ML20066B670
| ML20066B670 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/18/1990 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20066B667 | List: |
| References | |
| PROC-901218, NUDOCS 9101080232 | |
| Download: ML20066B670 (192) | |
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PUMP AND VALVE INSERVICE TESTING PROGRAM POINT BEACH NUCLEAR PLANT REVISION O December 18,1990 P
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TABLE OF CONTENTS 1.0 Introduction I 2.0 Applicable Documents 3.0 inservice Testing Program for Pumps 3.1 Code Compliance l' 3.2 Allowable Ranges of Test Quantitles 3.3 Test intervals i
3.4 Pump Program Table ,
3.5 Rollef Requests for Pump Testing 4.0 inservice Testing Program for Pumps 2
j 4.1 Code Compilance i 4.2 Testing Intervals
- 4.3 Stroke Time Acceptance Criteria 4.4 Check Valve Testing 4.5 Va!ve Program Table 4.6 Rollel Requests for Valve Testing APPENDICES
- k. A Pump Program Tables
- Unit 1 B Pump Program Tables . Unit 2 C Pump Program Requests for Rollel . Units 1 & 2 4
D Valve Program Tables . Unit 1 E Valve Program Tables Unit 2 F Valve Program Requests for Rollef Units 1 & 2 G Cold Shutdown Justifications H Valve Fall Safe Test Description t
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1 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
!. INSERVICE TESTING PROGRAM Revision 0 l December 18,1990 I
UNITS 1 AND 2 ii l
1.0 INTRODUCTION
Revision 3 of the Point Bcach (Units 1 & 2) ASME Inservice Inspection (IST) Program will be in eMeet through the end of the third 120 month (10 year) Interval unless changed and reissued for reasons other a than the routine update required at the start of the fourth Interval per 10 CFR 50.55a(g). The third ;
inspection interval for both units begin on December 31,1990.
D This document outlines the IST Program for Point Beach Plant, Units 1 and 2, based on the requirements of Section XI of the ASME Boller and Pressure Vessel Code,1986 Edhlon (the Code).
References in this document to 'lWP' or 'lWY' correspond to Subsections (WP and lWY, respectively, of the ASME Section XI,1986 Edition, unless otherwise noted.
As described in the second (1980) 120 month Interval program strict application of code selection criteria of 10 CFR 60.55a(g)(4)(II) would have resulted in application of different ASME XI code edition
! being applied to Unit 1 and Unit 2. In the second program a request was made to match Unh 1 and Unit 2 to the same code edition. A similar request accompanied this third 120 month program; the contents of this program have been prepared under the assumption the request is granted.
1.1 Interoretation 1.1.1 Where conflicts exist between 10 CFR 50.558 and ASME Section XI,10 CFR 50.55a takes precedence.
j 1.1.2 By 10 CFR 50.55a(g)(1), insewice testing of pumps and valves for plants with construction permits docketed prior to January 1,1971, is limited to those that are safety related. This applies to P8NP Units 1 and 2.
! 1.1.3 According to 10 CFR 50.55a(g)(1) and 10 CFR 50.55a(g)(4), inseNice testing shall be conducted in accordance with the appropriate edition / addenda of the code to the extent practical within the limitations of design, geometry, and materials of construction. Modifications to the plant, to accommodate changes in inservice testing requirements in later editions of the code are not specifically required.
1.1.4 The NRC, via Generic Letter 8944 and associated documents (References 2.0,2.9 and 2.10), has provided interpretations and modification of ASME XI.
2.0 REFERENCES
This program plan was developed per the requirements and guidance provided by the following documents:
2.1 Title 10, Code of Federal Regulations, Part 50 2.2 NRC Regulatory Guides DMslon 1 2.3 Standard Review Plan 3.9.6, ' Inservice Testing of Pumps and Valves' 2.4 Final Safety Analysis Report Point Beach Units 1 & 2 i 2.5 Point Beach Plant Unit 1 Technical Specifications 2.6 Point Beach Plant Unit 2 Technical Specifications Page 1 of 4
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
. INSERVICE TESTING PROGRAM Revision 0 December 18,1990 UNITS 1 AND 2
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2.7 ASME Boller and Pressure Vessel Code,Section XI,1986 Edition.
2.8 NRC Generic Letter 89-04, 'Ouidance on Developing Acceptable Inservice Testing Programs' 2.9 Point Beach Nuclear Plant Responses to GL 89 04, dated October 3,1989. March 2,1990, June 28,1990, and September 11,1990.
2.10 NRC minutes of public meetings on GL 89 04, dated October 25,1989.
3.g INSERVICE TESTING PROGRAM FOR PUMPS 3.1 Code Comollance This IST program for pumps is based on the requirements of subsection lWP of the code and any interpretations or additional requirements imposed by Reference 2.8. Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, nr en attemative test provides an acceptable level of quality and safety, relief from code requirements is requested pursuant to the requirements of 10 CFR 50.55a(g)(lli) and Reference 2.8.
3.2 Allowable Manoes of Test Quantitles The allowable ranges for test parsmeters as specified in Table IWP4100 2 will be used for all measurements of pressure, flow, and vibrations except es provided for in specific relief
( requests. In some cases the performance of a pump may be adequate to fulfill its safety function even though there may be a value of an operating parameter that falls outside the allowable ranges as set forth in Table IWP 3100 2. Should such a situation arise, an expanded allowable range may be determined, on a caso by case basis, in accordance with IWP 3210 and ASME Code Interpretation XI 17919.
3.3 Testino Intervals The test frequency for pumps included in the Program will be as set forth in IWP 3400 and related relief requests. A band of +25 percent of the test interval may be applied to a test schedule as allowed by the Point Beach Technical Specifications to provide for operational flexibility.
3.4 Pumo Procram Table Apoorvilces A and B list those pumps included in the IST Program w!!h references to parameters to be measured and applicable requests for relief, Pumps which provide a common, shared function for Units 1 and 2 are included in Appendix A. Any explanatory notes required for clarification of test requirements will be included at the end of the respective pump table to which the note applies.
3.5 RelW Peauests for Pumo Testina l Appendix C includes relief requests related to pump testing.
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 w December 18,1990 UNITS 1 AND 2 i
3.6 Evaluation of Data and Ecutoment Status Declaration V 3.6.1 The duty shift superintendent shall determine equipment operability by comparing test data against the acceptance limits. These limits are contained in an Operations standing order. Equipment with data exceeding these limits will be declared inoperable and Technical Specification LCOs eppiled.
3.6.2 Additional engineering evaluations, data trending, and data retention will be performed in accordance with ASME XI code and will be accompanied by equipment status declarations in accordance with plant administratNe procedures. ,
4.0 INSERVICE TESTING PROGRAM FOR VALVES 4.1 Code Comollance This IST Program for valves is based on the requirements of Subsection lWV of the Code and any interpretations or additional requirements imposed by Reference 2.8. Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, or an altemative test provides an acceptable level of quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50.55a(g)(lii) and Reference 2.8.
4.2 Testina Intervals The test frequency for vanes included in the Program will be as set forth in IWP 3400 and related relief requests. A band of +25 percent of the test Interval may be applied to a test schedule as allowed by the Point Beach Technical Specifications to provide for operational flexibilty. Where quarteriy testing of valves is impractical or otherwise undesirable, testing may be performed during cold shutdown periods as permitted by IWV 3412(a). Justifications for this deferred testing are provided in Appendix G with elaboration of Point Beach policy set forth in Rollef Request VRR 5.
4.3 Stroke Time Accentance Crtterla When required, the acceptance criteria for the stroke times of power operated vanes will be as set forth in lWV 3410 and Reference 2.8.
4.4 - Check Vane Testina Where required, full stroke exerclsing of check valves to the open position using system flow requir3s that a test be performed whereby the predicted full accident condition flowrate through the vaNo be verified and measured. Any deviation to this requirement must satisfy the requirements of Reference 2.8, Position 1, 4.5 _ Vane Procram Table Appendices D and E list those valves included in the IST Program with references to required testing, respectNe test intervals, and applicable requests for relief. Valves which serve a common, shared function for Units 1 and 2 are included in Appendix D. Any explanatory notes required for clarification of test requirements will be included at the end of the respectNe valve table to which the note applies.
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 UNITS 1 AND 2
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4.6 Rollef Aeouests for Valve Testina Appendtx F includes all relief requests related to valve testing.
4.7 Evaluation of Data and Eauloment Status Declaration 4.7.1 The duty shift superintendent shall determine equipment operability by comparing test data against the acceptance limits. These limits are contained in an Operations standing order. Equipment with data exceeding these limits will be declared inoperable and Technical specification LCOs applied.
4.7.2 Additional engineering evaluations, data trending, and data retention will be performed in accordance with ASME XI and will be accompanied by equipment status declarations in accordance with plant administrative procedures.
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
- j INSERVICE TESTING PROGRAM Revisioli 0 1
December 18,1990 APPENDIX A
( UNIT 1 PUMP PROGRAM TABLE LEGEND PUMP NUMBER Numerical designator indicated on the respectNo flow diagram.
FUNCTION Generic tmme/ function of the pump.
DRAWING NO. Corresponds to the flow diagram showing the pump.
TEST PARAMETERS The table indicates full code compliance by a 'YES' in the column astoclated with that specific parameter Where the test program devlates from the ende requirement, the respectNe relief request number Is noted.
PRR XX Where indicated, this refers to the specific relief request (See Appendix C) related to any devtstion regarding the measurement or analysis of a parameter.
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E POINT BEACH NUCLEAR PLANT INSERVICE TESTil ROGRAM ,
.s INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX A UNIT 1 PUMP PROGRAM TABLE Test Parameters Pump Lube Infet Diff Flow Bearing Number Function Dwg.No. Level Speed Press Press Rate Vib Temp Remarks P-002A Charging Pump 684J741 Yes Yes PRR-14 PRR-14 Yes PRR-7 PRR4 PRR-129.10 P0028 Charging Pump 684J741 Yes Yes PRR-14 PRR-14 Yes PRR-7 PRR4 PRR-1.2.9.10 P-002C Charging Pump 684J741 Yes Yes PRR-14 PRR-14 Yes PRR-7 PRRE PRR-119.10 P-004A BA Transfer 684J741 No N/A PRR-12 PRR-12 PRR-12 PRR-12 PRR4 PRR .127 9.10.11 P-0048 BA Transfer 684J741 No N/A PRR-12 PRR-12 PRR-12 PRR-12 PRR4 PRR-1.2.7 9.10.11 P-010A RHR 110E018 Yes N/A Yes Yes PRR-4 PRR-7 PRR4 PRR-119.10.
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i l P410B RHR 110E018 Yes N/A Yes Yes PRR-4 PRR-7 PRR4 PRR-129.10 {
] 16.17 P411A CC 110E018 Yes N/A Yes Yes Yes PRR-7 PRR-8 PRR-129.10 I
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! P-011B CC 110E018 Yes N/A Yes Yes Yes PRR-7 PRR4 PRR-119.10 16
, P-012A SFP Cooling 110E018 Yes N/A Yes Yes Yes PRR-7 PRR4 PRR-129.10 l 16 l
P4128 SFP Cooling 110E018 Yes N/A Yes Yes Yes PRR-7 PRR4 PRR-129.10 l l 16 I l P-014A Containment Spray 110E017 Yes N/A Yes Yes PRR4 PRR-7 PRR4 PRR-1.2.9.10 i 16 l
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POINT BEACH NUCLEAR Ft. ANT INSERVICE TESTlh IOGRAM '
wC INSERVICE TESTING PROGRAM Revision 0 -
December 18,1990 APPENDIX A t UNIT 1 PUMP PROGRAM TABLE l
Pump Lube Inlet Diff Flow Bearing Number Function Dwg.No. Level Speed Press Press Rate Vib Temp Remarks [
I P-0148 Containment Spray 110E017 Yes N/A Yes Yes PRR-6 PRR-7 PRR-8 PRR-119.10, i 16 I P-015A Safety injection 110E017 Yes N/A Yes Yes PRR4 PRR-7 PRR4 PRR-129.10 16.17 P415B Safety injecilon 110E017 Yes N/A Yes Yes PRR-3 PRR-7 PRR-8 PRR-129.10 16.17 P-029 AFW M-217 Yes Yes Yes Yes PRR-5 PRR-7 PRR-8 PRR-129.10 16.18 ,
8 L P-032A Service Water M-207 No N/A PRR-13 Yes Yes PRR-7 PRRE PRR-129.10 i 16 P-0328 Service Water M-207 No N/A PRR-13 Yes Yes PRR-7 PRR4 PRR-1.2.9.10. ,
16 P432C Sennce Water M-207 No N/A PRR-13 Yes Yes PRR-7 PRR4 PRR-129.10 !
16 P-032D Service Water M-207 No N/A PRR-13 Yes Yes PRR-7 -RR4 PRR-129.10 16 P-032E SerWe Water M-207 No N/A PRR-13 Yes ~
Yes PRR-7 PRRE PRR-129.10 i l -
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P-032F Service Water M-207 No N/A PRR-13 Yes Yes PRR-7 PRR4 PRR-129.10 I 16 j P-038A AFW M-217 Yes N/A Yes Yes PRR-5 PRR-7 PRRE PRR-129.10 16.18 :
P-0388 AFW M-217 Yes N/A Yes Yes PRR-5 PRR-7 PRR-8 PRR-129.10
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s POINT BEACH NUCLEAR PLANT INSERVICE TESTIN OGRAM .
wC INSERVICE TESTING PROGRAM Redsion 0 December 18,1990 APPEND!X A UNIT 1 PUMP PROGRAM TABLE Pump Lube Irdet Diff Flow Bearing Number Function Dwg.No. Level Speed Press Fress Rate Vib Temp Remarks P-070A FO Transfer M-219 Yes N/A Yes Yes Yes PRR-7 PRR4 PRR-1.2.9.10 16 P-070B FO Transfer M-219 Yes N/A Yes Yes Yes PRR-7 PRR4 PRR-1.2.9.10 16 P-111 A CSR Ch Water M-214 N/A N/A Yes Yes PRR-15 PRR-7 PRRE PRR-1.2.9.10 P-1118 CSR Ch Water M-214 N/A N/A Yes Yes PRR-15 PRR-7 PRRE PRR-12.9.10 P-112A CR Ch Water M-214 N/A N/A Yes Yes PRR-15 PRR-7 PRRE PRR-1.2.9.10 P-1128 CR Ch Water M-214 N/A N/A Yes Yes PRR-15 PRR-7 PRR4 PRR-1.2.9.10 l
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 i APPENDIX B i UNIT 2 PUMP PROGRAM TABLE l 1
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l LEGEND PUMP NUMBER Numerical designator indicated on the respectNe flow diagram. ;
FUN 0 TION Generic name/ function of the pump.
DRAWING NO. Corresponds to the flow diagram showing the pump.
TEST PARAMETERS The table Indicates full code compilance by a 'YES' in the column associated with that specific parameter. Where the test program de 'lates from the code requirement, the respectNo relief request number is t oted.
PRR XX Where indicated, this refers to the specific rollef reques' (See Appendix C) related to any deviation regarding the measurement or analysis of s parameter.
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- POINT BEACH NUCLEAR PLANT INSERVICE TESTh 'ROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX B UNIT 2 PUMP PROGRAM TABLES Test Parameters Pump Lube inlet Diff Flow Bearing
- Number Function Dwg.No. Level Speed Press Press Rate Vib Temp Remarks
- P-002A Charging Pump 685J175 Yes Yes PRR-14 PRA-14 Yes PRR-7 PRR4 PRR-12.9.10 j P-0028 Charging Pump 685J175 Yes Yes PRR-14 PRR-14 Yes PRR-7 PRR4 PRR-12.9.10 P-002C Charging Pump 685J175 Yes Yes PRR-14 PRR-14 Yes PRR-7 PRR4 PRR-119.10 P404A BA Transfer 685J175 N/A N/A PRR-12 PRR-72 PRR-12 PRR-12 PRR-8 PRR .12.7.9.10.11 P-0048 BA Transfer 685J175 N/A N/A PRR-12 PRR-12 PRR-12 PRR-12 PRR4 PRR-12.7.9.10.11 P-010A RHR 110E029 Yes N/A Yes Yes PRR-4 PRR-7 PRR4 PRR-12_R10.16.17 P410B RHR 110E3?9 Yes N/A Yes Yes PRR-4 PRR-7 PRR4 PRR-12.9.10.16.17 P-011 A CC 110E029 Yes N/A Yes Yes Yes PRR-7 PRR4 PRR-12.9.10.16 P-011B CC 110E029 Yes N/A Yes Yes Yes PRR-7 PRRE PRR-12.9.10.16 P-014A Cor@mment Spray 119E035 Yes N/A Yes Yes PRR4 PRR-7 PRR4 PRR-12.9.10.16 P-014B Conta;nment Spray 11 4035 Yes N/A Yes Yes PRR-6 PRR-7 PRR4 PRR-1,2.9.10.16 P-015A Safety friection 119E035 Yes N/A Yes Yes PRR-3 PRR-7 PRR4 PRR-12.9.10.16.17 P-0158 Safety injection 119E035 Yes N/A Yes Yes PRR-3 PRR-7 PRR4 PRR-12.9.10.16.17 P-029 AFW M-217 Yes Yes Yes Yes PRR-5 PRR-7 PRR4 PRR-12.9.10.16.18 Page 2 of 2
l' POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM l i llNSERVICE TESTING PROGRAM Revision 0 i December 10,1990 i APPENDIX C I I
PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2
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! REUEF REQUEST NO. PRR 1
,QQhEONENTS: Various SECTION XI REQUIREMENT:
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l The full scale range of each Instrument shall be three times the reference value or less. (IWP 4120) )
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_ BASIS FOR REUEF:
i Table IWP41101 requires the accuracy of instruments used to measure temperature and speed to be equal to or better than 45 percent for temperature and 22 percent for speed, both based on the full scale reading of the 4
instrument. This means that the accuracy of the measurement can vary as much as 215 percent and t6
- percent, respectively, assuming the range of the instruments extended to the allowed maximum.
l These IST pump parameters are often measured with portable test instruments where commercially available instruments do not necessarily conform to the Code requirements for range. In these cases, high quality calibrated instruments will be used where the ' reading' accuracy is at least equal to the Code-requirement for i full scale accuracy. This will ensure that the measurements are always more accurate than the accuracy as determined by combining the requirements of Table IWP 41101 and Paragraph IWP4120.
ALTERNATE TESTING:
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Whenever portable instruments are used for measuring performance parameters, the instruments will be such l.
that the ' reading' accuracy is as follows
- Temperature t5 percent Speed t2 percent 1
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Status: IST Program 1990
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, POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0
, December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF j UNITS 1 AND 2 REUEF REQUEST NO. PRR 2 COMPONENTL Applicable to all pumps in the Program SECTION XI REOUIREMENT:
Each inservice test shall loclude the measurement and observation of all quantitles in Table IWP 31001, (IWP4300)
Pump inlet pressure shall be measured before starting a pump and during the test. (rable IWP 31001)
BASIS FOR REUEF:
If a pump being tested is in operation as a result of plant or system needs, it is unreasonable to reconfigure system lineups simply to provkle for measurement of static inlet pressure.
Inlet pressure prior to pump startup is not a significant parameter needed for evaluating pump performance or its material condition.
ALTERNATE TESTING: .
When performing a test on a pump that is already in operation as a result of system or plant requirements, inlet
{ pressure will only be measur^ 1 during pump operation.
( Status: IST Program 1990 Page 2 of 21
, POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
- llNSERVICE TESTING PROGRAM Revialon 0 DGeember 18,1990 l APPENDIX C 4
PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2
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! REUEF REQUEST NO. PRR 3 UNITS: 1 and 2 l COMPONENTS: Safety injection Pumps, P 015 A&B 1
SECTION XI REQUIREMENT:
The resistance of the system shall be varied until either the differential pressure or the measured flowrate equals the corresponding reference value. The test quantitles shown in Tablo IWP 31001 shall then be measured or observed. (IWP 3100) ;
I When a reference value or set of values may have been affected by repair or routine servicing of a pump, a new l
reference value or set of values shall be determined, of the previous value reconfirmed by an inservice test run <
prior to, or within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after, retum of the pump to normal service. (IWP 3111) 1 BASIS FOR RELIEF: )
The inserv6ce testing of these pumps is accomplished by operating the pumps in a recirculation mode through a ftxed flow limiting orifice. The orifice is sbed such that pump operation is in the flat (horizontal) region of the pump characteristic curve where pump head is relatively independent of flowrote, Under these test conditions
( flowrate measurements may not be Indicative of pump performance.
NRC Generic Letter 8944, Position 9, allows elimination of flowrate measurements during quarterly testing where flowtate instrumentation is unavailable provided that appropriate Inservice tests are performed during cold shutdowns or refueling where full or substantial flow conditions can be establishod and flowrates measured.
The only practical means of establishing full or substantial flow and obtaining quantitative flowrate data during testing of these pumps requires pumping into the reactor coolant system (RCS). During plant operation under normal conditions, this is not possible due to the large differential between the RCS and the maximum pump discharge pressure. Under shutdown conditions when the RCS is de pressurized, operation in such a mode is precluded by low temperature over pressurization concems and restrictions.
Performing post maintenance testing for,all reference values would require a pl. ant shutdown and cooldown prior to retuming a repaired pump to service. Tests performed in the recirculation mode (quarterty) are sufficient to provide adequate assessment of the pump to perform its safety function.
ALTERNATE TESTING:
During each inservice test of these pumps performed in the recirculation mode via the fixed orifice, all required pump parameters (per IWP4100), except flow, will be measured, recorded, and evaluated.
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i POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 i PUMP PROGRAM REQUESTS FOR RELIEF j UNITS 1 AND 2 a i ( l l
At least once during eacn reactor refueling when significant flow can be established through an instrumented (flowrate) test circutt, an Inservice test will be performed where all required pump parameters will be measured
, and recorded at three (3) points along the pump curve. Test data taken at these points will be evaluated in accordance with IWP 3200.
Should maintenance be performed that requires post maintenance testing por INP 3111, testing will be performed as follows:
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if the plant is not in a refueling shutdown condition such that the testing in the recirculation mode is the only testing practical, then such testing will be performed and the test results evaluated per IWP 3111. Fo! lowing 1
this, the subject pump will be tested during the next refueling shutdown period where all parameters (including flowrate) will be measured and evaluated with respect to IWP 3111.
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- If the plant is in a refueling shut &#wn condition, the subject pump will be tested with all parameters (including flowrate) measured and evaluated with respect to IWP 3111.
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( Status: IST Program 1900; VRR 3 (Approved via GL 89 04)
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, POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM i INSERVICE TESTING PROGRAM Revision 0 l December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. PRR 4
- UNITS: 1 and 2 COMPONENTS: Residual Heat Removat Pumps, P 010 A&B SECTION XI REQUIREMENT:
! The resistance of the system shall be varied until either the differential pressure or the measured flowrato equals the corresponding reference value. The test quantitles shown in Table IWP41001 shall then be measured or observed. (IWP4100) l When a reference value or set of values may have been affected by repair or routino servicing of a pump, a new I reference value or set of values shall be determined, or the previous va!Ue reconfirmed by an inservice test run l prkx to, or within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after, retum of the pump to normal service. (IWP4111)
BASIS FOR RELIEF:
The only practical means of establishing full or substantial flow and obtaining quantitative and meaningful flowrate data during testing of these pumps requires pumping into the reactor coolant system (RCS). During plant operation under norma! conditions, this is not possible due to the large differential between the RCS and j the maximum pump discharge pressures. Thus, the quarterly inservice testing of these pumps is accomplished i by operating the pumps in a recirculation mode through a fixed flow limiting orifice. The ortflee is sized such l
that pump operation in the flat (horizontal) region of the pump characteristic curve where pump head is relatively l Independent of flowrate, in addition, the range and accuracy of the flow instrumentation do not provide adequate repeatabilty at the reduced flowrate available in this flow scheme. Under such test conditions, flowrate measurements may not be indicative of pump performance.
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- NRC Generic L.stter 8904, Position 9, allows elimination of flowrate measurements during testing where flowrate l Instrumentation is unavailable provided that appropriate inservice tests are performed during cold shutdc,wns or l refueling where full or substantial flow conditions can be established and flowrates measured.
Performing post maintenance testing forall reference values would require a plant shutdown and cooldown prior to retuming a repelred pump to service. Tests performed in the recirculation mode are sufficient to provide adequate assessment of the pump to perform its safety function.
l ALTERNATE TESTING:
During each inservice test of these pumps performed in the recirculation modo via the fixed orlflee, all required pump parameters (per IWP4100), except flow, will be measured.
During refueling shutdown periods when operation of the residual heat removal system is practical and significant flow can be established through an instrumented (flowrate) test circuit, an inservice test will be performed where all required pump parameters will be measured and recorded at three (3) points along the l pump curve. Test data taken at these points will be evaluated in accordance with IWP4200.
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 Should maintenance be performod that requires post maintenance testing per IWP 3111, testing wlll be performed as follows:
If the plant is not in a refueling shutdown condition such that the testing in the recirculation mode is the only testing practical, then such testing wl!I be performed and the test results evaluated per IWP 3111. Following this, the subject pump will be tested during the next refueling shutdown period where all parameters (including flowrate) will be measured and evaluated with respect to IWP 3111.
- If the plant is in a refueling shutdown condition, the subject pump will be testod with all parameters (Incitding fIcmrate) measured and evaluated with respect to IWP 3111.
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( Status: IST Program 1980; VRR-4 (Approved via GL 8944)
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' POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM i
INSERVICE TESTING PROGRAM Revision 0
' December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF 4
UNITS 1 AND 2 4
REUEF llEQUEST NO. PRR 5 l
,UffLt 1 and 2
_ COMPONENTS: Auxillary Feedwater Pumps, P 029( 2 pumps) and P 038 A&B SECTION XI REQUIREMENT:
The resistance of the system shall be varied until either the differential pressure or the measured flowrate equals the corresponding reference value. The test quantitles shown in Table IWP41001 shall then be measured or observed (IWP4100)
When a reference value or set of values may have boon affected by repair or routine servicing of a pump, a new reference valve or set of values shall be determinod, or the previous value reconfirmed by an Inservice test run prior to, or within 06 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after, retum of the pump to normal service. (IWP4t11)
BASIS FOR REllEF:
The only practical rneans of establishing full or substantial flow and obtaining quantitative and meaningful flowrato data during testing of these pumps requires pumping into the steam generators, During plant operation under normal conditions, this is und6sirable due to the possibility of causing thermal shock to the abxillary
( foodwater piping nozzles. For this reason the inservice testing of those pumps is accomplished by operating the pumpe in a recirculation mode through a fixed flow limiting orifice, The orifice is sized to provide pump operation in the flat (horizontal) region of the pump characteristic curve whero pump head is relatively independent of florate, in addition, flow instrumentation is not provided in this test scheme. Thus, under those test condklons, flowrate measurements are neither practical nor would they provide any meaningful information if available.
NRC Generic Letter 89-04, Position 9, allows elimination of flowrato measurements during quarterly testing where flowrate instrumentation is unavailable provided that appropriato inservice tests are performed during cold shutdowns or refueling where full or substantial flow conditions can be established and flowrates moasured.
Performing po6t maintenance testing for all reference values would require a plant shutdown and cooldown prior to retuming a repa' red pump to serv 6ce, Tests performed in the recirculation mode (quarterty) are sufficient to provide adequate assessment of the pump to perform its safety function.
ALTERNATE TESTING:
During each quarterly inservice test of these pumps performed in the recirculation mode via the fixed orifice, all required pump pararneters (per lWP4100), except f!ow, will be measured, recorded, and evaluated.
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Pago 7 of 21
i , POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
)
INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF j UNITS 1 AND 2 Should maintenance be performed that requires post maintenance testing per IWP 3111, testing will be performed as follows: *
- If the plant is not in a cold shutdown condition such that the testing in the recirculation mode is the only tssting practical, then such testing will be performed and the test results 6 valuated per IWP 3111. Following this, the subject pump will be tested during the next cold shutdown period where all parameters (including flowrote) wil be measured and evaluated with respect to IWP 3111, If the plant is in a cold shutdown condition, the subject pump will be tested with all parameters (including flowrate) measured and waluated with respect to IWP 3111, During cold shutdown periods when operation of the auxillary feedwater pumps pumping to a steam generator is possible without the potential of thermal shock, inservice testing will be performed where all required pump i parameters will be measured and recorded at three (3) points along the pump curve. Test data taken at these points will be evaluated in accordance with IWP 3200, Testing at cold shutdown will be at a frequency determined by intervals between shutdowns as follows:
For intervals of 3 months or longer each shutdown.
For intervals of less than 3 months testing is not required unless 3 months have passed since the last shutdown test of the subject pump,
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( Status: IST Program 1980; VRR 5 (Approved via GL 89 04) 1 I
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l POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 )
December 18,1990 4 APPENDIX C I j PUMP PROGRAM REQUESTS FOR RtillEF l 4 UNITS 1 AND 2 :
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1 f(EUEF REQUEST NO, PRR4 UNITS: 1 and 2 i COMPONENTS: Containment Spray Pumps, P 014 ASB SECTION XI REQUIREMENT:
4 The resistance of the system shall be varied until either the differential pressure or the measured flowrate equals the corresponding reference value. The test quantitles shown in Table IWP.31001 shall then be measured or observed. (lWP 3100)
BASIS FOR RELIEF:
The only practical means of estabilshing full or substantial flow and obtaining quantitative and meaningful flowrote data during testing of these pumps requircs pumping into the containment spray headers and into the containment atmosphere This is obviously impractical and undesirable. For this reason the quarterly inservice testing of these pumps is accomplished by operating the pumps in a recirculation mode through a fixed flow.
limiting orifice. The orifice la alzad such that pump operation is in the flat (horizontal) reglon of the pump characteristic curve where pump head is relatively independent of flowrate. Note also that flow instrumentation is not provided in the recirculation circuit nor in the constant recirculation line through the eductors. Thus, under these test conditions, flowrate measurements are not possible.
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During each inservice test of these pumps performed in the recirculation mode via the fixed orifice, all required pump parameters (per IWP 3100), except flow, will be measured, recorded, and evaluated.
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( - Status: IST Program 1900; VRR4 (Approved via GL 89-04)
Page 9 of 21
j POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0
- December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF 4
UNITS 1 AND 2
! REUEF REOUEST NO. PRR 7 UNITS: 1 and 2 COMPONENTS: M pumps in the IST Program SECTION XI REQUIREMENTS:
At least one displacement vibration amplRude (peak to-peak) composite) shall be read during each Inservice test.
The direction of dispiacement shall be measured in a plane approximately perpendicular to the rotating shaft, and in the horizontal or vertical direction that has the largest deflection for the particular pump Installation, (IWP-4510)
The allowable ranges of inservice test quantkles in relation to the reference values are tabulated in Table IWP.
3100 2. (lWP 3210)
BASIS FOR REUEF:
Measuring vibration in velocity unks rather than displecement is an Industry accepted practice considered to be more sensitko to small changes that are indicatNe of developing mechanical problems. Velocity measurements detect not only high-amplitude vibration, characteristic of major mechanical problems, but low amplhude vibmtion, as well, caused by misalignment, Imbalance, or minor bearing wear,
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it is impractical to search for the direction with the largest deflection and procedurally return to that precise location on successNe tests, in addition, the direction of maximum deflection may vary with the material condition and age of the pump thus eliminating consistency between test data. Adapting this reqqlrement to test procedures could cause confusion as to the proper locations for measuring pump vibration. Also, comparing subsequent test data to reference test data taken at different locations does not provide a good measure of pump degradation.
ASME/ ANSI OMa 1967 Operation and Maintenance Of Nuclear Power Plants, Part 6, Section 4.6.4 has adopted the concept of measuring vibration at two mutually perpendicular locations and comparing subsequeat test data to the reference value at that specific location.
Measuring vibration in velocity units is permitted by the n.ost recent version of OM b 1989 Standard For Intervice Testing At Nuclear Power Plants, Part 6.
! ALTERNATIVE TESTING:
Pump vibration measurements may be taken in either displacement or velocity units. Acceptance criterla for
- velocky measurements will conform to those set forth in OM b 1989, Part 6, Tables 3 and Sa.
i' For centrifugal and rotary (non-reciprocating) positNe displacement pumps vibration readings will be taken in a plane perpendicular to the operating shaft in two (2) mutually perpendicular directions. Test data shall be l evaluated per IWP 3100 with successNe vibration readings compared to reference values previously taken at that L specific location.
I Status: Proposed to NRC March 2,1990 as PRR 11 Page 10 of 21
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM i INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2
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REUEF REQUEST NO PRR4 UNITS. I and 2 COMPONENTS.; All pumps in the Program SECTION xLBEDUIREMENT:
The temperature of all centrifugal pump bearings outside the main flowpath and of the main shaft bearings of reciprocating pumps shall be measured at points selected to be responsive to changes in the temperature of the bearings. (IWP 3300,4310)
BASIS FOR REl,1F.fi The data associated with bearing temperatures taken at one year Intervals provides little statistical basis for determining the heremental degradation of a bearing or any meaningful trending infomiation or correlation.
In many cases the pump bearings are water cooled and thus, bearing tirrporatufe is a function of the temperature of the coollog medium, which can vary considerably.
V"esition measurements are a significantly more rollable indication of pump bearing degradation than are temperature meaturements. All pumps in the program are subjected to vibration measurements in accordance
{ with (WP 4SCO.
Although excessivt' bearing te nperature is an Indication of an imminent or existing bearing failure, it is highly unlikely that such a conditlen would go unnoticed durhg routine surveillance testing since it wot.!d manifest itself in other obvious indications such as audible noise, unusual vibration, increased motor current, etc.
Any potential gain from taking bearing rt.oasurements, which in most cases would be done locally using portable instrumentation, cannot offset the cost in terms of dilution of operator effort, distraction of operators from other primary duties, excessive operating perlods for standby pumps especially under mlnlmum flow conditions, and unnecessary personnel radiation exposure.
ALTERNATE TESTING:
9 Vibration monitoring will be performed using units of velocity Vla state-of the-art data analysis equipment provided Relief Request No. 7 is approved. Such vibration monitoring will provide adequate monitoring and evaluation of the matetial condition of the pump bearings.
( Status: Prooosed to NRC March 2,1990 as PRR 12 Page 11 of 21
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM - Revision 0 December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF g UNITS 1 AND 2 REUEF REQUEST NO. PRR 9 IJNITS; I and 2 COMPONENTS: M pumps in the Program SECTION XI R20UIREMENT:
inne presence or absence of liquid in a gage line could produce a difference of more than 0.25% in the indicated value of the measured pressure, means shall be provided to ensure or determine the presence or absence of ligeM at required for the static correction used. (lWP 4210)
, BASIS FOR REUEE:
I When this requirerrm is applied to the measurement of purrs suction pressure where measured pressures are at relative low tovels, thv 9.25.: limit is overly restrletive and oftentimes results in compilcated venting procedures and unneceuwy health phpa risks associated with handling and disposal of radioactive contaminated water with no commensurste gain or improvement of test reliability.
Nomully, the only quantitative use of suction pressure measurements, where significant accuracy is required, is in determining pump differential pressure or head. In most cases the pump discharge pressure exceeds the suction pressure by at least a factor of five (5). This being the case, a .25% error introduced into the suction pressure measurement results in an error of .05% in the differential pressure calculation. This is insignificant in light of the potential 6% error allowance applied to both the suction and discharge pressure instruments (Ref IWP-4110),
ALIFRNATE TESTING:
If the presence or absence of liquid in a page line used for sensing pump suction pressure could produce a difference of more than 0.25% in the calculated value of the pump differential pressure, means shall be provided to ensure or determine the presence or absence of liquid as required for the static correction used.
( Status: IST Program 1990 Page 12 of 21
1 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM l lNSERVICE TESTING PROGRAM Revision 0 l December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF j UNITS 1 AND 2 REUEF REQUEST NO. PRR.10 UNITS: 1 and 2 COMPONENTS: All pumps in the Program SECTION XI REQUIREMENT:
Instrument accuracy shall be within the limits of Table IWP 41101. (For pressure and flowrate this is
- 2 percent.) (IWP 4110)
The full scale range of each Instrurnent shall be three times the reference value or less (IWP 4120)
BASIS FOR RELIEF:
The Intent of Articles 4110 and 4120 is to ensure that the recorded test parameters are accurate within certain bounds, thereby providing assurance of accuracy and repeatability.
The articles do not provido any guidance on the specific bounds within which they apply, it is unclear whether or not primary sensors are considered.
{ Further numerous instrument loops in our facility utillze remote Indicators without redundant, local indication.
ALTERNATE TESTING:
For instruments which have primary sensors associated with the instrument loop (an orifice for flow, for example) the primary sensor accuracy is not considered. This will not affect repeatability.
For instruments which have Instruments and Indicators positioned locally, and when remoto, computerized Indication is used, Table 41101 will be applied.
For instrument loops which consist of transmitters and remote readouts, for pressure, differential pressure and flowrate, an acceptable accuracy is *3%
P-I Status: IST Program 1980: PRR 10 (Approved via GL 8944)
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Page 13 of 21
, POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF j UNITS 1 AND 2 REUEF REQUEST NO, PRR 11
.UN[IF,1 and 2 COMPONENTS: Boric Acid Transfer Pumps, P404 A&B SECTION XI REQUIREMENT:
The resistance of the system shall be varied until either the differential pressure or the measured flowrate equals the corresponding reference value. The test quantitles shown in Table IWP41001 shall then be measured or observed. (lWP4100)
BASIS FOR REU8~
The quarteriy in %e testing of these pumps is accomplished by operating the pumps in a recirculation mode in a circuit hav a no capability for flow measurement. A test circuit is available in which pump flowrate can be measured however ft requires injection of higNy concentrated bcric acid solution into the reactor coolant system. During plant operation, this is not practical since it would upset the reactor coolant boric acid balance and adversely effect reactor power and create a plant power transient. If injection were to be performed during cold shutdown periods (other than refueling) the result would be over boration of the RCS and associated potential operating difficulties during the subsequent plant startup.
NRC Generic l.etter 8944. Position 0, allows elimination of flowrate measurements during quarterly testing where flowrate instrumentation is unavailable provided that appropriate Inservice tests are performed during cold shutdowns or refueling where full or substantial flow conditions can be established and flowrates measured.
ALTERNATE TESTING:
During each Inservice test these pumps will be operated in the recirculation mode via the non-instrumented flow loop.
At least once during each reactor refueling an Inservic9 test will be performed where all required pump parameters will be measured, recorded, and evaluated in accordance with IWP4100.
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( Status: IST Program 1990 l
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Page 14 of 21 l 1
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 4
REUEF REQUEST NO. PRR 12 UNITS.1 and 2 COMPONENTS: Boric Acid Transfer Pumps, P-004 A&B SECTION XI REQUIREMENTS:
An Inservice test sha'l be run on each pump nominally every 3 months during normal plant operation, (IWP-3400(a))
Each inservice test shall include the measurement and observation of all quantitles in Table IWP 31001 except bearing temperatures, which shall be measured during at least one inservice test each year. (lWP 3300)
BASIS FOR REUEF:
The system Installations do not provide any mechani.m for measuring pump suction pressure, discharge pressure, or pump flowrate during normal plant opera..an. The only practical method of determining pump flowrate is to pump to the RCS, Due to the problems associated with over boration of the RCS. this can only be done during reactor refueling outages.
To prevent boric acid crystallation each of these pumps is encapsulated in insulation and is heat traced
.{ precluding access for measuring pump or motor vibration. It is impractical to routinely remove this insulation to prodde such access.
The CVCS system is configured such that any of the four (4) boric acid transfer pumps (2 in each unit) can supply either unit if necessary. This provides a significant amount of redundancy and reliability for the function of RCS boration, in consideration of this, a reduced frequency and reduced scope of testing of these pumps is adequate.
ALTERNATE TESTING:
During reactor refueling outages each of these pumps will be tested and flowrate will be verified to be adequate to serve its safety function. In conjunction with these tests pump vibration will be measured as practical considering the insulation encapsulation, f
Status: IST Program 1990 Page 15 of 21
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICA TESTING PROGRAM Revision 0 December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF
, UNITS 1 AND 2 REUEF REQUEST NO. PRR 13 UNITS: 1 and 2 COMPONEPRS: Service Water Pumps, P 032 A through F SECTION XI REQUIREMENT:
Each inservice test shall includd the measurement and observation of all quantitles in Table IWP 31001.
(lWP 3300)
Pump Inlet pressure shall be measured before starting a pump and during the test. (Table IWP 31001)
BASIS FOR REUEF:
The pumps listed above are vertical line shaft pumps submerged in the intake structure with no practical means of measuring pump Inlet pressure. The inlet pressure, however, can be determined by calculation using, as input, the measured height of water above the pump Inlet as measured at the intake.
During each Inservice test, the water leve' 'a the intake pit remains relatively constant, thus only one measurement of level and the associatec. suction pressure calculation need be performed.
ALTERNATE TESTING:
During testing of these pumps, one value of inlet pressure will be calculated based on water level at the intake structure.
Status: IST Program 1990 (formeriy IST Program 1980 Pump Note 4)
Page 16 of 21
POINT BEACH NUCLEAR Pl. ANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF
, UNITS 1 AND 2 1
REUEF REQUEST N0. PRR 14 UNITS: 1 and 2 COMPONENTS: CVCS Charging Pumps, P 002 A through C SECTION XI REQUIREMENT:
Each inservice test shall inclu;ie the measurement and observation of all quantitles in Table IWP 31001.
(lWP 3300)
BASIS FOR REUEF:
The CVCS configuration is such that there is no installed instrumentation provided for measuring charging pump suction c r differential pressures. Installation of temporary Instrumontation is burdensome and there is little value in measudng these parameters.
The Charging Pumps are multiple plunger, positke displacement reciprocating pumps where the pump discharge pressure is purely a function of pump design and is independent of suction pressure. This is reflected in ASME/ ANSI OMa 1987, Operation and Maintenance Of Nuclear Power Plants, Part 6 (Tables 2 and 3b) where this new standard requires measuremont and evaluation of pump discharge pressure as opposed to differential
( pressure. Further, suction pressure measurements are not required.
ALTERNATE TESTING:
During Insorvice testing of the Charging Pumps, suction and differential pressures will not be measured nor recorded, in lieu of this, pump discharge pressure will be measured and evaluated per IWP-3200 and IWP-6000.
( Status: IST Program 1990 Page 17 of 21
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM llNSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF 4
UNITS 1 AND 2 REUEF REQUEST NO. PRR 15 UNITS: 1 and 2 COMPONENTS: Cable Spreading Room Chilled Water Pumps, P 111 A&B Control Room Chilled Water Pumps, P 112 A&B SECTION XI REQUIREMENT:
Each inservice test shall include the measurement and observation of all quantitles in Table IWP 31001.
0WP 3300)
SASlS FOR REUEF:
The chilled water system configuration is such that there is no installed instrumentation provided for measuring .
flowrate, however, the installation does provide for the capability of operation under a constant (fixed) resistance mode such that pump can be monitored and evaluated from pump differential pressure.
ALTERNATE TESTING:
During inservice testing of these chilled water pumps, the pumps will be operated in a mode such that the system resistance is flxed and repeatable. During these tests, pump differential pressure will be measured and
~{ evaluated in accordance with IWP 3210.
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Status: IST Program 1990 l
Page 18 of 21 l
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF
[. UNITS 1 AND 2 REUEF REQUEST NO. PRR 16 UNITS- 1 and 2 COMPONENTS: All pumps in the program for which differential pressure is determined.
SECTION XI REQUIREMENT: Differential pressure is a measured parameter (IWP.3100,3110)
BASIS FOR RELIEF:
Pumps are not equipped with instruments which directly provide a value for differential pressure.
ALTERNATE TESTING:
Differential pressure will be a calculated value based on the values of suction an discharge pressure.
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3 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDlX C PUMP PROGRAM REQUESTS FOR RELIEF
! UNITS 1 AND 2 REUEF REQUEST NO. PRR 17
. UNITS- 1 and 2 COMPONENTS: Safety injection pumps, P 015A&B Residual Heat Removal Pumps P 010A&B SECTION XI REQUIREMENTS:
Each pump shall be run at least five minutes under conditions as stable as the system permits. At the end of thls time at least one measurement or observation of each of the quantitles specified shall be made and recorded (IWP 3500).
BASIS FOR REUEF:
When performing the three data point fu!!y instrumented, significant flowrate test at refueling shutdown conditions, the pumps use the RWST as a suction source and deliver to the refueling cavity. The RWST does not contain a sufficient amount of fluid to allow each pump to run at the reference point for five minutes plus get performance data at two other points.
The overall run time for the complete test of each pump (three or more data points) does exceed five minutes, f When performing periodic noninstrumonted rec;re line testing, the pump will be operated for at least five minutes.
ALTERNATE TESTING:
When performing three data point pump curve testing, which includes reference point data, an overall run time of f)ve minutes will be met. Pump operation during periodic recirc line testing will be at least five minutes in duration.
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. POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 Decernber 18,1990 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF
[ UNITS 1 AND 2 REUEF REQUEST NO. PRR 18 UNITS: 1 and 2 COMPONENTS: Auxiliary Feedwater Pumps, P429 (2 pumps) and P 038A&B SECTION XI REQUIREME@
Each pump shall be run at least five minutes under conditions as stable as the sys!em permits. At the end of this time, at least one measurement or observation of each of the quantitles specified shall be made and recorded (lWP4500).
BASIS FOR RELIEF:
. During cold shutdown periods when operation of the auxillary feedwater pumps pumping to a steam generator is possible without the potential of thermal shock, inservice testing will be performed such that all required pump parameters will be measured and recorded at three (3) points along the pump curve.
At this time, however, there is very little decay heat remaining in the RCS system. Sustained operation of auxilary feedwater at substantial flowrates causes significant pressure decreases in the reactor coolant system which challenge reactor coolant pump operation limits and cause reactor coolant level decreases due to
( temperature induced shrink.
ALTERNATE TESTING:
When performing three data point pump curve testing, which includes reference point data, an overall run time of ftve minutes will be met. Pump operation during periodic recirc line testing will be at least five minutes in duration.
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Page 21 of 21
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
-. INSERVICE TESTING PROGRAM Revision O December 18,1990 APPENDIX D l
UNIT 1 VALVE PROGRAM TABLES CONTENTS System EAge Auxillary Feedwater System S Auxillary Steam, Heating Steam, Chilled & Hot Water 8 Chemical and Volume Control 10 Component Cooling Water 13 Containment Spray 18 Delontzed and Reactor Makeup Water 21 Emergency Diesel Generator Air Start 22 Emergency Diesel Generator Fuel Oil 25 Heating and Ventilation 27 instrument Air 31 Maln Feedwater 35 Main and Reheat Steam 36 Post Accident Containment Vent / Monitoring 39 Primary Sampling 41 Reactor Coolant- 43
{ Safety injection and Residual Heat Removal 46 Service Air SS Service Water 56 Spent Fuel Pit Cooling 63 Waste Disposal 64 Notes 66 M. --
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Page 1 of 64
u-POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision O December 18,1990 APPENDIX D
( UNIT 1 VALVE PROGR/'M TABLES LEGEND VALVE The plant alpha numerical designator for the subject valve.
CORD The coordinate location of the valve on the designated drawing.
CLASS The ISI classification of the valve as per the respective ISI boundary drawings.
CAT The valve category per Paragraph IWV 2200.
SIZE The valve's nominal size in inches.
TYPE The valve type AP Pneumatic Pilot BA Ball BTF Butterfly CK Check DI Diaphragm GA Gate GL Globe
( SCK Stop/ Check SRV Safety / Relief NE Needle (throttle) l ACT The valve actuator type as fcilows:
AO Air operated HO Hydraulic-operated MA Manual valve MO Electric motor operated SA Self actuated SO Solenoid operated .. ,
' ,POb s
Designates.the no . I position of the valve during plant operation at pdO -
6' id) A4 3 [t ,, , o
- . . F 7 FDOf3Tv.. , . .
, elast requir,e, m entsjog'o asiollows:
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BT C Exercise to closed position. For power-operated valves, stroke times will be measured unless excluded by an associated relief request.
BT O Exercise to open position. For power operated valves, stroke times wlli be measured unless excluded by an associated relief request.
I BT EE Exerciso valve to verify proper operation and stroking with no stroke time measurements. Requires observation of system parameters or local observation nf
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valve operation.
Page 2 of 64
1 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision O !
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES
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BT PV Exercise of pneumatic pilot valve. Proper operation of the associated main valve verlfles operability.
CV C Exercise check valve to the closed poC.on.
CV.O Exercise check valve to the full open posl tion.
CV PO Partial stroke exercise check valve in the open direction.
CV PC Partial stroke exercise check valvo in the close direction.
FST Fall safe test.
1 INSP Disassembly and inspection of check valves.
plt Position Indication verification per IWV 3300.
RVT Safety / Relief valve setpoint test per ASME OMa 1.
SLT 1 Seat leakrate test per 10 CFR 50, App. J.
SLT 2 Seat leakrate test for pressure isolation valves per Technical Specification 15.3.16.
f SLT-3 Seat leaktate test for pneumatic check valves to verify capability of maintaining accumulator gas inventory following loss of supply system pressure. ,
SLT 4 Leak testing of safety injection accumulator check valves.
SLT5 Seat leakrate test to identify gross leakage. Specific leakage rates will not be measured but leakage will be determined and evaluated with respect to system operability and its capability to perform its safety function per IWV 3531.
SLT 6 Seat leakrate test to identify gross leakage. Specific leckage rates wiil bo measured and evaluated with respect to system operability and its capabiilty to perform its safety function per IWV 3521.
TEST FREO The required test interval aobreviations are defined as follows:
RR Each reactor refueling outage (cycle)
CS Cold shutdown (per Technical Spocifications)
E CS Cold shutdown with Event V testing required OR Ouarterly (Juring plant operation) 2Y Every 2 years SY Every 5 years 10Y Every 10 years l SR Prior to placing a system or component in operable status SP Other (see applicable request for rollef)
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Page 3 of 64
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision O December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES
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REMARKS Applicable requests for relief from code requirements (see Appendix F) are noted in the REMARKS column adjacent to the associated test requirement and designated VRR XX.
Appilcable notes are included in the REMARKS column and are designated NOTE XX. A list of notes is attached as the last page of the appendlx.
Cold shutdown testing justifications are provided in Appendix G. Each explanation is identified by a reference number (CSJ XX) that appears in the respective REMARKS column adjacent to the pertinent test requirements.
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POINT DEACH NUCLEAR PLANT INSERVICE TESTIN IOGRAM '
((0)) w INSERVICE TESTING PROGRAM Revision O December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: AuxRiary Feedwater DRAWING NO.: M-217 VALVE CORD FUNCTION C: ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS AF-00026 C4 1P-29 Suction 3 8 6 GA MA O BT-C OR AF-00039 E4 1P48A Suction 3 B 4 GA MA O BT-C OR AF-00052 F4 1P48B Suction 3 8 4 GA MA O BT-C OR AF-00100 B9 AFW to I A S/G 2 C 3 CK SA C CV-O CS CSJ-1 AF4)0101 D9 AFW to 18 S/G 2 C 3 CK SA C CV-O CS CSJ-1 AF-00102 B8 AFW to 1A S/G 2 A/C 3 CK SA A/C CV-O CS CSJ-1 CV-C CS CSJ-1 SLT-5 2Y AF-00t04 D8 AFW to IB S/G 2 A/C 3 CK SA A/C CV-O CS CSJ-1 CV-C CS CSJ-1 SLT-5 2Y AF-00106 B8 AFW to 1 A S/G 2 A/C 3 CK SA A/C CV-O CS CSJ-1 SLT-5 2Y AF-00107 D8 AFW to 1B S/G 2 A/C 3 CK SA A/C CV-O CS CSJ-1 .
SLT-5 2Y AF-00108 C7 1P-29 Disch Ck 3 C 4 CK SA C CV-O CS CSJ-2 AF-00109 D6 P-38A Disch Ck 3 C 3 CK SA C CV-O CS CSJ-2 AF-00110 F8 P-388 Disch Ck 3 C 3 CK SA C CV-O CS CSJ-2 i AF-00111 CS 1P-29 Suct Ck 3 C 6 CK SA C CV-PO OR CSJ,3 CV-O CS AF4)0112 E5 P-38A Suct Ck 3 C 4 CK SA C CV-PO OR CSJ-3 Cvo CS Page 5 of 64
. _ _ _ _ _ _ _. _- . . = _ _ . -_
, - e POINT BEACH NUCLEAR PLANT INSERVICE TESTIN tOGRAM. ~
w INSERVICE TESTING PROGRAM Revision O e i December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Auxiliary Feedwater DRAWING NOc M-217 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS AF-00113 F5 P-38B Suct. Ck- 3 C 4 CK SA C CV-PO OR CSJa CV-O CS AF-04000 C8 18 S/G AFW lsci 3 B 3 GL MO C BT-C OR PIT 2Y AF-04001 B8 1A S/G APNisol 3 8 3 GL MO C BT-C OR FIT 2Y AF-04002 C6 1P-29 Mini-flow 3 8 1 GA AO O BT-C OR FST OR h PIT 2Y AF-04006 DS 1P-29 Ser Wtr 3 8 6 GA MO O BT-O OR Sup PIT 2Y AF-04007 D6 P-38A Mini-flow 3 8 1 GA AO O BT-C OR FST OR PIT 2Y AF-04009 ES P-38A Ser Wtr 3 8 4 GA MO O BT-O OR Sup PIT 2Y AF-04012 E6 P-38A Press Con 3 8 3 GA AO O BT-O OR FST OR PIT 2Y AF-04014 E6 P-388 Mini-flow 3 8 1 GA AO O BT-C OR FST OR '
PIT 2Y AF-04016 F5 P-388 Ser Wtr 3 B 4 GA MO O BT-O OR Sup PIT 2Y Page 6 of 64
n an .m POINT BEACH NUCLEAR PLANT INSERVICE TESTIF -10 GRAM ,
INSERVICE TESTING PROGRAM Revision 0 ,
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Auxiliary Feedwater DRAWING NO.: M-217 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS AF-04019 F6 P-388 Press Con 3 8 3 GA AO O BT-O OR FST OR PIT 2Y AF-04021 E7 APN to 18 S/G 3 8 3 GA MO O BT-O OR BT-C OR ,
PIT 2Y AF-04023 D8 AFW to 1 A S/G 3 8 3 GA MO O BT-O OR BT-C OR PIT 2Y AF-04026 C6 P-029 Suction Rol 3 C 1 SRV SA C RVT 10Y AF-04027 F6 P-0388 Suction 3 C 1 SRV SA C RVT 10Y Rei -
AF-04028 E6 P-038A Suction 3 C 1 SRV SA C RVT 10Y Rei i l
l Page 7 of 64
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POINT BEACH NUCLEAR PLANT INSERVICE TEST PROGHAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Aux Steam. Heating Steam, Chilled and Hot Water ORAWING NO.: M-214, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO- REMARKS HV-00632 D7 - Aux Stm to Cont 2 A 3 GA MA C SLT-1 2Y VRR-23 Passive HV-00633 A7 Aux Stm Cond Ret 2 A 1.5 GA MA C SLT-1 2Y VRR-23 Passive HV-00808 B7 Aux Stm Cond Ret 2 A 15 GA MA C SLT-1 2Y VRR-23 Passive HV-00809 A7 Aux Stm Cond Ret 2 A 1.5 GA MA C SLT-1 2Y VRR-23 Passive
. HV-00818 C7- Aux Steam to Cont 2 A 3 GA MA C SLT-1 2Y VRR-23 Passive Page 8 of 64
- __-L. __ -_ - '-_W
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INSERVICE TESTIN. .OGRAM .
POINT BEACH NUCLEAh PLANT Revision O ,
wC INSERVICE TESTING P@ GRAM December 18,1990 A
APPENDIX D ,
UNIT 1 VALVE PROGRAM TANLES f
SYSTEM: Atu Steam Heating Steam, Chilled and Hot Water DRAW 1NG NO.: M-214. Sheet 1 SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT SA O CVPO OR VRR-31 j C8 Pump P-112A Disc NC A/C 3 CK HV40898A CV-C OR Ck l
O CV-PO OR VRR-31 Pump P-1128 Disc NC A/C 3 CK SA HV40900A 88 OR CV-C Ck SLT-5 OR INSP SP VRR-31 SA O CV-PO OR VRR-31 88 Pump P-111 A Disc NC A/C 3 CK l HV-00914A CV-C OR Ck SLT-5 OR INSP SP VRRG1 O CV-PO OR VRR-31 Pump P-111B D$sc NC A/C 3 CK SA HV-00916A A8 OR CV-C Ck SLT-5 OR INSP SP VRR-31 i
Page 9 of 64
- i. . .
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POINT BEACH NUCLEAR PLANT INSERVICE TESTI ROGRAM .
INSERVICE TESTING PROGRAM Revision O '
.- December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES
' SYSTEM: Chernical and Volume Contrcl DRAWING NO.: 684J741 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CV-00112B B10 RWST to Chg Pump 2 B 4 GA MO C BT-O OR PIT 2Y CV-00112C C10 VCT to Chg Pianp 2 B 4 GA MO O BT-C CS CSJ4 PIT 2Y CV-00142 C12 Charging Flow Cont 2. B 3 GL AO O BT-O CS CSJ-5 g FM G ,
PIT 2Y CV-00283A B12 Chg Pump Disc Sa! 2 C _75 SRV. SA C e RVT 10Y s CV@2838 B12 Chg Pump Disc Saf 2 C .75 SRV SA C RVT 10Y CV-00283C A12 Chg Pump Disc Saf 2 C .75 SRV i SA C RVT 10Y CV-00295 C14 Charging Hdr CR 1 C 3 CK SA O CV-O OR CV-00300A A14 RCP Sealinj Thrt! 2 A 1 NE MA T GT-C RR VRR-19 SLT-1 2Y CV-003008 A15 RCP Sealinj Thrti 2 A 1 NE MA T BT-C RR VRR-19 SLT-1 2Y CV-00304C A14 RCP Seal Wtr Sup 1 A/C 2 CK SA O CV-C RR VRR-12 SLT-1 2Y CV-00304D A15 RCP Seal Wtr Sup 1 A/C 2 CK SA O CV-C I:R VRR-12 SLT-1 RR CV-00313 C12 RCP Seal Wtr Ret 2 A 3 GA MO O BT-C CS CSJ6 i PIT 2Y
! SLT-1 2Y l
~
Page 10 of 64 l
POINT BEACH NUCLEAR PLANT INSERVICE TESTIN- OGRAM w C INSERVICE TESTING PROGRAM Revision 0 .'
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Chemical and Volume Control DRAWING NO.: 684J741 i
VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CV4)0313A C13 RCP Seal Wtr Ret 2 A 3 GL AO O BT-C CS CSJ4 FST CS CSJE PIT 2Y !
SLT-1 2Y CV-00323A A12 Aux Chargkg isol 2 A 2 GL MA C SLT-1 2Y Passive CV4)03238 C12 Chg HCV Bypass 2 A 2 GL MA C SLT-1 2Y VRR-23 Passive CV-00333A A6 BA Tmnsfer Pump ' 2 A/O 2 CK SA C CV-PO OR VRR-26 Disch CV-O RR VRR-26 CV-C OR SLT-5 2Y CV-003338 A6 BA Transfer Pump 2 A/C 2 CK SA C CV-PO OR VRR-26 Disch CV-O RR VRR-26 CV-C OR SLT-5 2Y CV-00350 A9 Emerg Boration 2 B 2 GA MO C BT-O OR FIT 2Y CV-00351 A9 Ernerg Boration Ck 2 C 2 CK SA C CV-O RR VRR-24 ,
CV-00357 B10 RWST to Chg Pump 2 C 4 CK SA C CV-O OR CV4)0370 C13 Chaging Hdr Ck 2 A/C 3 CK SA O CV-O OR CV-C RR VRR-13 SLT-1 RR Page 11 of 64
n n POINT BEACH NUCLEAR PLANT INSERVICE TES' PROGRAM ,
INSERVICE TESTING PROGRAM Revision 0 ,
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Chemical and Volume Control '
DRAWING NO.: 684J741 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CV-00371 D13 RCS Letdown Iso 2 A 2 GL AO O BT-C CS CSJ-7 FST CS CSJ-7 PIT 2Y SLT-1 2Y~
CV-00371A D13 RCS Letdown Iso 2 A 2 GL AO O BT-C CS CSJ-7 FST CS CSJ-7 PIT 2Y '
SLT-1 2Y CV-00384B C12 Chg Une HCV Ota 2 A .3 GL MA O BT-C CS CSJ-8 SLT-1 2Y VRR-23 CV4)1296 A14 Aux Charging Iso I A 2 GL AO C PIT 2Y 1 Passive l SLT-1 2Y i
Page 12 of 64
x .
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INSERVICE TESTib 10 GRAM POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM Revision O ,'
w December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES ]
SYSTEM: Component Cooling Water DRAWING NO.: 110E018. Sheet 1 CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION G3 RHR Cooling Water 3 8 to GA MO C BT-O OR CC40738A 2Y Sup PIT G2 RHR Cooling Water ? 8 10 GA MO C BT-O OR CC40738 Sun PIT 2Y l
Page 13 of 64
a
,Mk INSERVICE TESTih IOGRAM POINT BEACH NUCLEAR PLANT ,
Revision 0 w INSERVICE TESTING PROGRAM .
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Component Cooling Water DRAWING NO.: 110E018, Sheet 2 FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD 2 8 6 GA MO O BT-C CS CSJ-9 CC-00719 G11 Contairwnent CCW Sup PIT 2Y 2 A 4 GA MO O BT-C CS CSJ-10 CCOO754A F13 RCP Og Water Sup SLT-1 2Y PIT 2Y 2 A 4 GA MO O BT-C CS CSJ-10 CC-00754B F10 RCP Og Water Sup SLT-1 2Y PIT 2Y 2 4 CK SA O CV-C 2Y VRR-10 CC-00755A E13 RCP Og Wtr Sup A/C SLT-1 2Y VRR-23 Ck 2 4 CK SA O CV-C 2Y VRR-10 CC4X)755B E10 RCP Og Wtr Sup A/C f Ck SLT-1 2Y VRR-23 2 A 4 GA MO O BT-C CS CSJ-10 CCOO759A F11 RCP Og Wtr Ret LT-1 2Y VRR-23 PIT 2Y F8 RCP Og Wtr Ret 2 A 4 GA MO O BT-C CS C^*19 CC-007598 VRR-23 SLT-1 2Y PIT 2Y l
l Page 14 of 64
N POINT BEACH NUCLEAR PLANT INSERVICE TESTIN oOGRAM .
C INSERVICE TESTING PROGRAM Revision 0 '
December 18.1990 APPEN' UNIT 1 ~4AM TABLES -
) %
SYSTEM: Componou Ming Water DRAW lNG NO.: 110E018, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CC-00763A E12 ' RCP Og Wtr Pet 2 C 2 SRV SA C RVT 10Y S/R CC-00763B E8 RCP Og Wtr Ret 2 C 2 SRV SA C RVT 10Y S/R CC-00767 E7 Ex LD HX Og Wtr 2 A/C 2 CK SA C CV-C RR VRRM Sup SLT-1 RR VRR@
CC-000769 F5 Ex LD HX Og Wtr 2 A 2 GL AO C BT-C OR Ret FST OR FIT 2Y SLT-1 2Y r i 1
- Page 15 of 64
POINTBEACH NUCLEAR PLANT TNSERVICE TESTIN :OGRAM w C INSERVICE TESTING PROGRAM ' Revision 0 .'
. December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Component Cooling Water DRAWING NO : 110E018, Sheet 3 VALVE CORD FUNCTION - CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CC-00724A 18 CCW Pump Disch 3 A/C 10 CK SA O CV-O OR Check CV-C OR SLT-5 OR CC-00724B H8 CCW Pump Disch 3 A/C- ;0 CK SA O CV-O OR Check I CV-C OR SLT-5 OR CC-00773 111 CCW Normal 3 B 2 GL MA C SLT-6 2Y Passive Makeup CC-00779 J11 CCW Surge Tank 3 C 3 SRV SA C RVT 10Y Relief CC-00779A J11 CCW Surge Tk Vac 3 C 1 CK SA C CV-O OR Bkr CV-C OR CC-00815 111 CCW Emergency 3 8 2 GL MO C SLT-6 2Y Passive Makeup Page 16 of 64
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POINT BEACH NUCLEAR PLANT INSERVICE TESTIN eOGRAM .
w C' NSERVICE I TESTING PROGRAM
~
. Revision 0 .
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Component Cooling Water DRAWING NO : PBM-230 VALVE '! CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS i
CC-LW-63 H7 CCW Supply to 3 A 6 BTF AO O BT-C OR Raovro ste FST OR
. SLT-6 :iY
' PIT 2Y CC-LW44 A7 CCW Retum from 3 A 6 BTF AO O ST-C OR Radwaste FST OR SLT-6 2Y P'T 2Y l
l Page 17 of 64
n -
n POINT BEACH NUCLEAR PLANT INSERVICE TES PROGRAM ,
INSERVICE TESTING PROGRAM Revision 0 ~
December 18,19S3 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Contmment Spray DRAWING NO : M-110E017, Sheet 3
- VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI40836A F7 NaOH Supply 2 8 2 GL AO C BT-O CS CSJ-11 FST CS G 11 PIT 2Y SI408368 E7 NaOH Supply 2 8 2 GL AO C BT-O CS CSJ-11 FST CS CSJ-11 !
PIT 2Y l SI40840A G5 Spr Add Tank Vac 2 C .75 SRV SA C RVT 10Y Bkr ,
i SI408408 G5 Spr Add Ter* Vac 2 C .75 SRV SA C RVT 10Y Bkr SI40847A H8 Spray Add Educt 2 C 2 CK SA C CV4 OR Check SI-006478 D8 Spray Add Educt 2 C 2 CK SA C CV-O .A SI408S8A 13 RWST to CS Pump 2 C 6 CK SA C CV-PO OR VRR-8 P14A INSP SP VRR-8 SI-00858B C3 RWST to CS Pump 2 C 6 CK SA C CV-PO OR VRR4 j P148 INSP SP VRR-8 SI-008GGA Ito CS Pump 1-P14A 2 8 6 GA MO C BT-O OR Disch PIT OR SI-008608 11 0 CS Pump 1-P14A 2 8 6 GA MO C BT-O OR Disch PIT OR S140860C C10 CS Pump 1#148 2 8 6 GA MO C BT-O OR j Disch , PIT OR -
l Page 18 cl 64
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, POINT BEACH NUCLEAR PLANT INSERVICE TEST )ROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990
[
APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Cesiiwe4 Spray DVWING NO_: M-110E017. Sheet 3 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS S140860D C10 CS Pump 1-P148 2 B 6 GA MO C BT-O OR Disch PIT OR
, SI40862A III CS Pump 1-P14A 2 A/C 6 CK SA C INSP SP VRR-3 Disch SLT-1 RR VRR-23, 29 SI-008628 C11 CS Pump 1-P148 2 A/C 6 CK SA C INSP SP VRR-9 Disch SLT-1 RR VRR-23. 29 i SI-00864A H11 CS Pump Test 2 A .75 GL MA C SLT-1 2Y Passive Recirc VRR-23 i SI-008648 C11 CS Pump Test 2 A .75 GL MA C SLT-1 2Y Passive ,
Recirc VRR-23 i SI-00870A 13 RWST to CS Pump 2 A 6 GA MO O BT-O CS CSJ-29 !
P14A BT-C CS CSJ-29. Note 3 }
SLT-6 2Y Note 2 PIT 2Y [
SI408708 C3 RWST to CS Pump 2 A 6 GA MO O BT-O CS CSJ-29 P148 BT-C CS CSJ-29. Note 3 j , SLT-6 2Y Note 2 PIT 2Y i SI-00871A IS RHR to CS Pump 2 B 6 GA MO C BT-O OR I
, P14A BT-C OR .
, PIT 2Y SI-008716 C5 RHR to CS Pump 2 8 6 GA MO C BT-O OR P148 BT-C OR i j PIT 2Y SI-00872 l G6 Spray Add Tank Sat 2 C .75 RV SA C RVT 10Y Page 19 of 64
^
INSERVICE TESTih 10 GRAM POINT BEACH NUCLEAR PLANT Revision 0 .
w INSERVICE TESTING PROGRAM December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Deanzed/ Reactor Makeup Water DRAWlNG NO.: PBM-231 Sheet 2 SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT A 2 DI MA C SLT-1 2Y Passive DI4)0009 C10 DI Water Sup to 2 Cont 2 A 2 DI MA C SLT-1 2Y PassFe DI00011 C10 DI Water Sup to
^Axn l j l
l Page 20 of 64
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>M-INSERVICE TESTir aOGRAM _
POINT BEACH NUCLEAR PLANT Revision 0 INSERV!CE TESTING PROGRAM December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Eirwcy Desei Generator Air-Start DRAWING NO.: M-209 Sheet 12 TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT SIZE Dect-Dr Comp Disc 3 1.5 CK SA O/C CV-C OR DA-00100 E7 A/C SLi',3 2Y 1.5 CK SA O/C CVC OR DA-00112 E4 Dsf/ Ele Dr Comp 3 A/C SLT-3 2Y Dis J CK SA C CV-O OR VRR-25 DA-00125 C5 EDG Air Start Eq Ck
- 3 C .375 CV-C OR VRR-25 CK SA C CV-O OR VRR-25 DA-00126 C4 EDG Air Start Eq Ck 3 C .375 CV-C OR VRR-25 Bect-Dr Comp Disc 3 15 CK SA O/C CVC OR DA-00200 E7 A/C SLT-3 2Y 3 15 CK SA O/C CV-C OR DA40212 E4 Dst / Ele Dr Comp A/C SLT-3 2Y Dis ,
CK SA C CV-O OR VRR-25 DA-00225 C5 EDG Air Start Eq Ck 3 C .375 CV-C OR VRR-25
.375 CK SA C CV-O OR VRR-25 DA-00226 C4 EDG Air Start Eq Ck 3 C CV-C OR VRR-25 C .5 RV SA C SRV 10Y DA-03055A C6 Receiver T60A Relief 3 3 C .5 RV SA C SRV 10Y DA-030558 CG Recever T608 Relief 1
C 5 RV SA C SRV 10Y DA-03055C C6 Receiver T60C 3 Relief 3 C .5 RV SA C SRV 10Y DAC3055D C3 Receiver T600
! rem Page 27 of 64 J
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POINT BEACH NUCLEAR PLANT INSERVICE TESTIN dOGRAM -t INSERVICE TESTING PROGRAM Revision 0
['
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES I
SYSTEM: Emergency Desel Generator Air-Start DRAWING NO_: M-209. Sheet 12 .
VALVE CORD FUNCTION CLASS CAT SI2E TYPE ACT POS REOMT FREO REMARKS DA43055E C3 Receiver T60E Refid 3 C _5 RV SA C SRV 10Y DA-03055F C3 Receiver T60F Relief 3 C _5 RV SA C SRV 10Y I DA43056A C6 Receiver T61A Relief 3 C .5 RV SA C SRV 10Y DA-030568 CG Receiver TG1B 3 C _5 RV SA C SRV 10Y Relief ;
DA43056C CG Receiver T61C 3 C .5 RV SA C SRV 10Y Relief DA430%D C3 Receiver T61D 3 C .5 RV SA C SRV 10Y l
Relief DA43056E C3 Reciever T61E Relief 3 C .5 RV SA C SRV 10Y DA43056F C3 Receiver T61F Relief 3 C .5 RV SA C SRV 10Y I DA M 7A B4 EDG Starting Valve 3 8 .375 GL AO C BTC OR VRR-17 ;
i DA-03057B BS EDG Starting Valve 3 8 .375 GL AO C BT-O OR VRR-17 L DA-03058A B4 EDG Starting Valve 3 8 _375 GL AO C BT-O OR VRR-17 DA430588 BS . EDG Starting Valve 3 8 .375 GL AO C BT-O OR VRR-17 t
DA-06316A C5 EDG Start Air Relay 3 8 .375 GL SO C DT-O OR VRR-25 DAOG3168 C4 EDG Start Air Relay 3 8 3 75 Gt SO C BT-O OR VRR-25 [
DA OG317A C5 EDG Start Air Retay 3 8 _375 GL SO C BT-O OR VRR-25 Page 22 of 64
m 10 GRAM INSERVICE TESTR .
POINT BEACH NUCLEAR PLANT Revision 0 -
uf INSERVICE TESTING PROGRAM December 18,1990 p.
APPENDIX D . f. ,
UNIT 1 VALVE PROGRAMJfBLES
. -i,["-
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SYSTEM: Emergency Diesel for Air-Start DRAWING NO.: M-209. Sheet 12 d, . ~
s 1(rQ __
N CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUt 8 .375 GL SO C BT-O OR VRR-25 DA-063178 C4 EDG Start Air Relay 3 8 .375 GL SO C BT-O OR VRR-25 DA-06318A B5 EDG Start lAtr Pin 3 Eng 8 .375 GL SO C BT-O OR VRR-25 DA463188 B4 EDG Start Mir Pin 3
- Eng 8 .375 GL SO C BT-O OR VRR-25 DA-06319A B5 EDG starthtr Pin 3 Eng' B .375 GL SO C BT-O OR VRR-25 DA-063198 84 EDG Start Mtr Pin 3 Eng Page 23 of 64
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INSERVICE TESTih 10 GRAM .
POINT BEACH NUCLEAR Pl. ANT INSERVICE TESTING PROGRAM Revision 0 -
uJ December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Emergency Diesel Generator Fuel O3 DRAWING NO.: M-219 CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION 3 2 CK SA C CV-O OR FO-00014 C9 DFO Pump P-70A A/C Disc CV-C OR {
SLT-5 2Y j 89 DFO Pump P-70B 3 A/C 2 CK SA C CV-O OR FO 40019 Disc CV-C OR SLT-5 2Y DFO Pcmpout isol 3 A 2 GA MA C SLT-5 2Y PassNe FO-00024 D8 Fire P:trra Fuel Sup 3 A 2 GA MA C SLT-5 2Y Passhe FO 40034 H2 DFO Pump P-70A 3 .75 SRV SA C SLT-5 2Y PassFm FO 43910 C9 A/C S/R DFO Pump P-708 3 .75 SRV SA C* SLT-5 2Y PassFe j FO 43911 C9 A/C l S/R I H4 BoRer Day Tk Irdet 3 A 1 GA AO C BT-C 09 FO 43922 FST OR SLT-5 2Y t
I PIT 2Y G3 EDG Day Tk T31 A 3 A 1 GA MO C BT-C OR
- FO43930 l In BT-O OR SLT-5 2Y PIT 2Y l OR FO 43931 G2 EDG Day Tk T318 3 A 1 GA MO C BTC in BT-O OR SLT-5 OR PIT 2Y Page 24 of 64
POINT BEACH NUCLEAR PLANT -
INSERVICE TESTIT ROGRAM INSERVICE TESTING PROGRAM Revision 0 -
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Emergency Diesel Generator Fuel Oil DRAWING NO.: M-219 VALVE CORD FUNCTION Ct. ASS CAT SIZE TYPE ACT POS REOMT FREQ REMARKS FO 43940 D9 DFO Pump Press 3 A/C 1 GL SA C BT-EE OR VRR-33 Cont SLT-5 2Y FOc941 C9 DFO Pump Press 3 A/C 1 GL SA C BT-EE OR VRR-33 Cont SLT-5 2Y '
i t
t e
." age 25 of 64
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POINT BEACH NUCLEAR PLANT INSERVICE TESTIA 10 GRAM .
wC INSERVICE TESTING PROGRA.M Revision 0 -
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Heating and Ventilation DRAWING NO.: M-144. Sheet 1 and M-2207. Sheet I l
VALVE CORD FUh,~., TION CIASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SW-0297G C6 Spray PP Room 3 8 2 GL SO C FST OR T/C
~
Page 26 of 64
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POINT BEACH NUCLEAR PLANT INSERVICE TESTINt .OGRAM --
ggjC INSE! NICE TESTING PROGRAM Revision O .
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM- Heating and Ventiation DRAWING NO; M-144. Sheet 2 VALVE CORD FUNCTION Ct. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VNCR44639 D7 Control Room T/C NC B 3 GL AO O FST OR VNCSR-04640 H7 Cable Spread Room NC B 2 GL AO O FST OR T/C i
4 i
l h
Page 27 of 64
i m -
POINT BEACH NUCLEAR Pl. ANT INSERVICE TESTIL ROGRAM -
INSERVICE TESTING PROGRAM Revision 0 -
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Heating and Ventilation DRAWING NO.: M-215 Shed 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS f VNPSE43212 , H3 Cont Purge 2 A 36 BTF AO C BT-C CS CSJ-12
- Exhaust FST CS CSJ-12 SLT-1 2Y VRR-23, 29
_ PIT 2Y
, FST CS CSJ-12 SLT-1 2Y VRR-23, 29 PIT 2Y VNPSE-03245 F4 Cont Purge Supply 2 A 36 BTF AO C BT-C CS CSJ-12 FST CS CSJ-12 SLT-1 2Y VRR-23,29 4
FIT 2Y i
i r l !
i !
l
, I l
l i
i Page 28 of 64
c' POINT BEACH NUCLEAR Pl. ANT INSERVICE TESTII ROGRAM ,
INSERVICE TESTING PROGRAM Revision 0 .
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Heating ard Ventilaticm DRAWING NO.: M-215. Sheet 2 FUNCTION CLASS CAT SIZE TYPE A.CT POS REOMT FREO REMARKS VALVE CORD Cont Atmos Samp 2 CK SA O CVC RR VRR-16 RM43200AA G3 A/C 1 Retr SLT-1 RR RM43200A F3 Cont Atmos Samp 2 .? 1 GA AO O BT-C OR Retr FST OR SLT-1 2Y PIT 2Y F8 Cont Atmos Samp 2 A GA AO O BT-C OR RM 032008 1 FST OR S@
SLT-1 2Y PIT 2Y RM43200C G8 Cont Atmos Samp 2 A 1 GA AO O BT-C OR Sup FST OR SLT-1 2Y PIT 2Y t
Page 29 of 64
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POINT BEACH NUCLEAR PI_ ANT INSERVICE TESTil ROGRAM INSERVICE TESTING PROGRAM Revision 0 .
2 December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Instrument Air DRAW 1NG NO.: M-209. Sheet 5 VALVE CORD FUNCTION CLAS CAT SIZE TYPE ACT POS REOMT FREO REMARKS S
IA-00644 B5 Purge Viv 3244 Sup NC A/C _25 CK SA C CV-O OR CV-C OR SLT-3 2Y IA4)0645 C5 Purge Viv 3212 Sup NC A/C .25 CK SA C CV-O OR CV-C OR
, SLT-3 2Y Page 30 of 64
INSERVICE TESTI.N .40 GRAM -
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM Revision 0 -
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Instrument Air DRAW 1NG NO.: M-209 Sheet 7 CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCDON CLASS B5 Inst Air to Cont 2 A/C 2 CK SA C CV-C OR IA41182 VRR-23 SLT-1 2Y A GA MA C SLT-1 2Y VRR-23 IA41184 B5 Inst Air to Cont 2 1 Passive Inst Air to Cont 2 A/C 2 CK SA C CV-C OR IA41192 B5 SLT.1 2Y B4 Inst Air to Cont 2 A 2 GA AO O BT-C OR IA-03047 FST OR SLT-1 2Y PIT 2Y B4 Inst Air to Cont 2 A 2 GA AO O BT-C OR IA 43048 FST OR l
SLT-1 2Y PIT 2Y Page 31 of 64
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POINT BEACH NUCLEAR PLANT INSERVICE TEST 11 ROGRAM INSERVICE TESTING PROGRAM Revision 0 -
December 18,1990 l
APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Instrument Air DRAWING NO.: M-209, Sheet 11
, ti -
- VALVE COPD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS IA41206 G9 Inst Air to PORV NC A/C CK SA C CV-O CS CSJ-28 i CV-C CS CSJ-28 j SLT-3 2Y VRR-32 NOTE 1 IA-01209 G9 Inst Air to PORV NC A/C CK SA C CV-O CS CSJ-28 CV-C CS CSJ-28 SLT ' 2Y VRR-32 NOTE 1 IA41280 F6 Purge VIv 3245 Sup NC A/C 25 CK SA C CV-O CS CSJ-13 CV-C CS CSJ-13 SLT-3 2Y IA-01281 E6 Purge Viv 3213 Sup NC A/C .25 CK SA C CV-O CS CSJ-13
. CV-C CS CSJ-13 SLT-3 2Y IA41301 G10 Nil Sup to PORV NC A/C CK SA C CV-O CS CSJ-28 CV-C CS CSJ-28 SLT-3 2Y NOTE 1 IA-01302 G10 NR Sup to PORY NC A/C CK SA C CV-O CS CSJ-28 CV-C CS CSJ-28 2V SLT-3 NOTE 1 IA-01600 G9 Inst Air to PORV NC A/C CK SA C CV-O CS CSJ-28
, CV-C CS CSJ-28 SLT-3 2Y VRR-32 NOTE 1 Y
. Page 32 of 64
e i POINT BEACH NUCLEAR PLANT INSERVICE TESTIN ;OGRAM _
j .g . INSERVICE TESTING PROGRAM Revison 0 .
Decarrber 18,1990 l APPENDIX D UNIT 1 VALVE PROGRAM TABLES i SYSTEM: Instrument Air DRAWING NO_: M-209. Sheet 11 i
VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS IA41606 G9 Inst Air to PORY NC A/C CK SA C CV-O CS CSJ-28 Cvc CS CSA28 SLT,3 2Y VRRG2 NOTE 1 IA4)G308 G10 PORV NR Sup S/R NC C SRV SA C RVT 10Y NOTE 1 IA-06309 G10 PORV NR Sup S/R NC C SRV SA C RVT 10Y NOTE 1 IA46310 F10 PORV 430 NR Sup NC C GL SA O/C BT-EE CS CS128 Reg IA4311 F10 PORV 431C N4 Sup NC C GL SA O/C- BT-EE CS CS128 Reg
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Page 33 of 64 t
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- m n POINT BEACH NUCLEAR PLANT INSERVICE TESTIN IOGRAM I
IINSERVICE TESTING PROGRAM Revision 0 .
4 - December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Main Feedwater ~
DRAWING NO M-202. Sheet 2 -
VALVE CORD FUNCTION CtASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CS-00466AA C9 S/G 1A Feedwtr Ck 2 m/C 16 CK SA O CV-C RR VRR-21 SLT4 RR VRR-21
, CS W 66BB C9 S/G 1A Feedwtr C., 2 A/C 16 CK SA O CV-C RR VRR-21 SLT4 RR VRR-21 l CS-00476AA G9 S/G 18 Feedwtr Ck 2 A/C 16 CK SA O CV-C RR VRR-21 SLT-6 3R VRR-21 f
) CSe76BB G9 S/G 18 Feedwir ck 2 A/C 16 CK SA O CV-C RR VRR-21 4 SLT-6 RR VRR-21 i s-
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POINT BEACH NUCLEAR PLANT INSERVICE TEST 1h, 10 GRAM INSERVICE TESTING PROGRAM Revision O December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Main and Reheat Steam DRAWING NO.: MO-201, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS MS-02005 G8 Main Steam Safety 2 C 6 RV SA C SRV SY MS42006 G8 Main Steam Safety 2 C 6 RV SA C SRV SY MS42007 G7 Main Steam Safety 2 C 6 RV SA C SRV SY MS-02008 G7 Main Steam Safety 2 C 6 RV SA C SRV SY MS-02010 D8 Main Steam Safety 2 C 6 RV SA C SRV SY MS-02011 D8 Main Steam Safety 2 C 6 RV SA C SRV SV MS-02012 D7 Main Steam Safety 2 C 6 RV SA C SRV SY MS-02013 D7 Main Steam Safety 2 C 6 RV SA C SRV SY MS42015 H7 MS Atmos Stm 2 B 6 GL AO C BT-C CS CSJ-14 Dmp BT-O CS CSJ-14 PIT 2Y MS-02016 E7 MS Atmos Stm 2 B 6 GL AO C BT-C CS CSJ-14 Dmp BT-O CS CSJ-14 PIT 2Y MS-02017 G7 Main Staam 2 8 30 SCK AO O BT-C CS CSJ-15 Isolation PIT 2Y FST CS CSJ-15 MS-02017A G4 Mas Steam 2 C 30 CK SA O CV-C CS CSJ-16 NonRetum MS-02017CS H6 MSIV 2017 Air Plot NC B 1 AP SO C BT-PV CS CSJ-17 MSo2017DS H5 MSIV 2017 Air Plot NC B 1 AP SO C ST-PV CS CSJ-17 l Page 35 of 64
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POINT BEACH NUCLEAR PI_ ANT INSERVICE TESTIN 10 GRAM -
INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Main and Reheat Steam DRAWING NO; M0-201, Sheet 1 1
VALVE CORD FUI4CTION Cl. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS MS42010 D9 Main Steam 2 B 30 SCK AO O BT4 CS CSJ-15 Isolatk>n PIT 2Y FST CS CSJ-15 MS42018A D4 Main Steam 2 C 30 CK SA O CV-C CS CSJ-16 Nonretum MS42018CS EG MSIV 2018 Air PIot NC B 1 AP SO C BT-PV CS CSJ-17 MS-02018DS ES MSIV 2018 Air P5ot NC B 1 AP SO C BT-PV CS CSJ-18 MS42019 F6 AFW Steam Supply 2 B/C 3 SCK MO S BT-O OR CV-O OR BT-C OR l
PIT 2Y MS-02020 EG AFW Steam Supply 2 B/C 3 SCK MO S BT4 OR CV-O OR BT-C OR PIT 2Y MS42082 BS Main Steam to AFW 2 8 3 GL SA/ O BT-C OR VRR-1 Pump MA BT-O OR
- PIT 2Y MS-02083 C9 S/G Sample isol 2 A .75 DI AO O BT-C OR FST OR SLT-1 2Y FIT 2Y MS42084 F9 S/G Sample Isol 2 A .75 DI AO O BT-C OR FST OR SLT-1 2Y PIT 2Y Page 36 of 64
POINT BEACH NUCLEAR PLANT INSERVICE TESTit ROGRAM !
INSERVICE TESTING PROGRAM Revison 0 '
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Main and Reheat Steam DRAWING NO.: MO-201. Sheet 1 i
TYPE VALVE COF!D FUNCTION CLASS CAT SIZE ACT POS REOMT FREO REMARKS MS-02090 C8 SW to AFW F' ump 3 8 1 GL SO O BT-O OR VRR-20 i P-029 FST OR MS45958 B10 S/G Blowdown isol 2 A 2 GA AO O BT-C OR FST OR l SLT-1 2Y ;
FIT 2Y MS-05959 E10 S/G Blowdown isol 2 A 2 GA AO O BT-C OR
.. FST OR
. SLT-1 2Y l FTT 2Y j RS-SA49 F7 Radwaste Steam 2 8 . 3 GA AO O BT-C OR 4
Supply FST OR j PIT 2Y i I I
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j Page 37 of 64
O INSERVICE TESTIN (OGRAM POINT BEACH NUCLEAR Pl. ANT INSERVICE TESTING PROGRAM Revson 0 .
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Fost-Accidera Contammerit Vent / Monitoring DRAWING NO.: M-224 CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD l FUNCTION CLASS PostAcc Purge 2 A 2 DI MA C BT-O OR H2-V-04 DG 2Y VRR-23 SLT-1 Disch Post-Acc Purge 2 A 2 DI MA C ST-O OR H2-V-05 D6 VRR.23 SLT-1 2Y Disch GA MA C SLT-1 2Y VRR-23 D6 Post-Acc Purge 2 A 75 H2-V46 Passrve i i
Drain GA MA C SLT-1 2Y VRR-23 H2-V-07 D6 PostAcc Purge 2 A .75 Passhe Drain Di MA C SLT-1 2Y Passrve H2 V-08 E6 Post-Acc Atmos. 2 A 75 i Samp DI MA C SLT-1 2Y Passrve E6 Post-Acc Atmos. 2 A .75 H2-V-os Samp 2 A 2 Di MA C BT-O OR H2-V-12 DG Port-Acc Sendce VRR-23 SLT-1 2Y Air Sup 2 A 2 Of MA C BT-O OR Post-Acc Service H2-V-13 DG 2Y VRR-23 SLT-1 Air Sun
? DI MA C SLT-1 2Y VRR-23 H2-V-19 D7 Post-Acc Alt V:nt 2 A Passise DI MA C SLT-1 2Y VRR-23 H2-V-20 07 Post-Acc Alt Vent 2 A 2 Passive i
DI MA C ^ T-1 2Y VRR-23 H2-V-22 D7 Post-Acc Sup Drain 2 A 2 i l Passrve Page 38 of 64
i n. .. .n 1 POINT BEACH NUCLEAR PLANT INSERVICE TEST WMM ,
! IINSERVICE TESTING PROGRAM Revision 0 .
l December 18,1990 APPENDIX D I UNIT 1 VALVE PROGRAM TABLES I-1 SYSTEM: Post-Accdent Cordainment Verw/Moritoring DRAWING NO.: M-224 i
VALVE CORD FIRJCTION CLASS CAT SIZE TYPE ACT POS PEOMT FREO I REMARKS i H2-V-23 D7 Post Acc Sup Drah 2 A 2 DI MA C SLT-1 2Y VRR-23 Passive 4
I i
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POINT BEACH NUCLEAR PLANT INSERVICE TESTIN. (OGRAM -
INSERVICE TESTING PROGRAM Revision 0 ,
- December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Primary Samprog DRAWING NO.: 541F092 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SC-00951 G12 Press Stm Sample 1 A .375 GL AO C BT-C OR FST OR SLT-1 2Y PIT 2Y SC-00953 F12 Press Liq Sample 1 A _375 GL AO C~ BT-C OR FST OR SLT-1 2Y PIT 2Y SC-00955 E12 Hot Leg Sample 1 A .375 GL AO O/C BT-C OR FST OR SLT-1 2Y PIT 2Y SC40959 E12 RHR Sample i A .375 GL AO C BT-C OR FST OR SLT4 2Y PIT 2Y SC-009G6A G10 Press Stm Sample 1 A _375 GL AO C BT-C OR FST OR SLT-1 2Y PIT 2Y SC409668 F10 Press Liq Sample 1 A 55 GL AO C BT-C OR FST OR SLT-1 2Y l PIT 2Y Page 40 of 64
POINT BEACH NUCLEAR PLANT INSERVICE TESTih lOGRAM INSERVICE TESTING PROGRAM Revision 0 ,
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Primary Sampfing DRAWING NO_: 541F092 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FRfO REMARKS SC@966C E10 Hot Leg Sample 1 A .375 GL AO O/C BT-C OR FST OR SLT-1 2Y PIT 2Y F
l I
Page 41 of 64
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.A, INSERVICE TEST 1h IOGRAM .
PO!NT BEACH NUCLEAR PI_ ANT Revision 0 ,
INSERVICE TESTING PROGRAM December 18,1950 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Reector Coolant DRAWING NO.: 541F091. Sheet 1 TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT SIZE 2 GL AO C BT-C CS CSJ-18 RC4)0430 H5 Power-Operated Ret t B BT-O CS CSJ-18 FST CS CSJ-18 PIT 2Y 2 GL AO C BT4 CS CSJ-18 RC-00431C S Power-Operated Ref 1 8 ,I BT-O CS CSJ-18 FST CS CC4-18 PIT 2Y C 3 SRV SA C RVT SY RC-00434 17 Pressurizer Safety 1 C 3 SRV SA C RVT SY RC-00435 16 Pressurizer Safety 1 3 GA MO O BT-C OR Note 4 )
RC-00515 15 PORV Block Valve 1 B '
PIT 2Y 3 GA MO O BT-C OR Note 4 RC C 16 H5 PORV Block va!ve 1 B FIT 2Y l
1 Page 42 of 64
n - -
POINT BEACH NUCLEAR PLANT INSERVICE TESTit 30 GRAM .
INSERVICE TESTING PROGRAM Revision 0 ,
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Reactor Coolant DRAWING NO.i 541F091, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS RC-00508 D2 PRT Fill Line Iso 2 A 2 DI AO O/C BT-C OR FST OR SLT-1 2Y PIT 2Y RC-00528 D3 PRT Nitrogen Sup 2 A/C .75 CK SA O/C CV-C RR VRR-11 a
SLT-1 RR RC-00529 D3 PRT Fill Une Ck 2 A/C 2 CK SA O/C CV-C RR VRR-18 SLT-1 RR i RC-00538 E3 PRT Sample 2 A .375 GL AO O BT-C OR FST OR >
SLT-1 2Y PIT 2Y RC-00539 E3 PRT Sample 2 A .375 GL AO O BT-C OR i FST OR i SLT-1 2Y PIT 2Y _
RC@570A F5 RX Vessel Vent 1 8 1 GL SO C BT-O CS CSJ-19
. PIT 2Y j RC-005708 F5 RX Vessel Vent 1 B 1 GL SO C BT-O CS CSJ-19 PIT 2Y RC-00575A F5 RX Vess/ Press Vent 1 B 1 GL SO C BT4 CS CSJ-19 ;
PIT 2Y t RC-005758 F5 RX Vess/ Press Vent 1 B 1 GL SO C BT-O CS G-19 PIT 2Y
, Page 43 of 64
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POINT BEACH NUCLEAR PLANT . INSERVICE TESTih 10 GRAM .
INSERVICE TESTING PROGRAM Revision 0 '
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Reactor Coolara DRAWING NO_: 541F091, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS RC@S80A G5 Pressurizer Vent 1 B 1 GL SO C BT-O CS CSJ-19 PIT 2Y RC-005808 GS Pressurizer Vent 1 ts . GL SO C BT-O CS CSJ-19 PIT 2Y RC-00595 D3 PRT Nitrogen Sup 2 A .75 Di MA O/C BT-C OR SLT-1 2Y F
i 1
Page 44 of 64
POINT BEACH NUCLEAR PLANT INSERVICE TESTIA IOGRAM .
INSERVICE TESTING PROGRAM Revision 0 ,
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABl_ES SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E017. Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT PCS REOMT FREO REMARKS SI-00830A H7 SIS Accum Relief 2- C 1 SRV SA C RVT 10Y SI@8308 D7 SIS Accum Relief 2 C 1 SRV SA C RVT 10Y SI-834A H7 SIS Accum Vent 2 B 1 GL AO C BT-O CS CSJ-30 FST CS CSJ M PIT 2Y SI-8348 07 SIS Accum Vent 2 8 1 GL AO C BT-O CS CSJ M FST CS CSJ-30 PIT 2Y SI-00841A G8 SIS Accum Disch 2 8 10 GA MO O BT-C CS CSJ-20 PIT 2Y S140841B B7 SIS Accum Disch 2 B 10 GA MO O BT-C CS CSJ-20
, PIT 2Y SI-00842A G8 SIS Accum Disch 1 A/C 10 CK SA C CV-PO E-CS VliR-4 Ck CYC OR VRR-4 CV-PO RR VRR-4 INSP SP VRR-4 SLT-4 OR VRR-4 SI-008428 88 SIS Accum Disch 1 A/C 10 CK SA C CV-PO E-CS VRR-4 Ck CV-C OR VRR-4 CV-PO RR VRR-4 ,
INSP SP VRR-4 SLT-4 OR VRR-4 SIO0845A F8 SIS Cold Leg inj 1 A/C 2 CK SA C CV-O RR VRR-2 '
CV-C RR VRR-2 SLT-2 2Y VRR-22 Page 45 d 64
- x. g .
POINT BEACH NUCLEAR PLANT !NSERVICE TESTIN. .OGRAM -
led INSERVICE TESTING PROGRAM Revision 0 ,
- December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E017, Sheet 1 VALVE CORD I FU:10 TION I CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI-008456 D8 SIS Cold Leg inj 1 A/C 2 CK SA C ' CV-O RR VRR-2 CV-C RR VRR-2 SLT-2 2Y VRR-22 SI-00845C E8 SIS Core Deltge 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C RR VRR-2 SLT-2 2Y _
VRR-22 SI-00845D F8 SIS Core Deluge 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C RR VRR 2 SLT-2 2Y VRR-22 SI-00845E FS SIS Cold Leg inj - 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C RR VRR-2 SLT-2 2Y VRR-22 SI-00845F E8 SIS Cold leg Inj 1 A/C 2 CK SA C CV-O F.R VRR-2 CV-C RR VRR-2 SLT-2 2Y VRR-22 SI @ 846 H3 Accum Nit Supply 2 A 1 GL AO C BT-C OR FST OR FIT 2Y SLT-1 2Y SI-00850A A4 Cont Sump Hyd Isol 2 8 10 GA HO C BT-O OR PIT 2Y SI@ 8508 B6 Cont Sump Hyd Isol 2 B to GA 110 C BT-O OR PIT 2Y SIM 852A B7 RHR/LH Core 2 B 6 GA MO C BT-O ,
CS CSJ-21 l De!uge BT-C CS CSJ-21 PIT 2Y l
l Pap % d M m
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n n POINT BEACH NUCLEAR PLANT INSERVICE TESTI ROGRAM ,
INSERVICE TESTING PROGRAM Revision 0 ~
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety injection and Residual Heat Removal DRAVANG NO : 110E017. Sheet 1 VALVE CORD FUNCTION CLASS CA1 SIZE TYPE ACT POS REOMT FREO REMARKS SI-008528 A7 RHR/LH Core 2 B 6 GA MO C BT-O CS CSJ-21 Deluge BT-C CS CSJ-21 I
P:T 2Y T.I-00853A B8 RHR/LH Inj Check 1 A/C 6 CK SA C CV-PO E-CS VRR-3 CV-C E-CS VRR-3 CV-O RR VRR-3
- CV-C RR VRR-3 SLT-2 2Y VRR-22 St-00853B A8 RHR/LH Inj Check 1 A/C 6 CK SA C CV-PO E-CS VRR-3 CV-C E-CS VRR-3 CV-O RR VRR4 CV-C RR VRR-3 SLT-2 2Y VRR-22 SI-00853C B9 RHR/ Core Deluge 1 A/C 6 CK SA C CV-PO ECS VRR-3 CV-C E-CS VRR-3 CV-O RR VRR-3 CV-C RR VRRO SLT-2 2Y VRR-22 ,
SI-00853D A10 RHR/ Core Deluge 1 A/C 6 CK SA C CVPO E-CS VRR-3 CV-C E-CS VRR-3 CV-O RR VRR-3 !
CV-C RR VRR-3 !
I SLT-2 2Y VRR-22 SI-00861 A B4 RHR RX Ves ini S/R 2 C 75 SRV SA C RVT IOY Page 47 of 64
INSERVICE TESTit 'tOGRAM ,
POINT BEACH NOCLEAR PLANT Revision 0 '
!NSERVICE TESTING PROGRAM December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEAt Safety injection and Residual Heat Removal DRAWING NO.: 110E017, Sie 1 TYPE ACT POS REOMT FREO REMARKS i
CORD FUNCTION CLASS CAT SIZE VALVE C CV-PO E-CS VRR4 SIS Cold Leg inj Ck 1 A/C 10 CK SA SI @ 867A G9 CV-C E-CS VRR4 CV-PO RR VRR4 CV-C RR VRR-4 INSP SP VRR4 SLT-2 2Y VRR 22 SA C CV-PO CS VRR4 B9 SIS Cold Leg inj Ck 1 A/C to CK VRR4 SI @ 8678 CV-C 2Y CV-PO RR 4 CV-C Hr I INSP St (neta SLT-2 2~. - _ ,
SIE875A F6 SIS Test Recirc Ck 2 A/C l Cvc on !
SLT-5 2Y l
.75 CK SA C CV-O CR F5 SIS Test Rec:rc Ck 2 A/C SI @ 8758 CV-C OR SLT-5 2Y C BT-O CS CSJ-22 RX Vessel Safety ini 2 8 2 GL MO SI@878A E8 BT-C CS CSJ-22 PIT 2Y MO O BT-O CS CSJ-23 D8 SIS Loop Inj 2 B 2 GL Sim 878B BT-C CS CSJ-23 PIT 2Y MO C BT-O CS CSJ-22 E8 RX Vessel Safety inj 2 8 2 GL Sim 878C BT-C CS CSJ-22 PIT 2Y Page 48 of 64
.m m INSERVICE TESTI 'ROGRAM POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM Revision 0 .
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety injection and Reskfual Heat Removal DRAWING NO : 110E017. Sheet 1 CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS 2 B 2 GL MO O BT-O CS CSJ-23 SI-00878D F8 SIS Loop Inj BT-C CS CSJ-23 PIT 2Y 2 C .75 SRV SA C RVT 10Y SIM887 E4 Test une Saf A GL AO C BT4 CS CSJM, SI-00957 H4 N2 Supply Vent /Rel 2 1 FST CS CSJ-30 2Y SLT-1 PIT 2Y Page 49 of 64
m . . . .m m.
POINT BEACH NUCLEAR PLANT INSERVICE TESTIN IOGRAM .
INSERVICE TESTING PROGRAM Revision 0 Decembe* 18,1990-APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E017 Sheet VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI-00825A F5 SIS Pump Suction 2 B 12 GA MO- C BT-O OR PIT 2Y SI408258 F5 SIS Pump Suction 2 B 12 GA MO C BT-O OR PIT 2Y SI-008268 H7 SIS Pump Rendunt 2 8 8 GA MO C BT-O CS CSJ-24 Suct BT-C CS CSJ-24 PIT 2Y ,
SI40826C G7 SIS Pump Rendunt 2 B 8 GA- MO C BT-O CS CSJ-24 Suct BTC CS CSJ-24 PIT 2Y S140851A B4 Cont Sump Isol 2 8 to GA MO C BT-O OR PIT 2Y 4
SI-008518 B4 Cont Sump Isol 2 B to GA MO C BT-O CR 1 PR 2Y SI40854A D3 RHR Pump Suct Ck 2 A/C 10 CK SA C CV-O RR VRRE CV-C RR VRR4 SLT-6 RR VRR4 SI408548 C3 RHR Pump Suct Ck 2 A/C 10 CK SA C CV-O RR VRR4 CV-C RR VRR4
. SLT-6 RR VRRE S140856A D3 RHR Pump Suct 2 B 10 GA MO O BT-C CS CSJ-31 PIT 2Y S1408568 C3 RHR Pump Suct 2 B to GA MO O BT-C CS CSJ-31 PIT 2Y Page 50 of 64
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INSERVICE TESTE 10 GRAM POINT BEACH NUCLEAR PLANT Revision 0 .
INSERVICE TESTING PROGRAM -
December 18,1990
. APPENDIY. D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety Infection and Residual Heat Removal DRAWING NO.: 110E017. Sheet SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT RHR to SIS Pump 2 8 6- GA MA C BT-O OR SI-00857A E7 Suct RHR to SIS Pump 2 8 6 GA MA C BT-O OR l
S14X)8578 E7 Sty:t SIS Pump Disch 2 B 4 GA MO O BT-O OR SI @ 866A F3 BT-C OR PIT 2Y 2 B 4 GA MO O BT-O OR SI-008668 E3 SIS Pump Disch .
BT-C OR PIT OR SA C CV-PO OR VRR-7 SI-00889A F8 SIS Pump Disch Ck 2 A/C 6 CK CVC RR VRR-7 CV-O RR VRR-7 SLT-5 2Y SA C CV-PO OR VRR-7 SI-00889B rd SIS Pump Disch Ck 2 A/C 6 CK CV-C RR VRR-7 CV-O RR VRR-7 SLT-5 2Y CK SA C CV-PO OR VRR-27 E8 SIS Pump Mini-rec 2 C 2 SI@ 891A INSP SP VRR-27 Ck CK SA C CV-PO OR VRR-27 SI@8918 E8 SIS Pump Mini-rec 2 C 2 INSP SP VRR-27 Ck SIS Pump Mini-rec 2 C 2 CK SA C CV-O OR Sl@895 E5 .
-Ck l
Page 51 of 64
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INSERVICE TESTINi OGRAM POINT BEACH NUCLEAR PLANT .
Revision 0 w C INSERVICE TESTING PROGRAM December 18,1990
~
APPENDIX D l
UNIT 1 VALVE PROGRAM TABLES -
SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E017. Sheet CULSS -CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION F6 S!S Pump Suction 2 B 6 GA MO O BT-C OR SI-00896A PET 2Y E6 SIS Pump Suction 2 B 6 GA MO O BT-C OR SI-008968 PfT 2Y 2 A 2 GL AO O BT-C CS CSJ-25 SI-00897A E2 SIS Test Une Ret FST CS CSJ-25 SLT-5 2Y PIT 2Y 2 A 2 GL AO O BT-C CS CSJ-2S Sl@8978 E2 SIS Test Une Ret FST CS CSJ-25 SLT-5 2Y PIT 2Y Page 52 of 64
POINT BEACH NUCLEAR PLANT INSERVICE TESTINt OGRAM- -
tuC INSERVICE TESTING PROGRAM Revision 0 ,
' December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E018 Sheet 1 VALVE CORD. FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS RHG710A E4 RHR Pump Disch '2 C 8 CK SA C CV-PO OR Ck CV-O CS CSJ-26 .
SLT-5 2Y RH@7108 84 RHR Pump Disch 2 C 8 CK SA C CV-PO OR Ck CV-O CS CSJ-26 SLT-5 2Y RHm742 H6 RHR/RWST isol 2 A 8 GA MA C SLT-5 2Y RHM742A HS RHR/RWST isol 2 A 2 GL MA C SLT-5 2Y Sim 624 G7 RHR HX Outlet 2 B 8 BTF AO O PIT 2Y Passive SI@ 625 G7 RHR HX Outtet 2 B 8 BTF AO O PIT 2Y Passive Page 53 of 64
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INSERVICE TESTI >ROGRAM ,
POINT BEACH NUCLEAR PLANT Revision 0 INSERVICE TESTING PROGRAM December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Service Air DRAWING NO.: M-209f. Sheet 2 TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT SIZE GA MA C SLT-1 2Y Passive SA-00015 F7 Serv Air Cont Sup 2 A 4 2 4 CK SA C CV-C OR SA4)0017 F7 Serv Air Cont Sup A/C SLT-1 2Y l
l 1
1 I
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m INSERVICE TESTit - 10 GRAM POINT BEACH NUCLEAR PLANT _
INSERVICE TESTING PROGRAM Revision 0 ~
December 18,1990 i APPENDIX D l UNIT 1 VALVE PROGRAM TABLES
{
SYSTEM: Service Water DRAWING NO : M-207, Sheet 1 CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION SW40032A D2 SW Pp P-032A Disc 3 A/C 16 CK . SA O/C CV-O OR Ck CV-C OR g SLT-5 2Y SW40032B D1 SW Pp P432 sc 3 A/C 16 CK SA O/C CV-O OR Ck A CV-C OR d? SLT-5 2Y SW-00032C D1 SW Pp P-032CTEsc 3 A/C 16 CK SA O/C CV-O OR Ck- Cvc OR SLT-5 2Y SW40032D E2 SW Pp P-032D Disd 3 A/C 16 CK SA O/C CV-O OR .
Ck CV-C OR SLT-5 2Y SW-00032E Et SW Pp P432E Disc 3 A/C 16 CK SA O/C CV-O OR Ck CVC CR SLT-5 2Y SW-00032F Et SW Pp P-032F Disc 3 A/C 16 CK SA !O/C CV-O OR I Ck CV-C OR SLT-5 2Y SW to AFW Pp 3 C CK SA O CV-PO OR VRR-15 SW-00135A C7 1 INSP RR VRR-15 P-029 SW-02818 G6 Cable Sp Rm Ctr 3 8 3 GL MO O BT-O OR Sup PIT 2Y SW42818A F6 Cable Sp Hm Ctr 3 8 1.5 GL AO O FST OR T/C Page 55 of 64
m _.
POINT BEACH NUCLEAR PLANT INSERVICE TESTih 30 GRAM' -
W INSERVICE TESTING PROGRAM Revision O .
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Service Water DRAWING NO_: M-207. Sheet 1 .
VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SW-028188 F6 Cable Sp Rm Or 3 8 1.5 GL AO O FST OR T/C SW-02819 D6 Control Rm Or Sup 3 8 3 GL MO O BT-O OR PIT 2Y SW-02819A C6 Control Rm Or T/C 3 8 1.5 GL AO O FST OR ,
SW-028198 .D6 Control Rm Or T/C 3 B 1.5 GL AO O FST OR SW-02838 C3 G02 EDG HX Outlet 3 B 4 GA AO C BT-O OR '
FST OR PIT 2Y SW-02839 B3 G01 EDG HX Outlet 3 B 4 GA AO C BT-O OR FST OR PIT 2Y SW42869 H8 SW Hdr (West) Isol 3 B 14 BTF MO O BT-C OR PIT 2Y SW-02870 88 SW Hdr (West) Isol 3 B 14 BTF MO O BT-C OR PIT 2Y SW42890 E2 SW HMEr 3 8 24 BTF MO O BT-C OR Ce .s-Tle PIT 2Y SW-02891 E2 SW Header Cross- 3 8 24 BTF MO O BT-C OR Tie PIT 2Y SW-02929A G5 AFW Pump Rm Or 3 8 2 GL AO O FST OR T/C SW-029298 B5 AFW Pump Rm or 3 8 2 GL AO O FST OR T/C Page 56 of 64
m INSERVICE TESTI. ROGRAM .
POINT BEACH NUCLEAR PLANT Revision 0 _
INSERVICE TESTING PROGRAM December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Service Water DRAWING NO.: M-207. Sheet 2 i
CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS GA MO O BT-C CS CSJ-27 F5 Turb Hall C!rs in 3 8 6 SW-02880 PIT 2Y l
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WC INSERVICE TESTING PROGRAM Revision 0 December 18,1990 -
APPENDIX D !
UNIT 1 VALVE PROGRAM TABLES SYSTEM: Service Water DRAWING NO.: M-207. Sheet 3 VALVE CORD. FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SW-00012A E7 CCW HX-12A Outlet 3 B 2 GL AO O FST OR SW40012B E6 CCW HX-128 Outlet 3 8 2 GL AO O FST OR SW40012C E5 CCW HX-12C Otfiet 3 B 2 GL AO O FST OR SW-00012D E5 CCW HX-12D Out!et 3 B 2 GL AO O FST OH SW-00307 E5 CCW HX-12D Outlet 3 B 12 GA MA C BT-O OR SW-00315 ES CCW HX-12C Outlet 3 8 12 GA MA C BT-O OR SW-00322 E7 CCW HX-12A Outlet 3 B 12 GA MA C BTOO OR
^
SW40360 E6 CCW HX-128 Outlet 3 8 12 GA MA C BT-O OR SW40396A H6 Battery Rm Cooler 3 C 2 CK SA O CV-O OR Sup SW40397A H6 Battery Rm Cooler 3 C 2 CK SA O CV-O OR Sep SW-02816 B3 Svc Bldg HVAC Og 3 8 6 GA MO O BT-C OR lso PIT 2Y SW42930A B6 SFP Or Sup 3 B 8 GA MO O BT-C OR FIT 2Y SW42930B C6 SFP Or Sup 3 8 8 GA MO O BT-C OR PIT 2Y SW42977 D5 RHR Pump Rm Or 3 8 2 GL AO O FST OR i
T/C i
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.-v INSERVICE TESTl! ROGRAM -
PO!NT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM Revision 0 -
- December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Service Water DRAWING NO.: M-207 Sheet 3 CAT SIZE TYPE ACT POS REOMT FREO REAR 9KS VALVE CORD FUNCTION CLASS 3 8 8 GA AO O BT-C OR SW-LW41 G4 BDE/ Vent Cond in FST OR ;
PIT 2Y G3 3 8 8 GA AO O BT-C OR SW-W242 BDE/ Vent Cond OR Out FST PIT 2Y l
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POINT BEACH NUCLEAR PLANT INSERVICE TESTIN ;OGRAM .
uj INSERVICE TESTING PROGRAM : Revision 0 ,
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Service Water DRAWING NO.: M-207, Sheet 4 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SW-00015A B4 Cont Or Supply Ck 3 C 8 CK SA O CV-O OR SW-000158 B2 Cont Or Supply Ck 3' C 8 CK SA O CV-O OR SW-00015C B4 Cont Or Supply Ck 3 C 8 CK SA O CV-O OR SW-00015D B3 Cont Or Supply Ck 3 C 8 CK SA O CV-O OR SW-02907 G2 Cont Or Emerg 3 8 12 GA MO C BT-O OR Flow PIT 2Y SW42908 G4 ' Cont Or Emerg 3 B 12 GA MO C BT-O OR Row PIT 2Y SW-02959 DS Cont Or Disch S/R 3 C SRV SA C RVT 10Y SW-029G3 D2 Cont Or Disch S/R 3 C SRV SA C RVT 10Y SW42967 D4 Cout Or Disch S/R 3 C SRV SA C RVT 10Y SW-02971 D3 Cont Or Disch S/R 3 C SRV SA C RVT 10Y SW-04300 D1 Cavity Or Ret S/R 3 C SRV SA C RVT 10Y SW44301 D1 Cavity Or Ret S/R l 3 C SRV SA C RVT 10Y Page 60 d 64
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wt INSERVICE TESTING PROGRAM Revis:en O '
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Spent Fuel Pit Cooling DRAWING NO.: 110E018. Sheet 4 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SF-000009A F6 SFP Pp P-12A 3 A/C 8 CK SA O/C CV-O OR Disc Ch CV-C OR SLT-5 2Y SF-00010A F6 ' SFP Pp P-128 3 A/C 8 CK SA O/C CV-O OR Disc Ck CV-C OR SLT-5 2Y Page 61 of 64
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INSERVICE TESTING PROGRAM . Revision 0 -
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Waste Disposal DRAWING NO.: 684J971, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SF40816 C6 P-033 RWCP 2 A 2 DI MA C <
SLT-1 2Y VRR-23 Suction Passive i WL-01003A C6 RCDT Pump 2' A 3 DI AO O/C BT-C OR Suction FST OR SLT-1 2Y . VRR-23 PIT 2Y WL-01003B C6 RCDT Pump 2 A 3 DI AO O/C BT-C OR Suction i FST OR *
' SLT-1 2Y VRR-23
! N 2Y WL-01698 C6 RCDT to -19' 2 A 2 DI AO C SLT-1 2Y VRR-23 Sump PIT 2Y Passrve ,
WL-01721 C6 RCDT Pumps Suct 2 A 3 DI AO O/C BT-C OR Con FST OR SLT-1 2Y PIT 2Y '
Cont Sump Dr BT4 WL-01723 i C6 2 A 3 DI AO O/C OR '
FST OR SLT-1 2Y VRR-23
}
MT 2Y l WL-01728 CS Cont Sump Dr 2 A 3 DI AO O/C BT-C OR FST OR SLT-1 2Y VRR-23 PIT 2Y Page 62 of 64
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INSERVICE TESTING PROGRAM Revision O ,
December 18,1990 AFPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Waste Disposal DRAWING NO.: 684J971, Sheet 1 h FREO REMARKS VALVE CORD' FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT WG-01786 B5 RCDT Vent 2 A ? DI AO O BT-C OR FST OR SLT-1 2Y PIT 2Y WF-01787 B5 RCDT Vent 2 A 1 DI AO O BT-C OR SLT1 Y !
PIT 2Y WG41788 B5 RCDT Sample 2 A .75 DI AO O/C '6T-C OR FST OR SLT-1 2Y PIT 2Y WG-01789 B5 RCOT Sarrple 2 A .75 DI AO O/C BT-C OR FST OR SLT-1 2Y PIT 2Y Page 63 of 64
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w INSERVICE TESTING PROGRAM Revision O ,
December 18,1990 APPENDIX D UNIT 1 VALVE PROGRAM TABLES NOTES
- 1. These valves ar'd their respective test requ!rements are included in the IST Program for information and tracking purposes only. They do not necessarEy meet the requirements for inclusion per IWV-1100, but are identified for testing per NRC Generic Letter 9046. Thus, the tests specifW must not necessarly satisfy the corresponding requirements of Subsection IWV cr NRC Generic Letter 8944.
- 2. (11-08-90) Physical modifications are required to allow testing. . Testing will commence upon completion of modifications.
- 3. (11-08-90) These valves faR in a position opposite of that required. Manual stroke capability wil be demonstrated.
4 If a PORV is isolated in accordance with Technical Specifications, the associated block valve WHI be exercised at cold shutdown.
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM IINSERVICE TESTING PROGRAM Revision 0 ,
December 18,1990 j APPENDIX E ;
UNIT 2 VALVE PROGRAM TABLES l
l CONTENTS
. System Pag Auxilary Fecdwater System 5 2 Aux Steam, Heating Steam, Chilled and Hot Water 7 Chemical and Vdume Control 8 Component Cooling Water 11 Containment Spray 15 Delonized and Reactor Makeup Water 18 Heating and VentBation 19 instrument Air 21 Main Feedwater 24 Maln and Reheat Steam 25 Post Accident Containment Vent / Monitoring 28
~ Primary Sampilng 30 Reactor Coolant 32 Safety injection and Residual Heat Removal 35 Service Air 44 Service Water 45 Waste Olsposal 48 Notes 50 I
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4 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM-8 INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLES
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LEGEND VALVE The plant alpha numerical designator for the subject valve, CORD The coordinate location of the valve on the designated drawing.
CLASS The ISI classification of the valve as per the respective ISI bounGary drawings.
CAT The valve category por Paragraph IWV 2200.
SIZE The valve's nominal size in inches.
TYPE The valve type I AP Pneumatic Pilot BA Ball BTF Buttorfly CK Check DI Diaphragm
, GA Gate GL Globe SCK Stop/ Check SRV Safety / Relief
(
NE Needle (thrott!e)
ACT The valvo actuator type as follows:
AO Air operated HO Hydraulic operated MA Manual valve MO Electric motor operated SA Self actuated SO Solenold operated POS Designates the normal position of the valve during plant operation at power, REOMT Identifies the test requirements for a valve as follows:
BT-C Exercise to closed position. For oower operated valves, stroke times will be-measured unless excluded by an associated relief request.
BT-O Exercise to open position. For power operated valves, stroke times will be measured unless excluded by an associated relief request.
BT EE Exercise valve to verify proper operation and stroking with no stroke time meaurements. Requires observation of system parameters or local observation of valve operation.
( BT-PV Exercise of pneumatic pilot valve. Proper operation of the associated main valve verifles operability.
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- , POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 Dectmber 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLES
(
CV C Exercise check valve to the closed position.
CV O Exercise check valve to the full open position.
CV PO Partial stroke exercise check valve in the open position.
CV PC Partial stroke exercise check valve in the close direction.
FST Fall safe test INSP Disassembly and Inspection of check valves PIT Poaltion Indication verification per IWV 3300 RVT Safety / Relief valve setpoint test per ASME OMa 1 SLT 1 Seat leakrate test per 10 CFR 50, App J SLT 2 Seat leakrate test Ior pressure isolation valves per Technical Specification 15.3.16.
SLT4 Seat leakrate test for pneumatic check valves to verify capability of maintaining accumulator gas inventory following loss of supply system pressure.
( SLT 4 Leaktesting of safety injection accumulator check valves SLT 5 Seat leakrate test to identify gross leakage. Specific leakage rates will not be measured, but leakage will be determined and evaluated with respect to system operability and its capability to perform its safety function per IWV-3521.
SLT-6 Seat leakrate test to identify gross leakage. Specific leakage rates will be measured and evaluated with respect to system operability and its capability to perform its safety function per IWV-3521.
TEST FREO The required test interval abbreviations are defined as follows:
RR Each reactor refueling outage (cycle)
CS Cold shutdown (per Technical Specifications)
E CS Cold shutdown with Event V testing required OR Ouarterly (during plant operation) 2Y ' Every 2 years 5Y Every 5 years 10Y Every 10 years SR Prior to placing a system or component in operable status SP Other (see applicable request for relief)
)
(
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, POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLES I
REMARKS Applicable requests for relief from Code requirements (see Appendix F) are noted in the REMARKS column adjacent to the associated test requirement and designated VRR XX.
Applicable notes are included in the REMARKS column and are designated NOTE XX. A list of notes is attached as the last page of the appendlx.
Cold shutdown testing justifications are provided in Appendix G. Each explanation is identified by a reference number (CSJ XX) that appears in the respective REMARKS column adjacent to the pertinent test requirement.
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- INSERVICE TESTI ROGRAM POINT BEACH NUCLEAR PLANT Revision O
((0)) INSERVICE TESTING PROGRAM December 18,1990 -
1 APPENDIX E UNIT 2 VALVE PROGRAM TABLE j SYSTEM: Audiary Feedwater DRAWING NO.: M-217 CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS 3 8 6 GA MA O BT-C OR AF00064 G4 2P-29 Suction CK SA C CV-O CS CSJ-1 AF-00100 F9 AFW to 2A S/G 2 C 3 CK SA C CV-O CS CSJ-1 AF-00101 G9 AFW to 28 S/G 2 C 3 CK SA C CV-O CS CSJ-1 AF-00103 E8 AFW to 1 A S/G 2 A/C 3 CV-C 2Y SLT-5 CK SA C CV-O CS CSJ-1 AF-00105 G8 AFW to 18 S/G 2 A/C 3 CV-C 2Y SLT-5 l CK SA C CV-O CS CSJ-1 E8 AFW to 2A S/G 2 A/C 3 l AF-00106 CV-C 2Y l
SLT-5 CK SA C CV-O CS CSJ-1 G8 AFW to 28 S/G 2 A/C 3 AF-00107 CV-C 2Y SLT-5 i
4 CK SA C CV-O CS CSJ-2 AF-00108 G7 2P-29 Disch Ck 3 C 3 C 6 CK SA C CV-PO OR AF-00111 G5 2P-29 Suct Ck CSJ-3 CV-O CS 3 8 3 GL MO C BT-C OR AF-04000 G8 28 S/G AFW lsol 2Y PIT 3 8 3 GL MO C BT-C OR AF-04001 F8 2A S/G AFW Isol 2Y FIT Page 5 of 50
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POINT BEACH NUCLEAR PLANT INSERVICE TESTIN AOGRAM INSERVICE TESTING PROGRAM Revision O December 18,1990 APPEND:X E UNIT 2 VALVE PROGRAM TABLE l SYSTEM: AuxElary Feedwatm DRAWING: - M-217 f
CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS
. VALVE AF-04002 t'6 2P-29 Mini-flow 3 8 1 GA AO O BT-C OR FST OR FIT 2Y AF-04006 G5 2P-29 Ser Wtr Sup 3 8 6 GA MO O BT-O O3 PIT 2Y AF-04020 F7 AFW to 28 S/G 3 8 3 GA MO O BT-O OR BT-C OR FIT 2Y AF-04022 E8 ATW to 2A S/G 3 8 3 GA MO O BT-O OR BT-C OR FIT 2Y AF-04026 G6' 2P429 Suction Ret 3 C 1 SRV SA C .RVT 10Y l
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December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE %
SYSTEM. Aux Steem. Heating Steam ChBled ard Hot Water DRAWING NO.: M-2214. Sheet VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS HV @ 263 E2 Aux Steam to Cont 2 A 3 GA MA C SLT-1 2Y VRR73 Pass!ve HV-00286 C2 Aux Steam Cond 2 A 1.5 GA MA C SLT-1 2Y VRR-23 Ret Passive HV-00287 C2 Aux Steam Cond 2 A 1.5 GA MA C SLT-1 2Y VRR-23 Ret Passive HV-00636 .D2 Aux Steam to Cont 2 A 3 GA MA C SLT-1 2Y VRR-23 Passive HV-00637 C3 Aux Steam Cond 2 A 1.5 GA MA C SLT-1 2Y VRR-23 Ret ' Passive Page 7 of 50
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POINT BEACH NUCLEAR PLANT INSERVICE TEST. .ROGRAM
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INSERVICE TESTING PROGRAM Revision O ~
December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Chemical and Volume Control DRAWING NO.: 685J175 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CV-001128 B6 RWST to Chg Pump 2 B 4 GA MO C BT-O OR PIT 2Y CV-00112C C6 VCT to Chg Pump 2 B 4 GA MO O BT-C CS CSJ-4 PIT 2Y CV 00142 C8 Charging Flow Cont 2 B 3 b.. AO O BT-O CS CSJ-5 FST CS PR 2Y ,
CV40283A 88 Chg Pump Disc Sai 2 C .75 SRV SA C RVT 10Y CV-002838 B8 Chg Pump Disc Saf 2 C .75 SRV SA C RVT 10Y CV-00283C AB Chg Pump Disc Saf 2 C .75 SRV SA C RVT 10Y CV-00295 C10 Charging Hdr Ck 1 C 3 CK SA O CV-O OR CV-00300A C10 RCP Seal inj Thrtl 2- A 1 NE MA T BT-C RR VRR-19 SLT-1 2Y CV-003008 C11 RCP Seal Inj Thrtl 2 A 1 NE MA T BT-C RR SLT-1 2Y CV40304C C10 RCP Seal Wtr Sup 1 A/C 2 CK SA O CV-C RR VRR-12 SLT-1 2Y CV-OKM)4D C11 RCP Sea! Wtr Sup 1 A/C 2 CK SA O CV-C RR VRR-12 SLT-1 2Y CV40313 C8 RCP Seal Wir Ret 2 A 3 GA MO O BT-C CS CSJ-6 PIT 2Y SLT-1 2Y Page 8 of 50
INSERVICE TEST. 'ROGRAM POINT BEACH NUCLEAR PLANT Revision O INSERVICE TESTING PROGRAM December 18,1990
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APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Chemical and Volume Cor: trol DRAWING NO.: 685J175 CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS 2 A 3 GL , AO O BT-C CS CSJE CV40313A C9 RCP Seal Wtr Ret FST CS CSJD PIT 2Y SLT-1 2Y
' Passive 2 A 2 GL MA C SLT-1 2Y j CV40323A A9 Aux Chrging isol 2 GL MA C SLT-1 2Y VRR-23 CV403238 C9 Chg HCV Bypass 2 A Passive 2 CK SA C CV-PO OR VRR-26 CV40333A A3 BA Xfer Pump Disch 2 A/C
, CV-O RR VRR-26 CV-C OR SLT-5 2Y 2 CK SA C CV-PO CR VRR-26 CV-003338 A3 BA Xfer Pump Disch 2 A/C CV-O RR VRR-26 CV-C OR SLT-5 2Y Emerg Boration 2 B 2 GA MO C BT-O OR CV-00350 AS PIT 2Y l
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POINT BEACH NUCLEAR PLANT INSERVICE TESTit 30 GRAM w IN3ERVICE TE5flNG PROGRAM Reviscn O Decxuder 18,19%) -
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Chemical and Volume Control DRAWING NO : 684J741 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CV-00351 AS Emerg Boration Ck 2 C 2 CK SA C CV-O RR VRR-24 CV-00357 B6 RWST to Chg Pune 2 C 4 CK SA C CV-O OR CV-00370 C9 Charging Hdr Ck 2 A/C 3 CK SA O CV-O OR CV-C RR VRR-13
- SLT-1 RR CV-00371 D9 RCS Letdown Iso 2 A 2 GL AO O DT-C CS CSJ-7 FST CS CSJ-7 PIT 2Y l SLT-1 2Y CV-00371A D9 RCS Letdown Iso 2 A 2 GL AO O STC CS CSJ-7 FST CS CSJ-7 FIT 2Y SLT-1 2Y CV-003848 C8 Chg Une HCV Out 2 A 3 GL MA O BT-C CS CSJe SLT-1 2Y VRR-23 CV-01296 All Aux Charging Iso 1 A 2 GL AO C PIT 2Y k Passhe SLT-1 2Y j
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POINT BEACH NUCLEAR PLANT INSERVICE TESTI IOGRAM w INSERVICE TESTING PROGRAM Revision O December 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM Tt BLE SYSTEM: Component Coonng Water DRAWING NO.: 110E029 Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE 1.M ACT POS REOMT FREO REMARKS CC@738A G4 RHR Coorng Wtr 3 8 to GA MO C BT-O OR Sup PIT 2Y CC407388 G3 RHR Coorng W:r 3 8 to GA MO C BT-O OR _
M 2Y i
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INSERVICE TESTit AOGRAM POINT BEACH NUCLEAR PLANT Revision O INSERVICE TESTING PROGRAM ~
December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE <
SYSTEM Component Cooling Water DRAWING NO2110E029 Sheet 2 CAT SIZE TYPE ACT POS RECMT FREO REMARKS VALVE CORD FUNCTION Cf. ASS 2 B 6 GA MO O BT-C CS CSJ4 CC40719 G12 Cont CCW Sup PTT 2Y A 4 GA MO O BT-C CS CSJ-10 CC40754A F13 RCP Og Water Sup 2 SLT-1 2Y I 2Y PIT A 4 GA MO O BT-C CS CSJ-10 CC407548 F10 RCP Og Water Sup 2 SLT-1 2Y PIT 2Y 4 CK SA O CV-C 2Y VRR-10 CC40755A E13 RCP Og Wir Sup 2 A/C SLT-1 2Y VRR-23 Ck 4 CK SA O CV-C 2Y VRR-10 CC407558 E10 RCP Og Wir Sup 2 A/C SLT-1 2Y VRR-23 Ck A 4 GA MO O BT-C CS CSJ-10 CC40759A F11 RCP Og Water Ret 2 SLT-1 2Y VRR-23 PIT 2Y A 4 GA MO O BT4 CS CSJ-10 CC407598 F8 RCP Og Water Ret 2 SLT-1 2Y VRR-23 PIT 2Y 2 C 2 SRV SA C RVT 10Y CC-00763A E12 RCP Og Wir Ret '
S/R 2 C 2 SRV SA C RVT 10Y CC407638 EB RCP Og Wtr Ret S/R 2 CK SA C CV-C RR VRR-30 CC-00767 E7 Ex LD HX Og Wtr 2 A/C SLT-1 RR VRR-30 Sup l Page 12 of 50 ,
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- December 18,1990 -
4 APPENDIX E UNIT 2 VALVE PROGRAM TABLE -
I SYSTEM. Component Coorng Water DRAWING NO.: 110E029, Sheet 2 1
FUNCHON CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD t l
CC410769 FS Ex LD HX Og Wtr 2 A 2 GL AO C BT-C OR Ret FST OR l PIT 2Y SLT-1 2Y i
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INSERVICE TESTil ROGRAM POINT BEACH NUCLEAR PLANT Revision O INSERVICE TESTING PROGRAM '
December 18.1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Component Cooling Water DRAWING NO.: 110E029. Sheet 3 SIZE ' TYPE ACT POS REOMT FREQ REMARKS VALVE CORD FUNCTION CLASS CAT CC40724A G7 CCW Pump Disch 3 A/C to ' CK SA O CV-O OR Check CV-C OR SLT-5 OR CCW Pump Disch 3 A/C 10 CK SA O CVO OR CC-007248 F7 CV-C OR Check SLT-5 OR 8 2 GL MA C SLT-6 2Y Pastrve CC-00773 F9 CCW Normal 3 Makeup 3 C 3 SRV SA C RVT 10Y CC-00779 H9 CCW Surge Tank Relief CCW Surge Tk Vac 3 C 1 CK SA C CVO OR CC-00779A H9 '
Breaker CV-C OR 2 GL MO C SLT4 2Y Passrve CC-00815 F9 CCW Emerg 3 8 Makeup I
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APPENDIX E UNIT 2 VALVE PROGRAM TABLE '
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SYSTEM: Ca-enneiit Spray L DRAWING NO.: M-110E035. Sheet 3
- VALVE CORD FUNCTION CLASS CAT S!ZE TYPE ACT POS REOMT FREQ REMARKS !
SI40836A F7 NaOH Supply 2 8 2 GL AO C ET-O CS CSJ-11 FST CS CSJ-11 PIT 2Y SI-0083GB E7 NaOH Supply 2 B 2 GL AO C BT-O CS CSJ-11 ;
FST CS CSJ-11 i N W SI40840A G5 Spray Add Tank 2 C .75 SRV SA C RVT 10Y Vac Breaker SI408408 G5 Spray Add Tank 2 C 75 SRV SA C RVT 10Y vac Breaker S140847A H8 Spray Add Educt 2 C 2 CK SA C CV-O OR !
M SI-008478 D8 Spray Add Educt 2 C 2 CK SA C CV-O OR t
Creeck SI40858A 13 RWST to CS Pump 2 C 6 CK SA C CV-PO OR VRR4 P14A INSP SP VRR4 Slo 08588 C3 RWST to CS Pump 2 C 6 CK SA C CV-PO OR VRRE P148 INSP SP VRR4 ;
SI40860A 110 CS Pump 1-P14A 2 8 6 GA MO C BT-O OR Da* m OR SI-008608 11 0 CS Pump 1-P14A 2 8 6 GA MO C BT-O OR Discn m OR l
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December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Containment Spray DRAWING NOc M-110E035. Sheet 3
! CORD FUNCTION CLASS CAT S!ZE TYPE ACT POS REOMT FREO REMARKS VALVE C10 CS Pump 1-P14B 2 B 6 GA MO C BT-O OR SI40860C Disch FIT OR C10 CS Pump 1-P148 2 8 6 GA MO C BT-O OR SI-00860D ,
Disch FIT OR J CS Pump 1-P14A 2 6 CK SA C INSP SP VPR-9 SI-00862A III A/C SLT-1 RR VRR-23, 29 Desch CS Pump 1-P148 2 6 CK SA C INSP SP VRR-9 SI40862B C11 A/C SLT-1 RR VRR-23,29 Disch H11 CS Pump Test 2 A .75 GL MA C SLT-1 2Y Passive SI-00864A Recirc VRR-23 CS Pump Test 2 A .75 GL MA C SLT-1 2Y Passive SI-008648 C11 Recirc VRR-23 RWST to CS Pump 2 A 6 GA MO O BT-O CS CSJ-29 S140870A 13 P14A BT-C CS CSJ-29. Note 3 SLT-6 2Y Note 2
- PET 2Y RWST to CS Pump 2 A 6 GA MO O BT-O OR CSJ-29 SI408708 C3
(
l P148 BT-C OR CSJ-29. Note 3 SLT-6 2Y Note 2 f
PET 2Y SI-00871A 15 RHR to CS Pump 2 8 6 GA MO C BT4 OR P14A BT-C OR I PIT 2Y Page 16 of 50
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uj INSERVICE TESTING PROGRAM Revision O ~
December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Containment Spray DRAWING NOc M-110E035. S.%W3 FUNCTION CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD C1. ASS SI-00871B C5 RHR to CS Pump 2 8 6 GA MO C BT-O OR P148 BT-C OR FIT 2Y G6 Spray Add Tank Saf 2 C .75 RV SA C RVT 10Y SI-00872 l
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INSERVICE TESTING PROGRAM Revision O December 18,1990 1 APPENDIX E
, UNIT 2 VALVE PROGRAM TABLE i
SYSTEM. Desonized/ Reactor Makeup Water DRAWING NOc PBM-231, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS DI4)0009 E2 DI Water Sup to 2 A 2 DI MA C SLT-1 2Y Passive i Corit DI4)0011 E1 DI Water Sup to 2 A 2 DI MA C SLT-1 2Y Passive Cmt p j
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INSERVICE TESTih 10 GRAM POINT BEACH NUCLEAR PLANT Revision O INSERVICE TESTING PROGRAM December 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM; Heating and Ventilation DRAVANG NO.: M-2215. Sheet 1 CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS A 36 BTF AO C BT-C CS CSJ-12 VNPSE-03212 G3 Cont Purge Exhaust 2 FST CS CSJ-12 SLT-1 2Y VRR-23, 29 PTT 2Y A 36 BTF AO C BT-C CS CSJ-12 VNPSE43213 G3 Cont Purge Exhaust 2 FST CS CSJ-12 SLT-1 2Y VRR-23. 29 PIT 2Y
. CS CSJ-12 Cont Purge Supply 2 A 36 BTF AO C BT-C VNPSE-03244 5
D3 CSJ-12
! FST CS SLT-1 2Y VRR-23. 29 PIT 2Y A 36 BTF AO C BT-C CS CSJ-12 VNPSE-03245 D3 Cont Purge Supoly 2 FST CS CSJ-12 SLT-1 2Y VRR-23. 29 PIT 2Y w
l l
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POINT BEACH NUCLEAR PLANT INSERVICE TESTIA IOGRAM INSERVICE TESTING PROGRAM Revision O uj December 18,154K)
APPENDIX E UNIT 2 VALVE PROGRAM TABLE
)
SYSTEM: Heating and Ventiation DRAWING NO.: M-2215. Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS RM43200AA G3 Cont Atmos Samp 2 A/C 1 CK SA O CV-C RR VRR-16 <
Retr SLT-1 RR l RM43200A F3 Cont Atmos Samp 2 A 1 GA AO O BT-C OR Retr FST OR SLT-1 2Y FIT 2Y RM432006 F8 Cont Atmos Samp 2 A 1 GA AO O BT-C OR Sup FST OR I SLT-1 2Y PIT 2Y RMo3200C G8 Cont Atmos Samp 2 A 1 GA AO O BT-C OR Sup FST OR SLT-1 2Y PIT 2Y f
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POINT BEACH NUCLEAR PLANT INSERVICE TESTIN iOGRAM w INSERVICE TESTING PROGRAM Revison O December 18,1990 ~
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM Instrument Air DRAWING NOz M-209. Sheet VALVE CORD FUNCTION Ct. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS IA40876 E8 Purge Viv 3244 Suo NC A/C _25 CK SA C CV-O OR CVC OR
- SLT3 2Y !
IA40877 E8 Purge Viv 3212 Sup NC A/C .25 CK SA C CV-O OR CV-C OR SLT-3 2Y IA41315 E3 Inst Air to Cont 2 A/C 2 CK SA C CV-C OR SLT-1 2Y VRR-23 >
t IA-01316 E4 Inst Air to Cont 2 A 1 GA MA C SLT-1 2Y VRR-23 Passive IA-01324 F3 Inst Air to Cont 2 A/C 2 CK SA C CV-C OR !
SLT-1 2Y IA43047 E3 Inst Air to Cont 2 A 2 GA AO O BT-C OR ,
FST OR SLT-1 2Y PIT 2Y IA43048 F3 Inst Air to Cont 2 A 2 GA AO O BT-C OR ,
FST OR SLT-1 2Y
- M 2Y !
l l
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INSERVICE TESTIN IOGRAM POINT BEACH NUCLEAR Pt. ANT Revision O w C INSERVICETESTING PROGRAM December 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: tw Air DRAWING NO.: M-209. Sheet 11 POS REOMT FREO REMARKS CLASS CAT SIZE TYPE ACT VALVE CORD FUNCTION C CV-O CS CSJ-28 NC A/C CK SA IA-01335 F4 Inst Air to PORV CVC CS CSJ-28 SLT-3 2Y VRR-32 Note 1 C CV-O CS CSJ-28 NC A/C CK SA 1A-01338 G4 Inst Air to PORV CSJ-28 CV4 , CS SLT-3 2Y VRR-32 Note 1 C CV-O CS CSJ-13 Purge Viv 3245 Sup NC A/C .25 CK SA IA41401 H2 CVC CS CSJ-13 SLT-3 2Y C CV-O CS CSJ-13 Purge Viv 3213 Sup NC A/C 25 CK SA IA-01402 M1 CV-C CS CSJ-13 SLT-3 2Y C CV-O CS CSJ-28 l
NR Sup to PORV NC A/C CK SA IA41418 F4 CV-C CS CSJ-28 SLT-3 2Y Note 1 CK SA C CV-O CS CSJa IA41419 G4 NR Sup to PORY NC A/C CSJ-38 CV-C CS SLT-3 2Y Note 1 CK SA C CV-O CS CSJa IA41652 F4 Inst Air to PORV NC A/C CSJa Cvc CS SLT-3 2Y VRRG2 Note 1 l
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- POINT BEACH NUCLEAR PI_ ANT INSERVICE TESTib 10 GRAM w ;NSERVICE TESTING PROGRAM Revison O December 18,1990 '
APPENDIX E UNIT 2 VALVE PROGRAM TABLE ~
SYSTEM: Instrument Air DRAWING NO2 M-209, Sheet 11 VALVE CORD FUNCTION CIASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS IA41653 G4 Inst Air to PORV NC A/C CK SA C CV-O CS CSJ-28 CV-C CS CSJ-28 SLT4 2Y VRR-32 Note 1 l IA46308 F4 PORV Nit Sup S/R NC C SRV SA C RVT 10Y Note 1 i
IA46309 G4 PORV NR Sup S/R NC C SRV SA C RVT 10Y Note 1 IA46310 F5 PORV 430 NR Sup NC C GL SA O/C BT-EE CS CSJ-28 i N 1
IA-06311 G5 PORV 431C NR Sup NC C GL SA' O/C BT-EE CS CSJ-28 Reg i
i
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POINT BEACH NUCLEAR PLANT INSERVICE TESTI6 ROGRAM INSERVICE TESTING PROGRAM Reviston O December 18,1990 '
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM. Main Feedwater DRAWING NO.: M-2202, Sheet 2 VALVE CORD FUNCHON Ct. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CS-00466AA C2 S/G 1 A FW Ck 2 A/C 16 CK SA O CV-C RR VRR-21 SLT4 RR VRR-21 CS40466BB D1 S/G 1 A FW Ck 2 A/C 16 CK SA O CV-C RR VRR-21 SLT-6 RR VRR-21 CS40476AA G2 S/G 1B FW Ck 2 A/C 16 CK SA O CV-C RR VRR-21 SLT-6 RR VRR-21 CS40476BB H1 S/G 1B FW Ck 2 A/C 16 CK SA O CV-C RR VRR-21 SLT-6 RR VRR-21 Page 24 cf 50
INSERVICE TEST >ROGRAM POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM Revison 0 '
December 18,1990 APPENDIX E t
UNIT 2 VALVE PROGRAM TABLE <
SYSTEM: Main and Reheat Steam DRAWING NO.: M-2201. Sheet i l CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION Cf. ASS 2 C 6 RV SA C SRV SY MS42005 G3 Main Stm Safety G4 Main Stm Safety 2 C 6 RV SA C SW SY MS42006 2 C 6 RV SA C SRV SY MS-02007 G4 Main Stm Safety 2 C 6 RV SA C SRV SY MS42008 G4 Main Stm Safety 2 C 6 RV SA C SRV SY MS42010 D3 main Stm Safety C SRV SY l D4 Main Stm Safety 2 C 6 RV SA MS-02011 Main Stm Safety 2 C 6 RV SA C SRV SY MS42012 D4 2 C b RV SA C SRV SY MS42013 D4 Main Stm Safety 8 6 GL AO C BT-C CS CSJ-14 MS42015 H5 MS Atmos Sim 2 BT-O CS CSJ-14 Dmp PIT 2Y B 6 GL AO C BTC CS CSJ-14 MS42016 ES MS Atmos Stm 2 BT-O CS CSJ-14 Dmp
' PIT 2Y B 30 SCK AO O BT-C CS CSJ-15 MS42017 G5 Main Stm isolation 2 PIT 2Y FST CS W15 CK SA O CVC CS CSJ-16 MS-02017A G7 Main Stm Nonretum 2 C 30 B AP SO C BT-PV CS CSJ-17 MS42017CS H6 MSIV 2017 Air PEot NC 1 B AP SO C BT-PV CS CSJ-17 MS42017DS H6 MStV 2017 Air PBat NC 1 [
Page 25 of 50
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POINT BEACH NUCLEAR PLANT INSERVICE TESTIA 30 GRAM i INSERVICE TESTING PROGFAM ReWJon O '
December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Main ard Reheet Steam DRAWING NOc M-2201, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS MS-02018 DS Main Stm Isolation 2 B 30 SCK AO O BT-C CS CSJ-15 PIT 2Y FST CS CSJ-15 MS42018A D7 Main Stm Nonretum 2 C 30 CK SA O CV-C CS CSJ-16 MS-02018CS E6 MSIV 2018 Air Pilot NC B 1 AP SO C BT-PV CS CSJ-17 MS42018DS E6 MSIV 2018 Air Piet NC B 1 AP SO C BT-PV CS CSJ-18 MS42019 F6 AFW Steam Supply 2 2 B/C 3 SCK MO S BT4 OR CV-O OR BT-C OR PIT 2Y MS42020 E6 AFW Steam Supply 2 B/C 3 SCK MO S BT-O OR CV-O g OR BT-C OR PIT 2Y MS42082 88 Main Steam to AFW 2 8 3 GL SA/ O BT-C OR VRR-1 Pump MA BT-O OR PIT 2Y MS42083 82 S/G Sample Isol 2 A .75 DI AO O BT-C OR FST OR SLT-1 2Y PIT 2Y Page 26 of 50
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POINT BEACH NUCLEAR PLANT INSERVICE TESTI 'ROGRAM INSERVICE TESTING PROGRAM Revision O
~
December 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Main and Reheat Steam DRAWING NO.: M-2201, Sheet 1 i VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS MS-02084 F2 S/G Sample Isol 2 A .75 DI AO O BT-C OR FST OR SLT-1 2Y .
PIT 2Y MS-02090 89 SW to AFW Pump 3 B 1 GL SO O BT-O OR VRR-20 P-029 FST OR MS-05958 E2 S/G Blowdown isol 2 A 2 GA AO O BT-C OR FST OR SLT-1 2Y PIT 2Y MS45959 82 S/G Blowdown isol 2 A 2 GA AO O BT-C OR FST OR SLT-1 2Y PIT 2Y RS-SA-10 F9 RDW Steam Supply 2 8 3 GA AO O BT-C OR FST OR PIT 2Y I
i i
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POINT BEACH NUCLEAR PLANT INSERVICE TESTI. 'ROGRAM ,
INSERVICE TESTING PROGRAM Revision O ,
December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: PostN Containment Vert / Monitoring DRAWING NO.: M-224 VALVE CORD FUNCTION Ct. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS H2-V-04 DS Post-Acc Purge 2 A 2 Di MA C BT-O OR Disch SLT-1 2Y VRR-23 H2-V-05 D5 Post-Acc Purge 2 A 2 DI MA C BT-O OR Disch SLT-1 2Y VRR-23 H2-V-06 DS Post-Acc Purge 2 A .75 GA MA C SLT-1 2Y VRR-23 Drain Passive H2-V-07 DS Post-Acc Purge 2 A .75 GA MA C SLT-1 2Y VRR-23 Drain Passive H2-V-08 E5 Post-Acc Atmos 2 A 75 DI MA C SLT-1 2Y Passive Samp 4
H2-V-09 E5 Post-Acc Atmos 2 A .75 DI MA C SLT-1 2Y Passive Samp H2-V-12 DS Post-Acc Svc Air 2 A 2 DI MA C BT-O OR Sup SLT-1 2Y VRR-23 H2-V-13 DS Posth Syc Air 2 A 2 Di MA C BT-O OR Sup SLT-1 2Y VRR-23 H2-V-19 D5 Post-Acc Alt Vent 2 A 2 DI MA C SLT-1 2Y VRR-23 Passive H2-V-20 DS Post-Acc A!t Vent 2 A 2 DI MA C SLT-1 2Y VRR-23 Passive H2-V-22 D4 Post-Acc Sup Drain 2 A 2 DI MA C SLT-1 2Y VRR-23 Passive Page 28 of CO
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POINT BEACH NUCLEAR PLANT INSERVICE TEST 1h .30 GRAM eg
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INSERVICE TESTING PROGRAM Revision O December 18,1990 '
- APPENDIX E -
UNIT 2 VALVE PROGRAM TABLE i SYSTEM PoM-Accident Containment Vert / Monitoring
! DRAWING NO.: M-224 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS ;
H2-V44 DS Post-Acc Purge 2 A 2 DI MA C BT-O OR Disch SLT-1 2Y VRR-23 H2-V-23 D4 Post-Acc Sup Drain 2 A 2 DI MA C SLT-1 2Y VRR-23 Passive 6
i e
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INSERVICE TESTil ROGRAM POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM Revision O '
December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Primary Sampling DRAWING NO.- 541F448 FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VAL'E CORD Press Sim Sample A .375 GL AO C BT-C OR SC4)0951 F9 1 FST OR SLT-1 2Y PIT 2Y E9 Press Liq Sample A .375 GL AO C BT-C OR l SC@953 1 OR FST SLT-1 2Y PIT 2Y Hot Leg Sample A .375 GL AO O/C BT-C OR SCm E9 1 OR FST SLT-1 2Y PIT 2Y SC4)0959 D9 RHR Sample 2 A .375 GL AO C BT4 OR FST OR SLT6 2Y PIT 2Y F8 Press Stm Sample 1 A .375 GL AO C BT-C OR SC4X)966A FST OR SLT 1 2Y PIT 2Y E8 Press Liq Sampie 1 A .375 GL AO C BT-C OR SC-009668 FST OR SLT-1 2Y PIT 2Y I
Page 30 of 50 ,
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m INSERVICE TEST 1. 'ROGRAM POINT BEACH NUCLEAR PLANT >
Revision O INSERVICE TESTING PROGRAM December 18,1990 i
APPENDIX E '
UNIT 2 VALVE' PROGRAM TABLE SYSTEM: Primary Sampling DRAWING NO.: 541F448 CAT SIZE TYPE ACT POS REOMT FREO REMARKS l VALVE CORD FUNCTION CLASS ,
Leg Sample A .375 GL AO O/C BT-C OR SC40966C E8 1 FST OR SLT-1 2Y PIT 2Y i
f i
r f
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POINT BEACH NUCLEAR PLANT INSERVICE TEST 2ROGRAM INSERVICE TESTING PROGRAM Revision O December 18,1990 -
APPENDIX E ,
UNIT 2 VALVE PROGRAM TABLE .
I SYSTEM: Reactor Coolant DRAWING NOz 541F445, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS RC-00430 H5 Power-Operated Ret 1 B 2 GL AO C BT4 CS CSJ-18 BT-O CS CSJ-18 ;
FST CS CSJ-18 PIT 2Y RC4A,431C ! 15 Power-operated Ret 1 B 2 GL AO C BT-C CS CSJ-18 ;
BT-O CS CSJ-18 FST CS CSJ-18 PIT 2Y RC-00434 17 Pressudzer Safety 1 C 3 SRV SA C RVT SY RC-00435 16 Pressurizer Safety 1 C 3 SRV SA C RVT SY I RC-00515 15 PORV Block Valve 1 B 3 GA MO O BT-C OR PIT 2Y RC-00516 HS PORV Block Valve 1 B 3 GA MO O BT-C OR PfT 2Y Page 32 of 50
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INSERVICE TESTIN tOGRAM POINT BEACH NUCLEAR PLANT l INSERVICE TESTING PROGRAM Re Asion O December 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Reactor Coolant DRAWING NO.: 541F445. Sheet 2 R
CAT SIZE TYPE ACT POS REOMT FREO REMARVS VALVE CORD FUNCTION CLASS D2 PRT FE LineIso 2 A 2 DI AO O/C BT-C OR RC-00508 FST OR SLT-1 2Y PIT 2Y SA CV-C RR VRR-11 GC4)0528 D3 PRT Nitrogen Sup 2 A/C .75 CK O/C SLT-t RR 2 2 CK SA O/C CV-C RR VRR-18 RCOOS29 D3 PRT FB Une Ck A/C SLT-1 RR E3 PRT Sample 2 A .375 GL AO O BT-C OR RC-00538 FST OR SLT-1 2Y PIT 2Y E2 PRT Sample 2 A .375 GL AO O BT-C OR RC-00539 FST OR SLT-1 2Y PIT 2Y B GL SO C BT-O CS CSJ-19 RC4)0570A F5 RX Vess Vent 1 1 PIT 2Y B GL SO C BT-O CS CSJ-19 RC-00570B F5 RX Vess Vent 1 1 PET 2Y 8 1 GL SO C BT-O CS CSJ-19 RC-00575A F5 RX Vess/ Press Vent 1 PET 2Y 8 GL SO C BT-O CS CSJ-19 RC-005758 F4 RX Vess/ Press Vent 1 1 PET 2Y Page 33 of 50
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POINT BEACH NUCWAR PLANT INSERVICE TESTI. ROGRAM INSERVICE TESTING PROGRAM 7evision O Decenher 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM TABE
! SYSTEM: Reactor Coolant i
DRAWING NO.: 541F445. Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS RECMT FREO REMARKS RC-00580A GS Pressurizer Vent 1 B 1 GL SO C BT-O CS CSJ-19 l PIT 2Y RCo05808 G5 Pressurizer Vent 1 B 1 GL SO C BT-O CS CSJ-19 PIT 2Y RC-00595 D3 PRT Nitrogen Sup 2 A 75 DI MA O/C BT-C OR l SLT-1 2Y ,
t I
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INSERVICE TESTIT ROGRAM POINT BEACH NUCLEAR PUJ4T Revision O INSERVICE TESTING PROGRAM December 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM TABLE l
SYSTEM: Safety injection and Residual Heat Removal l
DRAWING NO.: 110E029, Sheet 1 SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT 2 C 8 CK SA C CV-PO OR RH@710A E4 RHR Pump Disch CSJ-26 CV-O CS Ck SLT-5 2Y i
2 C 8 CK SA C CV-PO OR RHm7108 B4 RHR Pump Disch CSJ-26 CV-O SC Ck SLT-5 2Y 2Y j 2 A 8 GA MA C SLT-5 RH@742 H6 RHR/RWST isol A 2 GL MA C SLT-5 2Y l RH@742A HG RHR/RWST isol 2 BTF AO O PIT 2Y Passive G7 RHR HX Outlet 2 B 8 Si m 4 BTF AO O PIT 2Y Passive G7 RHR HX Outlet 2 8 8 Si m s s
Page 35 of 50
, ,- n POINT BEACH NUCLEAR PLANT INSERVICE TEST 2ROGRAM .
INSERVICE TESTING PROGRAM Revision O December 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E035. Sheet 1 -
VALVE CORD FUNCTION Ct. ASS CAT SIZE TYPE ACT POS REOMT FREQ REMARKS SIC 0830A J10 SIS Accum Rdief 2 C 1 SRV SA C RVT 10Y SI-00830B F10 SIS Accum Relief 2 C 1 SRV SA C RVT 10Y SI40834A H7 SIS Accum Vent 2 8 1 GL AO C BT-O CS CSJ-30 FST CS CSJ @
PIT 2Y SI-008348 D7 SIS Accum Vent 2 B 1 GL AO C BT-O CS CSJ-30 FST CS CSJ @
PW 2Y SI40841A H10 SIS Accum Disch 2 8 10 GA MO O BT-C CS CSJ-20 PR 2Y SI-00841B E10 SIS Accum Disch 2 B to GA MO O BT-C CS CSJ-20 PIT 2Y S140842A H12 SIS Accum Disch 1 A/C 10 CK SA C CV-PO E-CS VRR-4 Ck CV-C OR VRR4 CV-PO RR VRR4
+
INSP SP VRR-4 SLT4 OR VRR4 SI-008428 E12 SIS Accum Disch 1 A/C 10 CK SA C CV-PO E-CS VRR4 Ck CV-C OR VRR-4 CVPO RR VRR-4 INSP SP VRR4 SLT-4 OR VRR-4 Page 36 of 50
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POINT BEACH NUCLEAR PLANT INSERVICE TESTit ROGR?.M INSERVICE TESTING PROGRAM RevisK)n O 4
- December 18,1990 ~
APPENDIX E UNIT 2 VALVE PROGRAM TABLE i
SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E035. Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI-00845A H12 SIS Cold Leg inj 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C RR VRR-2 SLT-2 2Y VRR-22 SI-008458 D12 SIS Cold Leg ini 1 A/C 7 CK SA C CV-O RR VRR-2 CV-C RR VRR-2 ,
SLT-2 2Y VRR-22 SI4)0845C G12 SIS Core Deluge 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C RR VRR-2 SLT-2 2Y VRR-22 SI4)0845D D12 SIS Core De?uge 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C RR VRR-2 g SLT-2 2Y VRR-22 SI4)0845E E12 SIS Cold Leg inj 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C RR VRR-2 SLT-2 2Y VRR-22 SI-00845F G12 SIS Cold Leg inj 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C RR VRR-2 SLT-2 2Y VRR-22 SI-00846 JS Accum Nit Supply 2 A 1 GL AO C BT-C OR FST OR FIT 2Y SLT-1 2Y SI4)0850A B7 Coot Sump Hyd Isol 2 B 10 GA HO C BT-O OR FIT 2Y Page 37 of 50
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POINT BEACi' NUCLEAR PLANT INSERVICE TESTil' 30 GRAM w INSERVICE T6 STING PROGRAM Revision O -'
De:s aber 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety friection and Resklual Heat Removal DRAWING NO.: 110E035, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS Sim8500 B10 Cont Sump Hyd Isol 2 B 10 GA HO C BT-O OR FIT 2Y SI40851A B5 Cont Sump Isol 2 3 10 GA MO C ST-O OR FIT 2Y SI-00851B A5 Cont Sump Isol 2 8 to GA MO C BT4 OR PIT 2Y SI40852A C11 RHR/LH Core 2 B 6 GA MO C BT-O CS CSJ-21 Deluge dT-C CS CSJ-21 PIT' 2Y SI408528 B11 RHR/LH Core 2 B 6 GA MO C BT-O CS CSJ-21 Deluge BT-C CS CSJ-21 PIT 2Y SI-00853A C12 RHR/LH Inj Check 1 A/C 6 CK SA C CV-PO E-CS VRR4 CV-C E-CS VRR4 CV-O RR VRR4 *
(.N-C RR VRR4 SLT-2 2Y VRR-22 .
SI40853B B12 RHR/LH Inj Check 1 A/C 6 CK SA C CV-PO E-CS VRR4 ;
CV-C E-CS VRR4 CV-O RR VRR-3 CV-C RR- VRR-3 i SLT-2 2Y VRR-22 !
Page 38 of 50
INSERVICE TEST PROGRA.M POINT BEACH NUCLEAR PLANT '
INSERVICE TESTING PROGRAM Revision O December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety injection and Residual Heat Removal l
DRAWING NO.: 110E035, Sheet 1 l
CAT SIZE TYPE ACT POS REOMT FREO REAMRKS VALVE CORD FUNCTION CLASS RHR/ Core Deluge A/C 6 CK SA C CV-PO ECS VRR-3 Sl40853C C13 1 CV-C E-CS VRR-3 CV-O RR VRR-3 CV-C RR VRR-3 SLT-2 2Y VRR-22 6 CK SA C CV-PO E-CS VRR-3 SI-00853D B13 RHR/ Core Deluge 1 A/C CV-C E-CS VRR-3 >
CV-O RR VRRO CV-C RR VRR-3 SLT-2 2Y VRR-22 RHR RX Ves inj S/R 2 C .75 SRV SA C RVT 10Y SI-00e61A C8 SIS Pump Disch 2 B 4 GA MO O BT-O OR SI-00866A H5 PIT 2Y H5 SIS Pump Disch 2 B 4 GA MO O BT-O OR SI-008668 1 FIT OR VRR4 SI40867A H13 SIS Cold Leg inj Ck 1 A/C to l CK SA C CV-PO CV-C E-CS E-CS VRR-4 CV-PO RR VRR-4 CV-C RR VRR-4 INSP SP VRR-4 SLT-2 2Y VRR-22 Page 39 of 50 I
INSERVICE TEST 3ROGRAM POINT BEACH NUCLEAR Pl. ANT -
Revision 0 INSERVICE TESTING PROGRAM December 18,1990 -
- APPENDIX E 1
UNIT 2 VALVE PROGRAM TABLE a.
SYSTEM: Safety injection and Residtni Heat Removal DRAWING NO.: 110E035. Sheet 1 SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT CK SA C CV-PO CS VRR-4 E13 SIS Cold Leg inj ck 1 A/C 10 SI-00867B CV-C 2Y VRR-4 CV-PO RR VRR-4 CV-C RR VRR4 INSP SP VRR4 SLT-2 2Y VRR-22 2 .75 CK SA C CV-O OR SI-00875A F7 SIS Test Recirc Ck A/C CVD OR SLT-5 2Y 2 .75 CK SA C CV-O OR SI-008758 F7 SIS Test Recirc Ck A/C CV-C OR SLT4 2Y l 2 GL MO C BT-O CS CSJ-22 l SI-00878A D12 RX Vessel Safety in] 2 B BT-C CS CSJ-22 PIT 2Y GL MO O BT-O CS CSJ-23 SI-00878B D12 SIS Loop Inj 2 8 2
' PIT 2Y B 2 GL MO C BT-O CS CSJ-22 )
SI-00878C G12 RX Vessel Safety in) 2 BT-C CS CSJ-22 i PIT 2Y 2 GL MO O BT-O CS CSJ-23 j SI4X)878D H12 SIS Loop inj 2 B PET 2Y C .75 SRV SA C RVT 10Y ,
SI-00887 F6 Test Line S/R 2 Page 40 of 50
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POINT BEACH NUCLEAR PLANT INSERVICE TESTil ROGRAM INSERVICE TESTING PROGRAM Revision O December 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM. Safety injection ansi Residtral Heat Remo.W DRAWING NO.: 110E035. Sheet 1 VALVE CORD' FUNCTION Ct. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI-00957 16 N2 Supply Vent / Ret 2 A 1 GL AO C BT-O CS CSJ N FST CS CSJ-30 SLT-1 2Y PIT 2Y r
4 Page 41 of 50
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INSERVICE TESTih 10 GRAM POINT BEACH NUCLEAR PLANT ~
Revision O e INSERVICE TESTING PROGRAM December 18,1990 -
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E035, Sheet 2 CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION SIS Pump Suction 2 B 12 GA MO C BT-O OR SI40825A HS FIT 2Y ,
HS SIS Pump Suction 2 8 12 GA MO C BT-O OR SI-008258 FIT 2Y _
2 B 8 GA MO C BT-O CS CSJ-24 SI-008268 J7 SIS Pump Rendunt Suct BT-C CS CSJ-24 PIT 2Y SIS Pump Rendunt 2 B 8 GA MO C BT-O CS CSJ-24 SI40826C 17 Suct BT-C CS CSJ-24 PIT 2Y l
RHR Pump Suct Ck 2 10 CK SA C CV-O RR VRR4 SI-00854A E4 A/C CV-C RR VRR4 SLT-6 RR VRR-6 RHR Pump Suct Ck 2 10 CK SA C CV-O RR VRR4 SI-008548 E4 A/C CV-C RR VRR4 SLT4 RR VRRE RHR Pump Suct 2 B to GA MO O BT-C CS CSJ-31 SI-00856A E4 PIT 2Y 2 B 10 GA MO O BT-C CS CSJ-31 SI-008568 E4 RHR PUMP Suct FIT 2Y G8 RHR to SIS Pump 2 B 6 GA MA C BT-O OR
! SI-00857A !
Suct i
G7 RHR to SIS Pump 2 8 6 GA MA C BT-O OR SI-008578 Suct Page 42 of 50
PO!NT BEACH NUCLEAR PLANT _ INSERVICE TESTI! ROGRAM INSERVICE TESTING PROGRAM Revision O .i December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E035. Sheet 2 VALVE COFtD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI-00889A 11 0 SIS Pump Disch Ck 2 C 6 CK SA C CV-PO OR VRR-7 ,
CV-O RR VRR-7 SLT-5 __
2Y SI-00889B H10 SIS Pump Disch Ck 2 C 6 CK SA C CV-PO OR VRR-7 i CV-O RR VRR-7 SLT-5 2Y SI4)0891A G9 SIS Pump Mini-rec 2 C 2 CK SA C CV-PO OR VRR-27 Ck INSP SP VRR-27 SI-008918 G9 SIS Pump Mini-rec 2 C 2 CK SA C CV-PO OR VRR-27 Ck INSP SP VRR-27 SI-00895 H5 SIS Pump Mini-Rec 2 C 2 CK SA C CV-O OR Ck
! SI-00896A 17 SIS Pump Suction 2 8 6 GA MO O BT-C OR Pli 2Y SI4)08968 H7 SIS Pump Suction 2 8 6 GA MO O BT-C OR PIT 2Y 4
SI4)0897A 12 SIS Test Line Ret 2 A 2 GL AO O BT-C CS CSJ-25 FST CS CSJ-25 SLT-5 2Y PIT 2Y SI4)08978 H2 SIS Test Line Ret 2 A 2 GL AO O BT-C CS CSJ-25 FST CS CSJ-25
- SLT-5 2Y PIT 2Y t
Pa9e <i 9 50
n POINT BEACH NUCLEAR PLANT INSERVICE TESTil ROGRAM INSERVICE TESTING PROGRAM Revision O '
December 18,1990 APPENDIX E -
UNIT 2 VALVE PROGRAM TABLE ,
SYSTEM: Service Air DRAWING NO_: M-209, Sheet 2 CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REQtJT FREO REMARKS VALVE 2 A 4 GA MA C SLT-1 2Y Passive SA-00015 F4 Service Air Cont Sup SA-00017 F4 Service Air Cont 2 A/C 4 CK SA C CV-C OR Sup SLT-1 2Y l
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n INSERVICE TEST )ROGRAM POINT BEACH NUCLEAR PLANT Revision 0 -
INSERVICE TESTING PROGRAM December 18,1990 l
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Service Water DRAWING NO.: M-207, Sheet 1 SIZE TYPE ACT POS REOMT FREQ REMARKS VALVE CORD FUNCTION CLASS CAT f 8 CK SA O CV-PO OR VRR-15 SW-00112A G7 SW to AFW Pp 3 C 1 INSP RR VRR-15 P-029 l
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INSERVICE TESTit . lOGRAM POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM Revision O ..--
a December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Servic's Water DRAWING NO.: M-2207. Sheet 1 CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION C6 WT Service Wtr inlet 3 8 6 GA MO O BT-C OR SW-02817 PIT 2Y 3 B 6 GA MO O BT-C CS CSJ-27 SW-02880 C5 Turb Hall Cirs in PIT 2Y Page 46 of 50
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POINT BEACH NUCLEAR PLANT INSERVICE TESTit 'lOGRAM w INSERVICE TESTING PROGRAM Revision 0 -
December 18,1990 '
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Service Water DRAWING NO.: M-207, Sheet 4 VALVE CORD FUNCTIOM Cl. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SW40015A G8 Cont Or Suppy Ck 3 C 8 CK SA O CV-O OR SW-00015B G6 Cont Or Supply Ck 3 C 8 CK SA O CV-O OR SW-00015C G7 Co'd Or Supply Ck 3 C 8 CK SA O CV-O OR SW-00015D G7 Cont Or Supply Ck 3 C 8 CK SA O CV-O OR SW42907 C8 Cont Or Emerg 3 8 12 GA MO C BT-O OR Flow PIT 2Y SW42908 C7 Cont Or Emerg 3 B 12 GA MO C BT-O OR Flow PIT 2Y SW42959 E8 Cont Or Disch S/R 3 C 1 SRV SA C RVT 10Y SW42963 E6 Cont Or Disch S/R 3 C 1 SRV SA C RVT 10Y SW42967 E7 Con 2 Or Disch S/R 3 C 1 SRV SA C RVT 10Y SW42971 E6 Cont Or Disch S/R 3 C 1 SRV SA C RVT 10Y SW44300 ES Cavity Or Ret S/R 3 C 1 SRV SA C RVT 10Y j SW-04301 E5 Cav!!y Or Ret S/R 3 C 1 SRV SA C RVT 10Y l
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3ROGRAM POINT BEACH NUCLEAR PLANT INSERVICE TEST '
INSERVICE TESTING PROGRAM Revision O ~
December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Waste Disposal DRAWING NO.: 684J971, Sheet CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS A 2 DI MA C SLT-1 2Y VRR-23 SF-00816 C6 P-033 RWCP 2 ,
Passive Suction RCDT Pump 2 A 3 DI AO O/C BT-C QR WL-010038 C6 Suction FST OR SLT-1 2Y VRR-23 PIT 2Y C6 RCDT Pump 2 A 3 DI AO O/C BT-C OR WL-010038 t
Suction FST OR SLT-1 2Y VRR-23 PIT 2Y A 2 DI AO C SLT-1 2Y VRR-23 WL-01698 C6 RCDT to El -19' 2 PIT 2Y Passive Sump i
C6 RCDT Pumps Suct 2 A 3 DI AO O/C BT-C OR j WL41721 Con FST OR l SLT-1 2Y PIT 2Y Containment Sump 2 A 3 DI AO O/C BT-C OR WL-01723 C6 Dr FST OR SLT-1 2Y VRR-23 PIT 2Y Containment Sump 2 A 3 DI AO O/C BT-C OR WL-01728 C6 Dr FST OR SLT-1 2Y VRR-23 PIT 2Y Page 48 of 50 l
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POINT BEACH NUCLEAR PLANT INSERVICE TEST! 'ROGRAM -
INSERVICE TESTING PROGRAM Revision O J-
. December 18,1990 '
APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Waste Disposal DRAWING NO.: 684J971. Sheet t VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS WG-01786 B5 RCDT Vent 2 A 1 DI AO O BT-C OR FST OR SLT-1 2Y PR 2Y WG41787 B5 RCDT Vent 2 A 1 DI AO O BT-C OR FST OR SLT-1 2Y PR 2Y WG41788 B5 RCDT Sample '2 A .75 DI AO O/C BT-C OR FST OR SLT-1 2Y PR 2Y WG-01789 B5 RCDT Sample 2 A _75 DI AO O/C BT-C OR FST OR SLT-1 2Y PW 2Y ,
t Page 49 of 50
l INSERVICE TEST) 'ROGRAM "-
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM Revision O ~
December 18,1990 APPENDIX E UNIT 2 VALVE PROGRAM TABLE NOTES
- 1. These valves and their respective test requirements are includ x1 in the IST Program for information arrJ tracking purposes only. They do not necessarily meet the requirements for inclusion per IWV-1100, but are identified for testing per NRC Genenc Letter 9046. Thus, the tests specifed must not necessarly sat *'sfy the correspording requirements of Subsection IWV or NRC Generic Letter 8944.
- 2. (11-08-90) Physical modifications are required to a3ow testing. Testing win commence upon comple' ion of modifications.
- 3. (11-08-90) These valves fall in a position opposite of that required. Manual stroke capability will be demonstrated.
- 4. If a PORV is isolated in accordance with Techrical specificatioins, the associated block valve will be exercised at cold shutdown.
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A e a POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0
< December 18,1990 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF
( UNITS 1 AND 2 REUEF REQUEST NO. VRR 1 SYSTEM: Various COMPONENTS: MS 02082 CATEGORY: Various FUNCTION: This is a generic Request for Rollef SECTION XI R!!OUIREMENT:
If, for power operated valves, an increase in stroke time of 50% or more for valves with full stroke times less than or equal to 10 seconds is observed, the test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed. (IWV 3417(a))
BASIS FOR REllEF:
The stroke time measurements taken during testing of fast acting valves (those less than 2 seconds) are subject to considerable variation due to conditions unrelateo to the material condition of the valve (eg. test conditions, operator reaction time), in accordance with Reference 2.8, Position 6, an alternate method of evaluating stroke times is considered acceptable.
ALTERNATE TESTING:
The stroke time evaluation for those valves designated in the IST Program Valve Tables (Appendices D & E) as
' fast acting' will not account for successive increases of measured stroke time per IWV 3417(a) with the change in test frequency as required. In lieu of this, the assigned maximum limiting value of stroke time will be established at two seconds. Upon exceeding the two-second limit, a valve will be declared Inoperable and corrective action taken in accordance with IWV 3417(b).
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I Status: IST Program 1030; Submitted as VRR 0 (Approved via GL 89 04) 1 Page 1 of 38
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POINT BEACH NUCLEAR Pl. ANT INSERVICE TESTING PROGRAM .
INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF I
UNITS 1 AND 2 REUEF REQUEST NO. VRR 2 SYSTEM: Safety injection (110E017, Sh 1 /110E035, Sh 1)
COMPONENTS: lA through F CATEGORY: A/C FUNCTION:
These valves open with differential pressure to provide flowpaths from the safety injection pumps to the reactor coolant system for emergency core cooling. They close to prevent backflow from the associated SIS Accumulators and from the low pressure safety Irijection system should portions of a train become faulted, in the normally closed position, they provide pressure isolation from the reactor coolant system.
SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
R6 SIS FOR REUEF:
Full stroke exercising of these valves would require operating a safety injection pump at nominal accident
{ flowrate and injecting into the reactor coolant system since no full flow recirculation path exists. During normal operation the safety injection discharge pressure of 1500 psig is insufficient to overcomo reactor coolant system pressure. During shutdown conditions, injection via the SIS pumps is precluded by restrictions related to low-temperature over pressurtzation protection concoms in accordance with Technical Specifications, Section 15.3.15.B.
The lack of a recirculation flowpath precludes partial stroking during operation and cold shutdown conditions.
These are simple check valves with no external means of position Indication, thus the only practical means of vertfying closure is by performing a leak test or backflow test. Such testing requires that the valve first be taken out of its safety position when it may operationally be left undisturbed, l.e., moved solely for test purposes. This reduction in plant safety la not warranted. Additionally, such testing occurs in radiation areas, thereby increasing personnel radiation exposure, ALTERNATE TESTING:
At each reactor refueling outage these valves will be full stroke exercised to the open position.
Valve seat leak testing wil be performed in accordance with Point Beach Technical Specification 15.3.16,
" Reactor Coolant System Pressure isolation Valve Leakage Tests."
( Status: IST Program 1900; f Jbmitted as VRR 2 (Approved via GL 8944)
Page 2 of 38
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. POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDlX F VALVE PROGRAM REQUESTS FOR RELIEF l.
UNITS 1 AND 2 REUEF REQUEST NO. VRR-3 SYSTEM: Safety injection (110E017, Sh 1/110E035, Sh 1)
COMPONENTS: SI 00853 A through D CATEGORY: A/C FUNCTION:
Valves SI 00853A&B open wl'h differential pressure to provide flowpaths from the low head safety injection pumps to the reactor vessel for emergency core cooling. Valves SI 00853C&D open with differential pressure to provide flowpaths from the low and high head safety injection pumps to the reactor vessel for emergency core cooling, in the closed position, they provide pressure isolation from the reactor coolant system.
SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IWV 3522. (IWV 3521)
BASIS FOR RELIEF:
g Full or partial stroking during normal operation is not possible because low head safety inject in pump discharge
\ pressure is insufficient to overcome reactor coolant system pressure, Even if pump discharge pressure were adequate, any stroking would cause the injection of cold borated water into the system, resuiti ig in power and thermal transients.
Stroke testing the subject valves during cold shutdowns is possible, however, not desirable unless ' Event V" leak testing is also scheduled. The ' Event V" testing assures valve integrity, thus minimizing the possibility of an inter-system LOCA which bypasses containment. Exercising these valves during overy cold shutdown.may reduce the assurance that a valve is, in fact, properly seated, as established via the ' Event V" testing.
ALTERNATE TESTING:
These valves wul be full-stroke exercised during pump full flow testing performed during refueling. In addition, they will be full stroke exercised during cold shutdown periods when performance of ' Event V' valve testing is required.
Seat leakage testing will be performed in accordance with Point Beach Technical Specification 15.3.16, " Reactor Coolant System Pressure Isolation Valve Leakage Tests."
( Status: IST Program 1980; Submitted as VRR-3 (Approved via GL 89 04)
Page 3 of 38
POINT BEACH NUCLEAR Pl. ANT' INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990-APPENDIX F VALVE PROGRAM REQUESTS FOR REUEF l
( UNITS 1 AND 2 REUEF REQUEST NO. VRR 4 SYSTEM: Safety injection (110E017, Sh 1 /110E035, Sh 1)
COMPONENTS: SI00867 A&B SI00842 A&B CATEGORY: A/C EUNCTION:
These valves open with differential pressure to provide flowpaths from the safety injection pumps and/or the Si accumulators to the reactor coolant system cold legs during an accident. They are normally closed. in the closed position they serve as reactor coolant system pressure isolation valves.
l SECTION XI REQUIREMENT:
Check valves shall be exerclsed at least once every 3 months, except as provided by IWV 3522. (IWV 3521)
BASIS FOR REUEF:
( During normal operation, neither safety injection pump discharge pressure of 1500 psig nor accumulator pressure of 760 psig, are sufficient to overcome reactor coolant system pressure. Full or partial stroke testing is, therefore, not possible.
During cold shutdown, partial or full stroke testing of valves SI 00867A, SI 00E42A, and SI 00842B via the use of the accumulators or safety injection pumps is not permitted so as to prevent the possibility of a low temperature over pressurization event. Partial stroking of SI 00867B is, however, possible using the RHR pumps.
l A full stroke test by dumping the accumulator to the reactor coolant system could be possible during refueling when the reactor vessel head is removed, but the volume and flowrate required for the test could result in damage to the core intomals. Thew is also the potential of forcing a nitrogen bubble into the reactor coolant system piping and refueling oasity resulting in possible safety impilcations which makes this testing concept inadvisable. ,
BASIS FOR EXTENDED INSPECTION INTERVAL:
Our response to NRC Generic Letter (GL) 8904 contained a justification of the long frequency surveillance intervals for 14I.00842A&B,14100867A, and 2 SI 00842A&B, and 2 SI 00867A. Valves 1 SI 00842A,1 SI-00867A&B,24100842A, and 24100867A&B are opened and inspected every ten (10) years. Valves 1-SI 00842B and 24100842B are not periodically opened and inspected because they require a complete core offload and RCS draindown.
l . The NRC, in position 2 of GL 8904, requested three items of information to support extension of the valve
' disassembly / Inspection intervals to longer than once every six years. Two of these items, review of industry experience and review of the installation of each valve, were addressed in the response to the generic letter.
_{. Since this information is current, no additional response is necessary.
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POINT BEACH NUCLEAR Pl. ANT , INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 The third item requires a disassembly and Inspection of each valve in the valve group. Valves 2 SI 00842A and 2 SI 00867A were disassembled in 1987. Valve 2-S1442B was not disassembled for the reasons presented above in the basis discussion.
In response to NRC Information Notice 88 05, in 1989 the retalning block studs in each of the valves in Unit 2 were replaced, and in the process each of these valves was disassembled and Inspected for freedom of motion as per the requirements of NRC Generic Letter 8944, Position 2.
During all inspections that have been performed on these valves to date, no defects have been discovered that would signify that they were not fully functional and capable of performing their required function to full stroke.
These valves have now performed acceptably at Point Beach for over 19 years with no indications of degradation. This is in agreement with industry experience that shows these valves to be extremely reliable.
The extended frequency inspection is, therefore, considered to be adequate with respect to the capability of effectNely detecting valve degradation.
The above justification satisfies the NRC's guidelines for extending the frequency for valve disassembly and inspection it does not specifically address our need for extending this frequency, however. This need is based on such factors as man-hours required to perform this work, radiation exposure received, effect or potential effect on plant operation, and the cost benefit value of the additional inspections.
ALTERNATE TESTING:
The following atternate testing will be performed:
- 1. A partial stroke test of these valves will be performed during the transttlon from hot shutdown to cold shutdown. This test will be considered to be a ' cold shutdown
- test. This test will not be performed if it wtl disturb an ' Event V' valve that is not requirod to be testing within the associated cold shutdown. At a minimum, however, this test will be performed once every reactor refueling outage. in the case of S1-008678, a partial stroke test will be performed at cold shutdown using an RHR pump.
- 2. Seat leakage tests of Sl40867A and SI 00867B will be performed in accordance with Point Beach Technical Specif, cation 15.3.16 ' Reactor Coolant System Pressure Isolation Valve Leakage Tests."
- 3. Seat leakaga tests of SI 00842A and $100842B WHI be performed quarterly coincident with the SI pump tests. A seat leakage rate of 5 gpm or less will be considered acceptable.
(
Page 5 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
, VALVE PROGRAM REQUESTS FOR RELIEF UNRS 1 AND 2
- 4. At least once within each 120 month inspection interval, valves 1 St 00842A,2 SI 00842A,1 SI-00867A&B, and 2 SI 00867A&B will be opened and their discs wil be checked to verify freedom of movement. The inspections will be staggered such that one valve from the group of s!x (including both Unit 1 and 2 valves) wil be inspected approximately every two to three years, if a condition is discovered during an inspection of a given valve that would have prevented it from stroking full open, the inspection dample wil be expanded. A second identical check valve in the same ,
unit wil be opened and inspected. Also, during the next refueling outage on the opposite unit, the sb%
valve to the Inoperable valve will be inspected. If a second valve is found inoperable in the expanded sample, all six (6) remaining valves from the group of eight (8) like valves will be inspected.
If the inspection must be expar:ded to include all eight valves, the inspections of those vabes in the unit which is not in a refueling shutdown condition shall be performed during the ner, tegularly scheduled refueling shutdown.
(
(
Page 6 of 38
4 4 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM flNSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F k VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 FIGURE VRR41 SI ACCUMUt.ATOR CHECK VALVES SAFETY INJECTION ACCUMULATOR 'A' FROM
' St PUMPS M
( ' e8"Ls Z SI-867A Z
SI-84 2A X
SI-841 A SAFETY INJECTION ACCUMULATOR 'B' RHR
' SUPPLY
, FROM e
' S1 PUMPS M
\
' #8"d"c : /)
SI-8678 M
51-8428 SI-8418 Status: IST Program 1990 I
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POINT BEACH NUCLEAR PLANT - lNSERVICE TESTING PROGRAM e llNSERVICE TESTING PROGRAM Revision 0
- December 18,1990
' APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF "4 -'
UNITS 1. AND 2 l
REUEF REQUEST NO. VRR 5 SYSTEM: Various COMPONENTS: All valves tested during cold shutdown conditions, i
CATEGORY; Various FUNCTION: Various SECTION XI REQUIREMENT:
Valves shall be exercised ... unless such operation is not practical during plant operation. If only limited r operation is practical during plant operation, the valve shall be part stroke exercised during plant operation and full stroke exercised during cold shutdowns. Full stroke exercising during cold shutdowns for all valves not full-stroke exercised during plant operation shall be on a frequency determined by the Intervals between shutdowns as follows:
For intervals of 3 months or longer exercise during each shutdown..(IWV 3412 and IWV 3522)
-... BASIS FOR REUEF:
In many' instances testing of all valves designated for testing during cold shutdown cannot be completed due to -
the brevity of an outage or the lack of plant conditions needed for testing specific valves. It has been the policy of the NRC that if testing commences in a reasonable time and reasonable efforts are made to test all valves, then outage extension or significant changes in plant conditions are not required when the only reason is to provide the opportunity for completion of valve testing.
ASME/ ANSI OMa 1987, Operation'and Maintenance Of. Nuclear Power Plants, Part 10 (Paragraphs 4.2.1.2 and 4.3.2.2) recognizes this issue and allows deferred testing as set forth below.
ALTERNATl? TESTING:
For those valves designated to be exercised or tested during cold shutdown, exercising shall commence as . _
soon as practical after the plant reaches a stable cold shutdown condition as defined by the applicable 1 Technical =
Specification but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shutdown. lf an outage is sufficiently long enough to :
pnwide for testing of all vanes required to be tested during the cold shutdown period, then the 48-hour 7 requirement need not apply if all valves are tested during the outage. Valve testing need not be performed more often than once every three (3) months except as provided for in IWP 3417(a) Completion of all valve testing 1
. during a cold shutdown outage is not required if plant conditions preclude testing of specific valves or if the .
length of the shutdown perlod is insufficient to complete all testing. Testing not completed prior to startup will be reocheduled for the next cold shutdown in a sequence such that the test schedule does not omit nor favor certain valves or groups of valves. For the purpose of this requirement, the term ' cold shutdown' refers to the respective condition as defined in the Technical Specifications. The program tables identify those valves to which cold shutdown testing applies.
Status: . IST Program 1990 Page 8 of 38 -
, POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM i . INSERVICE TESTING PROGRAM Revision 0 December 18,1990 l
APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR4 SYSTEM: Safety injection (110E017, Sh 2 /110E035, Sh 2)
COMPONENTS: S140854 A&B CATEGORY: A/C FUNCTION:
These valves open with differential pressure to provide flowpaths from the Refueling Water Storage Tank (RWST) to the suctions of the Residual Heat Removal (RHR) Pumps for low head safety injection into the reactor vessel.
During post LOCA recirculation, they close to prevent sump water from returning to the RWST.
SECTION XI PEOUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IWV 3522. (IWV.3521)
BASIS FOR REUEF:
j Valve stroking is not possible during normal operation because the RHR pump discharge pressure is insufficient i to cwercome reactor coolant system pressure during normal operation. During cold shutdown periods, full stroke testing of these valves is not possible because the reactor coolant system does not contain a sufficient expansion vc; me and there is no retum flowpath to the refueling water storage tank for recirculation.
ALTERNATE TESTING:
At least once during each reactor refueling thase valves will be full stroke exercised (open and closed) and their leak tight intopity verlfled oy means of a seat leak test.
(
Status: IST Program 1900; Submitted as VRR4 (Approved via GL 89-04) !
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF
( UNITS 1 AND 2 REUEF REQUEST NO. VRR 7 SYSTEM- Safety injection (110E017, Sh 2 /110E035, Sh 2)
COMPONENTS: SI00889 A&B CATEGOPY; C FUNCTIO' .
These valves onen with differential pressure to provide flowpaths from the safety injection pumps to the reactor coolant system for emergency core coding.
SECTION XI PCOUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
BASIS FOR RELIEF:
Full stroke exorcising of these valves would require operating a safety injection pump at nominal accident flowrate and i 'octing into the reactor coolant system since no full flow recirculation path exists. During normal
( operation the nfety injection pump discharge pressure of 1500 psig is insufficient to overcome reactor coolant
\ system presst 1. During cold shutdown conditions, injection via the SIS pumps is precluded by restrictions related to low . mperature over pressurization protection concems.
ALTERNATE TcCTING:
These valves v 11 be part stroke exercised quarteriy, At least once ciuring each reactor refueling outage these valvec will be full stroke exercised to the open position.
( Status: IST Program 1960; Submitted as VRR 7 (Approved via GL 89-04) l Page 10 of 38 -
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision O' December 18,1990 APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIE:
UNITS 1 AND 2 REUEF REOUTST NO. VRR 8 SYSTEM: Containment Spray (110E017, Sh 3 /110E035, Sh 3)
COMPONENTS: SI 00858 A&B CATEGORY: C FUNCTION:
These valves oper, with differential pressure to provide flowpaths from the refueling water storage tank to the suctions of the containment spray pumps.
SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, excer t as provided by IWV-3522. (IWV-3521)
BASIS FOR RELIEF:
Full stroke exercising of these valves would require operating the contahment spray pumps at nominal accident flowrate and spraying into the containment building since no full flow rec'rculation path exists. This is obv!ously
(, impractical and undesirable.
ALTERNATE TESTING:
These valves will be part stroke exercised during plant operation.
Each of these valves will be disassembled and inspected for operability du Ing refueling shutdowns.
Status: IST Program 1980; Submitted as VRR 8 (Approved via GL 8944)
J' Page 11 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM !
, llNSERVICE TESTING PROGRAM Revision 0 l December 18,1990 )
1 APPENDIX F !
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 9 SYSTEM: Containment Spray (110E017, Sh 3 /110E035, Sh 3)
COMPONENTS: SI 00862 A&B CATEGORY: A/C FUNCTION:
These valves open with differential pressure to provide flowpaths from the refueling water storage tank to the suctions of the contalnment spray pumps.
In the closed position, these valves serve as containment isolation valves.
SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IWV 3522. (IVN 3521)
BASIS FOR REUEF:
( Full or part stroke exercising of these valves would reqthe operating the containment spray pumps at nominal accident flowrate and spraying into the containment building since no recirculation path is available. This is obviously impractical and urMestrable.
These are almple check valves with no external means of position Indication, thus the only practical means of verifying closure is by performing a leak test or backflow test. Performing such tests of these valves involves considerable effort and system realignment such that routine testing during plant operation or cold shutdown
, outages is impractical.
L ALTERNATE TESTING:
During reactor refueling outages these valves wGI be seat leak tested in accordance with 10 CFR 50, Appendix J.
These valves WBI be disassembled and inspected for operability at reactor refueling outages.
( Status: 'IST Program 1980; Submitted as VRR.9 (Approved via GL 89-04)
-Page 12 of 38 i
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM I INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF k UNITS 1 AND 2 REUEF REOUEST NO. VRR 10
.0YSTEM. Component Cooling Water (110E018, Sh 2 /110E029, Sh 2)
_QQVPONENTS: CC-00755 A&B CATE0QEC A/C FUNCTIC%
These valvec open to provide flowpaths for cooling water to the reactor coolant pumps (RCP's are non saf:ty related) and close to provide containment isolation for the component cooling water system in the event of an accident.
SECTION XI REO'llREMENT:
Check valves shall tu exercised at least once every 3 months, except as provided by IWV 3522 (IWV 3521)
BASIS FOR REUEE; These are simple check veves with no extemal means of position indication, thus the only practical means of verifying closure is by perfo.Tning a leak test or backflow test. During plant operation, such testing would require
{ securing the RCP's which is not practical. Performing such tests of these valves involves considerable effort and eystem re-alignment such that routine testing during cold shutdown outages is impractical.
ALTERN ATE TESTING:
These valves wHI be exercised to the. closed position during seat leak tests performed in accordance with 10 CFR 50, Appendix J.
P Status: IST Program 1980; Submitted as VRR 10 (Approved via GL 89-04) l Page 13 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR
- 1 SYSTEM: Reactor Coolant (541F091, Sh 2 / 541E445, Sh 2)
COMPONENTS: RC40528 CATEGORY: A/C FUNCTION:
These valves open to provkle flowpaths for nitrogen supply to the pressurizer relief tanks (PRT's are non safety related) and close to provide containment isolation for the nitrogen system in the event of an accident.
SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IWV4522, (IWV-3521)
BASIS FOR REllEF:
Because nitrogen makeup to the PRT is seldom required, these valves are normally closed. These are simple f check valves with no extemal means of position indication, thus the only practical means of verifying closure is l {' by performing a leak test or backflow test. Performing such tests of these valves involves considerable effort and system re-alignment such that routine testing during plant operation or cold shutdown outages is impractical.
l . ALTERNATE TESTING:
During reactor refueling outages each of these valves will be full stroke exercised to the closed position and seat leak tested in accordance wtth 10 CFR 50, Appendix J.
t Status: IST Program 1980; Submitted as VRR.11 (Appros ad via GL 8944)
Page 14 of 38
POINT BEACH NUCLEAR PLANT INE2RVICE TESTING PROGRAM
, INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO VRR 12 SYSTEM: Chemical and Volume Control (684J741 / 685J175)
COMPONENTS: CV 00304 C&D CATEGORY: A/C FUNCTION:
These valves open to provide flowpaths for seal water injection to the reactor coolant pumps (RCP's are non-safety related) and close to provide containment isolation for the CVCS system in the event of an accident.
SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IWV 3522. (IWV-3521)
BASIS FOR REUEi::
These valves are normally open. They are simple check valves with no extemal means of position Indication, f thus the only practical means of verifying closure is by performing a leak test or bacMlow test. During plant
\ operation, such testing would require securing the RCP's which is not practical. Performing such tests of these valves involves considerable effort and system re-alignment such that routine testing during cold shutdown outages is impractical.
ALTERNATE TESTING:
During reactor refueling outages these valves will be verifled shut by means of seat leakage testing performed in accordance with 10 CFR 50, Appendix J.
Status: IST Program 1900; Submitted as VRR 12 (Approved via GL 8944)
Page 15 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
- INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
, ( VALVE PROGRAM REQUESTS FJR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 13 SYSTEM; Chemical and Vdume Control (GS4J741 / 085J176)
COMPONENTit; CV 00370 CATEGORY: A/C FUNCTION:
These valve 9 open to provide flowpaths for charging water into the reactor coolant system from the charging pumps. They close to provide containment isolation for the CVCS system in the event of an accident.
.EECTNN XI REQUIREMENI; Check valves shall be exercised at least once overy 3 months, except as provided by IWV 3522. (IWV 3521)
BASIS FOR REUEF:
This valve is normally open. It is a simple check valve with no external means of position Indication, thus the
[ only practical means of verifying closure is by performing a leak test or backflow test. During plant operation, 1 such testing would require securing the charglng pumps which is not practical or prudent and could result in a plant trip if done. Performing such tests of these valves involves considerable effort and system re alignment such that routine testing during cold shutdown outages is impractical.
ALTERNATE TE!qjtg During reactor refueling outages these valves will be vertfled shut by means of seat leakage testing perfctmed in accx>rdance with 10 CFR 50, Appendtx J.
r E -
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Status: IST Program 1900; Submitted as VRR 13 (Approved via GL 89-04)
Page 16 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM I INSERVICE TESTING PROGRAM Revision 0 l l
December 18,1990 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF 1
! UNITS 1 AND 2 REUEF REQUEST NO. \r.R 14 THIS PAGE INTENTIONALLY BLANK l i
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Page 17 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
, llNSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
(' VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 15
.G.Y.SIfjd; Service Water (M-207, Sh 1)
COMPONENTS: SW 00112A (Unit 2)
SW 00135A (Unit 1)
. CATEGORY: C FUNCTION:
These valves open to provide nowpaths to the steamdriven auxillary feedwater pumps (P 029) for bearing cooling water.
SECTION XI REQUIREMENTS:
Check valves shall be exercised to the position required in fulfill their function. Confirmation that the disc moves away from the seat shall be by visual observation, by electrical signal, by observation of substantially free flo v through the vatve, or by other positive means. (IWV 3522) Per NRC Generic Letter 89 04, if valve exercising is performed with system flow, there must be a quantitative measurement of flow to verify that full accident flow is attained.
BASIS FOR REUEF; There is no practical means of measuring flov' through these check valves. In accordance with NRC Generic Letter, an acceptable altemative is a program of valve disassembly and inspection to verify operability.
ALTERNATE TESTING:
During quarterly testing of the related auxillary feedwater pumps, the valves will be exercised and pump and turbine bearing temperatures will be monitored.
During reach reactor refueling outage, the valve associated with the unit undergoing refueling will be disassembled and inspected to verify operability.
( Status: IST Program 1990 t
l Page 18 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
. INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 16 SYSTEM: Heating and Ventilation (M 215, Sh 2,M 2215, Sh 2)
COMPONENTS: RM43200AA CATEGORY: A/C FUNCTION:
These valves open to provide a retum flowpath to the containment from the containment atmospheric monitoring system. They close for containment isolation.
SECTION XI REOUIREMENT:
Check valves shall be exercised at least once overy 3 months, except as provided by IWV 3522. (IWV 3521)
BASIS FOR REUEF:
During normal plant operation, gases from a continuous sampling system return sample flow to the containment through these lines / valves. To test those valves during operation or cold shutdown, it would be necessary to discharge potentially radioactNo gases to the environment. There is no mechanism to partial stroke these valves.
ALTERNATE TESTING:
During refueling outages each of these valves will be exercised to the closed position during seat leak tests performed in accon:iance with 10 CFR 50, Appendix J.
Status: IST Program 1990; Submitted as VRR 16 (Approved via GL 8944)
Page 19 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM llNSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F I
VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 17 SYSTEM: Emergency D6esel Generator Air Start (M 209, Sh 12)
COMPONENTS: DA43057 A&B DA 03058 A&B CATEGORY: B FUNCTION:
These valves operate to supply starting air on demand to the emergency diesel generator air starting motors and to isolate air to the motors after startup.
SECTION XI REQUIREMENT:
The stroke time of all power operated valves shall be measured to .... whenever such a vatvo is full stroke tested.
(IWV4413(b))
( If, for power operated valves, an increase in stroke time of 50% or more for valves with full stroke times less than or equal to 10 seconds is observed, the test frequency shall be irereased to once each month until corrective action is taken, at which time the original test frequency shall be resumed. (IWV 3417(a))
BASIS FOR RELIEF:
These are enclosed air pilot operated valves with no remote or local position indication and where the valve design prohlblts visual observation of valve operation or position. Thus, stroke time measurements are not possible.
Falure of a valve to operate property would result in unacceptable start and operation of the associa'ed diesel generators.
ALTERNATE TESTING:
VaNo stroke testing wIl be performed monthly in conjunction with the associated emergency diesel generator start testing. VaNo stroking parameters wil be considered acceptable if the diesel generator start is acceptable.
If a diesel generator fals to start, at no fault of the respectbe valve (s), the valve stroking parameters will be conaldered acceptable, which wtl be proven with the restart tc%ing diesel generator correctNe action.
Status: IST Program 1980; Submitted as VRR 17 (Approved via GL 8944)
Page 20 of 38
l POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
. INSERVICE TESTING PROGRAM Revision 0 l December 18,1990 APPENDIX F
' ( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 18 SYSTEM: Reactor Coolant (541F091, Sh 2 / 541E445, Sh 2)
COMPONENTS: RC00529 CATEGORY: A/C FUNCTION:
These valves open to provide flowpaths for makeup water supply to the Pressurizer Relief Tanks (PRT's are non.
safety related) and close to provide containment isolation in the event of an accident.
SECTION XI REQUIREMENT:
4 Check valves shall be exercised at least once every 3 months, except as provided by IWV 3522. (IWV 3521)
BASIS FOR RELIEF:
Tiw se are simple, normally closed, check valves with no extemal means of position Indication, thus the only practical means of verifying closure is by performing a leak test or backflow test. Performing such tests of these
( valves Irwdves considerable effort and system re-alignment such that routine testing during plant operation or cold shutdown outa0es is impractical.
ALTERNATE TESTINQ; Ouring reactor refueling outages each of these valves will be exercised to the closed position during seat leak tests performed in accordance with 10 CFR 50, Appendix J.
( Status: IST Program 1980; Submitted as VRR 18 (Approved via GL 8944)
Page 21 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM llNSERVICE TESTING PROGRAM RIvision 0 December 18,1990 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF
{ UNITS 1 AND 2 REUEF REQUEST NO. VRR 19
. SYSTEM: Chemical and Volume Control (684J741 / 685J175)
COMPONENTS: 1 CV4000 A&B 2 CV 00300 A&B CATEGORY: A FUNCTION:
These normally throttled open valves provide seat water to the RCP's during pump operation (RCPs are nonsafety-related.) and are closed upon direction of the operator for containment isolation.
SECTION XI REOUIREMENT:
Category A and B valves st,all be exercised at Mast once every 3 months, except as provided by IWV 3412(a),
IWV 3415, and IWV-3416. (IWV 3411)
MIS FOR REUEF:
Exercising these valves during RCP operation would result in significant damage to the pumps. During cold
{. shutdown periods, it is customary to maintain the RCP's in operation unless plant conditions required securing them. Thus, requiring the exercising of these valves would result in a considerable op6 rational burden. Note that these small manual valves are higNy reliable with respect to their capability to close and exercising during refueling outages will adequately demonstrate their operability.
ALTERNATE TESTING:
During reactor ref . allng outages these valves will be exercised to the closed position ar;d seat leak rate tested in accordare :e with 10CFR50, Appendix J.
Status: IST Program 1990 Page 22 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM IINSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
(' VALVE PROGRAM REQUESTS FOR RELIEF UNES 1 AND 2 REUEF REQUEST NO. VRR 20 SYSTEMS: Main Steam (M 201, M 2201)
.QQMPONENTS: 1 MS 02090 2-MS<t2090 CATEGORY: B FUNCTION:
These valves open upon start of the associated auxiliary feedwater pump to provide cooling water to the turbine bearings.
SECTION XI REQUIREMENT:
The stroke time of all power operated valves shall be measured to ...., whenever such a valve is full. stroke tested. (IWV 3413(b)
/ if, for power operated valves, an increase in stroke time of 50% or more for valves with full stroke times less than
( or equal to 10 seconds is observed, the test frequency shall be increased to once each month until corrective action la taken, at which time the original test frequency shall be resumed (IWV 3417(a))
BASIS FOR REUEF:
These are enclosed solenoid operated valves with no remote or local position Indication and where the valve design prohibits visual observation of valve operation or position. Thus, stroke time measurernents are impractical.
Falure of a valve to operate property would result in a lack of bearing cooling water pressure at the bearing cooling water inlet.
ALTERNATE TESTING:
These valves wW be exercised in conjunction with testing of the associated auxDiary feedwater pump. Proper operation of the valves will be determined by observing pump bearing cooling water pressure and bearing temperatures.
('
Status: IST Program 1980; Submitted as VRR 20 (Approved via GL 89-04)
Page 23 of 38
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM i INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF
( UNITS 1 AND 2 REUEF REQUEST NO. VRR 21
_ SYSTEM: Main Feedwster (M 202, Sh 2 / M 2202, Sh 2)
COMPONENTS: CS 00406 AA&BB CS40476 AA&BB CATEGORY: C FUNCTION:
The main feedwater line to eacn steam generator has two normally open, in line, series check valves. The function of these valves is to closed upon reversal of flow to ensure that auxillary feedwater flow is unimpalrod to at least one of the two steam generators while main foodwater is not avalicble. The series check valves also prevent simultaneous blowdown of both steam generators in the event of a main feed pipeline fallure, SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IWV 3522. (IWV 3521)
Valves that are normally open during plant operation and whose function is to prevent reversed flow shall be tested in a rnanner that proves that the disc travels to the seat promptly on cessation or reversal of flow.
{. (IWV 522(a))
FASIS FOR REUEF:
The main feed line to each steam generator consists of two series check valves. There are no position Indicators on these valves nor are there any pressure taps betwoon the valves. It is therefore not feasible, with the present plant conuguration, to verify indMdual valve closure . Closure of at least one of the two series check valves can be vertfled by measuring the differential pressure across, or leakage past the combination of both valves. This is adequate to ensure the safety function of the valvo combination is maintained and verified.
Prompt seathg of each valve on cessation or reversal of flow cannot be verified at the instant of closure since no direct Indication of valve disc position is evallable.
Valve testing can be conducted only during unit shutdowns since the flow of main feedwater to the steam generators must be secured in ord6r to perform the tests.
ALTEnNATE TESTING:
A valve exercise test of the main feedwater check valves will be conducted once each refueling outage. At least j
one of the series vatves will be vertfled closed after flow is secured by measuring the differential pressure across, or the leakage past, the series combination of valvos, i Additionally, once every 10 years, the main fbx! water chock valves will be opened and inspected. The l
inspections will be distributed so that at leant one valvo is inspected every two to three years, and all valves are inspected within a 10 year interval.
l Page 24 of 38 l
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
, INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 Since the split body construction of the second off check valves 466AA and 476AA limits access to the valvo internals, only those portions of the valve internals accesslble from a side access port will be inspected.
Complete disassembly of these valves is not practical since it would require that large pipe support structures would have to be cut and piping be moved.
The construction of the first off check valves 406BB and 476BB permits access to valve Internals for inspection with no known limitations.
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Status: IST Program 1980; Submitted as VRR 21 (Approved via GL 8944)
Page 25 of 38
h
! POINT CEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM J '
INSERVCE TESTING PROGRAM Revision 0 j December 18,1990 APPENDIX F I
VALVE PROGRAM REQUESTS FOR RELIEF
( UNITS 1 AND 2 REllEF REQUEST NO. VRR 22 UNITS: 1 id 2 SYSTEM: Safety injection / Residual Heat Removal (110E017 & 110E035)
COMPONENTS: S!40645 A through F SI 00853 A through D SI00867 A&B CATEGORY: A/C (Check Valves)
FUNCTION:
These check valves open to provide for high pressure and low pr, sure safety h'jection to the RCS. The motor.
operated valves open for residual heat removal recirculation during shutdown. Each of the:e valves is designated as a pressure isolation valve (PlV) and provides isolation of safegeard systems from the RCS.
SECTION XI REQUIREMENT:
The leakage rate for valves 6 Inches or greater shall be evaluated per Subsection IWV 3427(b). (I\W 3521)
BASIS FOR REll:F:
l 1.eak testing of these valves is primarily for the purpose of confirming their capability of preventing over.
pressurization and catastrophic failure of tho safety injection piping and components. In this regard, special leakage acceptance cPerla is established and included in the Point Beach Technical Specifications 15.3.16 that addresses the question of valve Integrity in a more appropriate manner for these valves. Satisfying both the Technical Specification and the Ccde acceptance criterla is not warranted and implementation would be difficult and confusing.
ALTERNATE TESTING:
J The leakage rate acceptance criteria for these valves will be established per the Point Beach Technical
- Specifications, 1
- 1. Leakage rates less than or equal to 1.0 gpm are considered acceptable.
l
- 2. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 ppm are considered acceptable if the latest measured rate has not exceed the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
- 3. Leakage rates greater than 1.0 gpm, but less than or equal to 5.0 gpm, are unacceptable if the latest measured rate exceeded the rate determ!ned by the previous test by an amount that reduces the nurgin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater. '
- 4. Leakage rates greater than 5.0 gpm are unacceptable.
Page 26 of 38
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
, INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
-( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 23 SYSTEM: Primary Containment
_ COMPONENTS: Containment isolation Valves per Table VR 51 CATEGORY: A or A/C l FUNCTION: These valves are closed to provide containment isolation.
SECTION XI REQUIREMENT:
1 Category A valves shall be seat leak tested and a maximum permissible leakage rate shall be specified IndMdual valve leakage rates shall be evaluated per IWV4426 and liW4427. (IWV4426 IYN 3427, NRC Generic Letter 8904)
SASIS FOR RELIEF:
Due to the conf 1guration of the system piping and components, in many cases indMdual leakage rate tests are impractical. In these cases it is customary to perform tests with the test volume between valves in series or behind valves in parallel paths. This concept of testing and evaluation is consistent with the intent of 10CFR$0, Appendix J ALTERNATE TESTING:
l In those cases where individual valves testing is impractical, valves will be leaktested simultaneously in mult!plo valve arrangements and a maximum permissible leakage rate will be applied to each combination of valves. Test results from tests of multiple valves will be evaluated in accordance with IWV 3426 and IWV 3427 and 10 CFR 50, Appendix J.
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Status: GL 8944 response submittal dated 10/3/89, item 10 Page 27 of 38 L. _ . -
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F y
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 23 (Cont.)
TABLE VR 51 SYSTEM VALVES Audiary Steam HV 00632 HV 00809 HV 00633 HV40818 HV 00008 Chemical & Vol. Control CV 00323B CV 00384B Component Cooling Water CC00755 A&B CC00759 A&B Containment Spray SI00862 A&B SI00864 A&B Heating & Ventilation VNPSE 03212 VNPSE 03244 VNPSE43213 VNPSE 03245
( Instrument Alr IA 01182 1A 01184 Post Acc Containment H2 V 04 H2 V 13 Vent / Monitoring H2 V 05 H2 V 19 H2 V 06 H2 V 20 H2 V 07 H2 V 22 H2 V 12 H2 V 23 Waste Disposal WL 00816 WL 01728 WL 01698 WL-01003A WL 01723 WL 01003B
(
Page 20 of 38
l POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM l INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 24 SYSTEM: Chemical and Volume Control (684J971) f0MPONENTS: CV 00351
, CATEGORY: C FUNCTION:
These valves open to provide a f'owpath for emergency boration from the boric acid transfer pumps to the suction of the charging pumps providing for emergency boration of the RCS.
SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 rnonths, except as provided by IWV 3522 (liW 3521)
SASJS FOR REllEF Testing these valves in the open direction requires the introduction of highly concentrated boric acid solution from the boric acid makeup tanks to the suction of the charging pumps. This, in turn, would result in the addition of excess boron to the RCS which would adversely affect plant power level and operational parameters
{ with the potential for an undesirable plant transient and a plant trip or shutdown. During cold Shutdown, the introduction of excess quantitles of boric acid is undesirable from the aspect of maintaining proper plant chemistry and the inherent difficuttles that may be encourf. ens! during the subsequer t startup.
ALTERNATE TESTING:
These valves will be exercised as required during each reactor refueling outage.
( Status IST Program 1990 l
Page 29 of 38
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM l
. INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
(' VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REC'IEST NO. VRR 25 UNITS: 1 and 2 l SYSTEM: Emergency Diesel Generator Air Start (M 209, Sh 12) i COMPONENTS: DA 00125 DA 06316 A&B '
DA 00126 DA06317 A&B
, DA 00225 DA06310 A&B DA 00220 DAM 319 A&B CATEGORY: B/C FUNCTION:
)
These valves operate as required to supply starting air and to sequence starting operations of the emergency I diesel generators.
SECTION XI REOUIREMENT:
The stroke time of all power operated valves shall be measured to the nearest second, ..., whenever such a valve is full stroke tested. (IWV 3413(b))
Check valves are to be full stroke tested per Reference 2.0, Position I including quantitative measurements verifying design flow through a valve.
BASIS FOR RELIEF:
These valves are integral (skid-mounted) with the diesel air start system for each emergency diesel generator with no valve position Indication mechanism and, as such, there is no practical method for measuring the stroke times or flowrates of each individual valve if a valve were to fall to stroke as required it would be reflected in an unacceptable starting time and/or performance of the respact;ve diesel generator.
ALTERNATE TESTING:
These valves wil be exercised in conjunction with testing of the emergency diesel generators. Stroke times of Category B valves will not be measured nor will flowrates through check valves, but the starting time for each diesel generator wil be verified to be acceptable.
l Status: IST Program 1990 l
Page 30 of 38 L__, _ , - _ - _ _ _ ._ _ - - - - - . - -- - --- - -
POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM l INSERVICE TESTING PROGRAM Revision 0 t December 18,1990 -
APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 i I
REUEF REQUEST NO. VRR 26 1
UNITS: 1 and 2 l
SYSTEM: Chemical and Volume Control System (664J971) !
COMPONENTS: CV00333 A&B CATEGORY; C FUNCTION:
These valves open to provide a flowpath from the boric acid makeup pumps to the emergency boration header and close to prevent recirculation flow through an idle pump. i SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by !\W 3522. (IWV.3521)
BASIS FOR RELIEF:
Full stroke testing these valves requires operating the boric acid makeup pumps at or near rated flow and verifying full accident flow through each valve.1his can be performed during plant operation, however there is no instrumentation available in the test loop by which flow can be measured.
Flow through the Individual valves can be measured by pumping into the charging pump suction header and measuring charging flow using Installed instrumentation. This, however, requires the introduction of highly concentrated boric acid solution from the boric acid makeup tanks to the suction of the charging pumps. This, in tunt, would result in the addition of excess boron to the RCS which would adversely affect plant power level and operational parameters with the potential for an undesirable plant transient and a plant trip or shutdown.
During cold shutdown, the introduction of excess quantitles of boric acid is undesirable from the aspect of maintaining proper plant chemistry and the inherant difficuttles that may be encountered during the subsequent startup,in over boration of the RCS, in addition to the above, there is no flowrate measurement instrumentation Installed in this flowpath.
ALTERNATE TESTING:
Each of these valves will be partial stroke exercised quarterly.
_ , _ During testing of the boric acid makeup pumps performed during each reactor refueling, system flowrate will be measured to verify full stroke of these valves.
( Status: IST Program 1990 Page 31 of 38
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM l l INSERVICE TESTING PROGRAM Revision 0 ,
] December 18,1990 i l
! APPENDlX F 1
! ( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 RELIEF REQUEST NO. VRR 27 1
1 1YSTEM: Safety injection (110E017. Sh 2 /110E035, Sh 2)
COMPONENTS: SI00891 A&B CATEGORY: C FUNCTION:
These valves open to provide flowpaths from the safety injection pumps to the refueling water storage tank to provide for mlntmum flow through the respective pumps in the event they are operating under low or no flow
! conditions, i SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IVN 3522. (IWV 3521)
BASIS FOR RELIEF:
There is no flowrate instrumentation available to verify valve full stroke exercising as required by Reference 2.8, Position 1.
ALTERNATE TESTING:
During quarterly pump testing each of these valves will be partial stroke exercised via recirculation through the minimum flow test circults with rio flow measurements.
During each reactor refueling outage at least one of these valves will be disassembled, inspected, and manually stroked to verify operability, inspections shall be scheduled such that valves will be checked in a rotating
- sequence such that each valve is subject to inspection at least once every six (6) years. Should a valve under inspection be found to be Inoperable, then the other Valve in that unit will be inspected during the same outage, after which the rotational inspection schedule will be re initiated. This satisfies the requirements of Generic Letter 8944, Position 2.
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l-l Status: IST Program 1990 (Approved vla GL 69-04)
Page 32 of 38
, POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 28 TIIIS PAGE INTENTIONALLY BLANK
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Page 33 of 38
.' POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
. INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 29 i UNITS: 1 and 2 SYSTEM: Primary Containment COMPONENTS: Valves 6 Inches NPS and larger subject to leakage rate testing per 10 CFR 50. Appendix J.
1 SATEGORY: A/C (Check Valves) l A (Motor operated valves) i f.Uf.CJ102 Each of these valves is designated as a containment isolation valve malntaining the leakrate integrity of the primary containment in the case of an accident.
SECTION XI REQUIREMENT:
The leakage rate for valves 6-inches or greater shall be evaluated per Subsection IWV 3427(b). (IWV 3521)
BASIS FOR RELIEF:
The usefulness of applying this requirement does not justify the burden of compilance. This position is supported by NRC Generic Letter, Position 10
- ALTERNATE TESTING:
Leakrate test results for valves 6 inches or greater (NPS) will be evaluated per IWV-3426 and IWV 3427(a) however, the requirements of IWV 3427(b) will not be applied. This satisfies the requirements of Generic Letter 8944, Position 10.
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l Status: IST Program 1990 (Approved via GL 8944)
Page 34 of 38
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s . POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
. INSERVICE TESTING PROGRAM Revision 0 j December 18,1990 !
l APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 RELIEF REQUEST NO. VRR 30 UNITS: 1 and 2 SYSTEM: Component Cooling Water (110E010, Sh 2 /110E029, Sh 2)
' COMPONENTS:
_ 1 0 0 00767 2 CC 00707 CATEGORY: A/C FUNCTION:
These valves open to provide flowpaths for cooling water to the excess letdown heat exchangers which are non, safety related components. They also close to provide containment isolation for the component cooling water system in the event of an accident.
SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by M%3522. (I\W-3521)
BASIS FOR RELIEF:
These are simple check valves with no external means of position Indication, thus the only practical means of verifying closure is by performing a leaktest or backflow test. Performing such tests of these valves involves considerable effort and system re alignment such that routine testing during plant operation or cold shutdown -
outages is impractical.
ALTERNATE TESTING; During reactor refueling outages each of these valves will be exercised to the closed position during seat leak tests performed in accordance with 10 CFR 50, Appendix J.
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Status: IST Program 1980; Submitted as VRR 15 (Approved via GL 89-04)
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.' POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
. INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR-31 SYSTEM: Chilled Water (M 214, Sh 2)
, COMPONENTS: HV 00890A, HV 000900A, HV 00914A, HV 000916A CATEGORY: A/C FUNCTION:
These valves open with differential pressure to provide flowpaths from the control room and e sble spreading {
room chilled water pumps to the respective cooler units. Each closes to prevent recirculation ' low through an idle pump.
SECTION XI REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IWV 3522, (IWV.3521)
't
.BMIS FOR RELIEF:
There is no instrumenta!!on available with which to measure system flowrate in order to satisfy the requirements
( of NRC Generic Letter (GL) 89-04, Position 1 for full stroke exercising check valves.
ALTERN ATE TESTING:
The following alternate testing will be performed:
- 1. A partial stroke test of these valves will be performed during inservice testing of the associated chilled water pumps.
- 2. Each of these valves will be disassembled and inspected for operabuity at least once every six (6) years.
Inspections w!!! be scheduled on a staggered basis such that one valve be inspected every two years, il during a valve inspection a condition is discovered that would have prevented the subject valve from stroking full open, the inspection sample will be expanded to include the second identical check valve in the same chilled water system If during an expanded sample inspection a condition is discovered that would have prevented the second subject valve from stroking full open, the inspection sample will be expanded to include the remainder of the valves.
( Status: IST Program 1990; (Approved via GL 89-04)
Page 36 of 38
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, POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX F i VALVE PROGRAM REQUESTS FOR RELIEF i I
UNITS 1 AND 2
)
RELIEF REQUEST NO. VRR-32 SYSTEM: Instrument Air (M 209, Sh 11)
COMPONENTS; 1 lA 01206,1 lA 01209,1 IA 01600, and 1 IA 01606 2 IA 01335, 2 IA 01338,1 lA 01652, and 1 lA 01653 CATEGORY: A/C FUNCTION:
These valves open with differential pressure to provide flowpaths for operating alt from the plant instrument air
, system to PORV's. In the event of a loss of air pressure in the instrument air system they close to prevent diversion of the nitrogen backup pneumatic supply that provides gas for operatloa of the PORV's.
SECTION XI REQUIREMENT:
Category A valves shall be leak tested in accordance with Paragraph IWV 3420.
BASIS FOR REllEF:
The plant configuration for these valves is such that two valves are instal led in series with no test connection in
( the common piping between them that could be used to test the valves individually The function of closure and Isolation can be accomplished with only one valve, thus if either valve has acceptable leaktight integrity, then the system remains fully functional, Testing two valves in combination adequately demonstrates the functional adequacy of the system.
Note that these values are included in the testing program for information and tracking purposes and do not strictly meet the requirements of IWV 1100 for inclusion.
ALTERN ATE TESTING:
These valves will be leak tested in combination such that the measured leakrate will be assigned to the combination as though it were a single valve.
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f Status: IST Program 1990 Page 37 of 38
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. 4s POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING FROGRAM Revision 0 December 18,1990 APPENDIX F
( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REllEF REQUEST NO VRR 33 SYSTEM: Emergency Diesel Generator Fuel Oil (M 219)
COMPONENTS: FO-03940 and F043941 CATEGORY: A/C FUNCTION:
These valves operate to control fuel oli transfer Pump discharge pressure and provide a flowpath to prevent pump or piping damage after pump start before the day tank Inlet valves are fully opened. After flow is established to the day tanks, these valves close to prevent diversion of fuel oil back to the Emergency Fuel Tank.
l- SECTION XI HEOUIREMENT:
Valves shall be exercised (full stroke) to the position required to fulfill their function. (IWV.3412)
BASIS FOR RELIEF:
Since these are essentially back pressure riv alating valves requiring no outsida source of power to operate, they are exempt from stroke time measurements per IWV 3413, however, it is not practical to perform a full stroke test since the position of the valve disc cannot be determined visually or by any other practical means.
Considering the type and function of these valves, an operational (functional) test is an effective way of ascertaln!ng the condit!on of the valves and proving their operability.
& TERNATE TESTING:
These valves will be subjected to an operational test to verify proper operation with lespect to limiting and controlling the fuel oil piping pressure during fuel oil transfer pump operation. During these tests, system operating parameters will be monitored to determine vatve operability.
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Status: IST Program 1990 l --
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PRCGRAM l
INSERVICE TESTING PROGRAM Revision 0 3
December 18,1990 APPENDIX G COLD SHUTDOWN JUSTIFICATIONS
[
This appendix is intended to provide the justification for performing valve exercising only at cold shutdown conditions as permitted by IWV 3412(a),3415 and 5322. Specifically included in this category are the following:
- A vawe whose failure in a position other than its normal position could jeopardize the immediate Safety of the plant or system components;
- A valve whose fallure in a position other than its normal position could cause all trains of a safeguard system to be Inoperable;
- A valve whose failure in a position other than its normal position that might cause a translent that could lead to a plant trip:
When test requirements or conditions are precluded by system operation or access.
Cold shutdown testing is performed under conditlons outlined in Relief Request VRR 5.
Audiarv Feedwater (M 217)
CSJ 1 AF 00100, AF 00101, AF 00102, AF 00104, AF 00106, and AF 00107 AuxHlary Feodwater Supply Check Valves Full stroke exercising of these valves would require operation of a related auxillary feedwater pump and
{. Injection of cold water (85'F) into the hot (450'F) feedwater supply piping. This, in tum, would result in unacceptable thermal stress on the feedwater system piping components.
CSJ 2 AF 00108, AF 00109 and AF 00110 Auxillary Feedwater Pump Discharge Check Valves Full stroke exercising of these valves would require operation of the related auxillary feedwater pump and injection of cold water (85'F) into the hot (450'F) feedwater supply piping. This, in tum, would result in unacceptable thermal stress on the feedwater system piping components.
CSJ 3 AF 00111, AF 00112 and AF 00113 Aux 111ary Feedwater Pump Suction Check Valves Full stroke exercising of these valves would require operation of a related auxillary feedwater pump and injection of cold water (BS'F) into the hot (450'F) feedwater supply piping. This, In tum, would result in unacceptable thermal stress on the feodwater 6ystem piping components. These valves will be partial stroke tested during quarterly testing via the minimum flow recirculation lines.
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! *- POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 ,
December 18,1990 APPENDIX G
, COLD SHUTDOWN JUSTIFICATIONS
(
Chemical & Vdume Control (684J741)
CSJ4 CV 00112C Volume Control Tank Outlet Valve Closing this valve during operation of a charging pump would isolate the VCT from the charging pump suction header damaging any operating charging pumps and Interrupting the flow of charging water l flow to the RCS with the potential of RCS transient and plant trip.
CSJ5 CV 00142
, Charging Flow Control Valve Closing this valve during operation isolates the charging pumps from the RCS and would result in undesirable pressurizer level transients with the potential for a plant trip and potentlal damage to the charging pumps. If the valve failed to reopen, then a expedited plant shutdown would be required. )
CSJ 6 CV 00313 and CV 313A 1
RCP Seal Water Return Valves Exercising these valves to the closed position when the associated reactor coolant pump (RCP) in operation would Interrupt flow from the respective RCP seals and result in pump damage.
( CSJ 7 CV 00371 and CV 00371 A Letdown Une isolation Valves Closing either of these valves during operation isolates the letdown line from the RCS and would result in undesirable pressurizer level translents with the potential for a plant trip. If a valve failed to reopen, then a expedited plant shutdown would be required.
CSJ 8 CV 00384B Charging Une HCV Outlet Valves Closing the6, valves during operation will interrupt flow of charging water flow to the RCS with the potential of RCS transient and plant trip.
Comoonent Codina Water (110E018)
CSJ 9 CC00719 Containment Cooling Water Supply Valves This valve is required to be open to ensure continued cooling of reactor coolant pump auxillary components. Closing this valve during plant operation would result in severe RCP damage leading to plant operation in a potentially unsafe mode and a subsequent plant shutdown.
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM
] INSERVICE TESTING PROGRAM Revision 0 2
December 18,1990 APPENDIX G COLD SHUTDOWN JUSTIFICATIONS CSJ.10 CC00754 A&B and CC-0075g A&B RCP Cooling Water Supply /Retum isolation Valves These valves are required to be open to ensure continued cooling of reactor coolant pump auxillary corr,ponents. Closing any of these valves during plant operation would result in severe RCP damage leading to plant operation in a potentially unsafe mode and a subsequent plant shutdown.
,Qontalnment Sorav System (110E017)
CSJ 11 S100836 A&B Sodlum Hydroxide (NaOH) Supply Valves in order to exercise these valves w3hout contaminating the containment spray piping with sodlum hydroxide would require Isolating the NaOH supply from the containment spray eductors. This, in turn, tenders the sodlum hydroxide additive subsystem for both trains of containment spray inoperative during the test period.
CSJ 29 SI 00870A&B RWST to Containment Spray Pumps Exercising this valve during power operation !3 not practical because the supply of water to the pump
/T would be isolated, thereby making the system unable to perform its safety function should it be required to do so.
Heatina and Ventilation (M 215)
- CSJ 12 VNPSE 03212, VNPSE 03213, VNPSE 03244, and VNPSE 03245 Containment Purge Supply and Exhaust Valves These valves are administratively maintained locked in the closed position at all times when the plant is operating and are considered to be 'out of service.' They are only opened during cold shutdown and
- refueling outages. Due to the large size of these valves and the potential for damage as a result of frequent cycling, it is not prudent to operate them more than is absolutely necessary.
instrument Air (M 209)
CSJ 13 Unit 1 1A 01280 and 1A 01281, Unit 2 IA 01401 and 1A41402 Containment Purge Valve Air Supply Check Valves These valves and other vanes required for exercising are located within the containment bulding and, as such, are not readily accessible during plant operation at power.
l CSJ 28 Unit 1 IA 01206,01209,01301,01502 and Unit 21A 01335,01338,01418,01419, Instrument Air and l Nitrogen Supply to PORVs and 1A 06310 and (A 06311 Nitrogen Supply Pressure Regulators l PORV Pneumatic Supply Valves l
These salves need only be tested prior to entering a condition where LTOP precautions must be administered (10. cold shutdown). Furthermore, exercising these valves requires containment entry and operation of the PORV's which is not advisable during plant operation at power, (GL 90 06)
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0
, December 18,1990 APPENDIX G COLD SHUTDOWN JUSTlHCATIONS Main and Raheat Steam (M 201)
CSJ 14 MS42015 and MS42016 Main Steamline Atmosphe lc Dump Valves Opening these valves during plant operation at power wRl result in an undesirable poner transient with the potential for exceeding reactor core power limit or a plant trip.
CSJ 15 MS42017 and MS42018 Main Steam Isolation Valves During plant operation at power, closure of either of these valves is not practical as it would require isolating a steam generator which would result in a severe transient on the steam and reactor systems 5
and a reactor plant trip.
CSJ 10 MS 02017A and MS42018A Main Steam Non Retum Valves Exere! sing these valves requires isolating the associated steam generator which is not practical without a plant shutdown, and, if performed during plant operation, will result in a plant trip.
CSJ 17 MS42017CS, MS 02017DS, MS 02017CS, and MS42017DS
{ MSIV Air Plot Valves Testing of these valves can result in closure of the related MSIV. During plant operation at power, closure of any MSIV is not desirable as it would cause isolation of a steam generator which would result in a severe transient on the steam and reactor systems and a reactor plant trip.
Reactor Coolant (541F091 / 541F445)
CSJ 18 RC 00400 and RC-00431C Power Operated Relief Valves (PORVs)
Due to the potential impact of the resulting transient should one of these valves open prematurely or stick in the open position, it is considered imprudent to cycle them during plant operation. In accordance with NRC Generic Letter g046, they wRl be exercised when practical wth the reactor shutdown and at reduced reactor coolant system pressure.
CSJ 1g RC00570 A&B, RC00575 A&B, and RC 00580 A&B Reactor Coolant System Vents These are isolation valves for the reactor coolant system, falute of a valve to close or significant leakage following closure could result in a loss d coolant in excess of the limits imposed by Technical Specification 15.3.1.0 leading to a plant shutdown. Furthermore, if a valve were to tal open or valve Indicatk>n tal to show the valve retumed to the fully closed position following exercising, prudent plant operation would probably likely result in a plant shutdown.
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POINT PCACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX G COLD SHUTDOWN JUSTIFICATIONS Safety Inleetion / Residual Heat Removal (110E017 /110E018)
CSJ 20 SI 00841 A&B Safety injection Accumulator Discharge Valves Durin0 plant operation in any mode above cold shutdown these valves are required to remain open and disabled. Oosing one of these valves renders the associated accumulator unavailable for injection in tho event of a LOCA. Oosing either of these vanes during plant ope 1 tion is considered to be imprudent and unsafe.
CSJ 21 SI 00852 A&B RHR/LH Core Delugs Motor Operated Valves ,
Opaning these valves with the RCS at normal pressures could expose the downstream safety injection piping to RCS pressure with the only protection being the two check valves. This is considered to be imprudent and an unwarranted challenge to plant safety.
CSJ 22 SI00878 A&C Reactor Vessel Safety injection Motor-Operated Valves During plant operatlon in any mode above cold shutdown these valves are required to remain open and disabled. Oosing one of these valves renders the associated accumulator unavailable for injection in
( the event of a LOCA. Closing either of these valves during plant operation is considered to be imprudent and unsafe.
CSJ 23 SI 00878 B&D Safety injection Loop Motor Operated Valves
, These valves remain open during power operation. Exercising these valves will result in isolation of one I
of the injection flowpaths to the RCS. This is considered imprudent and sa unwarranted compromise of plant safety.
CSJ-24 SI On826 C&C Sl Pump Redundant Suction From the BAST's Exercising these valves requires closure of the downstream valve, SI 00826A or the mini-flow valve from the RWST to preclude overfilling the BAST's from the RWST. Operation in either configuration would isolate all water sources from both Si pumps with the potential of the loss of fu,wlonality in the event of an accident.
I
! , CSJ 25 SI 00897 A&B Safety injection Pump Mini Rectre To RWST Cosing either of these valves isolates the minimum flow recire lines from both SI pumps and, in the i l- event of SI Initiation at elevated RCS pressure, both pumps could sustain damage with the potential of I rendering both safety injection pumps inoperable.
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.. POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990
[r APPENDIX G COLD SHUTDOWN JUSTIFICATIONS
(
CSJ 26 RH40710 A&B RHR Pump Discharge Check Valves g During normal plant operation, the RHR Pumps cannot develop sufficient discharge pressure to pump through these valves to the RCS and full stroke exercise them in the open direction.
CSJ 30 SI 00957 and SI40834A&B Accumulator Nitrogen Supply Vent Valve and Accumulator Vent Valve f'
Stroking these valves during operation has the potential for reducing plant safety, if a series valve were to leak, accumulator nitrogen pressure could drop below that required to maintain the accumulator operable. Stroke testing at cold shutdown when accumulators are not required provides a satisfactory demonstration of valve operability without the possibility of compromising plant safety, Service Water (M 207)
CSJ-2? SW 02880 Turbine Plan, Service Water Supply Valve Closing this valve results in securing cooling water to the turbine plant auxillaries including the main turbine, main generator, steam generator feedwater pumps, condensate pumps and other supporting equipment. If, during testing, this valve were to fall to reopen for any extended period of time, the
( assoc!ated turbine generator and various support components would sustain significant damage.
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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision O December 18,1990 APPEN0lX H VALVE FAP. SAFE TEST DESCRIPTION ASME Section XI, Article IWV 3415, states the following for vahes having fall safe actuators.
'VaNos with fal safe actuators shall be tested by observing the operation of the valves upon loss of actuator power.'
Thlt type of test demonstrates that a vane will go to its required position to fulfl!I its safety function upon loss of actuator power.
The following describes the requirements for fal safe tests for the different types of actuators.
Actuator Tvoe Fall Safe Test Motor Valve wHl fal as is. No test required.
Solenoid Vah s fals to its safe position upon loss of power to the solenoid.
Air VaNo fans to its safe position upon loss of control alt to the actuator and/or 3 loss of control power to its associated solenoid valve.
A fall-safe tes' un only be performod on solenold-operated or alr-operated valves. Upon loss of power, a motor operaterAe is Incapable of moving and falls as is.
Fall safe testing of motor operators will not be performed.
A fall safe test of solenoid operated valves WHI be conducted by doenergizing the solenoid and observing that the vane moves to its fau safe position. Deenergization of the solenoid will be performed by operating the valve control switch to the position that corresponds to the faH safe position (i.e., open or shut).
3
% A faR-safe test of air-operated vanes wil be conducted by doenorgtzing the solenold control valve, which will, in tum, vent alt from the valve Tuator and result in tho valve moving to its fall safe position. Operation of the AOV control switch to the positlor, correyx>nding to the fad safe position (i.e., open or shut) will deonergize the solenold-operated vane and vent sir from the AOV's actuator, in some cases, a controller,1/P (electric / pneumatic) converter, and a positioner is used to control air to the actuator of an AOV. For these cases, one of the following methods will be used to perform a fall safe test of the AOV.
- 1. Secure power to the I/P converter which in tum wil secure air to the AOV actuator.
- 2. With the controller in manus 1, adjust the vane to its fal safo position. Operation of a controller in this manner sends a minimum control signal to the I/P cuiverter and causes the I/P converter to cut off air to the valve actuator, This is simBar to securing contrc4 power to the I/P converter, except a small control signal is stRI present.
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