range, Alert Range and Required Action Range for Fuel Oil Transfer Pump flow rate (Q), the ranges specified in OM Part 6, Table 3b for centrifugal pump flow rate shall be used. For the purpose of determining the Acceptable Range, Alert Range and Required Action Range for Fuel Oil Transfer Pump discharge pressure (P), the ranges specified in OM Part 6. Table 3b for centrifugal pump differential pressure shall be used. i for the purpose of determining the Acceptable Range, Alert Range and Required Action Range for t Fuel Oil Transfer Pump vibration (V), the ranges specified in OM Part 6, Table 3a-for centrifugal pump vibration shall be used. l For the purpose of making Fuel Oil Transfer Pump f vibration measurements, the requirements of } OM Part 6, para. 4.6.4(a) shall apply. NRC APPROVAL STATUS Approved. Reference safety evaluation dated January 2 20, 1993 for Unit 1. Reference NUREG-0797, SER j Supplement 26 for Unit 2. } i i F l l l A-4 Rev. 2 April 30, 1993
CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A RELIEF REQUEST NO. V1 SYSTEM (See VALVE NUMBER) VALVE NUMBER Main Steam 2MS-0021 2MS-0022 2MS-0023 2MS-0024 2MS-0025 2MS-0058 2MS-0059 2MS-0060 2MS-0061 2MS-0062 2MS-0093 2MS-0094 2MS-0095 2MS-0096 2MS-0097 2MS-0129 2MS-0130 2MS-0131 2MS-0132 2MS-0133 Reactor Coolant 2-8010A 2-8010B 2-8010C CATEGORY C CLASS 2 (Main Steam); 1 (Reactor Coolant) DESCRIPTION Main Steam Safety Valves; Pressurizer Safety Valves TEST REQUIREMENT -0M Part 1, para. 7.2, " Testing After Installation Prior to Initial Electric Power Generation" (General requirement) -0M Part 1, para. 7.2.1.1 (Class 1 Safety Valves): "Within 6 months prior to initial fuel loading, each valve shall have its set pressure verified. Set pressure verification shall be determined by pressurizing the system up to the valve set pressure and opening the valve, or the valve may be tested at or below normal system operating pressures with an assist device." -0M Part 1, para. 7.2.2.1.a (Main Steam Safety Valves): "After system heatup, but prior.to initial reactor criticality, each valve shall be subjected to the following tests. 1. Set pressure verification shall be determined by pressurizing the system up to the valve set pressure and opening the vaive, or the valve may be tested at or below normal system operating pressure with an assist device. 2. Compliance with the Owner's seat tightness criteria shall be verified." BASIS FOR RELIEF The primary intent of the subject Code paragraphs is to require testing of Class 1 (Pressurizer) and Main Steam Safety Valves shortly before a Pressurized Water Reactor plant is initially started up. This requirement is reasonable when one considers the safety significance of these valves and the fact that years may elapse between A-5 April 30, 1993
CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A BASIS FOR RELIEF the manufacturer's shop test and the time the (continued) valves are first placed in service. However, the Code also seems to imply that the required testing, for this specific instance only, should be done with the valves in-place. While in-place testing may apparently offer a convenience in that valve removal and reinstallation is averted, removal of the valves from the system for testing (at a testing lab), can yield equally valid test results and offer some distinct advantages. In particular, valve maintenance and adjustment can be accomplished more easily in the testing lab environment. For example, the Pressurizer and Main Steam Safety Valves are known to experience seat leakage after cycling. After set pressure verification the valves often must be disassembled (while retaining spring compression) so that the disc insert and nozzle seating surfaces can be lapped. If the set pressure verification was performed in-place, the subsequent seat' leakage repairs would entail cooldown and depressurization of the Reactor Coolant and Main Steam Systems. Following valve repair and reassembly the. systems would then have to be heated back up and repressurized to conduct a valve seat leakage retest. (Recall that OM Part I requires seat leakage testing to be done under the same temperature conditions and using the same fluid media as for the set pressure verification.) Pressurizer and Main Steam Safety Vahre testing and maintenance can be performed at a testing lab, on the other hand, and thereby eliminate the need to cycle the entire reactor plant. The test lab facilities allow the exact operating conditions (fluid media, temperature stability'and ambient temperature) of the valves to be simulated for testing and provide easy access to the valves should any maintenance be required. Actual set pressure on steam can be verified at a testing lab without utilizing an assist device. The additional activities associated with testing the valves at a lab-such as valve removal, shipping and reinstallation car be accomplished safely by applying the procedural and quality controls normally required for such work. The valves are rigged, boxed, and shipped in the vertical position and.are receipt inspected both at the testing lab and upon their return to the plant. Reinstallation involves the routine closure of gasketed joints which is verified subsequently through inservice leakage testing. A-6 April 30, 1993
i CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A BASIS FOR RELIEF Based on the above, a valid OM Part 1 performance _ (continued) test of the Pressurizer and Main Steam Safety Valves can be had through either in-place testing or testing in a lab. SUBSTITUTE TEST For the purpose of accomplishing Main Steam and Pressurizer Safety Valve testing prior to initial electric power generation, the following requirements will apply: ~ 1. Within 6 months of initial fuel loading, each Pressurizer Safety Valve shall have its set pressure verified. 2. Either before or after installation and within 6 months prior to initial reactor criticality, each Main Steam Safety Valve shall be subjected to the following tests; i a) set pressure verification b) compliance with the Owner's seat tightness criteria shall be verified. NRC APPROVAL STATUS Approved. Reference NUREG-0797, Supplement 25 for 2 Unit 2. This Relief Request is not applicable to Unit 1. b i i .l i ? l i A-/ Rev. 2 i April 30, 1993
r CPSES UNIT 1 & 2 INSERVICE TESTING PLAN l APPENDIX A RELIEF REQUEST NO. V2 i e SYSTEM (See VALVE NUMBER) VALVE NUMBER Auxiliary Feedwater i 1AF-0215/0216 1AF-0217/0218 1AF-0219/0220 1AF-0221/0222 1AF-0223/0224 1AF-0226/0227 I 1AF-0228/0229 1AF-0230/0231 1AF-0232/0233 1AF-0234/0235 l 2AF-0221/0222 2AF-0223/0224 2AF-0226/0227 [ 2AF-0228/0229 2AF-0230/0231 2AF-0232/0233 2AF-0234/0235 2AF-0236/0291 2AF-0237/0238 2AF-0239/0240 i Component Coolina Water 1CC-1079/1080 1CC-1081/1082 l 2CC-1091/1092 2CC-1093/1094 Instrument Air (Control Room HVAC) 1C1-0644/0645 1C1-0646/0647 i Diesel Generator Auxiliaries 1D0-0058/0063 100-0059/0062 1 1D0-0060/0065 100-0061/0064 2D0-0058/0074 200-0059/0075 l 200-0060/00,6 200-0061/0077 l Main Steam 1MS-0680/0681 1MS-0682/0683 IMS-0684/0685 1MS-0686/0687 2MS-0663/0664 2MS-0665/0666 2MS-0667/0668 2MS-0669/0670 l l Safety Iniettion (Reactor Coolant) { 151-0166/0167 151-0168/0169 l 2SI-0166/0167 251-0168/0169 CATEGORY A/C, C CLASS 3 i A-8 . April 30, 1993
CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A DESCRIPTION These check valves form the boundary between the non-safety Instrument Air or Nitrogen supply systems and the safety-grade accumulator and i receiver tanks. The tanks provide an emergency air or nitrogen supply to certain safety-related components. The check valves are required to close upon failure of the air or nitrogen supply system in order to contain the compressed gas in the tanks. 1 TEST REQUIREMENT -0M Part 10, para. 4.3.2, " Exercising Tests for Check Valves". BASIS FOR RELIEF Each valve listed above is one of two check valves in series at the inlet to a safety-grade accumulator or receiver tank. In each case, only one check valve is required in order to meet the safety class interface criteria of ANSI N18.2a-1975. However, two check valves are provided for added reliability, not for redundancy. The safety-a related components served by the accumulator and receiver tanks are redundant to other similar components which have their own dedicated safety-grade air supplies. As long as one of the check valves in the pair is capable of closure, then the safety analysis assumptions for the pair of check valves are met. Some of the check valve pairs do not have provisions for testing each valve individually. However, the closure capability of each pair of check valves can be verified. SUBSTITUTE TEST Each pair of series check valves will be exercise tested at the required frequency by some positive means-to verify the closure capability of at least one of the valves. No additional exercise testing will be performed unless there is an indication that the closure capability of the pair of valves ( is questionable In that case, both valves will be declared inoperable and not returned to service until they are either repaired or replaced. i NRC APPROVAL STATUS Approved. Reference safety evaluation dated 2 ) January 29, 1993 for Unit 1. Reference NUREG-0797, SER Supplement 26 for Unit 2. i i t t A-9 Rev. 2 April 30, 1993 i
i i CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A RELIEF REQUEST t40. V3 SYSTEM (See VALVE NUMBER) j VALVE NUMBER Auxiliary Feedwater 1AF-0215/0216 1AF-0217/0218 1AF-0219/0220 i 1AF-0221/0222 1AF-0223/0224 1AF-0226/0227 + 1AF-0228/0229 1AF-0230/0231 1AF-0232/0233 l 1AF-0234/0235 2AF-0221/0222 2AF-0223/0224 2AF-0226/0227 2AF-0228/0229 2AF-0230/0231 2AF-0232/0233 2AF-0234/0235 2AF-0236/0291 2AF-0237/0238 i 2AF-0239/0240 Component Coolina Water 1CC-1079/1080 1CC-1081/1082 2CC-1091/1092 ~2CC-1093/1094 Instrument Air (Control Room HVAC) 1C1-0644/0645 101-0646/0647 Main Steam IMS-0680/0681 IMS-0682/0683 IMS-0684/0685 1MS-0686/0687 l 1 2MS-0663/0664 2MS-0665/0666 i 2MS-0667/0668 2MS-0669/0670 i Safety injection (Peactor Coolant)- f 151-0166/0167 151-0168/0169 251-0166/0167 251-0168/0169 CATEGORY A/C CLASS 3 i DESCRIPTION These check valves form the. boundary between the non-safety Instrument Air or Nitrogen supply systems and the safety-grade accumulator and ) receiver tanks. The tanks provide an emergency air or nitrogen supply to certain safety-related components. The check valves are required to close upon failure of.the air or nitrogen supply system ( in_ order.to contain the compressed gas in the tanks. TEST REQUIREMENT -0M Part 10, para. 4.2.2, " Valve Seat Leakage Rate Test". A-10 April 30, 1993
) CPSES UNIT 1 & 2= INSERVICE TESTING PLAN APPENDIX A BASIS FOR RELIEF Each valve listed above is one of two check valves f in series at the inlet to a safety-grade accumulator or receiver tank. In each case, only one check valve is required in order to meet the safety class interface criteria of ANSI N18.2a-1975. However, two check valves are provided for [ added reliability, not for redundancy. The safety-related components served by the accumulator and receiver tanks are redundant to other similar components which have their own dedicated safety-grade air supplies. As long as one of the check valves in the pair is capable of meeting its leakage rate criteria, then the safety analysis assumptions for the pair of check valves are met. Some of the check valve pairs do not have provisions for testing each valve individually. l Howeter, the leakage rate of each pair of check valves can be verified. SUBSTITUTE TEST Each pair of series check valves will be leakage rate tested at the required frequency to verify i acceptable seat leak-tightness of at least one of the valves. No additional leakage rate testing l will be performed unless there is an indication that the seat leak-tightness of the pair of valves is questionable. In that case, both valves will be i declared inoperable and not returned to service until they are either repaired or replaced. NRC APPROVAL STATUS Approved. Reference safety evaluation dated 2 January 29, 1993 for Unit 1. Reference NUREG-0797. SER Supplement 26 for Unit 2. l i ) i e } t i i A-11' Rev. 2 April 30, 1993
CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A RELIEF REQUEST NO. V4 1 SYSTEM Containment Spray i VALVE NUMBER 1CT-0142 1CT-0145 1CT-0148 1CT-0149 2CT-0142 2CT-0145 2CT-0148 2CT-0149 CATEGORY A/C, C CLASS 2 OESCRIPTION -Containment Spray Header Check Valves (CT-0142, CT-0145) j -Containment Spray Pump Suction Check Valves from the Recirculation Sumps-(CT-0148, CT-0149) l i TEST REQUIREMENT -0M Part 10, para. 4.3.2.4(c), "... disassembly every refueling outage to verify operability of check valves may be used." BASIS FOR RELIEF The subject valves are burdensome to disassemble and inspect every refueling outage. A significant amount of borated and potentially contaminated water must be drained from the system and disposed i of to accomplish the disassemblies.
- Further, disassembly of these large valves diverts considerable manpower away from the refueling I
activity. l The valves are all of the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions including valve orientation. No wear related degradation is anticipated for these valves because they are all located in portions of the system l which do not experience flow during normal operation. Due to the similarities between these i valves, the condition of the valve inspected during the Substitute Test will be representative of the other valves in the group. SUBSTITUTE TEST Verify operability of the subject check valves through disassembly and inspection of one of the t four valves in each unit at each refueling outage for that unit. The disassembled valve will be verified to be capable of full-stroking and it will be verified that the internals of the valve are structurally sound (no loose or corroded parts). Also, the disk will be manually exercised. i i A-12 April 30,1993
CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A SUBSTITUTE TEST A different valve from each unit will be (continued) disassembled, inspected and manually full-stroke exercised at each successive refueling outage until i the entire group for that unit has been tested. If the disassembled valve is not capable of being full-stroke exercised or there is binding or l failure of valve internals, the remaining valves in the group for that unit will also be disassembled, inspected, and manually full-stroke exercised during the same outage. Once this is completed, the sequence of disassembly will be repeated unless extension of the interval can be justified. NRC APPROVAL STATUS This Relief Request is pre-approved by Generic 2 Letter 89-04, Attachment 1, Position 2. (Also reference safety evaluation dated January 29, 1993 for Unit 1 and NUREG-0797, SER Supplement 26 for i Unit 2.) t ) i l I i i i i i t f t i e f A-12 Rev. 2 April 30, 1993 l i i
CPSES UNIT 1 & 2 INSERVICE TESTING PLAN [ APPENDIX A RELIEF REQUEST NO. V5 SYSTEM Chemical and Volume Control VALVE NUMBER 1CS-8350A/1CS-8367A ICS-8350B/1CS-8367B 1CS-8350C/1CS-8367C 1CS-83500/1CS-8367D 1-8378A/1-8378B 1-8379A/1-83798 2CS-8350A/2CS-8367A 2CS-83508/2CS-83678 l 2CS-8350C/2CS-8367C 2CS-8350D/2CS-8367D 2-8378A/2-83788 2-8379A/2-8379B CATEGORY C i CLASS 1 DESCRIPTION RCP Seal Injection Lines and Charging / Alternate Charging Lines / Reactor Coolant Pressure Boundary Isolation Check Valves l TEST REQUIREMENT -0M Part 10, para. 4.3.2, " Exercising Tests for i Check Valves". BASIS FOR RELIEF Each pair of valves listed above constitutes two check valves in series at a CVCS/RCS interface. Two Safety Class 1 check valves are provided in accordance with the safety class interface criteria of ANSI N18.2a-1975 in order to isolate the interfacing Class 2 system. Either of the check valves provided can perform this function. The system design, however, does not include the test connections necessary to close exercise test each of the series check valves individually. The system design does include sufficient test conr.ections to verify the check function of each pair of valves (i.e., verification that at least i one of the valves will close). l Offsetting the inability to separately test each series check valve are the following design features: i 1. Both of the Class 1 check valves at each l interface lie within the secondary shield wall inside containment and thus are afforded ( protection from dynamic events and missiles generated elsewhere in containment. 2. The interfacing portions of the CVCS system i are designed and constructed as Safety Class i 2 and are seismically qualified. A-14 April 30, 1993-i
r.' CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A BASIS FOR RELIEF 3. The interfacing portions of the CVCS system (continued) are designea for pressures greater than or equal to RCS pressure. 4. Upstream of each of the subject check valve pairs, the interfacing CVCS lines contain a separate Containment Isolation check valve and power operated valve which are close exercise tested individually. SUBSTITUTE TEST Each pair of series check valves will be exercise tested at the required frequency by some positive means to verify the closure capability of at least one of the valves. No additional exercise testing will be performed unless there is an indication that the closure capability of the pair of valves is questionable, in that cPre, both valves will be declared inoperable and not returned to service until they are eithor repaired or replaced. NRC APPROVAL STATUS Denied. The substitute testing described above may 2 continue to be implemented until startup from the-third refueling outage for Unit 1 and until startup from the first refueling outage for Unit 2. However, by July 1, 1993 either this relief request must be revised and. resubmitted for NRC staff approval or a test method must be developed for verifying each valve's closed function ano the relief request withdrawn. Reference safety evaluation dated January 29, 1993 for Unit 1. Reference NUREG-0797, SER Supplement 26 for Unit 2. t A-15 Fev. 2 April 30, 1993
CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A RELIEF REQUEST NO. V6 SYSTEM Demineralized and Reactor Makeup Water ' VALVE NUMBER 10D-0006/100-0065 10D-0064/100-0066 200-0002/200-0006 200-0008/20D-0009 CATEGORY C CLASS 3 DESCRIPTION These check valve pairs form the boundary between the non-safety Demineralized Water System or Waste Processing System and the safety-grade Reactor Makeup Water Storage Tank (RMWST) to preclude draining the RMWST upon failure of the non-safety systems. TEST REQUIREMENT OM Part 10, para. 4.3.2, " Exercising Tests for Check Valves". BASIS FOR RELIEF Each pair of valves listed above constitutes two check valves in series at a Class 3/Non-Safety piping interface. Two Safety Class 3 cneck valves are provided in accordance with the safety class interface criteria of ANSI N18.2a-1975 in order to isolate the interfacing non-safety system. Either of the check valves provided can perform this function. The system design, however, does not include the test connections necessary to close exercise test each of the series. check valves individually. The system design does ir.clude sufficient test connections to verify the cneck function of each pair of valves (i.e., verification that at least one of the valves will close). Offsetting the inability to separately test cach series check valve is the availab11ity of the other unit's RMWST. Each unit's RMWST normally provides inventory for niakeup to various safety-related syLtems in that unit "ia ' r ' actor Makeup Water Pumps. The two unit * - sr Makeup Water Pumps, however, are cross-ct aaJ (but normally isolated) at their suctions, crscharges and miniflow lines such that either the Unit 1 RMWST or the Unit 2 RMWST can be aligned to sipply any of the Reactor Makeup Water users in either. unit. In the unlikely event that one unit's tark contents are. lost through & makeup line failure in combination with the failure of both makeup lina check valves to close 'the other unit' ank wob be unaffected. A-16 April 30, 1993 t..
l CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A SUBSTITUTE TEST Each' pair of series check valves will be exercise tested at the required frequency by some positive means to verify the closure capability of at least One of the valves. No additional exercise testing will be performeo unless there is an indication that the closure capability of the pair of valves is questionable. In that case, both valves will be i declared inoperable and not returned to service until they are either repaired or replaced. NRC APPROVAL STATUS Approved. Reference safety evaluation dated l2 l January 29, 1993 for Unit 1. Reference NUREG-0797. SER Supplement 26 for Unit 2. l i i t i 1 t h A-17 R.c ^ At. : 30, 1993
CPSES UNIT 1 & 2 INSERVICE TESTING PLAN APPENDIX A RELIEF REQUEST NO. V7 SYSTEM Safety Injection VALVE NUMBER 1-8956A 1-8956B 1-8956C 1-8956D 2-8956A 2-8956B 2-8956C 2-8956D CATEGORY A/C CLASS 1 DESCRIPTION Check valves in the ECCS flowpath from the Safety Injection Accumulators to the Reactor Coolant System / Reactor Coolant System pressur e isolation valves. TEST REQUIREMENT -0M Part 10, para. 4.3.2.4(c). ".. disassembly every refueling outage to verify operability of check valves may be used." BASIS FOR RELIEF The subject valves are burdensome to disassemble and inspect every refueling outage. Because of their location below the RCS cold leg elevations and the fact that no positive isolation provisions exist between these valves and the RCS, the RCS must be maintained in a reduced inventory condition for the duration of the valve disassemblies. Also, the main Residual Heat Removal System flowpaths (for which these check valves form a boundary) and portions of the Safety Injection System must be removed from service and drained to facilitate the valve disassemblies. Draining of these systems produces significant amounts of liquid radwaste i which must subsequently be processed. The valve disassembly activity itself can result in significant personnel radiation exposures depending on fuel performance and due to the valves' close proximity to the reactor coolant loops.
- Further, i
disassembly of these large valves diverts considerable manpower away from the refueling activity. The valvcs are all of the same design (manufacturer, size, model number, and materials of construction) and have thE same service conditions including valve orientation. No wear related degradation is anticipated for these valves because 5 they are all located in p7rtions of the system which do not experience flow during normal operation. Due to.the similarities between these valves, the condition of the valve inspected during the Substitute Test will be representative of the other valves in the group. A-18 April 30, 1993
CPSES UNIT 1 & 2 ' INSERVICE TESTING PLAN U APPENDIX A SUBSTITUTE TEST Verify operability of the subject check valves l through disassembly and inspection of one of the four valves in each unit at each refueling outage for that unit. The disassembled-valve will be verified to be capable of full-stroking and it will be verified that the internals of the valve are structurally sound (no loose or corroded parts), f Also, the disk will be manually exercised. l A different valve from each unit will be l disassembled, inspected, and manually full-stroke-exercised at each successive refueling outage until the entire group for that unit has been tested. If the disassembled valve is not e!pable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves'in the group for that ur,it will also be disassembled, inspected, and manually full-stroke exercised during the same outage. Once this is completed, the sequence of disassembly will be repeated unless extension of the interval can be justified. i NRC APPROVAL STATUS This Relief Request is pre-approved by Generic 2 Letter 89-04, Attachment 1, Position 2. (Also E reference safety evaluation dated January-29, 1993 for Unit 1 and NUREG-0797, SER Supplement 26 for Unit 2.) A-19 Rev. 2 April 30, 1993 i
= l c l. E i COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE TESTING' PLAN FOR PUMPS AND VALVES-t FIRST INTERVAL EFFECTIVE PAGE LISTING PAGE 1 0F 5 'l l BELOW IS A LEGEND FOR THE EFFECTIVE PAGE LISTING: Revision 0 Submitted July 1, 1992 { Revision 1 February 3, 1993 l Revision 2 April 30, 1993 j l l P_a_qq Revision /Date Cover Sheet Re. vision 2 l 1 (Table of Contents) April 30, 1993 ) a 1-1 Revision 2 i 1-2 Revision 2 -l 1-3 Revision 2 j l 1-4 . April 30, 1993 2-1 Revision 0 2-2 Revision 0 2-3 . Revision'0' 2-4 Revision 0 'l Table 0. Page 1 of 4 Revision 0 l Table 0, Page 2 of 4 Revision 0 Table 0. Page 3 of 4 Revision 2 Table 0, Page 4 of 4 Revision 0: Table 0, Notes, Page 1 Revision 2 3-1 Revision 0 l 3-2 Revision 0 3-3 Revision 0 3-4 Revision 0 3-5 Revision 0-l Valve Table Index, Page 1 of 3 Revision 2 Valve Table Index, Page 2 of 3 April 30, 1993 Valve Table Index, Page 3 of 3 April 30, 1993 Table 1, Page 1 of 11 Revision 0 Table 1, Page 2 of 11 Revision 0 l Table 1, Page 3 of 11 Revision 0 l Table 1 Page 4 of 11. Revision 0 EPL-1 April 30, 1993 l
j i ] 1 COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES FIRST INTERVAL- 'l EFFECTIVE PAGE LISTING ll PAGE 2 0F 5 i Table 1, Page 5.of 11 Revision 0 l Table 1 Page 6.of 11 Revision 0-Table 1, Page 7 of 11 Revision 0 Table 1, Page 8 of 11 Revision 0 Table 1, Page 9 of 11 Revision 2 { Table 1, Page 10 of 11 Revision 0 Table 1, Page 11 of 11 Revision 0-
- l Table 1, Notes,-Page 1
. Revision 2 'j Table 2, Page 1 of 10 Revision 0 'j Table 2, Page 2 of 10 Revision 0 Table 2, Page 3 of 10 Revision 0 Table 2, Page~4 of~1'O April 30, 1993 Table 2, Page 5 of 10 Revision.2 y Table 2, Page 6 of 10 Revision 2 Table 2, Page 7 of 10 Revision 0 R Table 2, Page 8 of 10-Revision 0 Table 2, Page 9 of 10 Revision.0 'l Table 2, Page 10 of 10 Revision 0 Table 2, Notes, Page 1 Revision-0 Table 2, Notes, Page 2 Revision 0 1 Table 3, Page 1 of 1 ' Revision 2 i Table 4, Page 1 of 12 Revision 1 i Table 4, Page 2 of 12 Revision 0 Table 4, Page 3 of 12 Revision 0 Table 4, Page 4 of 12 Revision 0 l Table 4, Page 5 of 12 Revision 0 Table 4, Page 6 of 12 Revision 2 -l Table 4, Page 7 of 12 Revision'0 l Table 4, Page 8 of 12 Revision 0 i Table 4, Page 9 of 12 Revision 2 Table 4, Page~10 of 12 Revision 0 Table 4, Page 11 of 12 Revision 2 .i Table 4. Page 12 of 12 Revision 0 Table 4, Notes, Page 1 Revision 0 Table 4 Notes, Page 2 Revision 0 Table 4. Notes, Page 3 Revision 2 i Table 4, Notes, Page 4 Revision 2 f . Table 5, Page 1 of 6 Revision 0 Table 5; Page 2 of 6 Revision 0 Table-5,.Page 3 of 6 Revision 0 Table 5, Page 4 of 6 Revision 0" j EPL-2 April 30, 1993 y 'i I ..m._
1 COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 l INSERVICE TESTING PLAN FOR PUMPS AND VALVES i FIRST INTERVAL. EFFECTIVE PAGE LISTING l PAGE 3 0F 5 Table 5, Page 5 of 6 Revision 0 1 Table 5, Page 6 of 6 Revision 0 Table 5, Notes, Page 1 Revision 0 Table 6, Page 1 of 2 Revision 0 -{ Table 6, Page 2 of 2 Revision 0 i Table 7, Page 1 of 4 Revision 0 Table 7, Page 2 of 4 April 30, 1993 i Table 7, Page 3 of 4 April 30. 1993 Table 7, Page 4 of 4 April 30, 1993 j Table 7, Notes, Page 1 Revision 0 Table 8, Page 1 of 6 Revision 0 Table 8, Page 2 of 6 Revision 0 Table 8, Page 3 of 6-Revision 0 l Table 8, Page 4 of 6 Revision 0 Table 8, Page 5 of 6 Revision 0 i Table 8, Page 6 of 6 Revision 0 Table 8 Notes, Page 1 April 30, 1993 j Table 9, Page 1 of 12 Revision 2 Table 9, Page 2 of 12 Revision 2 Table 9, Page 3 of 12 Revision 2 .i Table 9,.Page 4 of 12 Revision 2 Table 9, Page 5 of 12 April 30, 1993 Table 9, Page 6 of 12 April 30, 1993 3 Table 9, Page 7 of 12 April 30, 1993 Table 9, Page 8 of 12 April 30,-1993 Table 9, Page 9 of 12 April 30, 1993-Table 9, Page 10 of 12 April 30, 1993 i Table 9, Page 11 of 12 April 30, 1993 Table 9, Page 12 of 12 April 30, 1993-Table 9, Notes, Page 1 Revision 0 Table 10, Page 1 of 3 Revision 0 Table 10, Page 2 of 3 Revision 0 ' Table 10 Page 3 of 3 Revision 0 Table 10, Notes, Page 1 Revision 0 j Table 11, Page 1 of 3 Revision 0 Table 11, Page 2 of 3 Revision 0 Table 11, Page 3 of 3 Revision'2 Table 11, Notes, Page 1 Revision 2 I EPL-3 April 30, 1993 .j .t
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i COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES l FIRST INTERVAL EFFECTIVE PAGE LISTING -i PAGE 4 0F 5 i Table 12, Page 1 of 2 Revision 0 i Table 12, Page 2 of 2 Revision 0 -l f Table 13, Page 1 of 17 Revision 0. ] Table 13, Page 2 of 17 Revision 2 Table 12, Page 3 of 17 Revision 0 Table 13, Page 4 of 17 Revision 0 i Table 13, Page 5 of 17 Rev.ision 0 -Table 13, Page 6 of 17 Revision'2 i Table 13, Page 7 of 17 Revision 2-j Table 13 Page 8 of 17 Revision 0 j Table 13, Page 9 of 17 Revision 0 Table 13,' Page 10 of 17 Revision 2 i Table 13, Page 11 of 17 Revision 2 Table 13, Page 12 of 17 Revision 2 i Table 13. Page'13 of 17 Revision 0 Table 13, Page 14 of 17 Revision 0 Table 13, Page 15 of 17 Revision 1 Table 13, Page 16 of 17 Revision 0 l Table 13, Page 17 of 17 Revision 0 Table 13 Notes, Page 1 Revision 2 Table 13, Notes, Page 2 April 30, 1993 Table 13, Notes, Page 3 April 30, 1993 [ Table 14, Page 1 of 3 Revision 0 Table 14, Page 2 of 3 Revision 0 Table 14, Page 3 of 3 Revision 0 Table 14, Notes, Page 1 Revision 0 j Table 15, Page 1 of 1 Revision 0_ 1 Table 15, Notes, Page 1 Revision 0 Table 16, Page 1 of 2 Revision 0 Table 16, Page 2 of 2 Revision 0 'i Table 16, Notes, Page 1 Revision 0 Table.17, Page 1 of 12 Revision 2 Table 17, Page 2 of 12 Revision 2 Table 17, Page 3 of 12 Revision 0 Table 17, Page 4 of 12 Revision 0 i Table 17, Page 5 of 12 Revision 0 f Table 17,-.Page 6 of 12 . Revision 0 l Table 17, Page 7 of 12 Revision 0 j Table 17, Page 8 of 12 Revision 2 i Table 17,.Page 9 of 12 Revision 2 .l EPL-4 April 30, 1993' E_ 1
'O a. I i I COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES l FIRST INTERVAL EFFECTIVE PAGE LISTING f PAGE 5 0F 5 !.t -Table 17, Page 10 of 12 Revision 2 j Table 17, Page 11 of 12 Revision 2 j Table 17, Page 12 of 12 Revision O' I Table 17, Notes, Page 1 April 30, 1993 Table 17, Notes, Page 2 Revision 2 l A-1 Revision 0 A-2 April 30, 1993 A-3 April 30, 1993 'i A-4 Revision 2 i A-5 April 30,1993 A-6 April 30, 1993 A-7 Revision 2 A-8 April 30, 1993 A-9 __ Revision 2 A-10 April 30, 1993 A-11 Revision 2 i A-12 April 30, 1993 l A-13 Revision 2 A-14 April 30, 1993 ~ A-15 Revision 2 i A-16 April 30,'1993 A-17 Revision 2 ~ A-18 April 30, 1993 A-19 Revision 2 EPL, Page 1 of 5 April 30, 1993 EPL, Page 2 of 5 April 30, 1993 EPL, Page 3 of 5 April'30, 1993 l EPL, Page 4 of 5 April 30, 1993 i EPL, Page 5 of 5 April 30, 1993 l l 1 l t EPL-5 April 30, 1993 f e}}