ML20202E598
| ML20202E598 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/25/1997 |
| From: | Mays R, Reimer D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20202E592 | List: |
| References | |
| PROC-971125, NUDOCS 9712080087 | |
| Download: ML20202E598 (21) | |
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COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES FIRST INTERVAL l
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i i REVISION 12-4 4
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1-i Prepred By: 2 8. Ma # M M Date: //AOf7 Engineerin6 Programs'Sufervisor j Approved By:DNNMR Date:\\-25 'I7 l- Manager. Technical Support 4
- Approved By
- Mb tr Date:llIL9'7 Plant fianager
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9712090087 971125 PDR ADOCK 05000445 PM p
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s COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2
' INSERVICE TESTING PLAN FOR PUMPS AND VALVES FIRST INTERVAL
- TABLE OF CONTENTS SECTION 1.0 - GENERAL INFORMATION 1-1 1.1 - Introduction 11 1.2 - Code Edition and Addenda 1-1 1.3 - Dates of Test Interval 1-2 1.4 - Approval Status 1-2 1.5 - Reference 2 1-3 SECTION 2.0 - INSERVICE PUMP TESTING PLAN 2-1 2.1 - Pump Testing Code 2-1
- 2.2 - Scope 2-1 2.3 - Pump Testing Table Format 2-2 Table 0 - Inservice bnp Testing Plan SECTION 3.0 - INSERVICE VALVE TESTING PLAN 3-1 3.1 - Valve Testing Code 3-1
, 3.2 - Scope 3-1 3.3 - Valve Testing Table Format 3-2 3.4 - References 3-5 Table 1 - Auxiliary Feedwater Table 2 - Component Cooling Water Table 3 - Chilled Water (Safety)
Table 4 - Chemical and Volume Control Table 5 - Containment spray 1
Table 6 - Demineralized and Reactor Makeup Water Table 7 - Diesel Generator- Auxiliaries Table 8 - Feedwater Table 9 - Main Steam Table 10 - Reactor Coolant i Table 11 - Residual Heat Removal Table 12 - Spent Fuel Pool Cooling Table 13 - Safety Injectic, Table 14 - Service Water Table 15 - Ventilation (Control Room Air Conditioning)
Table 16 - Vents and Drains Table 17 - Misc. Containment Isolation Valves APPENDIX A - RELIEF REQUESTS FOR PUMPS AND VALVES A-1 COMANCHE PEAK - UNITS 1 AND 2 i November 26, 1997
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, CPSES/IST PLAN 3.0 INSERVICE VALVE TESTING PLAN 3.1 Valve Testing Code As mentioned in Section 1.0 this IST Plan has been developed to the requirements of the 1989 Edition of ASME BPVC.Section XI. Except in cases where relief has been specifically requested, the valve testing plan meets the applicable requirements of Subsection IWA and the requirements of Subsection IWV as modified by 10CFR50.55a(b)(2)(v11) regarding containment isolation valve leakage rate testing.
By reference f.om Subarticle IWV-1100. the actual valve testing requirements and rules are taken from ASME/ ANSI OM Part 10. By reference from Subarticle IWA-1600, the 1987 Edition of ASME/ ANSI OM including the 1988 Addenda was used in the preparation of this valve testing plan. (Note that IWA-1600 actually references the 1987 Addenda to OM: however, no such addenda was ever publisi.eJ. The 1988 Addenda was the first addenda to 0M to be published and was the addenda which issued Part 10 for the first time.)
By reference from OM Part 10. paragraph 4.3.1. the pressure relief device testing requirements in this plan are taken from ASME/ ANSI OM Part 1. By reference from Subarticle IWA-1600, the 1987 Edition of ASME/ ANSI OM was used in specifying pressure relief device testing requirements. (No addenda apply.)
3.2 Scope The scope of the Inservice Valve Testing Plan is derived from the requirements of OM Part 10 (paras. 1.1 and 1.2) and OM Part 1 (para.
1.1) as modified by 10CFR50.55a(f)(4). The valves selected for inclusion in this testing ple. are those active or passive ASME Class 1, 2 and 3 valves and pressure relief devices (and their actuating and position indicating systems) which are required to perform a specific function:
a) in shutting down a reactor to the cold shutdown condition, or b) in maintaining the cold shutdown condition or c) in mitigating the consequences of an accident.
Excluded from this testing plan are:
a) valves used only for operating convenience such as vent.
drain. instrument and test valves, or b) valves used only for system control, such as pressure regulating valves, or c) valves used on y for system or component maintenance.
Further, the valve actuating system test scope does not include external control and protection systems responsible for sensing plant conditions and providing sionals for valve operation.
COMANCHE PEAK - UNITS 1 AND 2 3-1 November 26, 1997
,, 'CPSES/IST PLAN
. The active valves and pressure relief devices in the scope of this
- testing plan are described in the CPSEc Final Safety Analysis Report
, (FSAR), Sections 3,9N.31 and 3.98.3.2. " Pump and Valve Operability Assurance", and are tabulated in FSAR Tables 3.9N 10 and 3.98 10.-
" Active Valves". ASME Code Class 2 and 3 pressure relief devices 8-that only protect systems / components that perform a safety function as described above are not tabulated in FSAR Tables 3.9N-10 and 3.9810. but have been included in this testing plan under Revision -
- 8. These valves will be tested oser the required test interval of 10 years commencing upcn the issuance of Revision 8. Consistent 12 with the philosophy discussed in Referenc? 1. these specific thermal relief valves ao not require the two additional valve tests following as-found set-pressure determination failures. However, if performance data indicates that more frequent testing is needed to -
assure valve function, then the testing frequency should be modified. In lieu of tests, valve replacement may be performed as' ,
an alternative to testing. This philosophy only applies to thermal-relief valves whose only function is to protect system 3/ components that have a safety function. These valves are identified in the IST-Plan by having a Safety Function Position listing of "N/A". These are the only valves in the IST plan so marked.
- The passive-valves and pressure relief devices.in the scope of this testing plan were identified by icview and are those valves and pressure relief devices which perform a nuclear safety function but are not active and for which leakage testing or position indicator
-testing is required.
A listing of the above described active and passive valves and pressure relief devices can be found in Tables 1 through 17 of this IST Plan.
3.3 Valve Testing Table Format Detailed information and testing requirements for the valves included in this IST Plan are summarized in Tables 1 through 17. A separate table has been prepared for each plant system which contains valves in the scope of the plan. The tables are arranged in alphabetical order by system name:
Auxiliary Feedwater Table 1 Component Cooling Water Table 2 Chilled Water (Safety) Table 3 Chemical and Volume Control Table 4 Containment Spray Table S COMANCHE PEAK - UNITS 1 AND 2 3-2 Rev. 12 November 26, 1997
,, CPSES/IST PLAN Demineralized and Reactor Makeup Water Table 6 Diesel Generator Auxiliaries Table 7 Feedwater Table 8 Main Steam Table 9 Reactor Coolar Table 10 Residual Heat ke.0 val Table 11 Spent Fuel Pool Cooling Table 12 Safety Injection Table 13 Service Water lable 14 Ventilation (Control Room Atr Conditiontng) Table 15 Vents and Drains Table 16 Miscellaneous Containment Isolation Valves Table 17 The guidance in References 1.5.2, 1.5.8 and 1.5.9 was used to the j- greatest extent possible in formatting the tables, Following is a j discussion of the types of information presented in the tables.
- 1. Valve Identification - Valve identification includes the valve number field and a brief description of the valve safety function (in the Remarks field). In each table, the valves are arranged in numerical order by the four digit location number which forms the root of each valve number.
See Flow Diagram M1-0200, " Mechanical Symbols and Notes", for a discussion of valve numbering conventions and abbreviations. The valve numbers shown in Tables 1 through 17 are the same numbers used on the respcctive flow diagrams to identify the valves.
For valves which exist in both Unit 1 and Unit 2 and for which the test requirements are the same, the unit designator prefixes have been dropped from the valve numbers in the tables. The valve numbers in this case should be underQod to be prefixed by "1" (or CP1) and "2" (or CP2), as appropriate. If a valve is in a cormion system, exists in one unit only, is numbered differently between units or has different test requirements between units, then the unit designator is shown.
- 2. Flow Diagram Number - The flow diagram number field indicates on which drawing the valve may be found. The flow diagram numbers are prefixed by "M1" to indicate a Unit 1 drawing and by "M2" to inaicate a Unit 2 drawing. The suffix lif any) indicates the drawing sheet number. Drawing coordinates are indicated in parentheses below the flow diagram number for ease in locating a valve.
- 3. Valve / Actuator Type - The valve / actuator type field classifies valves by style and means of actuation. See the COMANCHE PEAK - UNITS 1 AND 2 3-3 November 26, 1997
CPSES/IST PLAN
' Valve Table ladex Gt the end of this section for a listing of valve and actuator type acronyms and their meanings.
- 4. Size - The size field indicates the nominal valve size in inches,
- 5. Code Class The code class field indicates the ASME Boiler and Pressure Vessel Code. Section Ill classification for the valve.
- 6. Category - The category field indicates the cidssification of the valve according to characteristics described in OM Part 10, paragraph 1.4. See the Valve Table Index at the end of-this section for a listing of valve categories and their l meanings.
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- 7. Function - The function field indicates the manner in which a l valve acccmplishes its required safety function (s). "A" denotes an active valve and "P" denotes a passive valve with the terms defined as follows:
Active valves - valves which are required to change obturator position to accomplish their required safety function (s).
Passive valves - valves which maintain obturator position and are not required to change obturator position to accomplish their required safety function (s).
Obturator - valve closure member (disk, gate, plug, ball, ,
etc.)
- 8. Safety Function Position - The safety function position field indicates the position (open or closed) to which a valve must '
move or remain in to accomplish its required safety function (s). The open and closed positions are indicated by "0" and "C" respectively.
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COMANCHE PEAK - UNITS 1 AND 2 3-4 November 26, 1997
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CPSES/IST PLAN S
- 9. Test Parameters / Schedule - The test parameters / schedule field denotes the Code test requirements and test frequencies for valves in the IST Plan. The test parameters include leak test. exercise test, fail safe test and position indicator test. Not all test parameters are applicable to all valves.
4 Rather, the parameters to be tested for any valve are dependent on the valve / actuator type, category, and function.
Valves which have both an open and closed safety function
- position a'id for which the test requirements or frequencies die different in the two positions, have their open and closed test requirements identified separately. Test
- parameters which are not applicable to a particular valve are indicated "N/A".
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Required test parameters or test frequencies for which relief is requested are indic6ted by the specific Relief Request number (All pump and valve relief requests are contained in Appendix A of this IST Plan.) In cases where the ;erformance of a valve full-stroke exercise test is limited to cold shutdowns or refueling outages, a table footnote is provided which justifies this determination. See the Valve Table Index at the end of this section for a listing of test parameter and schedule acronyms and their meanings.
- 10. Footnotes - Footnotes containing additional valve testing information are located at the back of each system valve j table and are referenced in the tables by the footnote number in parentheses.
3.4 References 12
, 1. NUREG/CP-0152. " Proceedings of the Fourth NRC/ASME Symposium on Valve and Pump Testing". July 15-18. 1996, pages 38-19 through 3B-21.
i COMANCHE PEAX - UNITS 1 AND 2 3-5 REV. 12 November 26, 1997
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CDMAMCHE PER STEMt ELECTRIC STATION IMITS I & 2 IfMRVICE VALVE TE5ilE PLAN TABLE 1 - AUIlilARY FEEDdATER Page 12 l E l 0 '1. M-0075. M-0078. M-00s3. M-0086 #-0093. M-0098. M-0101. M-0106. AFW to Steam Gene ator Header Chect Jaives. are full-strtie exercised at
- cold shutdtwts These valves tannot be full or part strtAe open exercised dtring piant operation because such testing would unnecessat sly tubject the steam Evator nozzles to therani transients from toe cool auxiliary fee &ater for =Atch they are not designed and could result in steam generator 4r transients. The valves cannot be est cised closed during plant operattu f' the same reasons. However, the valves are verified to be Ch3 periodically daring plant cperetton through upstream tergerature monitoring f the piping and pe-2
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,i 2. Reitef valves do not perform a fic safety function. Relief valves are used to protect systems /copporets that perform a specific safety 8 function. Consistent with the 11osophy discussed in leFEG/CP 0152 ( Proceedings of the Fourth NRC/RM Sympostte on Valve and Pupp Testing'. 12 July 15-18. 1996, pages 3*-19 38-21). these relief valves do not require the two addtttonal valve tests folloutng as-fourd set-pressure determ nation failures. In lieu cf tes'.s. valve replacement may te yformed as an alternative to testirq. However, if performance data indicates that more frequent testing is needed to assure valve function. then t.e
- testing frequenr.y should be modified, 4
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CD%NCHE PEAK STE#t ELECTRIC STATION UNITS 1 & 2 1
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IEERVICE VALVE TESTIE PLAN i TABLE 2 - C01PONENT CDCLIE WATER PAGE 13 NDTES j i
1 5. X-PV-3583. -3584. 3585. -358C. Control Room A/C Condenser Cooling Flow Control Valves, are exegt from inservice testing per CM Part 10. para. !
1.2(a)(2). These valves are motor operated and fail as-is and thus are not subject to fail-safe testing. ;
- 6. FV-4650A. -46508. L. Safety Chillers Cooling Flowpath Isolation Valves; HV-4524. -4525. -4526. -4527 Non-Safety Loop Cooltrg Flowpath Isolation Valves. are full-stroke exercised at cold shutdowns. These valves cannot ba full-stroke exercised during plat.t operation because i securing flow to test the valves would interrupt cooling to essential equipnent causing undesirable transients or possibly equipment damage '
The cooling water flow pertubation resulting from Closing or even partially Closing FV-4650A or B can trip the ventilation cht11ers due to hig> [
condenser presm which among other things. causes a loss of Containment cooling. Chiller recovery after a trip is slow and equipment such as ;
Ex-core Neutron Detectors could easily exceed allowable temeratures. Closing HV-4524. -4525. -4526 or -4527 will result in this same j ventilation cM11er transient as well as loss of essential cooling to the RCP bearing oil coo'ers and motor air coolers and the instrument air 1
- i. cogressors introducing an unnecessary risk of costly damage HV-4524. -4525. -4S26. -4527 cannot be part-stroke close exercised because their ;
j control systems are such that the valves are either fully open or fully closed.
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- 7. Relief valves do not perform a specific safety function. Relief valves are used to . protect systems /cogonents that perform a specific safety 8 I function. Consistent with the philosophy discussed in NUREGICP-0152 (" Proceedings of the fourth NRC/ASE Symosits on Valve and Pug Testing *. 12 :
I July 15-18.1996. pages 38-19 thru 38-21), these relief valves do not require the two a@tional valve tests following as-found set-pressure [
determination failures. In lieu of tests, valve replacement may be performed as an alternative to testing. R>eer. if performance data ;
, indicates that more frequent testing is needed to assure valve finction. then the testtrg frequency should be modified. t i I i
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m C0MANCHE PEAK STEN 1 ELECTRIC STATION tmITS 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 3 - OtILLED liATER (SVETV)
PAGE 2 ffdll
- 1. Relief valves e not perform a specific safety furction. Relief valves are used to protect systems /cogonents that perform a specific safety 8 function. Consistent with the philos,phy discussed in NUREG/CP-0152 CProceedings of the Fourth NRC/A9E Symostum on valve and Pump Testing". 12 July 15-18.1996. pages 3B-19 thru 38-21). these relief valves do not require the t o additional valve tests following as-found set-press -
determination failures. In lieu of tests. valve replacement may be perfomed as an alterriative to testing. However if yformance data indicates that more fregAW. testing is needed to assure valve function. then the testing frequency shc=41d be modified.
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! INSERVICE VALVE TESTI1G PLAN i j TABLE 4 - DEMICAL and V(LtlME CDNTRCL i PAGE 16 I
i The check valves in both the nomal and alternate charging lines are relied on to perform their closed reactor coolant pressure boundary function at all 2 {
t times when this functton is required. Therefore. the close exercise test schedule must be maintained for all four check valves, regardless of whida i
} charging line is designated to be in service.
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- 9. Under the provis'ons of 10CFR50.55atf)(6)(tt). the NRC 5taff has incosed aumented inservke test requirements for relief valves 1-8510A.1-85108. 2-l 8510A. 2-85108. As directed by the safety evaluation Jated January 29. 1993 for tmit I and Is) REG-0797. SER Sumlesent 26 for Unit 2. the following i frequency requirements shall apply (in lieu of the rA Part 1. para.1.3.4 frequmcy requiremmts) for performance testing the subject valves.
A. Ow valve from each unit shall be performance tes! Mi each fuel cycle. Both valves from each unit shall be performance tested within any two
! fuel cycles.
1 f l 8. If the tested valve from a given unit fails the set pressure determination portion of the performance test. then the other valve from that unit
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j shall be performance tested. If the tested valve from a given unit fails one of the other criteria of the performance test (i.e.. visual j i examination. seat tightness determination or balancing device integrity verification). then the cause shall be evaluated and the need to test 4 the other valve from that unit shall be determined.
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- C. Both valves from a given unit shall be performance tested following any system actuation editch results in the valves discharging. This
- performance test shall be performM2 at the rest cold shutdown of sufficient duration to perform these activities. l
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- 10. Relief valves do not perform a specific safety functions. Relief valves are used to protect systems / components that perform a spectfte safety function. 8 f' j Consistent with the philosophy discussed in NUREG/CP-0152 (~ Proceedings of the Fourth NRC/ASME Symposim on Valve and Pug Testing *. July 15-18. 1996. 12 j pages 33-19 thru 3B-21). these reitet valves do not require the two ad$ttional valve tests following as-found wt-pressure detersmation failures. In l 4 lieu of tests. valve replacement may be performed as an alternative to testing. Hommer, if performance data indtrates that more frequent testing is f d
needad T.o assure valve function then the testing frequency should be modified.
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C0%NCHE fDK STEAM ELECTRIC $TATION LMITS 1 & 2 ~
I EERVICE VALVE TESTI E PLAN TABLE 5 - CONTA % ENT SDRAY Page 7 E
- 1. CT-0142. CT-0145. Contairmet spray Header Check Valves: CT-0148. CT-0149. Containment Spray Pep Suction Check Valves from the Retirculation Swps. are disasseeled at refueling outages to verify ogerablitty. Full or part-itroke exercising these valves with flow is not practicable.
In the case of CT-0142 and CT-0145. the flowpath downstream of the valves is open to the Containnent Building via the spray headers. No neaningful flow can be achieved t.W these valves without celuging the Containnent and causing a significant cleanup problem and potential equipment damege. In the case of CT-0148 and CT-0149. the flowpath tr.treas of the valves is open to the norwelly dry Containment Rectrculation supps. Surp inventory only e c ts post-accide t when the RW5T has been depleted. Flooding the sums for test purposes would intro &ce contaminants into the Contatnnent Spray System and the RW5T which otherwise contain reactor quality water. Additionally. surp makeup would be required at a high rate to protect the Contatreent $ pray Pwps from a loss of suction.
- 2. Relief valves do not perform a spectf1c safety function. Helief valves are used to protect systers/cogrJoents that perform a specific safety 8 function. Consistent with the philosophy discussed in 10 REG /CP.0152 CPrWings of the Fourth NRC/A5K Sympostum on Valve and Pwp Testing'. 12 July 15-18.1996. pagn 38-19 thru 3B-21). these relief valves do not require the two aettional valve tests following as-found set-pressure determination failures. In Iteu of tests, valve replacement may be performed as an alternative to testing. W. tf performance data indicates that more frequen'. testing is medad to assure valve fwiction, then the testtng freque' icy should be modtfied.
Rev. 12 November 26.1997
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CD1ANCHE FEAK STEArt ELECTRIC STATION tNITS 1 & ? ;%l INSEPVICE VALVE TESTING PLAN 4' TABLE 7 - DIESEL GENERATGi AUXILIARIES '
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- 1. 00-0107. 00-0207 Jacket Water Tevrature Control valves are exerct from 'nservice testing per Of Part 10.1.2(a)(2). These three-way valves have a W 7
self-catained thermostatic element ditch causes them to sodulate in response to changing jacket water tenperature to divert sore or less flow throu;h -f
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the Jacket Water Cooler. as required. The valves d> not fati safe and thus are ret subject ta fat 1-safe testing.
- 2. Reitef valves do not perform a specific safety function. Relief valves are used to protect systems /conponents that perform a scecific safety function. 8 Consistent with the philosophy discussed in NUREG/CP-0152 (" Proceedings of the Fourth NRC/ASME Synoostum on Valve and Pump Testing . July 15-18. 1996. 12 pages 38-19 thru 38-21). these relief valves do not reautre the two aditional valve tests follmstry as-found set-pressure & termination fattures. In lieu of tests, valve replacement may te performed as an alternative to testing. Honever, if performance data indicates that more frequent testMg is needed to assure valve function thei tha testing frequency should be nodified.
- 3. Valves SV-3421-lE. SV-3421-1F. SV 3422-1E. and SV-3422-1F are being added by Eestgr. Pbdtfications95-094 (Untt 2) and 95-095 (Unit 1). The testing 10 requirement for each valve becomes effective after its respective train has been accepted by operations.
K l Rev. 12 l W 26. 1997
CDMANCHE PEAK STE#t ELECTRIC STATION UVITS 1 & 2 '
IICERVICE VALVE TESTING PLAN TABLE 11 - RESIDUAL HEAT RO G AL Page 5 i
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- 1. HV-4178 and HV-a179 are part of Process Sar@ ling System and HV-4182 is part of Post Accident Sampling System but are included trt this table ;
because their safety functions are more closely associated with Residual Heat Removal System. ,
- 2. The test frequency requirements of Technical Soecification 4.4.5.2.2 apply for leak testing of 8701A. 87018. 8702A. 87028. iAtch are more 2 restr1ctive than the test frequency requhements of 01 Part 10. para. 4.2.2.3(a). '
- 3. 8701A. 87018. 8702A. 87028. RHR Suction Isolatim Valves from the RCS Hot Legs, are full-stroke enercised at cold shut @wns. These valves i cannot be full or part-strcke exercised durtrg plant operation because they are interlocked to rematn closed to prevent overpressurtzing the l relatively low pressure Residi.a1 Peat Removal System fran the high pressure Reactor Coolant System. j
- 4. 8708A and 87083. RHR Suction Relief Valves. are Passive and are therefore exegt from performance testing. (Reference Of Part 10. Table 1.) i Technicai Spectf tcation 4.4.8.3.2(c). however. requires that these valves 5e performance tested to the requirements of A9E Section II. I
- 5. 8730A and 87308. RHR Pump Discharge Check Valves, are full-strde open exercised at cold shutdowns. These valves cannot be full-strate open
. exercised during plant operation because the normal flowpath discharges into the relatively higher pressure Reactor Coolant Systas. Also. the alternate flowpath through the RHR to RWST return Itne carnot be used during plant operatton since opening this Itne defeats both trains of the l Low Pressure Safety Injection System. Part-stroke open exercising these valves during plant operatton is not practicable. The only pessible !
flowpath is through the SI test header which yields ficwrites too small (agprox. 5 gpm) to be meaningful for assessing the operational readtness i of these valves. The valves are full-strde close exercised at cold shutdowns at the same frequency as the open exercising for the reasons described above. !
- 6. 8716A and 87168. RHR Train A & 8 Pisap Discharge Crosstle Valves, are full-stroke exercised at cold shutewns. These valves cannot be full- ! !
stede exercised during plant operation because the closure of either valve coincident with the fatture of an RHR pum would render the systes capable of providtng flow to only two RCS cold legs during post-LOCA injection. whereas the design bases for the Emergency Core Cooling System assume flow to all four cold legs. (Reference IE Information Notice No. 87-01.) 8716A and 87168 cannot be part-stroke exerciset because their I control systems are such that the valves are eitner fully open or fully closed. l
- 7. Relief valves do not perform a specific safety fisiction. Relief valves are used to protect systems / components that perform a specific st.fety 8 function. Consistent with the philosophy discussed in MPEG/CP-0152 (" Proceedings of the Fourth NRC/A5ME Syneestou on Valve and Pum Testing". 12 l
July 15-18.1996. pages 38-19 thru 38-21), these relief valves do rot require the tie additional valve tests following as-foisia set-pressure
' determination failures. In 11eu of tests. valve replacement may be pwformed as an alternative to testing. Hotever. if performance data indicates that more frequent testing is needed to assure valve function. then the testing frequency should be modifted. !
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CO W O E PEAK STEAM ELECTRIC STATION UNIT 1 & 2 INSERVICE VALVE TESTING PLAN TABLE 13 - SAFETY If0ECTION Page 23 WFES
- 9. 8818A. B. C. D. B948A. B. C. D. Low Head Safety Injection flowpath Check Valves, are full-stroke exercised at refueling cutages to verify operabiitty. 4 These valves cannot be full or part-stroke open esercised during plan
- operatton because the relatively higher pressure of the Reactor Coolant System will not allow forward flow through these paths. Part-stroke esercising of these check valves during plant operation via the Si test header is not practicable because this path yields flowrates too small (amroximately 5 gpm) to be meaningful for assessing the operational readiness of tMse valves. It is not practicable to full stroke exercise these valves at cold shutdowns because the acoustic emission testing needed to vertfy the valves 93 full-open requires both Residual Heat Removal Pureps running and all Reactor Coolant Pugs secured to perform a satisfactory test. Both Residual Heat Removal Pu gs are required to flow through a single SI header to achieve the hydraulic transient necessary to create the acoustic signa %re. During the test Residual Heat Removal flow must be secured. The Reactor Coolant Pums sust te secured to lower backgand noise sufficier.tly to record the acoustic signature. A parttal stroke of these valves could be perforined at cold shutdown using the same test lineup with only one Residual Heat Removal Pum runn,ng.
Non-intrusive testing techniques. such as the acoustic emission method applied here is considered *other posittee means" as defined in ASPE/ ANSI 09-1987 Part 10. Paragraph 4.3.2.4(a). During the initial acoustic emission testing for these valves. the system flow conditions were estabitshed to cause tha valves to fully stroke. During subsequeet testirg. all valves shall be fully strok'd at repeatable system conditions. The acoustic emission monitoring of the valves, however, will only be performed on one valve per group per outage on a rotating schedule each time testing is perfomed (a samling program).
The groups will be four valves each. 881BA. B. C. D. and 8948A. B. C. D. If problems are found with the samle valve. all valves in the affected grow must be tested ustng acoirstic emission monitoring during the same outage.
The subject check valves are full-stroke close exercised at cold shutd>ns because acoustic entssion monitoring is not required for these tests.
- 10. Relief valves do not peform a specific safety function. Relief waives are used to protect systems /comonents that perform a specific safety function. 8 Consistent with the philosophy discussed in MJREG/CP-0152 (" Proceedings of the Fourth NRC/A5K Sygostum on Valve and Pwp Testing . July 15-18. 1996. peges 12 38-19 thru 38-21) these relief valves do not requ re the two additional valve tests following as-found set-pressure oetermination fattures. In iteu of tests. valve replacement may be performed as an alternative to testtng. %ever. If performance data indicates that more frequer.t testing is needed to assure valve function. then th*' ing frequency should be modified.
Rev.12 November 26.1997
~.
COWOE PEAK STEM ELECTRIC STATION LMITS 1 & 2 IN5ERVICE VALVE TESTING PUUI TABLE 14 - SERVICE WATER Page r
!0IU
- l. Not Used. 6
- 2. HV-4395 and HV-4M. Lwy ATW Supply Valves. are full-strd e exercised at refueling outag n . These valves provide isolation at the Service Water end of the normally dry emergency crosstie Itne to the Auxtitary Feedwatee System. At least one of the two valves is rewired to be opened to supply the AFW pumps in the unitkely event that the Class 3 Condensate Storage Tar
- swely ts depleted. The valves are provided with motor operators for convenience only and do not respond automatically to any plant condttton. In the event that the valves are required to be opened egle time entsts to reposition the valves manually. tf required. Full or part-stroke exercising cf these valves during plant operation and coM shutdown is not practicable due to the precautions necessary to prevent introducing lakewater tnto the normally dry emergency AFW crosstie 1tne and possibly into the steam generators. The esercise test for the valves is a lengthy process requiring draining of the respective Service Water train and subsegient reftiling. During this time the Service Water train is L,uvallable to perform its normal safety functions.
Relief valves doict perform a specific safety function. Relief valves are used to protect systems / components that perform a specific safety 8-3.
function. Consisitent with the philosophy discussed in NUREG/CP-0152 (* Proceedings of the Fourth NRC/ASME Sygostism on Valve and Puy Testing *, 12 July 15-18.1996. pages 38-19 thru 35-21). these reitef valves do not rewire the two additional valve tests following as-found set-pressure detensination fattures. In lieu of tests. valve replacement may be performed as an alternative to testing. However. if performance data indicates that more frequent testing is needed to assure valve function. then the testing frequerry should be sodtfted.
Rev.12 bvod;er 26. 1997
s
, COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2
,., INSERVICE TESTING PLAN FOR PUMPS AND VALVES FIRST INTERVAL i
EFFECTIVE PAGE LISTING
) PAGE 1 0F 5 j BELOW IS A LEGEND FOR THE EFFECTIVE PAGE LISTING:
Revision 0 Submitted July 1, 1992 Revision 1 february 3, 1993 Revision 2 April 30, 1993 i Revision 3 November 19. 1993
- Revision 4 October 7, 1994 Revision 5 February 15, 1995
- Revision 6 October 5, 1996 Revision 7 October 16, 1996 Revision 8 January 31, 1997 Revision 9 June 26, 1997
. Revision 10 September 3, 1997 Revision 11 October 10, 1997 Revision 12 November 26, 1997
. Eggg Revision /Date Record of Changes October 7, 1994 Cover Sheet Revision 12 i (Table of Contents) November 26, 1997 1
1-1 Revision 2 12 Revision 3 1 1-3 Revision 2 14 April 30, 1993 21 Revision 0 22 Revision 0
. 23 Revision 0 24 Revision 0 25 Revision 0 Table 0. Page 1 of 4 Revision 0 ,
Table 0. Page 2 of 4 Revision 0 '
Table 0. Page 3 of 4 Revision 2 Table 0. Page 4 of 4 Revision 0 i Table 0, Notes, Page 1 Revision 2
. 3 November 26, 1997 32 Revision 12 3-3 November 26, 1997 34 November 26, 1997 3-5 Revision 12 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 12 January 31, 1997 Table 1. Page 2 January 31, 1997 Table 1. Page 3 January 31, 1997 EPL 1 November 26, 1997
+
. COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2
, INSERVICE TESTING PLAN FOR PUMPS AND VALVES FIRST INTERVAL
' EFFECTIVE PAGE LISTING PAGE 2 0F 5 Table 1. Page 4 January 31, 1997 Table 1. Page 5 January 31, 1997 Table 1 Page 6 January 31, 1997 Table 1, Page 7 January 31, 1997 Table 1._Page 8 January 31. 1997 Table 1, Page 9 January 31, 1997 Table 1, Page 10 January 31. 1997 Table 1, Page 11 Revision 8 Table 1 Page 12 Revision 12 Table 2, Page 1 nf 13 January 31. 1997 Table 2. Page 2 January 31, 1997 Table 2, Page 3 January 31, 1997 Table 2. Page 4 January 31,1997 Table 2, Page 5 January 31, 1997 Table 2. Page 6 January 31. 1997 Table 2. Page 7 January 31, 1997 Table 2. Page 8 January 31, 1997 Table 2, Page 9 January 31, 1997 Table 2. Page 10 Revision 8 Table 2. Page 11 Revision 8 Table 2. Page 12 January 31, 1997 Table 2. Page 13 Revision 12 Table 3. Page 1 of 2 Revision 8 Table 3 Page 2 Revision 12 Table 4. Page 1 of 16 January 31. 1997 Table 4. Page 2 January 31, 1997 Table 4, Page 3 January 31. 1997 Table 4. Page 4 January 31,1997 Table 4. Page 5 January 31, 1997 Table 4 Page 6 January 31, 1997 Table 4. Page 7 January 31, 1997 Tab'c 4. Page 8 January 31, 1997 Table 4. Page 9 January 31, 1997 Table 4. Page 10 January 31, 1997 Table 4. Page 11 January 31, 1997 Table 4. Page 12 Revision 8 Table 4. Page 13 January 31, 1997 Table _4, Page 14 January 31, 1997 Table 4. Page 15- January 31. 1997 Table 4. Page 16 Revision 12 Table 5. Page 1 of 7 January 31, 1997 Table 5. Page 2 January 31, 1997 Table 5. Page 3 January 31, 1997 ,
Toble 5. Page 4 January 31, 1997 Table 5 Page 5 January 31, 1997-Table 5. Page 6 Revision 8
. Table 5. Page 7 Revision 12 EPL 2 November 26, 1997
COMANCHE PEAK STEAM ELECTRIC STAl!0N UNITS 1 & 2 f INFIRVICE TESTING PLAN FOR PUMPS AND VALVES FIRST INTERVAL
, EFFECTIVE PAGE LISTING PAGE 3 0F 5 Table 6. Page 1 of 3 Revision 11 Table 6. Page 2 October 5, 1996 l Table 6 Page 3 Revis1or.11 Table 7 Page 1 of 7 September 3, 1997 Table 7 Page 2 January 31, 1997 Table 7. Page 3 January 31, 1997 Table 7 Page 4 January 31, 1997 Table 7. Page 5 Revision 8 Table 7. Page 6 Revision 10 Table 7. Page 7 Revicion 12 Table 8 Page 1 of 6 Revision 0 Table 8, Page 2 of 6 Revision 0 Table 8. Page 3 of 6 Revision 0 Table 8, Page 4 of 6 Revision 0 Table 8. Page 5 of 6 Revision 0 Table 8. Page 6 of 6 Revision 0 Table 8, Notes. Page 1 April 30, 1993 Table 9. Page 1 of 12 Revision 2 Table 9 Page 2 of 12 Revision 2 Table 9 Page 3 of 12 Revision 9 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 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 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 Rcvision 0 Table 11 Page 1 of 5 January 31, 1997 Table 11, Page 2 January 31, 1997 Table 11. Page 3 January 31, 1997 Table 11, Pag 6 4 Revision 8 Table 11, Page 5 Revision 12 Table 12. Page 1 of 2 Revision 0 Table 12. Page 2 of 2 Revision 0 Table 13. Page 1 of 23 January 31, 1997 Table 13 Page 2 -January 31, 1997 Table 13, Page 3 January 31, 1997 Table 13. Page 4 Januiry 31, 1997 EPL-3 November 26, 1997
, COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2
.. INSERVICE TESTING PLAN FOR PUMPS AND VALVES FIRST INTERVAL
' EFFECTIVE PAGE LFJING PAGE 4 0F 5 Table 13. Page 5 January 31, 1997 Table 13. Page 6 January 31, 1997 Table 13. Page 7 January 31, 1997 Table 13. Page 8 January 31. 1997 Table 13. Page 9- January 31, 1997 Table 13. Page 10 January 31. 1997 Table 13. Page 11 January 31, 1997 Table 13. Page 12 January 31. 1997 l
Table 13. Page 13 January 31, 1997 Table 13. Page 14 January 31. 1997 i
Table 13. Page 15 Revision 9 Table 13. Page 16 Revision 9 Table 13. Page 17 January 31, 1997 Table 13. Page 18 Revision 8 Table 13. Page 19 Revision 8 Table 13. Page 20 January 31, 1997 Table 13. Page 21 January 31, 1997 Table 13. Page 22 Revision 9 Table 13. Page 23 Revision 12 Table 14. Page 1 of 5 January 31, 1997 Table 14. Page 2 January 31, 1997 l Table 14. Page 3 January 31. 1997 i Table 14. Page 4 Rivision 9 Table 14. Page 5 R1 vision 12 Table 15. Page 1 of 1 Revision 0 Table 15. Notes. Page 1 Revision 0 Table 16. Page 1 of 2 Revision 0 Tabla 16. Page 2 of 2 Revision 0 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 Tabie 17. Page 5 of 12 Revision 0 Table 17. Page 6 of 12 Revision 0 Table 17. Page 7 of 12 Revision 0 Table 17. Page 8 of 12 Revision 2 Table 17. Page 9 of 12 Revision 2 Table 17. Page 10 of 12 Revision 2 Table 17. Page 11 of 12 Revision 2 Table 17. Page-12 of 12 Revision 0 Table 17. Notes. Page 1 April 30. 1993 Table 17. Notes. Page 2 Revision 2 A1 Revision 0 A2 April 30,1993 A3 April 30.1993 A-4 Revision 2 A5 April 30, 1993 EPL-4 November 26, 1997
- COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES FIRST INTERVAL
- EFFECTIVE PAGE LISTING PAGE 5 0F 5 A6 April 30, 1993 -
A7 Revision 2 A8 April 30, 1993 A9 Revision 2 A-10 April 30. 1993 A 11 Revision 2 A 12 April 30, 1993 A-13 Revision 2 A 14 April 30, 1993 A 15 Revision 2 A-16 April 30, 1993 A 17 Revision 2 A-18 April 30, 1993 A 19 Revision 9 EPL. Page 1 of 5 November 26, 1997 EPL, Page 2 of 5 November 26, 1997 EPL. Page 3 of 5 November 26, 1997 EPL, Page 4 of 5 November 26. 1997 EPL, Page 5 of 5 Nivember 26, 1997 EPL-5 November 26, 1997