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Pump & Valve Inservice Testing Program Point Beach Nuclear Plant
	ML20079B785
Person / Time
Site:	Point Beach
Issue date:	05/28/1991
From:	; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20079B782	List: ML20079B780; ML20079B785;
References
	PROC-910528, NUDOCS 9106170244
	Download: ML20079B785 (195)
	v • d • e

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PUMP AND VALVE INSERVICE TESTING PROGRAM POINT BEACH NUCLEAR PLANT REVISION 1 May 28,1991 O

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TABLE OF CONTENTS 1

1.0 Introduction j 2.0 ApplicaNe Documents 3.0 Inservice Testing Program for Pump 3 3.1 Code Compilance 3.2 AllowaNe Ranges of Test Quantitles j 3.3 Test intervals l 3.4 Pump Program Table i 3.5 Rollef Requests for Pump Testing l

4.0 Inservice Testing Program for Pumps 4.1 Code Compliance I 4.2 Testing Intervals -

4.3 Stroke Time Acceptance Crtteria 4.4 Check Valve Testing 4.5 Valve Program Table 4.6 Relief Requests for Valve Testing p APPENDICES

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'n A Pump Program Tables - Unit 1 B Pump Program Tables Unit 2 C Pump Program Requests for Relief - Units 1 & 2 O Valve Program Tables Unit 1 E Valve Program Tables - Unit 2 F Valve Program Requests for Relief - Units 1 & 2 G Cold Shutdown Justifications H Valve Fall Safe Test Description i

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 2 THIRD INTERVAL May 28,1991

) UNITS 1 AND 2

1.0 INTRODUCTION

Revision 0 of the third ASME Inservice Test (IST) Program for Point Beach (Units 1 & 2) will be in effect through the end of the third 120-month (10-year) Interval unless changed and relssuod for reasons other than the roudne update required at the start of the fourth interval por 10 CFR 50.55a(g). The third interval for both units begins on December 31,1990.

This document outlines the IST Program for PC,,,t Mach Plant, Units 1 and 2, based on the requirements of Section XI of the ASME Beser and Pressure Vessel Code,1986 Edition (the Code).

References in this document to *lWP' or '.WV" correspond to Subsections IWP and IWV, respecth/ely, of the ASME Section XI,1986 Edition, unless otherwise notod.

As described in the second (1980) 120-month Interval program strict application of code selection criteria of 10 CFR 50.55a(g)(4)(li) would have resulted in application of different ASME XI code odition being appiled to Unit 1 and Unit 2. In the second program a request was made to match Unit 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 50.55a and ASME Section XI,10 CFR 50.55a takes precedonce.

V 1.1.2 By 10 CFR 50.55a(g)(l), inservice 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 PBNP Units 1 and 2.

1.1.3 According to 10 CFR 50.E5a(g)(1) and 10 CFR 50.55a(g)(1), inservice 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 materlats 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 2.8. 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, Pait 50 2.2 NRC Regulatory Guides - Division 1 2.3 Standard Review Plan 3.9.6, " Inservice Testing of Pumps and Valves

O 2.4 Final Safety Analysis Report, Point Beach Units 1 & 2 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 2 THIRD INTERVAL May 28,1991 i UNITS 1 AND 2 2.7 ASME Boiler and Pressure Vessel Code,Section XI,1986 Edition.

2.8 NRC Generic Letter 8944, 'Gundance on Developing Acceptable Inservice Testing Programs

l 2.9 Point Beach Nuclear Plant Responses to GL 8944, dated October 3,1909, March 2,1990, June 28,1990, and September 11,1990.

2.10 NRC minutes of public meetings on GL 8944, dated October 25,1989.

3.0 INSERVICE TESTING PROGRAM FOR PUMPS 3.1 Code Comollance This IST program for pumps is based on the requirements of subsection IWP 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 afternative 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.

3.2 Allowable Ranoes of Test Quantitles The allowable ranges for test parameters as specified in Table IWP-3100-2 will be used for all J measurements of pressure, flow, and vibrations except as 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 case-by<,ase basis, in accordance with IWP-3210 and ASME Code interpretation XI 179-19.

3.3 Testina 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 Proaram Table Appendices A and B list those pumps included in the IST Program with 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 Appendtx 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 Relief Reauests for Pumo Testino Appendix C includes relief requests related to pump testing.

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R; vision 2 THIRD INTERVAL May 28,1991 UNITS 1 AND 2 (O) v 3.6 Evaluation of Data and Eautoment StatutDeclaratlQD 30.1 The duty shift superintendent shall determine equipment operability by comparing test data against the acceptance limits. These limits are contained in an Operations ctanding order. Eculpment with dats excooding these limas will bo declared inoperable and Technical Specification LCOs applied.

3.6.2 Additional engineering evaluations, data trending, and data rotention will be performed in accordance with ASME XI code and will be accompanied by equipmont status declarations in accordance with plant administrative procedures.

4.0 _ INSERVICE TESTING PROGRAM FOR VALVES 4.1 Code Comollance This IST Program for valves is based on the requirements of Subsection IWV of the Code and any interpretations or additional requirements imposed by Reference 2.8. Where these requirements have been determinod to be imp actical, conformance would causo unreasonable hardship without any compensating increase in safety, or an attemative test provides an acceptable level of quality and safety, relief from Code requirements is requestod pursuant to the requirements of 10 CFR 50.55a(g)(lii) and Reference 2.8.

(m)v 4.2 Dstina Intervals The test frequency for valves included in the Program will be as set forth in IWP-3400 and related relief roquests. A band of +25 percent of the test intervai may be applied to a test schedulo as allowed by the Point Beach Technical Specifications to provide for operational flexibility. Where quarterly testing of valves is impractical or otherwise undesirable, testing may be performed during cold shutdown periods as permitted by IWV-3412(a). Justlfications for this deferred testing are provided in Appendix G with elaboration of Point Beach policy set forth in Relief Roquest VRR-5.

4.3 Stroke Time Accentance Criteria When required, the acceptance criteria ic< 6he stroke times of power-operated valves will be as set forth in IWV-3410 and Reference 2.0.

4.4 Check Valve Testina Where required, full stroke exercising of check valves to the open position using system flow requires that a test be performod whereby the predicted fall accident condition flowrate through the valve be verified and measured. Any deviation to this requirement must satisfy the requirements of Reference 2.8, Position 1.

4.5 Valve Proaram Table Appendices D and E list those valves included in the IST Program with references to required O testing, respective test intervals, and applicable requests for relief. Valves which serve a Q common, shared function for Units 1 and 2 are included in Appendix D. Any explanatory notes required for clarification of test requirements wPI be included at the end of the respective valve table to which the noto applies.

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 2 THIRD INTERVAL May 28,1991 (v UNRS 1 AND 2 o

4.6 Holief Reaugsts for Valve Testina Appendix F includes all rollof requests related to valve testing.

4.7 EY.A!uallon of Data and Eaulomont Status Declaration 4.7.1 The duty shift superintendent chall determine equipment operabDity by comparing test data against the acceptance limits. These limits are contained in an Operations standing order. Equipment with data excooding these limits will be declared inoperable and Technical specification LCOs appilod.

4.7.2 Additional engineering evaluations, data trending, and data rotention will be performed in accordance with ASME XI and will be accompanlod by equipment status declarations in accordance with plant administrative procedures.

4.8 Backaround Document References All appendices of this IST Progiam are consistent with the following IST Program Background Document revisions:

Anoendix .TJ11e Eexislaa .Date.

' A Main and Rehoat Steam 0 B Auxillary Feodwater System 0 C Main Feedwater System 0 D Service Water System 0 E Reactor Coolant System 0 F Chemical and Volume Control System 0 G Safety injection and Residual Heat Removal System 0 H Containment Spray System 0 l Component Cooling System 0 J Spent Fuel Pit Cooling System 0 K Emergency Diesel Generator Air Start and Fuel Oil Transfer Systems 0 L Heating, Ventilation, and Air Conditioning Systems O M Auxillary Steam System, Heating Steam, Chilled & Hot Water Systems 0 N Instrument and Service Air Systems 0 0 Post-Accident Containment Vent / Monitoring System 0 P Primary Sampling System 0 0 Waste Disposal System 0 R De-lonized/ Reactor Makeup Water System 0 i

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991

\ APPENDIX A UNIT 1 PUMP PROGRAM TABLE LEGEND PUMP NUMBER Numerical designator indicated on the respectNe fic.t diagram.

FUNCTION Generic name/ 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 associated with that specific parameter Where the test program deviates from the code requirement, the respectNe relief request nurnber is noted.

PRR XX Where indicated, this refers to the specific rollef request (See Appendtx C) related to any deviation regarding the measurement or analysis of a parameter,

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INT BEACH NUCLEAR PLANT INSERVICE TESTING M

- INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX A UNIT 1 PUMP PROGRAM TABLE Test Parameter-Pump Lube inlet Diff Flow Bearing Number Function Dwg.No. Level Speed Press Press Rate vb Temp Remarks 1

P-002A Charging Pump 684J741 Yes Yes PRR-14 PRR-14 Yes PRR-7 PAR-8 PRR-129.10 P-002B Charging Pump 684J741 Yes Yes PRR-14 PRR-14 Yes PRR-7 PRRE PRR-119.10 P-002C Charging Pump 684J741 Yes Yes PRR-14 PRR-14 Yes PRR-7 PRR-8 PRR-119,10 P-004A BA Transfer 684J741 No N/A PRR-12 PRR-12 PRR-12 PRR-12 PRR-8 PRR ,117, 9.10,11 P-0048 BA Transfer 684J7M1 No N/A PRR-12 PRR-12 PRh-12 PRR 12 PRR4 PRR-117, 9.10.11 P-010A RHR 110E018 Yes N/A Yes Yes PRR-4 PRR-7 PRR-8 P3R-119,10, 16.17 P-010B RHR 110E018 Yes N/A Yes Yes PRR-4 PP.R-7 PRR4 PRR-1,2.9.10, 16,17 P-011 A CC 110E018 Yes N/A Yes Yes Yes PRR-7 PRR-8 PRR-1,2,9,10,

6 P-011B CC 110E018 Yes N/A Yes Yes Yes PRR-7 PRR-5 PRR-129.10, 16 P412A SFP Cooling 110E018 Yes N/A Yes Yes Yes PRR-7 PRR4 PRR-1,2,9,10, 16 P-012B SFP Cooling 110E018 Yes N/A Yes Yes Yes PRR-7 PRR-8 PRR-119.10.

16 i

P414A Containment Spray 110E017 Yes N/A Yes Yes PRR4 PRR-7 PRR4 PRR-1,2,9,10, 16 --

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q INSERVICE TESTING 1

,UINT BEACH NUCLEAR PLANT U Revision 1

-- INSERVICE TESTING PROGRAM May 28,1991 APPENDIX A UNIT 1 PUMP PROGRAM TABLE Lt m Inlet Diff Flow Bearing Pump V6 Temp Remarks Dwg.No. Leiel Speed Press Press Rate Number Function PRRE PRR-7 PRR-8 PRR-1,2,9,10 Containment Spray 110E017 Ye N/A Yes Yes j P-014B 16 _

Yes PRR-3 PRR-7 PRR-8 PRR-119,10, Safety injection 110E017 Yas N/A Yes P-015A t 16,17 PRR-3 ."'P. 7 PRR-8 PRR-1,2,9,10, 110E017 'Yes N/A Yes Yes P-0158 Safety injection 16,17 Yes PRR-5 PRR-7 PRR PRR-119,10, AFW M-217 Yes Yes Yes P-029 16.18 Yes Yes PRR-7 PRR-8 PRR-119,10, Service Water M-207 No N/A PRP-13 P-032A 16 Yes PRR-7 PRR-8 PRR-1,2,9,10, M-207 No N/A PRR-13 Yes P-032B Service Water 16 l

Yes Yes PRR-7 PRO,4 PRR-1,2,910, M-207 No N/A PRR-13 P-032C Service Water 16 Yes Yes PRR-7 -RR4 PRR-129.10, M-207 No N/A PRR-13 P-032D Service Water 16 Yes Yes PRR-7 PRR-8 PRR-119,10, M-207 No N/A PRR-13 P-032E Service Water 16 Yes Yes PRR-7 PRR4 PRR-1,2,9,10, M-207 No N/A PRR-13 P-032F Service Water 16 Yes PRR-5 PRR-7 PRR-8 PRR-1,2.9.10, ,

AFW M-217 Yes N/A Yes P-038A 16,18 l Yes PRR-5 PRR-7 PRR4 PRR-1,2,9,10, AFW M-217 Yes N/A Yes P-0388 16,18 l

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INSERVICE TESTING RAM UOINT BEACH NUCLEAR PLANT Revision 1 j- !NSERVICE TESTING PROGRAM May 28,1991 APPENDIX A UNIT 1 PUMP PROGRAM TABLE l

Lube inlet Diff Flow BearM Pump Press Rate Vib Temp Remarks Dwg.No. Level Speed Press Number Function Yes PRR-7 PRR4 PRR-1,2.9.10, M-219 Yes N/A Yes Yes P470A FO Transfer 16 Yes PRR-7 PRR-8 PRR-1,2,9,10, ;

M-219 Yes ?!/A Yes Yes P470B FO Transfer 16 PRR-7 PRR4 PRR-119.10, M-214 N/A N/A Yes Yes - PRR-15 P-111 A CSR Ch Water 16 PRR-15 PRR-7 PRR-8 PRR-119,10, N/A Yes Yes P-111B CSR Ch Water M-214 N/A 16 PRR-15 PRR-7 PRR-8 PRR-119,10, N/A Yes Yes P-112A CR Ch Water M-214 N/A 16 PRR-15 PRR-7 PRR-8 PRR-129.10, N/A Yes Yes P-112B CR Ch Water M-214 N/A 16 1

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE iESTING PROGRAM Revision 0 December 18,1990 APPENDIX B O UNIT 2 PUMP PROGRAM TABLE LEGEND PUMP NUMBER Numerical designator Indicated on the respective flow diagram.

FUNCTION Generic name/ function of the pump.

DRAWING NO. Corresponds to the flow dlagram showing the pump.

TEST PARAMETV. , The table indicates full code compliance by a 'YES* In the column associated with that specific parameter Where the test program deviates from the code requirement, the respective relief request number is noted.

PRR XX Where Indicated, this refers to the speellic relief request (See Appendix C) related to any deviation regarding the measurement or analysis of a parameter.

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m POINT BEACH NUCLEAR PLANT INSERVICE TESTib RAM INSERVICE TESTING PROGRAM Revision 0 December 18,1990 APPENDIX B UNIT 2 PUMP PROGRAM TABLES Test Parameters i

Pump Lube Intet Diff Flow Bearing Number Function Dwg.No. Level Speed Press Press Rate Vib Temp Remarks i

P-002A Charging Pump 685J175 Yes Yes PRR-14 PRR-14 Yes PRR 7 PRR4 PRR-119.10 P-0028 Charging Pump 685J175 Yes Yes PRR-14 PRR-14 Yes PRR-7 PRR4 PRR-119.10 P-002C Charging Pump 685J175 Yes Yes PRR-14 PRR-14 Yes PRR-7 PRR-8 PRR-1.2.9.10 P-004A BA Transfer 685J175 N/A N/A PRR-12 PRR-12 PRR-12 PRR-12 PRR-8 PRR 117.9.10.11 P-0048 BA Transfer 685J175 N/A N/A PRR-12 PRR-12 PRR-12 PRR-12 PRR4 PRR-117.9.10.11 P-010A RHR 110E029 Yes N/A Yes Yes PRR-4 PRR-7 PRR4 PRR-1.2.9.10.16.17 P-010B RHR 110E029 Yes N/A Yes Yes PRR-4 PRR-7 PRR-8 PRR-1.2.9.10.1617 P-011 A CC 110E029 Yes N/A Yes Yes Yes PRR-7 PRR-8 PRR-1.2.9.10.16 P-011 B CC 110E029 Yes N/A Yes Yes Yes PRR-7 PRRE PRR-1.2.9.10.16 P-014A Contrinment Spray 119E035 Yes N/A Yes Yes PRR4 PRR-7 PRR-8 PRR-119.10.16 P-014B Containment Spray 119E035 Yes N/A Yes Yes PRR4 PRR-7 PRR4 PRR-1.2.9.10.16 P-015A Safety injection 119E035 Yes N/A Yes Yes PRR4 PRR-7 PRR4 PRR-119.10.16.17 P-0158 Safety injection 119E035 Yes N/A Yes Yes PRR-3 PRR-7 PRR4 PRR-119.10.16.17 P-029 AFW M-217 Yes Yes PRR4 Yes Yes PRR-5 PRR-7 PRR-119.10.16.18 Page 2 of 2

POINT BEACH NUCLEAR PLANT INSERVICE TEST!NG PROGRAM INSERVICE TESTING PROGRAM Revision 1

' May 28,1991 APPENDIX C O PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. PRR 1

.CGAPONENTS: Various SECTION XI REQUIREMENT:

The full scale range of each Instrument shall be three times the reference va!ue or less. (IWP-4120)

BASIS FOR REllEF:

Table IWP-41101 requires the accuracy of instruments used to measure temperature and speed to be equal to or better than 15 percent for temperature and t2 percent for speed, both based on the full scsle reading of the instrument. This means that the accuracy of the measurement can vary as much as 215 percent and 16 percent, respectively, assuming the range of the Instruments extended to the allowed maximum.

These IST pump parameters are often measured with portable test instruments where commerclally 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 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-4110-1 and Paragraph IWP-4120.

ALTERNATE TESTING:

Whenever poq3b!e instruments are used 'or measuring performance parameters. the instruments will be such that the " reading

accuracy is as follows Temperature 15 percent Speed 22 percent v Status IST Program 1990 Page 1 of 21

POINT BEACH N'JCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 l May 28,1991 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. PRR 2

_ COMPONENTS: Applicable to all pumps in the Program SECTION XI REQUIREMENT:

Each inservice test r, hall include the measutomont and observation of all quantitles in Tablo IWP 31001.

(lWP 3300)

Pump inlet pressure shall be measured before starting a pump and during the test. (Tablo IWP 31001)

SASIS FOR PgyEE If a pump being tested is in operation as a result of plant or system noods. It is unreasonable to reconfigure system lineups simply to provide for measurement of static inlet pressure.

Inlet pressure prior to pump startup is not a significant parameter needed for ovaluating pump performance or its material conditloa.

ALTf RN ATE TESTING:

When performitig a test on a pump that is already in operation as a result of system or plant requirements, inlet pressure will only be measured during pump operation.

Status: IST Program 1990 Page 2 of 21

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 :

REUEF REQUEST NO. PRR4 UNITS: 1 and 2 COMPONENTS: Safety injection Pumps, P 015 A&B

,$ECTION 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 IWP 3100-1 shall then be measured or observed. (IWP 3100)

When a reference value or set of values may have been affected by repair or routine servicing of a pump, a new reference value or set of vcJues shall be determined, or the previous value reconfirmed by an inservlee test run prior to, or within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months ahor, retum of the pump to normal service. (IWP 3111)

BASIS FOR REllEF:

The Inservice testing of these pumps is accomplished by operating the pumps in a recirculation mode through a fixed flow-limiting orifice. The ortfice is sized such that pump operation is in the flat (horizontal) region of the i pump characteristic curve where pump head is relatively independent of flowrate. Under these test conditions flowrate measurements may not be Indicative of pump performance, NRO Generic Letter 8944, Position 9. allows elimination of flowrate measurements during quarterly testing wherc flowrate instrumentation is unavailable provided that appropriate Inservice tests are performed during cold i shutdowns or refueling where full or substantial flow conditions can be established and flowrates measured.

The only practical means of establishing full or substantial flow and obtalning quantitative flowTate data during testing of these pumps requires pumping intn 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 forjglj reference values would require a plant shutdown and cooldown prior to returning a repaired pump to service. Tests performod 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 IWP-3100), except flow, will be measured, recorded, and evaluatrx!.

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM !

INSERVICE TESTING PROGRAM Revision 1 l May 28,1991 !

APPENDIX C I PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 l l

At least once during each reactor refueling when significant flow can be established through an instrumented (flowrate) test circult, an inservice test will be performed where all required pump paramotors will bo measured and recoeded 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 IWP-3111, testing will 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 will be performod and the test results evaluated por 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. j If the plant is in a refueling shutdown condition, the subject pump will be tested with all parameters (including flowrate) measured and evaluated with respect to IWP-3111.

i Status: IST Program 1980; VRR-3 (Approved via GL 89-04)

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX C f K PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. PRR4 UNITS.1 and 2 COMPONENTS: Residual Heat Removal Pumps, P 010 A&B SECTION XI REQUIREMENT:

The resistance of the system shall be varied unta either the differentlat pressure or the measured flowrate equals the corresponding referencc value. The test quantitles shown in Table IWP-31rvb1 shall then be measured or observed. (IWP-3100)

When a reference value or set of values may have been affected by repair or routine servicing of a pump, a new reference value or set of values shall be determined, or the previous value reconfirmed by an inservice test run prior to, or within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after, return of the pump to normal service. (lWP-3111)

BASIS FOR REllEF:

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 normal conditions, this is not possible due to the large differential between the RCS and O

3 the maximum pump discharge pressures. Thus, the quarterly inservice testing of these pumps is accomplished by operating the pumps in a recirculation mode through a fixed flow-limiting ortflee. The orifice is sized such that pump operation in the flat (horizontal) region of the pump characteristic curve where pump head is relatively independent of flowrate. In addition, the range and accuracy of the flow instrumentation do not provide adequate repeatability at the reduced flowrate available in this flow scheme. Under such test conditions, flowrate measurements may not be Indicative of pump performance.

NRC Generic Letter 89-04, Position 9, allows elimination of flowrate measurements during 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.

Performing post maintenance testing forail reference values would require a plant shutdown and cooldown prior to retuming a repaired pump to service. Tests performed in the recirculation mode 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 p - tmeters (per IWP-3100), 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 a!! 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.

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF 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 refueling shutdown condition such that the testing In the rocirculation modo is the only testing practical, then such testing will be performed and the test results evaluated por IWP4111. Following this, the subject pump will be testod during the next refueling shutdown period whero 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 (including flowrate) measured and evaluated with respect to IWP-3111.

Status: IST Program 1980; VRR-4 (Approved via GL 89-04)

Page 6 of 21

i POINT BF.ACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 9 REUEF REQUEST NO. PRR-5

.Vl((.S 1 and 2 COMPO14ENTS, Auxiliary Feedwater Pumps, P 029( 2 pumps) and P438 A&B SECTION XI REQUIREMENT; The resistance of the system shall be varied unti either the differential pressure or the measured flowrate equals the corrosponding reference value. The test quantities shown in Table IWP-31001 shall then be measured or obsorved. (IWP-3100)

When a reference value or set of values may have been affected by repair or routine servicing of a pump, a new reference value or set of values shall be determined, or the previous value reconfirmed by an inservice test run prior to, or within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after, retum of the pump to normal service. (IWP-3111)

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 steam generators. During plant operation under normal conditions, this is undesirable due to the possibility of causing thermal shock to the auxillary feedwater piping nozzles. For this reason the inservice testing of these pumps is accomplished by operating the pumps in a recirculation mode through a fixed flow-limiting orifice. The orifice is sized to provide pump operation in the flat (horizonta!) region of the pump characteristic curve where pump head is relatively independent of flowrate. In addition, flow instrumentation is not provided in this test scheme. Thus, under these test conditions, flowrate measurements are neither practical nor would they provide any meaningful information if available.

l NRC Generic Letter 8944, Position 9, allows elimination of flowrate measurements during quarterly testing where flowrate instrumentation is unavaBable provided that appropriate inservice tests are performed during cold j

shutdowns or refueling where full or substantial flow conditions can be established and flowrates measured.

Performing post maintenance testing for.ai! reference values would require a plant shutdown and cooldown prior j to returning a repaired pump to sar ,ce. Tests performed in the recirculation mode (quarterly) are sufficient to j provide adequate assessment ol se pump to perform its safety function.

t ALTERNATE TESTING:

During eacn quarteriy 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.

O Page 7 of 21 ,

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 ANr) 2 Should maintenance be periormod that requires post maintenance testing per IWP-3111, testing will be performod as fol lows:

If the plant is not in a cold shutdown condition such that the tosting in the rocirculation rixxje is the only testing practical, then such testing will be performed and the test results evaluated por IWP-3111. Following this, the subject pump will be tested during the next cold shutdown period whore all parameters (including flowrate) will 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 evaluated with respect to IWP-3111.

During cold shutdown periods when operation of the auxiliary foodwato' pumps pumping to a steam generator is possible without the potential of thermal shock, inservice testing will bo 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. Testing at cold shutdown will be at e troquency 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 requirod unless 3 months have passed since the last s shutdown test of the subject pump.

Status: IST Program 1930; VRR 5 (Approved via GL 8904)

Page 8 of 21

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX C

) PUMP PROGRAM REQUESTS FOR RELIEF V UNITS 1 AND 2 REUEF REQUEST NO. PRR4 UNITS: 1 and 2 COMPONENTS: Containment Spray Pumps, P 014 A&B AECTION 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 showr. In Table IWP-31031 shall then be measured or observed. (IWP 3100)

BASIS FOR REllEF:

The only practicel means of establishlr g full or substantial flow and obtaining quantitative and meaningful flowrate data during testing of these pumps requires 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 is sized such that pump operation is in the flat (horizontal) region 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 rneasurements are not possible.

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 1980; VRR-6 (Approved via GL 8944)

Page 9 of 21

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. PRR-7 UNITS: 1 and 2 COMPONENTS: All pumps in the IST Program SECTION XI REQUIREMENTS:

At least one displacement vibration amplitude (peak-to-peak) composite) shall be read during each Inservice test.

The direction of displacement 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. (lWP-4510)

The allowable ranges of inservte test quantities in relation to the reference values are tabulated in Table IWP-3100-2. (lWP-3210) 3 ASIS FOR REUEF:

Measuring vibration in velocity units rather than displacement is an industry accepted practice considered to be more sensitive to small changes that are indicative of developing mechanical problems. Velocity measurements

. detect not only hlgh-amplitude vibration, characteristic of major mechanical problems, but low-amplitude v vhration, as well, caused by misalignment, Imbalance, or minor bearing wear.

It is impractical to search for the direction with the largest deflection and procedurally retum to that precise location on successive 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 .wquirement to test procedures could cause confusion as to the proper locations for measuring pump vibration. Also, ccmparing subsequent test data to reference test data taken at different locations does not provide a good measure of pump degradation.

ASME/ ANSI OMa 1987, 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 subsequent test data to the reference value at that specific location.

Measuring vibration in velocity units is permitted by the most recent version of OM-b 1989 - Standard For Inservice Testing At Nuclear Power Plants, Part 6.

Al.TERNATIVE TESTING:

Pump vibration measurements may be taken in either displacement or velocity units. Acceptance criteria for velocity measurements will conform to those set forth in OM-b-1989, Part 6. Tables 3 and 3a.

For centrifugal and rotary (non-reciprocating) positive 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 evaluated per IWP-3100 with successive vibration readings compared to reference values previously taken at that specific location.

Status; Proposed to NRC March 2,1990 as PAR 11 Page 10 of 21

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX C p) i' PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 RELIEF REQUEST NO. PRF,-8 UNITS.1 and 2 COMPONENTS: All pumps in the Program SECTION XI REQUIREMENT:

The temperature of all centrifugal pump beadngs 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 RELIEF:

' The data associated with bearing temperatures taken at one-year intervals provides little statistical basis for determining the incremental degrachtion of a bearing or any mean!ngful trending information or correlation.

In many cases the pump bearings are water-cooled and thus, bearing temperature is a function of the temperature of the cooling medium, which can vary considerably.

O

( Vibration measurements are a significantly more reliable indication of pump bearing degradation than are temperature measurements. All pumps in the program are subjected to vibration measurements in accordance with IWP-4500. -

Although excessive bearing temperature is an indication of an imminent or existing bearing failure, it is highly unlikey that such a condition would go unnoticed during routine surveillance testing since it would manifest itself in other obvious indications such as audible noise, unusual vibration, increased motor current, etc.

Any potential gain from taking bearing measurements, 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 periods for standby pumps especially under minimum flow conditions, and unnecessary personnel radiation exposure.

ALTERNATE TESTING:

Vibration monitoring will be performed using units of velocity via 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 material condition of the pump bearings.

O Status: Proposed to NRC March 2,1990 as PRR 12 Page 11 of 21

POINT DEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 i

May 28,1991 APPENDIX C O PUMP PROGRAM REQUESTS FOR RELIEF UNRS 1 AND 2 REUEF REQUEST NO. PRR-9

.UlflJj; 1 and 2

.CQl.tPONENTS: All pumps in 'ho Program E.CILQN XI REQUIREMENT:

If the presence or absence of liquid in a gago line coul(1 produce a difference of more than 0 25% in the trWicated value of the moasurtd pressure, means shall be provided to ensuro or determine the presence or absence of !! quid as requirod for the static correction usei (IWP 4210)

BASIS FOR RELIEF; When this toquiremont is appfled to the moasutomont of pump suction pressure whoro measured pressures are at relatNe low lovols, the 0.25% limit is overty rettrictNe ard oftentimes results in comp!!cated venting procoduros and unnecessary health physics risks associated with handling and disposal of radioactko contaminated water with no commensurate gain or Improvement of test rtdlability.

O Normally, the only quantitatNo use of suction pressuro measutomonts, whero significant accuracy is toquirod, is in dctormining pump difforonilai pressure or head. In most casos the pump discharge pressure exceeds the suction pressure by at !oast a factor of flvo (5). This being the caso, a .25% error introduced into the suction piessure measutomont results in an otror of .05% in the drtforential pressure calculation. This is insignificant in light of the potential 6% orror allowance appilod to both thes suction and discharge pressure instruments (Ref IWP4110).

'lTERNATE TESTING;

.he presence or absence of liquid in a page line used for sensing pump suction pressure could produce a dlfiorence of more than 0 25% in the calculated value of the pump drtfotontial pressure, means shall be provid(d to ensure or rietermine thu presence or absence of liquid as requirod for the static correction usal O Status: IST Program 1990 Page 12 of 21

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Rsvision 1 May 28,1991

APPENDIX C

[ PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 :

1 REUEF REQUEST NO. PRR 10

.UMIft 1 and 2 ,

SOMPONENTS: M pumps in the Program SECTION XI REQUIREMENT: !

4 instrument accuracy shall be within the limas of Table IWP41101, (For pressure and flowrato 'Ns is s2 porcent.) (IWP 4110)

The full scale range of each instrument shall be three times the referenco vahm ~S (lWP-4120)

SASIS FOR REUEF; 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 repeatabnity.

The articlos do not provido any guidance on the specific bounds within which they apply, it is uncloar whether or not primary sensors are considered.

Further numerous instrument loops in our facility utillzo remoto indicators without rodundant, local indication ALTERNAJE TESTING:

For instruments which have primary sonsors associated with the instrument loop (an ortflee for flow, for example) the primary sensor accuracy is not considered. This will not affect repeatabil;ty, For instruments which have instruments and indicators positionoci locally, and when remoto, computorized ,

Indication is used. Table 41101 will be applied. <

Por instrument loops which consist of transmitters and remote roadouts, for pressure, diffotontial pressure and flowrate, an acceptable accuracy is s3%

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t O Status: IST Program 1990: PRR 10 (Approvod via GL 8944)

Page 13 of 21

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX C PUMP PROGRAM REQUESTS FOR REUEF UNITS 1 AND 2 1

REUEF REQUEST NO PRR.It UNITS.1 and 2 COMPONENTS: Boric Acid Transfer Pumps, P-004 A&B SECTION XI REQUIREMENT: l The resistance of the system shall be varied untu olther the differential presst,re or the measured flowrate equals the corresponding reference value. The test quantitios shown in Table IWP41001 shall then be moasured or observed. (IWP-3100)

BASIS FOR RELIEF:

4 The quarteriy inservice testing of these pumps is accomplished by operating the pumps in a rocirculation modo in a circuit having no capability for flow measurement. A test circuit is available in which pump flowrato can be moasured however it requires Injoction of highly concentrated boric acid solution into the reactor coolant system. During plant operation, thlJ ls not practical since it would upset the reactor coolant boric acid ba'ance i and adversely effect reactor power and create a plant power translent. If injection were to be performed during i 4

cold shutdown periods (other than refueling) the result would be over boration of the RCS and associated potential operating difficuttles during the subsequent plant startup. l l

NRC Generic Letter 8904, Position 9, allows elimination of flowtate measurements during quarteriy testing where flowrate Instrumentation is unavailable provided that appropriate inservice tests are performed during cold l shutdowns or refueling where full or substantial flow conditions can be establishod and flowrates measured.

ALTERNATE TESTING:

During each inservice test these pumps will bo operated in the recirculation mode via the non instrumented flow loop.

At least once during each reactor refueling an Inservice test will be porformod where all required pump parameters will be measured, recorded, and evaluated in accordance with IWP 3100.

i Status: IST Program 1990 Page 14 of 21

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM

INSERVICE TESTING PROGRAM Rsvision 1 May 28,1991 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 i

I REUEF REQUEST NO. PRR 12 UNITS: 1 and 2 l l

COMPONENTS: Boric Acid Transfer Pumps, P004 A&B j SECTION XI REQUIREMENTS: ,

An inservice test shall be run on each pump nomirmily every 3 months during normal plant operation. (lWP- l 3400(a))

Each Inservice test shall include tne measursmont and observation of all quantillos in Tablo IWP 31001 except i boaring temperatui , which shall be measured during st least one inservice test each year. (IWP4300)

BASIS FOR REUEF-The system installations do not provide any mechanism for measuring pump suction pressure, discharDe pressure, or pump flowrate during normal plant operation. The only practical method of dotormining pu 3p flowrate is to pump to the RCS. Due to the problems associated with over-boration of the RCS, this cari only be done during reactor refueling outages. ;

To prevent boric acid crystallation each of those pumps is encapsulated in insulation and is heat traced procluding access for measuring pump or motor vibration. It is impractical to routinely rensve this instatinn to provide such access.

The CVCS system is r:onfigured such that any of the four (4) boric acid transfer pumps (2 in each unit) can f supply olther unit if necessary. This provides a significant amount of rodundancy and rollability for the function of RCS boration. In consideration of this, a reduced frequoney and reduced scopo of testing of thoso pumps is adequate.

ALTERNATE TESTING:

During reactor refueling outages each of those pumps will bo tostod and flowrote will be vortflod to be adoquate to serve its safety function. In conjunction with these tests pump vibration will be measured as practical i considering the insulation encapsulation.

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Page 15 of 21

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 PUMP PROGRAM REQUESTS 'OR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. PRR 13

.UN[I.S; 1 ard 2

.QQMPONENTS: Service Water Pumps, P432 A through F

.SEQI1ON XI REQU1BEMENI; Each inservice lost shall include the measurement and observation of all quantities in TatWe IWP 31001.

(IWP 3300)

Pump inlot pressure shall be measurtd tx foro starting a pump ard during the test. (TatWo IWP 31001)

DASISfQR Q R'.iL.EF:

The pumps listed above oro vertical lino shaft pumps submer00d in the lntako structure with no practical means of measuring pump inlet pressure. Tt.a inlet pressure however, can bo dolormined by calculation using, as input, the measured holght of water above the pump inlet as measurod at the intake.

During each inservice test, the water level in the intake pit romains rsdatkoly constant, thus only ono moasuromont of level and the associated suction pressuto calculatlon nood be perform (d ALIEB14AllLIESTING, During testlng of those pumps, one value of inlet pressure will be calculattd based on water levol at the intako struClure.

Status: IST Program 10% (formerly IST Program 1980 Pump Noto 4)

Pago 10 of 21

POINT BEACH NUCLEAR PLANT

' UqjlNSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM ,

r Revision 1 '

j. APPL / SIX C May 28,1991 ,

i f'Mirt PHOGRAM REQUESTS FOR RELIEF !

Ut4WS 1 AND 2 i F

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REUEF REQUEST NO. PRR 14 UNITS; 1 and 2 1

COMPONENTS; CVCS Charging Pumps, P-002 A through C

_SECTION XI REQUIREMENT: l Each inservice test shall include the measuremont and observation of all quantities in T (lWP-3300)

BASIS FOR REllEF; i

The CVCS configuration is such that there is no installed instrumentation prov suction in orthese measuring differential parameters, pressures. Installation of temporary lnstrumentation is burdensom t

The Charging Pumps are multiple plunger, positNe41splacement reciprocating pu discharge pressure is purely a ful : tion of pump deslM and is Independent of suction .

this new standard requires measurement and evaluation pressure. Further, suction pressure measurements are not required, ALTERNATE TESTING:

During inservice testing of the Charging Pumps, suction and differential pressures will recorded in lieu of this, pump discharge pressure will be measured and evaluated per I i

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Status: IST Program 1990 Page 17 of 21

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 20,1991 APPENDIX C PUMP PROGRAM REQUESTS FOR RELIEF UM!TS 1 AND 2 REUEF REQUEST NO. PRR 15

.uti[IS; 1 ard 2 COMPONENTS: Cat %e Sproading Room Chillod Water Pumps, P-111 A&B Control Room Chillod Water Pumps, P 112 A&B JECTION XI REQUIREMEffI; Each Inservice test shall include the measurement and observation of all quantities in Table IWP-31001.

(lWP 3300)

EASIS FOR REUEF:

The chilled water system configuration is such that thoto is no Installed instrumentation provided for measuring flowrate, however, the installation does provide for the capability of operation under a constant (fixed) resistance modo such that pump can be monitored and evaluated from pump differential pressure.

ALTERNATE TESTINQ; During inservice testing of these chilled water pumps, the punips will be operated in a modo such that the system resistance is fixed and repoatablo. During those tests, pump difforontlal pressure will be measured and evaluated in accordance with IWP-3210.

l Status: IST Program 1990 I

l Page 18 of 21 l

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 AP'?ENDIX C PUMP PROGRAM REQUESTS FOR RELIEF IJNITS 1 AND 2 REUEF REQUEST NO. PRR 10 Mtif12: 1 and 2 COMPONENIS: NI pumps in the program for which differential pressure is determined.

SECTION XI REQt@_EMENI: Differentlat pressure is a measured paramotor (IWP-3100,3110)

DA$1S FOR REUEF:

Pumps are not equippod with instruments which directly prosW a value for ddforential pressure.

ALTERNATE TESTING: ,

Differential pressure will be a calculated value based on the values of suction and discharge pressure.

Page 10 of 21

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX C PUMP PROGRAM REOUESTS FOR REUEF UNITS 1 AND 2 REUEF REQUEST NO PRR 17 UNITS 1 ard 2 COMPONENTS: Safety injection pumps, P415A88 Residual Heat Removal Pumps, P410A8B

_SECTION XI REQUIREMENTS:

Each purnp shall be run at least fNe minutes under conditions as stat 90 as the system permhs. At the ord of this 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 fully instrumented, significant flowrate test at refueling shutdown conditions, the pumps use the RWST as a suction source and dolNer 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 (Ne 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 fNo minutes.

When performing periodic noninstrumented recirc line testing, the pump will be operated for at hast INo minutos.

MIL 81NATE TESTING:

When performing three data point pump curve testing, which includes reference point data, an overall run tirne of ftvo minutes will be mot Pump operation during periodic recirc line testing will be at least (No minutes in duration.

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Page 20 of 21 I

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM l INSERVICE TESTING PROGRAM Rsvision 1 !

May 28,1991 [

APPENDIX C l PUMP PROGRAM REQUESTS FOR REUEF UNiis 1 AND 2 1

I REUEF REQUEST NO. PRR 18 j

UNITS- 1 and 2

_ COMPONENTS: Ausi!!ary Foodwater Pumps P420 (2 pumps) ard POSSA&B ;

JECTION XI REQUIREMENT: I Each pump shall be run at least five minutes under conditions as stat 40 as the system permits. At the end of ,

this time, at least one measurement or observation of each of the quantitles specified shall be made ard recorded (IWP 3500).

BASIS FOR RELIEE:

During cold shutdown periods when operation of the auxiliary foedwater pumps pumping to a steam generator is possible without the potential of thermal shock, inservice tosting will be poriormed such that all required pump 4 parameters will be measured and recorded at three (3) # ints along the pump curve.

At this time, however, there is very little decay beat roma l in the RCS system. Sustalnod oporation of auxlitary feedwater at substantial flowrates causes signifk pressure decreases in the roactor coolant system which challenge reactor coolant pump operation limits ar- ause reactor coolant level decreases due to to nperature induced shrink.

ALTERN ATE TESTING:

When periorming three data point pump curve testing, which includos reference point data, an overall run time of fNo minutes will be met. Pump operation during porlodic recirc line testing will be at least Ove minutos in duration.

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2 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R vision 1 May 28,1991 APPENDIX D j UNIT 1 VALVE PROGRAM TABLES l

^

l CONTENTS i .iiYntt!D faQt ;

t Auxtlary Feodwater System 6 !

8 i Auxtlary Steam, Heating Steam, ChNied & Hot Water Chemical and Volume Contrd 10 '

Component Cooling Water 13 Containment Spray 10 ,

De'colzad and Reactor Makwp Water 20

, Emergercy Dional Generator Air Start - 21 l Emergency Diesel Generator fuel 01 24 Heating and Ventiation 20 !

Instrument Air 30 Main Foodwater 34 1 Mann and Reheat Steam 35 1

Post Accidert Containment Vent / Monitoring 38 !

Primary Sampling 40 ,

Reactor Coolant 42 3

Safety injection and Residual Heat Removal 45 '

Service Air 54 Service Water - 55 Spent Fuel Pit Cooling 01 i Wastn Disposa! 62 Notes 64 J

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r Pago 1 of 64 j

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM l INSERVICE TESTING PROGRAM R:; vision 1 May 28,1991 s

APPENDIX D UNIT 1 VALVE PROGRAM TABLES LEGINQ VALVE The plant alpha numerical designator for the subject valve.

CORD The coordinato location of the vatve on the designated drawing.

CLASS The ISI classification of the valve as por the respoetNo ISI bourdary drawings.

CAT The valve category por Paragraph liW 2200.

SIZE The salve's nominal size in inchos.

TYPE The valve type AP Pnoumatic Pilot BA Ball BTF Buttorfly CK Chock 01 Diaphragm GA Gate s GL Globe SCK Stop/ Chock SRV Safety /Rollef NE Noodle (throttle)

ACT The valve actuator type as follows:

AO Alt oporated HO Hydraulic oporated MA Manual vatve 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 valve as follows:

BT-C Exercise to closed positkin. For powor-operated vanes, stroke timos will be measured unless excludod by an associated relief request.

BT4 Exorcise to open position. For power-operated vaNos, stroke times will be measured unless excluded by an asso; lated relief requor,t.

BT-EE Exorcise valve to verity proper oporation and stroking with no stroke timo measuromonts. Requires observation of system paramotors or local observation of C vaNo operation.

I Page 2 of 64

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R; vision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TADLES DT PV Exorciso of pneumatic puot valve. Propor operation of the tassociated main vatve vortflos operability.

CV-C Exorcise chock vatve to the cics A positlort CV O Emorcise check valve to tra l'.dl<>pon position-CV PO Partial stroke exorcise chock valvo in the open directiort CV PC Partial. stroke oxortise chock vales in the closo direction.

FST Fai safe test.

INSP Disassembly and inspection of chock valvos.

PIT Position Indication vertfication por IWV 3300.

RVT Safetv/Rollof valve setpoint test por ASME-OMa 1.

O SLT t Seat loaktate test por 10 C"H 50, App. J.

SLT-2 Seat loakrate test for presstre isolation valves por Technical Specification 15 316.

SLT 3 Soat leakrate test for pneumatic chock vatvos to vortfy capabutty of maintaining accumulator gas inventory following loss of supply system pressure.

SLT-4 Leak testing of saloty injoNion accumulator check valvos.

SLT 5 Seat loaktato test to identity gross leakago. Specific laakage rates wul not be measured but leakage will be dotormheed and ovaluated with respect to system operability ard its capabilty to miorm hs safety function.

SLT4 Seat leakrate test to identify gross leakage. Specific leakago rates wlil be measurod and evaluated with respect to system operabiltry and its capability to perform its safety function.

TEST FREO The required test interval abbrovlations are defined as follows:

RR Each reactor refueling outage (cycle)

CS Cold shutdown (por Technical Spocifications)

E-CS Cold shutdown with Event V tosting required OR Ouarteriy (during plant operation) tY Once por calendar year 2Y Every 2 ynars SY Every 5 years 10Y Every 10 years s SR Prior to placing a system or compooont in operablo status SP Other (see applicable roquest for rollof)

Page 3 of 64

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX D i UNIT 1 VALVE PROGRAM TABLES I i

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REMARKS Applicatie requests for rollet from code requirements (see Apperdk F) are noted in the REMARKS cdemn adjacent to the associated test requirement and designated VRR XX, Applicalde notes are included in the REMARKS column ard are designated NOTE.XX A list of r6.s is attached as the last page of ttw apperdk.

Cold shutdown testing justifications are pro &d in Appendix 0. Each explanation is identified by a reference number (CSJ XX) truit appears in the respective REMARKS column adjacent to the pertinent test requirements.

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i f '] POINT BEACH NUCLEAR PLANT O INSERVICE TESTING C3AAM l

, . INSERVICE TESTING 'OGRAM b Revison 1 May 28,1991 C

APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: AuxElary Feedwater DRAWING NO.: M-217 i

SIZE TYPE ACT POS REOMT FREO REMARKS I VALVE CORD FL*NCTION CLASS CAT 1P-29 Suc!kwi 3 B 6 GA MA O BT-C OR AF-00026 C4 E4 1P-38A Suction 3 8 4 GA MA O BT-C OR AF4X)039 F4 1PG88 Suction 3 B 4 GA MA O BT-C OR AF-00052 3 CK SA C CV-O CS CSJ-1 AF-00100 89 AFW to 1 A S/G 2 C 3 CK SA C C/4 CS CSJ-1 AF-00101 DJ AFW to 18 S/G 2 C SA CVO CS CSJ-1 AF-00102 88 AFW to 1 A S/G 2 A/C 3 CK A/C CVO CS CSJ-1 SLT-5 2Y CV-O CS CSJ-1 AF43104 DG AFW to 1B S/G 2 A/C 3 CK SA A/C CV-C CS CSJ-1 SLT-5 2Y SA CV-O CS CSJ-1 AF-00106 BS AFW to 1 A S/G 2 A/C 3 CK A/C CV-C CS CSJ-1 l SLT-5 2Y CVO CS CSJ-1 AF-00107 DG AFW to 1B S/G 2 A/C 3 CK SA A/C CV-C CS CSJ-1 l SLT-5 2Y 4 CK SA C C/4 CS CSJ-2 AF@108 C7 1P-29 Disch Ck 3 C I CVO CS CSJ-2 AF-00109 DG P-38A Disch Ck 3 C 3 rX SA C CK SA C CV-O CS CSJ-2 AF-00110 F8 P-38B Disch Ck 3 C 3 3 C 6 CK SA C CV-PO CR AF-00111 CS 1P-29 Suct Ck CV-O CS CSJ-3 Page 5 of 64

] POINT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TEST NG PP.OGRAM Revson 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Aux 21ary Feedwater DRAVANG NO.: M-217 VALVE CORD FUNCTICN CLASS CAT GIZE TYPE ACT POS REOMT FREO REMARKS AF-00112 E5 P48A Suc Ck 3 C 4 CK SA C CV-PO OR CV4 CS CSJ,3 AF-00113 F5 P-388 Suct. Ck 3 C 4 CK SA C CV-PO OR CV-O CS CSJ,3 AF-04000 C8 1B S/G AFW lsol 3 B 3 GL MO C BT-C CR FIT 2Y AF-04001 B8 1 A S/G AFW isol 3 B 3 GL MO C BT-C OR FIT 2Y AF44002 C6 1P-29 MinLflow 3 B 1 GA AO O BT-C CS VRR-28,CSJ41 FST CS CSJ-31 PIT 2Y AF-04006 DS 1P-29 Ser W!r 3 '8 6 GA MO O BT-O CR Sup PIT 2Y AF440C7 D6 P-38A MinL50w 3 8 1 GA AO O BTC CS VRR-28 CSJ-31 FST CS CSJ-31 P!T 2Y AF-04009 E5 P-38A Ser Wtr 3 B 4 GA MO O BT-O CR Sup PIT 2Y AF-04012 E6 P-38A Press Con 3 0 3 GA AO O BT-O OR FST OR PIT 2Y AF-04014 E6 P-38B Mini-flow 3 B 1 GA AO O BT-C CS VRR-28.CSJ-31 FST CS CSJ41 PIT 2Y Page 6 cf 64

l- INSERVICE TESTING RAM

']r-u N csEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM

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s Revision 1 D May 28,1991 APPENDIX D l UNIT 1 VALVE PROGRAM TABLES SYSTEM Auxfisry Feedwater DRAWING NO.: M-217 POS REOMT FREO REMARKS FUNCTION Ct. ASS CAT S!ZE TYPE ACT VALVE CORD j

8 4 GA MO O BT-O OR A -04016 F5 P-388 Ser Wir 3 PIT 2Y St;p 8 3 GA AO O BT4 OR AF-04019 F6 P-3SB Prea Con 3 FST OR P!T 2Y I

8 3 GA MO O BT4 OR AF-04021 E7 AFW to 18 S/G 3 BT-C OR PTT 2Y B 3 im MO O BT-O OR AF-04023 D8 AFW to 1 A S/G 3 BT4 OR P!T 2Y RVT 10Y l C6 1PM9 Suction 3 C 1 SRV SA C AF-04026 Ret SRV SA C RVT 10Y AF-04027 F6 P@88 Suction 3 C 1 Rei SRV SA C RVT 10Y AF-040<1 E6 P-038A Suction 3 C 1 Ret ._

Page 7 cf 64

[~p!NT BEACH NUCLEAR PLANT f] INSERVICE It.silNG 2 RAM

( !NSERVICE TESTING PROGRAM Revision 1 May 28,1st APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEht Aux Steem. Heating Steam Chr.ed and Hot Water DRAWING NO.: M-214. Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREQ REMARKS b HV@632 D7 Am Stm to Cont 2 A 3 GA MA C SLT-1 2Y VRR-23 Passhe HV-00633 A7 Aux Stm Cond Ret 2 A 15 GA MA C SLT-1 2Y VRR-23 Passhe HV@8'X3 B7 Aux Stm Cond Ret 2 A 1.5 GA MA C SLT-1 2Y VRR-23 PassNe HV-00009 A7 Aux Stm Cond Ret 2 A 13 GA MA C SLT-1 2Y VRRC Passt.e HV-00819 C7 Aux Steam to Cont 2 A 3 GA MA C SLT-1 2Y VRR-23 PassNe Page 8 d SS

POINT BEACH NUCLEAR PLANT INSERVICE TESTING NM INSERVICE TESTING PRCC-RAM Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Aux Steam Heating Steam. ChEed ard Hot Water l DRAWING NO_: M-214. Sheet 2 i

VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT ~ POS RECMT FREO REMARKS HV-00898A C8 Pump P-112A Disc NC A/C 3 CK SA O CVPO OR VRR41 l Ck CV4 OR SLT-5 CY INSP SP VRR-31 HV@900A B8 Pump P-112B Disc NC AfC 3 CK SA O CV-PO OR VRR41 Ck CV-C '

CR SLT-5 2Y INSP SP VRR41 HV@914A Pump P-111A Disc NC I B3 A/C 3 CK SA O CVSO CR VRR41 Ck CVC CR l SLT-5 2Y INSP SP VRR41 HV-00916A A8 Pump P-111B Disc NC A/C 3 CK SA O C/-PO OR VRR-31 Ck CV-C OR SLT-5 2Y INSP SP VRR41 Page 9 of 64

_ _ ___ __ _ _ _ __ __ . _ _ _ _ _l

l INSERVICE TESTING RAM (N

\ Revnpon 1 INSERVICE TESTING PROGRAM SPOINT BEACH NUCLEAR PLANT May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM Chemical ard Volume Coreroi DRAWING NO: 684J741 CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS RWST to Chg Pumo 2 B 4 GA MO C BT-O OR CV@t 12B B10 P:T 2Y B 4 GA MO O BT-C CS CSJ4 CV @ t12C C10 VCT to Cteg Pump 2 PIT 2Y GL AO O BT-O CS CSJ-5 CV-00142 C12 Charging Flow Cort 2 B 3 f FST CS PfT 2Y C .75 SRV SA C RbT 10Y CVM283A B12 Chg Pump Disc Saf 2 f '

C .75 SRV SA C RVT 10Y CVm2838 B12 Chg Pump Disc Saf 2 2 C .75 SRV SA C r /T 10Y l CV-00283C A12 Chg Pump Disc Saf C 3 CK SA O CV-O OR I CV4uM C14 C 6. @ .0 Hdr Ck 1 NE MA T BT-C RR VRR-19 CV-00300A A14 RCP Sea!Irj Thril 2 A 1 SLT-1 2Y l NE MA T BT-C RR VRR-19 CVmB A15 RCP Seal Inj Thrt! 2 A 1 SLT-t 2Y VRR-12 I RCP Seal Wtr Sup 2 CK SA O CV-C RR CV-00304C A14 1 A/C SLT-1 2Y CK SA O CV-C RR VRR-12 CV-00304D A15 RCP Seal Wir Sep 1 A/C 2 SLT-1 2Y l

A 3 GA MO O BT-C CS CSJ4 CV-00313 C12 RCP Seal Wtr Ret 2 PTT 2Y SLT-1 2Y Page 10 of 64

] POINT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TESTING PROGRAM b Revision 1 May 28,1991

APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Chemcal and Vdume Contrd DRAWING NO.: 684J741 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CV40313A C13 RCP Seal Wtr Ret 2 A 3 GL AO O BTC CS CSJ4 FST CS CSJ4 PIT 2Y SLT-1 2Y CV40323A A12 Aux Charging Isol 2 A 2 GL MA C SLT-1 2Y Passive CV40323B C12 Cbg HCV Bypass 2 A 2 GL MA C SLT-1 2Y VRR-23 Passhre CV40333A 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 CV403338 AS BA Trans*er Pump 2 A/C 2 CK SA C CV-PO OR VRR4s 1

Drsch -

C/4 RR VRR-26 C/C OR SLT-5 2Y CV-00350 A9 Emerg Boration 2 B 2 GA MO C BT-O OR PIT 2Y CV40351 A9 Emerg Boration Ck 2 C 2 CK SA C CV4 RR VRR-24 i

CV-00357 B10 RWST to Chg Pump 2 C 4 CK SA C CVO OR CV40370 C13 Charging Hdr Ck 2 A/C 3 CK SA O C/C OR i C/C RR VRR-13

l SLT-1 RR Page 11 of 64

(SPOINT BEACH NUCLEAR PLANT O INSERVICE TESTING RAM i ' INSERVICE TESTING PROGRAM Revrsion 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Chemical and Volume Control DRAWING NOc 684J741 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CV@371 D13 RCS Letdown Iso 24d[I 2' -

GL AO O BT-C CS CSJ-7 FST CS CSJ-,

PIT 2Y SLT-1 2Y CV-00371 A D13 RCS Letdown Iso 2 .A 2 GL AO O BT-C CS CSJ-7 FST CS CSJ-7 PIT 2Y SLT-1 2Y CV403848 C12 Chg Line HCV Out 2 A 3 GL LM O BT-C CS CSJ4 SLT-1 2Y VRR-23 CV-01296 A14 Aux Chargirg Iso 1 A 2 GL AO C PIT 2Y Pass!ve SLT-1 2Y Page 12 of 64

'~'N INSERVICE TESTING RAM s

W

'NPOINT BEACH NUCLEAR PLANT lNSERVICE TESTING PROGRAM {d Revson 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM Cwvcs+ d Coding Water Dft%VING NOc 110E018. Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CC-00738A G3 RHR Coding Water 3 8 to GA MO C BT-O OR Sup PIT 2Y CCm7388 G2 RHR Coding Water 3 8 to GA MO C BT O OR Se m n Page 13 of 64 i

RAM

[]PO!NT BEACH NUCLEAR PLANT C INSERVICE TESTING Rev:s:on 1 t ' INSERVICE TESTirJG PROGRAM May 28,1991 D

APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM Corpcs+1 Coc4ing Water DRAWING NO.: 110E018. Sheet 2 EMF POS RECMT FREO REMARKS CLASS CAT TYPE ACT VALVE CORD FUNCTION BT-C CS CSJ-9 2 8 6 GA MO O CC@719 G11 Contan1 ment CCW P!T 2Y Suo BTC CS CSJ-10 RCP Og Water Sup 2 A 4 GA MO O CC&754A F13 SLT-1 2Y PIT 2Y BT-C CS CSJ-10 RCP Og Water Sup 2 A 4 GA MO O CC@754R F10 SLT-1 2Y PTT 2Y CV-C 2Y VRR-10 RCP Og Wir Sup 2 A/C 4 CK SA O CCM755A E13 SLT-1 2Y VRR-23 Ck CV4 2Y VRR-10 4 CK SA O CC@755B E10 RCP Og Wir Sup 2 A/C 2Y VRR-23 SLT-1 Ck BT-C CS CSJ-10 RCP Og Wir Ret 2 A 4 CA MO O CC@759A F11 SLT-1 2Y VRR-25 pit 2Y O BT-C CS CSJ-10 RCP Og Wir Ret 2 A 4 GA MO F8 VRR-23 CC-007598 l SLT-1 2Y P!T 2Y l

Page 14 of 64

[3 POINT BEACH NUCLEAR PLANT -

INSERVICE TESTING RAM

' INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES

SYSTEM: Cuupcr=nt Coding Water DRAWING NOc 110E018, Sheet 2 i

VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS RECMT FREO REMARKS l CCM76M E12 RCP Og Wtr Ret 2 C 2 SRV SA C RVT 10Y

S/R CCM7638 E8 RCP Og Wtr Ret 2 C 2 SRV SA C RVT 10Y S/R CC@767 E7 Ex LD HX Og Wtr 2 A/C 2 CK SA C CV-C ,

RR VRRm Sup SLT-1 RR VRROJ CC@0769 F5 Ex LD HX Og Wir 2 A 2 GL AO C BTC OR Ret FST OR PTT 2Y SLT-1 2Y l

i a

l l

i Page 15 of 64 l

ODOINT BEACH NUCLEAR PLANT N INSERVICE TESTING RAM INSERVICE TESTING GRAM Revison 1 May 28,1991 APPEND!X D i UNIT 1 VALVE PROGRAM TABLES SYSTEM: Coupcie E Coding Water i DRAWING NO 110E018. Sheet 3 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CCOO724A 18 CCW Pump Disch 3 A/C 10 CK SA O CV-O OR Check CV-C OR SLT-5 OR CC40724B H8 CCW Pump Disch 3 A/C 10 CK SA O CV-O OR Check CVC OR SLT-5 OR CCo0773 111 CCW Normal 3 B 2 GL MA C SLT-6 2Y Passte Makeup CC40779 411 CCW Surge Tank 3 C 3 SRV SA C RVT 10Y Renef CC40779A J11 CCW SurDe Tk Vac 3 C 1 CK SA C CV-O OR Bkr CV-C CR

~

y CC40815 111 CCW Eirs eyc 3 B 2 GL MO C SLT-6 2Y Passive g

Makeup PIT 2Y Page 16 of 64

f;gPOINT BEACH NUCLEAR PLANT N INSERVICE TESTING JRAM (h' INSERVICE TESTING PROGRAM Revrs,on 1 APPENDIX D May 28,1991 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 CCN-LW-63 H7 W Supply to 3 A 6 BTF AO O BT-C OR Radwaste FST OR SLT-6 2Y PET 2Y CCW-LW44 A7 CCW Retum from 3 A 6 BTF AO O BT-C OR Radwaste FST OR g

SLT-6 2Y PTT 2Y l

l l

j l

1 Page 17 of 64

INSERVICE TESTING RAM

/'~~hPOINT BEACH NUCLEAR PLANT Revision 1

~lNSERVICE TESTING PROGRAM ,

"- May 28,1991 AFPENDIX D UNIT 1 VALVE PROGRAM TABLES OYSTEM: Containment Spray DRAWING NO.: M-110E017. Sheet 3 ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION Cl. ASS CAT SIZE TYPE AO C BT-O CS CSJ-11 SI-00836A F7 NaOH Supply 2 B 2 GL FST CS CSJ-11 PIT 2Y AO C BT-O CS CSJ-11 SI408368 E7 NaOH Supply 2 B 2 GL FST CS CSJ-11

- P!T 2Y SRV SA C RVT 10Y SI40840A G5 Spr Add Tank Vac 2 C .75 Bkr C .75 SRV SA C RVT 10Y SI408408 G5 Spr Add Tank Vac 2 Bkr 2 C 2 CK SA C CV-O OR SI T847A H8 Spray Add Educt Check 2 C 2 CK SA C CV-O OR SI408478 D8 Spray Add Educt Check CK SA C CVPO OR VRR4 ,

SI-00858A 13 RWST to CS Pump 2 C 6 VRR4 l INSP SP P14A CK SA C CV-PO OR VRR4 SI-008588 C3 RWST to CS Pump 2 C 6 INSP SP VRRE P148 2 B 6 GA MO C B -O OR SI40800A 11 0 CS Pump 1#14A PIT OR Disch 2 B 6 GA MO C BT-O OR SI-00800B 110 CS Pump 1#14A PIT OR Disch 2 B 6 GA MO C ST-O OR SI40860C C10 CS Pump 1#148 PIT OR Dirch l

Page 18 of 64

SPOINT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TESTING PROGRAM d Revision 1 May 28,1991 APPENDIX D

~

UNIT 1 VALVE PROGRAM TABLES

!YSTEM: Containment Sprav DRAWING NO.: M-110E017, Sheet 3 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARPS SI-00860D C10 CS Pump 1-P14B 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-9 Disch ; SLT-1 RR VRR-23, 29 J

SI-00862B C11 CS Pump 1-P14B 2 A/C 6 CK SA C INSP SP VRR-9 Disch SLT-1 RR VRR-23,29 S!40864A H11 CS Pump Test 2 A .75 GL MA C SL. -1 2Y Passive Recire VFR-23 SI-008648 C11 CS Pump Test 2 A .75 GL MA C SLT-1 2Y Passive Recirc VRR-23 SI40870A 13 RWST to CS Pump 2 A 6 GA MO O BT-O OR P14A BT-C OR Note 3 SLT-6 2Y Note 2 PIT 2Y SI-00870B C3 RWST to CS Pump 2 A 6 GA MO O BT-O OR P148 BT-C OR Note 3 SLT-6 2Y Note 2 PIT 2Y SI40871A 15 RHR to CS Pump 2 B 6 GA MO C BT-O OR P14A BT-C OR FIT 2Y SI40871B C5 RHR to CS Pump 2 B 6 GA MO C BT-O OR P148 BT-C OR PIT 2Y SI-00872 G6 Spray Add Tank Sai 2 C .75 RV SA C RVT 10Y Page 19 of 64

P !NSERVICE TESTING RAM

(~'N OINTTESTING INSERVICE BEACH NUCLEAR PLANT PROGRAM [V~) Revision 1 May 28,1991 APPENDlX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Delonized/ Reactor Makeup Water DRAWING NO.: PBM-231, Sheet 2 VALVE CORD R'NC_T1ON CLASS CAT SIZE TYPE ACT POS REOMT FREQ REMARKS DI N C10 DI Water Sup to 2 A 2 DI MA C SLT-1 2Y Passive Cont DI-00011 C10 D1 Water Sup to 2 A 2 DI MA C SLT-1 2Y Passive Cont Page 20 of 64 n .-..--__-..--_.-___N

NPOINT BEACH NUCLEAR PLANT INSERVICE TESTING - ~5 RAM

.a clNSERVICE TESTING PROGRAM , Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Emergency Diesel Generator Air-Start DRAWING NO.: M-209. Sheet 12 i VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS DA40100 E7 Dect-Dr Comp Disc 3 A/C 1.5 CK SA O/C CV-C OR SLT-3 2Y DA40112 E4 Dsf/ Ele Dr Comp 3 A/C 1.5 CK SA O/C CV-C OR Dis SLT4 2Y DA-00125 C5 EDG Air Start Eq Ck 3 C .375 CK SA C CV-O OR VRR-25 CV-C OR VRR-25 DA40126 C4 EDG Air Start Eq Ck 3 C .375 CK SA C CV-O OR VRR-25 CV-C OR VRR-25 DA-Ou200 E7 Elect-Dr Comp Disc 3 A/C 1.5 CK SA O/C CV-C OR SLT-3 2Y DA-00212 E4 Dst /Be Dr Comp 3 A/C 1.5 CK SA O/C CV-C OR Dis SLT-3 2Y DA-00225 C5 EDG Air Start Eq Ck 3 C .375 CK SA C CV-O OR VRR-25 CV-C OR VRR-25 DA-00226 C4 EDG Air Start En Ck 3 C .375 3 2A C CV-O ' OR VRR-25

CV-C OR VRR-25 i DA-03055A C6 Receker TODA Relief 3 C .5 RV SA C RVT 10Y DA-03055B C6 Reciever T608 3 C .5 RV SA C RVT 10Y Relief DA-03055C C6 Receiver T60C 3 C .5 RV SA C RVT 10Y Relief DA-03055D C3 ReceNer T600 3 C 5 RV SA C RVT 10Y Retiei Page 21 of 64 t

INSERVICE TESTING RAM

[] POINT BEACH NUCLEAR PLANT Q

\ / Revision 1 t lNSERVICE TESTING PROGRAM May 28,1991 U

APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Emergency Diesel Generator Air 4 tart DRAW 1NG NO.. M-209, Sheet 12 POS REOMT FREO REMARKS CLASS CAT SIZE TYPE ACT VALVE CORD FUNCTION 3 C .5 RV SA C RVT 10Y l DA-03055E C3 Receker T60E Relief RV SA C RVT 10Y C3 ReceNer T60F Reflef 3 C .5 DA-03055F RV SA C RVT 10Y Receiver T61 A Relief 3 C .5 DA-03056A C6 RV SA C RVT 10Y DA-030568 C6 ReceNer T618 3 C .5 Relief SA C RVT 10Y ReceNer T61C 3 C .5 RV DA,"3056C C6 Relief SA C RVT 10Y 3 C .5 RV DAEK)S60 C3 Receiver T61D Relief SA C RVT 10Y 3 C .5 RV DA-03056E C3 Reciever T61E Relief SA C RVT 10Y Receber T61F Relief 3 C .5 RV DA-03056F C3 BT-O CR VRR-17 EDG Starting Valve 3 8 .375 GL AO C J DA-03057A B4 BT-O OR VRR-17

)

EDG Starting Vafve 3 8 .375 GL AO C DA-030578 B5 BT-O OR VRR-17 EDG Starting Vane 3 8 .375 GL AO C DA-03058A B4 BT-O OR VRR-17 EDG Starting Vane 3 B .375 GL AO C DA-030588 B5 BT-O OR VRR-25 EDG Start Air Relay 3 8 .375 GL SO C DA-06316A C5 l

BT-O OR VRR-25 EDG Start Air Relay 3 8 .375 GL SO C DAE316B C4 BT-O OR VRR-25 EDG Start Air Relay 3 B .375 GL SO C DAE317A C5 Page 22 of 64

INSERVICE TESTING RAM

('

7CKPOINT BEACH NUCLEAR PLANT

, INSERVICE TESTING PROGRAM ( Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Emergency Diesel Genemtor Air-Start DRA%1NG NO.: M-209, Sheet 12 l l

POS REOMT FREO REMARKS FUNCTION CLASS CAT SIZE TYPE ACT VALVE CORD C BT-O OR VRR-25 C4 EDG Start Air Relay 3 B .375 GL SO DA-063178 C BT-O OR VRR-25 BS EDG Start Mir Pin 3 B .375 GL SO DA-06318A Eng C BT-O OR VRR-25 B4 EDG Start Mtr Pin 3 8 .375 GL ^ SO DA M 18B Eng C BT-O OR VRR-25 B5 EDG Start Mtr Pin 3 8 .375 GL SO DA 06319A Eng l C BT-O OR VRR-25 B4 EDG Start Mir Pin 3 8 2 75 GL SO DA-06319B Eng Page 23 of 64

NPOINT BEACH NUCLEAR PLANT INSERVICE TESTING RAM jlNSERVICE TESTING PROGRAM

~

V Revision 1 May 28,1031 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Emergency Diesel Generator Fuel OR DRAWING NO.: M-219 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO ROAARKS FO RO14 C9 DFO Pump P-70A 3 A/C 2 CK SA C CV-O OR Disc CV-C OR SLT-5 2Y FO RO19 B9 DFO Pump P-708 3 A/C 2 CK SA C CV-O OR Disc CV-C OR SLT-5 2Y FO-0CO24 D8 DFO Pumpout isol 3 A 2 GA MA C SLT-5 2Y Passive FORO34 H2 Fire Pump Fuel Sup 3 A 2 GA MA C SLT-5 2Y Passive FOR910 C9 DFO Pump P-70A 3 A/C .75 SRV SA C SLT-5 2Y Passive S/R FO42911 C9 D O Pump P-70B 3 A/C 75 SF"/ SA C SLT-5 2Y Passive S/R FO43922 H4 Boler Day Tk Inlet 3 A 1 GA AO C BT-C OR FST OR SLT-5 2Y PIT 2Y FO43930 G3 EDG Day Tk T31 A 3 A 1 GA MO C BT-C OR in BT-O OR SLT-5 2Y PIT 2Y FO 43931 G2 EDG Day Tk T31B 3 A 1 GA MO C BT-C OR in B T-O OR SLT-5 OR FIT 2Y Page 24 of 64

POINT BEACH NUCLEAR PLANT . INSERVICE TESTING RAM

[] INSERVICE TESTING PROGRAM[x Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Emergency Diesel Generator Fuel OH DRAWING NO.: M-219 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS FO43940 D9 DFO Pump Press 3 A/C 1 GL SA C BTEE OR VRR43 Cont SLT-5 2Y FO43941 C9 DFO Pump Press 3 A/C 1 GL SA C BT-EE OR VRR43 Cont SLT-5 2Y Page 25 of 64

C'NPOINT BEACH NUCLEAR PLANT / INSERVICE TESTING RAM

( INSERVICE TESTING PROGRAM b]' Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Heating and Ventiation l DRAWING NO.: M-144, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO ! REMARKS SW42976 C6 Spray PP Room 3 8 2 GL SO C FST OR M-2207 Sh 1 T/C SW-02977 B7 RHR PP Room 3 8 2 GL AO O FST OR M-207 Sh 1 l T/C l l

Page 26 of 64

f^ POINT

'N, BEACH NUCLEAR PLANT [ '\, INSERVICE TESTING RAM i INSERVICE TESTING PROGRAM \m/ Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Heating and Ventiation DRAWING NO.: M-144, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VNCR-04639 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

Page 27 of 64

(NPOINT BEACH NUCLEAR PLANT INSERVICE TESTING RAM i INSERVICE TESTING PROGRAM ,, Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Heating and Ventiation DRAWING NO.: M-215. Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VNPSE-03212 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 VNPSE-03213 H4 Cont. Purge 2 A 36 BTF AO C BT-C CS CSJ-12 Exhaust -

FST CS CSJ-12 SLT-) 2Y VRR-23, 29 PIT 2Y VNPSE-03244 F3 Cont. Purge Supply 2 A 36 STF AO C BTC CS CSJ-12 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 PIT 2Y i

{

Page 28 of 64 i

L

INSERVICE TESTING RAM

[] POINT BEACH NUCLEAR Pl. ANT

( INSERVICE TESTING PROGRAM V Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Heating and Ventilation DRAVr1NG NO.: M-215, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS RMO3200AA G3 Cont Atmos Samp 2 A/C 1 CK SA O CV-C RR VRR-16 Retr SLT-1 RR RM43200A F3 Cont Atmos Samp 2 A 1 GA AO O BT-C OR Retr FST OR SLT-1 2Y PIT 2Y RM43200B F8 Cont Atmos Samp 2 A 1 GA AO O BT-C OR Sup FST OR SLT-1 2Y PIT 2Y RM-03200C G8 Cont Atmos Samp 2 A 1 GA AO O BT-C OR Sup FST OR SLT-1 2Y ;

PIT 2Y l

1 Page 29 of 64

[~'N POINT BEACH NUCLEAR PLANT i

('

INSERVICE TESTING RAM D,!!NSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Instrument Air DRAWING NO.: M-209 Sheet 5 VALVE CORD FUNCTION Ct.AS 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 VRR-14 IA M S C5 Purge V!v 3212 Sup NC A/C .25 CK SA C CV-O OR CV-C OR SLT-3 2Y VRR-14 Page 30 of 64

s

- 3 POINT BEACH NUCLEAR PLANT INSERVICE TESTING 1 RAM lNSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Instrument Air DRAWING NO.: M-209. Sheet 7 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS IA41182 B5 Inst Air to Cont 2 2 A/C CK SA C CV-C OR SLT-1 2Y VRR-23 IA-01184 B5 Inst Air to Cont 2 A MA 1 GA C SLT-1 2Y VRR-23 Passive IA41192 B5 Inst Air to Cont 2 2 CK A/C SA C CV-C OR SLT-1 2Y IA-03047 B4 Inst Air to Cont 2 A 2 GA AO I O BT-C OR FST OR SLT-1 2Y I t PIT 2Y l IA43048 B4 Inst Air to Cont 2 A 2 GA AO O BT C OR

iST OR SLT-1 2Y PET 2Y Page 31 of 64

/ INSERVICE TESTING RAM 3 POINT BEACH NUCLEAR PLANT Revision 1 INSERVICE TESTING PROGRAM k_.-

{ ( May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES l

SYSTEM: Instrument Air DP. AWING NO.: M-209, Sheet 11 I

TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT SIZE CK SA C CV-O CS CSJ-28 IA41206 G9 Inst Air to PORV NC A/C CV-C CS CSJ-28 SLT4 2Y VRRG2 Note 1 l

CK SA C CV4 CS CSJ-28 IA41209 G9 Inst Air to PORV NC A/C CV-C CS CSJ-28 SLT-3 2Y VRR-32 Note

l CK SA C CV-O CS CCJ-13 IA-01280 F6 Purge Viv 3245 Sup NC A/C .25 CV-C CS CSJ-13 SLT4 2Y VRR-14 l

CK SA C CV4 CS CSJ-13 IA-01281 E6 Purge Viv 3213 Sup NC A/C .25 CV-C CS CSJ-13 SLT-3 2Y VRR-14 l

l CK SA C CV-O CS CSJ-28 IA-01301 G10 Nit. Sup to PORV NC A/C CV-C CS CSJ-28 SLT-3 2Y Note 1 l

CK SA C CV-O CS CSJ-28 IA41300 G10 Nit Sup to PORV NC A/C CV-C CS CSJ-28 SLT-3 2Y Note 1 l

CK SA C CV-O CS CSJ-28 IA41600 G9 Inst Air to PORV NC A/C CV-C CS CSJ-28 SLT-3 2Y VRR-32 l

Note 1 l l

Page 32 of 64

INSERVICE TESTn4G RAM

[] POINT BEACH NUCLEAR PLANT

('

\ Revision 1

.__AINSERVICE TESTING PROGRAM

~

May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES .-

SYSTEM: Instrument Air DRAVANG NO.: M-209. Sheet 11 RECMT FREO REMARKS CLASS CAT SIZE TYPE ACT POS VALVE CORD FUNCTION CV-O CS CSJ-28 NC A/C CK SA C IA-01506 G9 Inst Air to PORV CV-C CS CSJ-28 SLT-3 2Y VRR42 Note 1 RVT 10Y Note 1 PORV Nlt Sup S/R NC C SRV SA C IA m 308 G10 RVT 10Y Note 1 PORV Nlt Sup S/R NC C SRV' SA C IAM309 G10 BT-EE CS CSJ-2S F10 PORV 420 N3 Sup NC C GL SA O/C IAM310 Reg BT-EE CS OSJ-28 F10 PORV 431C Nit Sup NC C GL SA O/C IA-06311 Reg Page 33 cf 64

[ . _ _ -

gPOINT BEACH NUCLEAR PLANT INSERVICE TESTING ^ RAM

,1NSEP.VICE TESTING PROGRAM s Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Maln Feedwater DRAWING NO.: M-202, Siwet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CS40466AA C9 S/G 1 A Feedwtr Ck 2 A/C 16 CK SA O CV-C RR VRR-21 SLT-6 RR VRR-21 CS4046688 C9 S/G 1 A Feedwtr Ck 2 A/C 16 CK SA O CVC RR VRR-21 SLT4 RR VRR-21 CS-00476AA G9 S/G 18 Feedwtr Ck 2 A/C 16 CK SA O CV-C RR VRR-21 SLT-6 RR VRR-21 CS40476BB G9 S/G 1B Feedwtr ek 2 A/C 16 CK SA O CVC RR VRR-21 l _

SLT4 RR VRR-21 t

Page 34 of 64 i

l gPOINT BEACH NUCLEAR PLANT [] INSERVICE TESTIN RAM

['"N k JINSERVICE TESTING PROGRAM C/ Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Main and Reheat Steam DRAWING NO.: M0-201. Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS MS42005 G8 Main Steam Safety 2 C 6 RV SA C RVT SY MS42006 G8 Main Steam Safety 2 C 6 RV SA C RVT SY fAS42007 G7 Main Steam Safety 2 C 6 RV SA C RVT SY MS-02008 G7 Main Steam Safety 2 C 6 RV SA C RVT SY MS-02010 D8 Main Steam Safety 2 C 6 RV SA C RVT SY j l

MS42011 D8 Main Steam Safety 2 C 6 RV SA C RVT SY j MS42012 D7 Main Steam Safety 2 C 6 RV SA C RVT SY l I

MS42013 D7 Main Steam Safety 2 C 6 RV SA C RVT SY MS4?015 H7 MS Atmos Stm 2 B 6 GL AO C BT-C O Dmp BT-O O l PIT 2Y MS42016 E7 MS Atmos Stm 2 B 6 GL AO C O l BT-C Dmp BT-O O PIT 2Y MS42017 G7 Main Steam 2 8 30 SCK AO O BT-C CS CSJ-15 Isolation FST CS CSJ-15 PET 2Y MS42017A G4 Main Steam 2 C 30 CK SA O CV-C CS CSJ-16 NonReturn MS42017C H6 MSIV 2017 Air Plot NC B 1 AP SC C BT PV CS CSJ.17 MS-020179 H5 MSIV 2017 Air Piot NC B l1 AP SO C BT-PV CS I CSJ-17 Page 35 of 64

) POINT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TESTING PROGRAM (w Revision 1 May 28,1991 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-02018 D9 Main Steam 2 B 30 SCK AO O BT-C CS CSJ-15 Isolation FST CS CSJ-15 PIT 2Y MS-02018A D4 Main SNm 2 C 30 CK SA O CV-C CS CSJ-16 l Nonretum MS42018C E6 MSIV 2018 Air Phot NC B 1 AP SO C BT-PV CS CSJ47 MS42018D ES MS!V 2018 Air Phot Ns B 1 AP SO C BT-PV CS CSJ-17 MS-02019 F6 AFW Steam Supply 2 B/C 3 SCK MO S BT-O OR CV-O 9R BT-C Oh ,

PIT 2Y MS42020 E6 AFW Steam Supply 2 , B/C 3 SCK MO S BT-O OR CV-O OR BT-C OR FIT 2Y ,

MS-02082 B5 Main Steam to AFW 2 B 3 GL SA/ O BT-C OR VRR-1 ;

Pump MA BT-O OR PIT 2Y l MS-02083 C9 S/G Sample Isol 2 A .75 DI AO O BT-C OR FST OR SLT-1 2Y PIT 2Y MS-32084 F9 S/G Sample Isol 2 A .75 DI AO O BT-C OR FST OR SLT-1 2Y l

PIT 2Y Page 36 of 64

RAM NPOINT BEACH NUCLEAR PLANT

'lNSERVICE TESTING PROGRAM

('

s INSERVICE TESTING Revision 1 M May 28,1991 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 MS42000 C8 SW to AFW Pump 3 8 1 GL SO O BT-O OR VRR-20 P-029 FST OR MS-05958 B10 S/G Blowdown isol 2 A 2 GA AO O BT-C OR FST OR SLT-1 2Y PIT 2Y MS45959 E10 S/G Blowdown isol 2 A 2 GA AO O BT-C OR FST OR SLT-1 2Y ,

PIT 2Y RS-SA49 F7 Radwaste Steam 2 B 3 GA AO O BT-C OR Supply FST OR PIT 2Y l

l t

Page 37 of G4

INSERVICE TESTING F RAM OPOINT BEACH NUCLEAR PIANT s Revision 1

_,. .llNSERVICE TESTING PROGRAM May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Post-Accident Containment Vent /Monfroring DRAWING NO.: M-224 POS REOMT FREO REMARKS FUNCTION CLASS CAT SIZE TYPE ACT VALVE CORD MA C BT-O 1Y VRR44 D6 Pest-Acc Purge 2 A 2 DI H2-V-04 SLT-1 2Y VRR-23 Disch MA C BT-O 1Y VRR44 D6 Post-Acc Purge 2 A 2 DI ,

H2 V45 SLT-1 2Y VRR-23 )

Disch I C SLT-1 2Y VRR-23 Post-Acc Purge 2 A 75 GA . MA l H2-V-06 D6 Pass.%

Drain l

C SLT-1 2Y VRR-23 Post-Acc Purge 2 A .75 GA MA l H2-V-07 D6 Passive Drain MA C SLT-1 2Y Pass %

E6 Post-Acc Atmos. 2 A .75 DI H2-V-08 l &m MA C SLT-1 2Y Passfve E6 Post-Acc Atmos. 2 A .75 DI H2-V49 !

Samp I f l

C BT-O 1Y VRR-34

! l 2 A 2 DI MA l H2-V-12 D6 Post-Ace Service 2Y VRR-23 I

SLT-1 Air Sup l

MA C BT4 1Y VRR44 D6 Post-Acc Service 2 A 2 DI l H2-V-13 SLT-1 2Y VRR-23 Air Sup C BT-O 1Y VRR-34 2 A 2 DI MA k H2-V-19 D7 Post-Acc Alt Ven! 2Y VRR-23 SLT-1 MA C BT-O 1Y VRR44 D7 Post-Acc Alt Vent 2 A 2 DI l H2-V-20 SLT-1 2Y VRR-23 MA C BT-O 1Y VRR-34 D7 Post-Ace Sup Drain 2 A 2 DI l H2-V-22 SLT-1 2Y VRR-23 Page 38 of 64

POINT BEACH NUCLEAR PLANT ,O} INSERVICE TESTIN RAM INSERVICE TESTING PROGRAM (s Revision 1 May 28,199^

APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Post-Accident Containment Vent / Monitoring DRAWING NO.: M-224 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS H2-V-23 D7 Post Acc Sup Drain 2 A 2 DI MA C BT-O 1Y VRR-34 SLT-1 2Y VRP'3 Page 39 of 64

POINT BEACH NUCLEAR PLANT N INSERVICE TESTING $ RAM s

- INSERVICE TESTING PROGRAM ReviRw! 1 May 28,1991 W ,

l APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Primary Samping ,

j DRAW NG NO.: 541F092 !

VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS !

, SC-00951 G12 Press Stm Sampe 1 A .375 GL AO C BT-C OR [

FST OR ,

SLT-1 2Y '

pit 2Y !

SC40953 F12 Press Liq Sampe 1 A .375 GL AO C BT-C OR FST OR SLT-1 2Y PIT 2Y SC-00955 E12 Hot Leg Sampe 1 A .375 GL AO O/C BT-C OR i

! FST OR ,

SLT-1 2Y [

PIT 2Y j SC-0]959 E12 RHR Samps 2 A .375 GL AO C BT-C OR FST OR f

SLT4 2Y PIT 2Y l l

SC-00966A G10 Press Stm Sampe 1 A .375 GL AO C BT-C OR l FST OR [

SLT-1 2Y L M 2Y I

SC-00966B F10 Press Liq Sampe 1 A .375 GL AO C BT-C OR l FST OR SLT-1 2Y PIT 2Y I

i Page 40 of 64

/ \ POINT BEACH NUCLEAR PLANT [ }

INSERVICE TESTING ^ RAM INSERVICE TESTING PROGRAM (./

(d Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Primary Sampling DRAWING NO.: 541F032 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SC-00966C E10 Hot Leg Sample 1 A .375 GL AO O/C BT-C OR FST OR SLT-1 2Y PIT 2Y Page 41 of 64

POINT BEACH NUCLEAR PLANT f INSERVICE TSTING Revrion 1 RAM O_ INSERVICE TESTING PROGRAM \

May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Reactor Coolant DRAWING NO.: 541F091 Sheet 1 VALVE COFD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREC- REMARKS RC-0040 H5 Power-Operated Rel 1 B 2 GL AO C BT-C CS CSJ-18 BT-O CS CSJ-18 l FST CS CSJ-18 PIT 2Y RC 00431C 15 Pcmer-Operated Ret 1 8 2 GL AO C BT-C CS CSJ-18 DT4 CS CSJ-18 FST CS CSJ-18 PIT 2Y RC-00434 17 Pissunzer Safety 1 C 3 SRV SA C RVT SY RC-0045 16 Pressurtzer Safety 1 C 3 SRV SA C RVT SY RC-00515 15 PORV Block Valve 1 B 3 GA MO O BT-C OR Note 4 PIT 2Y RC-00516 H5 PORV Block vatve 1 B 3 GA MO O BT-C OR Note 4 PIT 2Y i

l L

1 i

Page 32 of 64

POINT BEACH NUCLEAR PLANT '

INSERVICE TESTING PROGRAM (d) x INSERVICE TESTIN Revision 1 RAM APPENDIX D May 28,1991 UNIT 1 VALVE PROGRAM TABLES SYSTEM:

Reactor Coolant DRAWING NO.: 541F091, Sheet 2 VALVE CORD FUNCTION CLASS CAT S!ZE TYPE ACT POS

~

RC4)0508 D2 REOMT FREO PRT Fill Une Iso 2 A REMARKS 2 DI AO O/C BT-C OR FST OR SLT-1 2Y RC-00528 D3 PIT 2Y PRT Nitrogen Sup 2 A/C 75 CK SA

~ O/C CV-C RR VRR-11 RC4)0529 D3 SLT-1 RR PRT Fi!! Une Ck 2 A/C 2 CK SA O/C CV-C RR RC4K)538 SLT-1 VRR-18 E3 PRT Sample RR 2 A 375 GL AO O BT-C OR FST OR SLT-1 2Y RCA)0539 E3 PIT 2Y PRT Sample 2 A .375 GL AO O BT-C OR FST OR SLT-1 2Y '

RC-00570A F5 PIT 2Y RX Vessel Vent t B 1 GL SO C BT-O CS RC4)C570B PIT CSJ-19 F5 RX Vessel Vent 2Y 1 B 1 GL SO C BT-C CS CSJ-19 RC-00575A F5 PIT 2Y RX Vess/ Press Vent 1 B 1 GL SO C BT-O CS RC-005758 PIT CSJ-19 F5 2Y RX Vess/ Press Vent 1 B 1 GL SO C BT-O CS PIT CSJ-19 2Y Page 43 of 64

O POINT BEACH NUCLEAR PLANT "N INSERVICE TESTIN RAM S

INSERVICE TESTING PROGRAM (h Revision 1 M&y 28,1991 APPENDIX D UNIT 1 VALVE I 'ROGRAM TABLES SYSTEM: Reactor Coolant DRAWING NO.: 541F091, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS RC-00580A G5 Pressurizer Vent 1 B 1 GL SO C BT-O CS CSJ-19 PIT 2Y RC-005808 GS Pressurizer Vent 1 8 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 SLT-1 2Y Page 44 of 64

INSERVICE TESTING GRAM POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM

['

L Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E017, Sheet 1 TYPE ACT POS REOMT FREO RDAARKS VALVE CORD FUNCTION CUGS CAT SIZE SRV SA C RYr 10Y SI40830A H7 SIS Accum Relief 2 C 1 l I

C SRV SA C RVT 10Y SI-008308 D7 SIS Accum Relief 2 1 GL AO C BT-O CS CSJ40 SI40834A H7 SIS Accum Vent 2 B 1 I FST CS CSJ-00 PIT 2Y GL AO C BT-O CS CSJa0 SI-00834B D7 SIS Accum Vent 2 B 1 FST CS CSJ 30 FIT 2Y MO O BT-C CS CSJ-20 SI-00841 A G8 SIS Accum Disch 2 B 10 GA PTT 2Y l CS CSJ-20 2 8 10 GA MO O BT-C SI-00841B B7 SIS Accum Disch PET 2Y SA C CV-PO E-CS VRR4 SI-00842A G8 SIS Accum DLs's 1 A/C 10 CK CV4 OR VRR-4 Ck VRR-4 CV-PO RR INSP SP VRFA SLT-4 OR VRR-4 l SA C CV-PO E-CS VRR4 B8 SIS Accum Disch 1 A/C 10 CK SI40842B CV-C GR VRR4 Ck VRR4 CV-PO RR INSP SP VRR-4

( SLT-4 OR VRR-4 l I

SA C CV-O RR VRR-2 CK F8 SIS Cold Leg inj 1 A/C 2 S140845A CV-C RR VRR-2 l' SLT-2 2Y VRR-22 Page 45 of 64 I

g'"5.

(v}gPOINT lNSERVICE TESTINGBEACH NUCLEAR PLANT PROGRAM h)

\v' INSERVICE TESTIN ' RAM Revision 1 APPENDIX D May 2R.1991 UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E017. Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE l ACT POS REOMT FREQ REMARKS SI@ 845B 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 Deluge 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C n.' VRR-2 SLT-2 2Y VRR-22 SI M845D F8 SIS Core Deluge f ,

A/C 2 CK SA C CV-O RR VRR-2 l

CV4 RR VRR-2 SLT-2 2Y VRR-22 Sl@S45E F6 SIS Cold Ieg inj 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C RR VRR-2 SLT-2 2Y VRR-22 SI@ 845F E8 SIS Cold leg inj 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C FA VRR-2 SLT-2 2Y VRR-22 l SI-00846 H3 Accurn Nit Supply 2 A 1 GL AO C BT-C QR FST OR I FIT 2Y SLT-1 2Y SI@ 850A A4 Cont Sump Hyd Isol 2 8 10 GA HO C BT-O OR FIT 2Y SI-008508 B6 Cont Sump Hyd Isol 2 B to GA HO C BT-O OR FIT 2Y SIM852A B7 RHR/LM Core 2 8 6 GA MO C BT-O i

Deluge CS CSJ-21 BT-C CS CSJ-21 PIT 2Y Page 46 of 64

i INSERVICE TESTING PROGRAM Revson 1 l May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEht Safety Injection ar.d Residual Heat Removat DRAWING NO; 110E017, Sheet 1 l VALVE N Ftr4CT10N CUGS CAT SIZE TYPE ACT POS REOMT FREO REMARKS Si408528 37 RHR/Ui Core ? B 6 GA MO C BT-O CS CS121 , I Deluge BT-C CS CSS 21 PIT 2Y S140853A B8 RHC/LH Inj Check T A/C 6 CK SA C CV-PO ECS VRR4 CV-C E CS VRR4 CVO RR VRR-3 CV-C RR VRR-3 i SLT-2 2Y VRR-22 '

Slo 08538 A8 RHR/LH Inj Check 1 A/C 6 CK SA C CV-PO E-CS VRRO CV-C E-CS VRRO CV-O RR VRR-3 CVC RR VRR-3 SLT-2 2Y VRR-22 i l

Slo 0853C B9 RHR/ Core Deluge 1 A/C 6 CK SA C CV-PO ECS VRR4 l CV-C ECS VRR4 i CVO RR VRR4 l CV-C RR VRR-3 ;

SLT-2 2Y VRR-22 i SIC 0853D A10 RHR/ Core Deluge 1 A/C 6 CK SA C CV-PO E-CS VRR4 CV-C ECS VRR-3 l CVO RR VRR-3 CV-C RR VRR-3 SLT-2 2Y VRR-22 l

SI40861 A B4 RHR RX Ves ini S/R 2 C .75 SRV SA C RVT 10Y l

Page 47 of 64 j

~] POINT BEACH NUCLEAR PLANT p INSERVICE TESTING RAM

\

plNSERV:CE TESTING PROGRAM \j Re nsion 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety injection and Residual Heat Removal DRAW:NG NO.: 110E017. Sheet 1

! VALVE CORD FUNCTION CAT SIZE TYPE ! ACT CLASS POS RECMT FREO REMARKS SI-00667A G9 SIS Cold Leg inj Ck 1 A/C 10 CK SA C CV-PO ECS VRR4 CVC E-CS VRR4 CV PO RR VRR4 l

CV-C RR VRRA INSP SP VRR4 SLT-2 2Y VRR-22 SI-008678 89 SIS Cold Leg inj & 1 A/C 10 CK SA C CV-PO CS VRR4 CV-PO E-CS VRR4 CV-C E-CS VRR4 CV-PO RR VRR4 CV-C RR VRR4 INSP SP VRR4 SLT-2 2Y VRR-22 SI-00875A F6 SIS Test Recire Ck 2 A/C .75 CK SA C CV-O OR CV-C OR SLT-5 2Y SI-008758 F5 SIS Test Recirc Ck 2 A/C .75 CK SA C CV-O OR CV-C OR SLT-5 2Y SI-00878A E8 RX Vessel Safety inj 2 8 2 GL MO C BT-O CS CSJ-22 BT-C CS CSJ-22 i

PIT 2Y SIK 8788 DC SIS Loop inj 2 B 2 GL MO O BT-O CS CSJ-23 BT-C CS CSJ-23 P!T 2Y Page 48 c4 64

ORAM

/

INSERVICE TESTIN POINT BEACH NUCLEAR PLANT Re Asson 1 INSERVICE TESTING PROGRAM May 28.1991 APPEND!X D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety injection and Residua! Heat Removal DRAWING NO.: 110E017. Sheet 1 POS RECMT FREO REMARKS CLASS CAT SIZE TYPE ACT VALVE CORD FUNCTION C BT-O CS CSJ-22 RX Vessd Safety Ini 2 8 2 GL MO SIM878C EB BT-C CS CSJ-22 FIT 2Y 2 B 2 GL MO O BT-O CS CSJ-23 f SIM878D F8 SIS Loop Inj CS CSJ 23 j BT-C i

PIT 2Y SRV SA C RVT 10Y SI-00887 E4 Test Line Sa* 2 C .75 CS CSJ-30 Si@957 H4 N2 Suppy Vent / Ret 2 A 1 GL AO C BT-O CSJ @

lg FST CS SLT-1 2Y F

FIT 2Y l

Page 49 of 64

OINT BEACH NUCLEAR Pl. ANT \ INSERVICE TESTING RAM NSERVICE 'TSTING PROGRAM Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVC PROGRAM TABLES SYSTEM: Safety injection and Residual Hea* Removal DRAWING NO.: 110E017. Sheet 2 VA1.VE 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 S1408268 H7 SIS Pump Rerdunt 2 8 8 GA MO C BT-O CS CS.'24 Suct BT-C CS CSJ-24 PIT 2Y SI00826C G7 S!S Pump Rendunt 2 B 8 GA MO C BT-O CS CSJ-24 Suct BT-C CS CSJ-24 PIT 2Y S140851A B4 Cont Sump Isol 2 B 10 GA MO C BT-O OR FIT 2Y SI40851B B4 Cont Sump Isol 2 B to GA MO C BT-O CR PIT 2Y SI40854A D3 RHR Pump Suct Ck 2n A/C 10 CK SA C CV-O RR VRR4 Cyc RR vRR4 SLT-6 RR VRR4 SI-008548 C3 RHR Pump Suct Ck 2 A/C to CK SA C CV-O RR VRR-6 CV-C RR VRR-6 SLT4 RR VRR4 l SI40856A D3 RHR Pump Suct 2 B to GA MO O BT-C OR FIT 2Y l SI408568 C3 RHR Pump Suct 2 8 10 GA MO O BT-C OR P!T 2Y Page 50 of 64

] POINT BEACH NUCLEAR PLANT INSERVICE icdiiNG RAM

' INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Safety injection anc! Residual Heat Removal DRAW;NG NO; 110E017. Sheet 2 VALVE CORD FUNCTION Ct/.SS CAT S!ZE TYPE ACT POS REOMT FREO REMARKS St@857A E7 RHR to SIS Pump 2 B 6 GA MA C BT-O OR !

Suct i SI-008578 E7 RHR to S!S Pump 2 8 6 GA MA C BT-O OE Suct SIG866A F3 S!S Pump Disch 2 B 4 GA MO O BT-O OR i BT-C OR FIT 2Y i SI@86GB E3 SIS Pump Dsch 2 B 4 GA MO O BT-O OR BT-C OR t PtT 2Y SI-00889A F8 SIS Pump Disch Ck 2 A/C E CK SA C CV PO OR VRR-7 CV-O i RR VRR-7 ;

i SIG8898 FC sis Pump Disch Ck 2 A/C 6 CK SA C CV-PO OR VRR-7 l CV-O RR VRR-7 SI-00891A E8 S!S Fump Min!-rec 2 C 2 CK SA C CV-PO OR VRR-27 Ck INSP SP VRR-27 l

SI-008918 E8 SIS Pump Mini-rec 2 C 2 CK SA C CV-PO OR VRR-27 Ck INSP SP VRR-27 51 @ 895 E5 SIS Pump Mini-rec 2 C 2 CK SA C CV-O OR Ck SI-00806A F6 SIS Pump Suction 2 B 6 GA MO O BT-C OR

~

PIT 2Y SI-008968 E6 SIS Pump Suction 2 8 6 GA MO O BT-C OR .

! PIT 2Y Page 51 of 64

l l

gPOINT BEACH NUCLEAR PLANT INSERVICE iI:siING RAM y L% SERVICE TESTING PROGRAM v e Rev sion 1 j May 28,1991

APPENDIX 0 UNIT & VALVE PROGRAM TABLES h* N Safety injection and Residual Heat Remcr<al l DRAWING NO; 110E017. Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI-00897A E2 SIS Tes: Une Ret 2 A 2 GL AO O BTC CS CS425 FST CS CS525 SLT-5 2Y PIT 2Y SIC)8978 E2 SIS Test Line Ret 2 A 2 GL AO O BT-C CS CSS 25 FST CS CSJ25 SLT-5 2Y PIT 2Y i

l Page 52 of 64

[N POINT s BEACH NUCLEAR PLANT / INSERVICE TESTING RAM i

W INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX D r UNIT 1 VALVE PROGRAM TABLES l I

SYSTEM: Safety Iriection ard Residual Heat Remaf DRAWING NOc 110E018, Sheet 1 l VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS RECMT FREO REMARKS j i

RH@710A E4 RHR Pump Disch 2 C 8 CK SA C CV-PO OR l Ck CV-O CS CSJ26 RH407108 B4 RHR Pump Disch 2 C 8 CK SA C CV-PO OR ,

Ck CV-O CS CSJ26 l l

RH-00742 H6 RHR/RWST isol 2 A 8 GA. VA C SLT-5 2Y RH-00742A H6 RHR/RWST 1 sol 2 A 2 GL MA C SLT-5 2Y RH40624 G7 RHR HX Outlet 2 B 8 STF AO O PIT 2Y Note 2 !

Passive RHOO625 G7 RHR HX Outlat 2 B 8 STF AO O PIT 2Y Note 2 Passive l l

i k

Page 53 of 64

]FOINT BEACH NUCLEAR Pt. ANT INSERVICE TESTING PROGRAM h)

'V INSERVICE IEd11NG Revision 1

' RAM May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Service Air DRAWING NO - M-209. Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMAP.KS SA@015 F7 Serv Air Cont Sup 2 A 4 GA MA C SLT-1 2Y ) Passhe SA@017 F7 Serv Air Cont Sup 2 A/C 4 CK SA C CVC OR SLT-1 2Y l

i I

i i

i Page 54 of 64 i

GPOINT BEACH NUCLEAR PLANT INSERVICE TESTIN RAM INSERVICE TESTING PROGRAM j Revissor.1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLt J SYSTEM: Service Water DRAWING NO.: M-207. Sheet 1 VALVE CORD FUNCTION Ct. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SWRXX32A D2 SW Pp P432A Disc 3 A/C 16 CK SA O/C CV-O OR Ck CVC OR SLT-5 2Y SW40032B D1 SW Pp P4328 Dtsc 3 A/C 16 CK SA O/C CV-O OR Ck Cyc OR SLT-5 2Y SW-00032C D1 SW Pp P432C Disc 3 A/C 16 CK SA O/C CV-O OR Ck CV-C OR SLT-5 2Y SW40032D E2 SW Pp P-032D Disc 3 A/C 16 CK SA O/C CV-O OR Ck CVC OR SLT-5 2Y SW00032E El SW Pp P432E Disc 3 A/C 16 CK SA O/C CV-O OR Ck CV-C OR SLT-5 2Y SW-00032F El SW Pp P432F Disc 3 A/C 16 CK SA O/C CV-O OR Ck CV-C OR SLT-5 2Y SW40135A C7 SW to AFW Pp 3 C 1 CK SA O CV-PO OR VRR-15 P429 INSP RR VRR-15 SW-02818 G6 Cable Sp Rm Cr 3 B 3 GL MO O BT-O OR Sup PIT 2Y SW-02818A F6 Cable Sp Rm Or 3 B 1.5 GL AO O FST OR T/C l Page 55 of 64

SPOINT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TESTING PROGRAM Q Revision 1 May 28,1991 AP9ENDIX D UNIT 1 VALVE PROGRAM TABLES

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i SYSTEM: Service Water DRAWING NO.: M-207, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SW-02818B F6 Cable Sp Rm Or 3 B 1.5 GL AO O FST OR T/C SW42819 D6 Control Rm Or Sup 3 8 3 GL MO O BTC OR m 2Y

_t SW-02819A C6 Control Rm Or T/C 3 8 1.5 GL AO O FST OR ,-

SW42819B D6 Control Rm Or T/C 3 8 1.5 GL AO O FST OR SW4283d C3 G02 EDG HX Out'et 3 8 4 GA AO C BT-O OR FST OR '

PIT 2Y i SW-02839 B3 G01 EDG HX Outlet 3 B 4 GA AO C BT-O OR FST OR P1T 2Y I l

SW42869 H3 SW Hdr (West) Isol 3 8 14 BTF MO O BT-C OR l PTT 2Y SW42870 B8 SW Hdr (West) Isai 3 B 14 BTF MO O BT-C OR FIT 2Y SW42890 E2 SW Header 3 B 24 BTF MO O BTC OR Cross-Tie PIT 2Y SW42891 E2 SW Header Cross- 3 8 24 BTF MO O BT-C OR Tie PIT 2Y SW-02929A G5 AFW Pump Rm or 3 B 2 GL AO O FST OR ,

T/C SW-02929B B5 AFW Pump Rm Or 3 B 2 GL AO O FST OR T/C Page 56 of 64

INSERVICE TESTING RAM POINT BEACH NUCLEAR PLANT Revision 1 j INSERVICE TESTING PROGRAM May 28.1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Sendce Water DRAWING NO.: M-207. Sheet 2 POS REOMT FREO REMARKS FUNCTION CLASS CAT S!ZE TYPE ACT VALVE CORD MO O BT-C CS CSJ-27 SW42880 F5 Turb Ha!! Ors in 3 8 6 GA FIT 2Y i

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OPOINT BEACH NUCLEAR PLANT INSERVICE TESTING RAM

' INSERVICE TESTING PROGRAM Rev:sion 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Service Water DRAWING NOz M-207. Sheet 3 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREQ REMARKS SW40012A E7 CCW HX-12A Outlet 3 8 2 GL AO O FST OR SW40012B E6 CCW HX-128 Outbt 3 8 2 GL AO O FST OR SW40012C ES CCW HX-12C Outlet 3 B 2 GL AO O FST OR SW400120 E5 CCW HX-12D Outlet 3 B 2 GL. AO O FST OR SW40307 E5 CCW HX-12D Outlet 3 8 12 GA MA C BT-O CS CSJ42 SW-00315 E5 CCW HX-12C Outlet 3 B 12 GA MA C BT-O CS CSJ42 SW-00322 E7 CCW HX-12A Outlet 3 B 12 GA MA C BT-O CS CSJ42 SW40360 E6 CCW HX-12B Outlet 3 B 12 GA MA C BT-O CS CSJ42 SW40396A H6 Battery Rm Cooler 3 C 2 CK SA O CVO OR Sup SW-00397A H6 Battery Rm Cooler 3 C 2 CK SA O CV-O OR Sup SW428i6 B3 Svc Bldg HVAC Og 3 8 6 GA MO O BT-C OR iso PIT 2Y SW-02930A B6 SFP Or Sup 3 8 8 GA MO O BT-C OR PIT 2Y SW429308 C6 SFP Or Sup 3 i B 8 GA MO O BT-C OR FIT 2Y SW-02977 D5 RHR Pump Rm or 3 B 2 GL AO O FST OR See H&V T/C System Page 58 of 64

(~'SPOINT BEACH NUCLEAR PLANT

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INSERVICE TESTI Revision 1 RAM

'y%N;. INSERVICE TESTING PROGRAM May 28,1991

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APPENDIX D UN. 1 VALVE PROGRAM TABLES SYSTEAt Service Water DRAWING NO.: M-207 Sheet 3 VALVE CORD FUNCTION Ct. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SW-LW41 G4 BDE/ Vent Cond in 3 8 8 GA AO O C-C OR FST OR PIT 2Y SW4.W42 G3 BDE/ Vent Cond 3 8 8 GA AO O BT4 OR Out FST OR PIT 2Y i

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] POINT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TESTING PROGRAM Revson 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Service Water ORA'MNG NO2 M-207. Sheet 4 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SW40015A B4 Cont Or Supply Ck 3 C 8 l CK SA O CV-O OR SW400158 B2 Cont Or Suppif Ck 3 C 8 CK SA O CV-O OR SW40015C B4 Cont Or Supply Ck 3 C 8 CK SA O CV-O OR SW40015D B3 Cont Or Supply Ck 3 C 8 CK SA O CV-O OR SW42907 G2 Cont Or Emerg 3 B 12 GA MO C BT-O OR Pow FTT 2Y SW42908 G4 Cont Or Emerg 3 8 12 GA MO C BT-O OR now PIT 2Y SW-02959 D5 Cont Or Disch S/R 3 C SRV SA C RVT 10Y SW42963 D2 Cont Or Disch S/R 3 C SRV SA C RVT 10Y SW42967 D4 Cont Or Disch S/R o 3 C SRV SA C RVT 10Y SW-02971 D3 Cont Or Disch S/R 3 C SRV SA C RVT 10Y SW44300 D1 Casity Or Ret S/R 3 C SRV SA C RVT 10Y SW-04301 D1 Cavity Or Ret S/R 3 C SRV y SA C RVT 10Y l Page 60 of 64

POINT BEACH NUCLEAR PLANT INSERVICE TESTING ~ RAM

' INSERVICE TESTING PROGRAM -

Revson 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM: Spent Fuel P!t Coolirg DRAWING NOc 110E018. Sheet 4 VALVE CORD FUNCTION CLASS CAT S ZE TYPE ACT POS REOMT FREO REMARKS SF-00009A F6 SFP Pp P-12A 3 A/C 8 CK SA O/C CV4 OR Disc Ck Cyc OR SLT-5 2Y SF-00010A F6 SFP Pp P-12B 3 A/C 8 CK SA O/C CV-C OR Disc Ck CV-C OR i SLT-5 2Y Page 61 of 64

y I POINT BEACH NUCLEAR PLANT ] INSERVICE TESTIN RAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES SYSTEM. Waste Disposal DRAWING NOr 684J971. Sheet 1 VALVE CORD FUNCTION Ct. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SF-00816 C6 P-033 RWCP 2 A 2 DI MA C SLT-1 27 VRR-23 Suction '

Passht W141003A C6 RCDT Fump 2 A 3 DI AO O/C BT-C OR Suction FST OR SLT-1 2Y VRR-23 PIT 2Y l

WL-010038 C6 RCDT Pump 2 A 3 DI AO O/C BT-C OR Suc: ion FST OR

! SLT-1 2Y VRR-23 l PIT 2Y WL01698 C6 RCDT to Sump 2 A 2 DI AO C BT-C OR FST OR SLT-1 2Y VRR-23 M W WL41721 C6 RCDT Pumps Suct 2 A 3 DI AO O/C BT-C OR Con FST OR i SLT-1 2Y pit 2Y WL-01723 C6 Cont Sump Dr ? A 3 DI AO O/C RT-C OR FST OR i SLT-1 2Y VRR-23 i 3

PIT 2Y WLO1728 C6 Cont Sump Dr 2 A 3 DI AO O/C B'-C QR FST OR SLT-1 2Y VRRC P!T 2Y

T INSERVICE TESTIN RAM POINT BEACH NUCLEAR PLANT Rev: son 1

- INSERVICE TESTING PROGRAM May 28,1991 APPENDIX D UNIT 1 VALVE PROGRAM TABLES l

f SYSTEM: Waste Disposai l DRAWING NO.: 684J971. Sheet 1 ACT POS REOMT FREO REMARKS VALVE CORD FUNCDON Ct. ASS CAT SIZE ' TYPE 2 A 1 DI AO O BT-C QR WG41786 B5 RCDT ent FST OR SLT-1 2Y P!T 2Y i 2 A 1 DI AO O BT-C OR WF41787 85 RCDT Vent OR FST SLT-1 2Y PIT 2Y BTC OR WG41788 B5 RCDT Sample 2 A .75 DI AO O/C PST OR l

SLT-1 2Y PIT 2Y 2 A .75 DI AO O/C BT-C OR WG-01739 B5 RCDT Sample ,

FST OR SLT-1 2Y PIT 2Y Page C3 of 64

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POINT BEACH NUCLEAR PLANT INSERVICE Itciti RAM

- INSERVICE TESTING PROGRAM V Revtsion 1 May 28,1991 APPENDIX D '

UNIT 1 VALVE PROGRAM TABLES NOTES

1. These valves and their respective test rega..e 6 are induded in the IST Pn9.ii. for information and tracking purposes only. They do not r%wif meet the requirements for inclusion per IWV-1100, but are identified for testing per NRC Generic Letter 904S. Thus, the tests spectied must not rwrmor:y satsry the m + Jing regtA.cos of subsection IWV or NRC Generic Lacer 8944.

2. (1148-90) Physical modfications are required to allow testing. Testing wE commence upon completion of modifications.

f

3. (1148-90) These valves fat in a position opposite of that required Manal stroke capabity wE be demonstrated.

4. If a PORV is isolated in accordance with Technical SptcAdew the associated block valve wE de exs.cised at cold shutdoet l

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i POINT BEACH NUCLEAR PLANT INSERVICE TESTINO PROGRAM i

INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E

) UNIT 2 VALVE PROGRAM TABLES o

CONTENTS

Aniem fAQt 1 Audiary Foodwater System 5 Aux Steam, Heating Steam, Chilled and Hot Water 7 Chemical and Vdume Contrd 8 Component Cooling Water 11 Containment Spray 15 Delontred and Reactor Makeup Water 18 l Heating and Verdation 19 Instrument Air 21

Main Foodwater 24 l Main and Reheat Steam 25 Post Accident Containment Vent / Monitoring 28 Primary Sampling 30 i Reactor Coolant 32 !

Safety injection and Residual Heat Removal 35 '

4 Service Air 44 l

Service Water 45 i Waste Disposal 48 Notes 50 l

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Page 1 of 50 l

, 'it POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM l lNSERVICE TESTING PROGRAM R; vision 1 !

May 28,1991 !

i APPENDIX E i UNIT 2 VALVE PROGRAM TABLES l

! LEGEND i VALVE The plant alpha-numerical designator for the subject valve. l l

! The coordinate location of the valve on the designated drawing CORD (

i Ct. ASS The ISI classW6 cation of the valve as per the respective ISI boundary drawings, i

) !

1 CAT The valve category per Paragraph IWV 2200, !

i SIZE The valve's nominal site in inches.

TYPE The valve type !

l 3 AP Pneumatic Plot BA Ball ;

BTF Butterfly J CK Check DI Diaphragm ,

GA Gate OL Globe :

SCK- Stop/ Check SRV Safety / Relief NE Noodle (throttle) i l ACT The valve actuator type as follows: i i

AO Alr operated HO Hydraulic-operated

MA Manual valve

MO Electric motor operated i SA Self-actuated SO Solenoldgerated POS Designates the normal position of the valve during plant operation at power.

REOMT Identifies the test requirements for a valve as follows: :

t BT-C Exercise to closed position. For poweroperated valves, stroke times will be ,

measured unless excluded by an associated relief request. ,

i BT-O Exercise to open position. For power operated valves, stroke times will be measured unless excluded by an associated relief request.

i BT EE Exercise valve to verty proper operation and stroking with no stroke timo meaurements. Requ'*es observation of system parameters or loca! observation of l valve operation.

l BT PV Exercise of pneumatic pilot valve. Proper operation of the assoclated main valve vertfles operabany.

Page 2 of 'A

4 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R: vision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLES CV-C Exercise check valve to the closed posklon.

CV-O Exercise check vatve to the full open poshion.

CV-PO Partial stroke exercise check vnNe in the open poshion, CV PC Partial-stroke exercise check valve in the close direction.

FST Fai safe test INSP Disassembly arvi inspection of check varves PIT Poshion Indication verification per fWV4300 RVT Safety / Relief valve setpoint test per ASME OMa 1 SLT.1 Seat leaktate test per 10 CFR 50, App J SLT 2 Seat leakrate test for pressure isolation valves per Technical Specification 15.3.10 SLT4 Seat leaktate test for pneumatic check valves to vetWy capabsity of maintaining accumulatst pas inventory following loss of supply system pressure, SLT 4 Leaktesting of safety injection accumulator check valves SLT S Seat leakrate test to identify gross leakage. Specific leakage rates will not be measured, but leakage wHl be determined and evaluated with respect to system operabuhy and Rs capabuhy to perform its safety function.

t SLT 6 Seat leakrate test to identify gross leakage Specific leakage rates will be measured i and evaluated wkh respect to system operabutty and its capability to perform its ,

safety function.

TEST FREO The required test interval abbreviations are defirud as follows:

RR Each reactor refueling outage (cycle)

CS Cold shutdown (per Technical Specifications)

E CS Cold shutdown with Event V testing required OR Ouarterfy (during plant operation) i 1Y Once Per Calendar Year '

2Y Every 2 years i SY Every 5 years ;

10Y Every & years !

SR Prior to placing a system or component in operable status i SP Other (see applicable request for relief)

Page 3 of 50

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

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R:: vision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLES .

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REMARKS Applicatie requests for relief from Ccde requirements (see Apperdix F) are noted in the REMARKS column adjacent to the associated test requirement ard designated VRR XX. i Applicatde rues are included in the REMARKS ccdumn ard are designated NOTE XX. A list of notes is attached as the last page of the appendtx.

Cold shutdown testing justifications are provided in Apperdix G. Each ,xplanation is identified by a reference number (CSJ XX) that appears in the respectNe REMARKS column adjacent to i the pertinent le6t requirement.

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y !NT BEACH NUCLEAR PLANT INSERVICE TESTING M

- INSERVICE TESTING PROGRAM Revtson 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEFA Auxilary Feedwater DRAWING NOc M-217 VALVE CORD FUNCTION CL/.SS CAT SIZE TYPE ACT POS REOMT FREO REMARKS AF-00064 G4 2P-29 Suction 3 8 6 GA Mi !O BT-C OR AF-00100 F9 AFW to 2A S/G 2 C 3 Cr( I SA C CVO CS CSJ-1 AF-00101 G9 AFW to 28 S/G 2 C 3 CK SA C CVO CS CSJ-1 AF-00103 EB AFW to 2A S/G 2 A/C 3 CK SA C CV-O CS CSJ-1 CV-C CS CSJ-1 SLT-5 2Y AF-00105 G8 AFW to 28 S/G 2 A/C 3 CK SA C CV-O CS CSJ-t CV-C CS CSJ-1 SLT-5 2Y AF-00106 E8 AFW to 2A S/G 2 A/C 3 - CK SA C CV-O CS CSJ-1 CV-C CS CSJ-1 SLT-5 2Y AF m107 G8 AFW to 2B S/G 2 A/C 3 CK SA C CV-O CS CSJ-1 CV-C CS CSJ-1 SLT-5 2Y AF @ 108 G7 2P-29 Disch Ck 3 C 4 CK SA C CV-O CS CSJ-2 AF-00111 G5 2P-29 Suct Ck 3 C 6 CK SA C CV-PO CR CV-O CS CSS 3 AF-04000 G8 28 S/G AFWisol 3 8 3 GL MO C BT-C OR PIT 2Y AF-04001 F8 ~% S/G AFW isoi 3 8 3 GL MO C BT-C OR PTT 2Y Page 5 cf 50

m INT BEACH NUCLEAR PLANT s INSERVICE lesilNG INSERVICE TESTING PROGRAM Resis;on 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM Auxliary Feedwater DRAWING: M-217 I VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS AF44002 F6 2P-29 Minitow 3 B 1 GA AO O BT-C CS VRR-28,CSJ41 FST CS CSJ-31 m W AF44006 G5 2P-29 Ser W:r Sup 3 B 6 GA MO O BT-O CR FIT 2Y AF44020 F7 AFW to 28 S/G 3 8 3 GA MO O BT-O CR BT-C CR PIT 2Y AF-04022 E8 AFW to 2A S/G 3 8 3 GA MO O BT-O CR BT-C CR PIT 2Y AF44026 G6 2P-029 Suction Rei 3 C 1 SRV SA C RVT 10Y Page 6 of 50

90lNT BEACH NUCLEAR Pl. ANT -

INSERVICE TESTING

- INSERVICE TESTING PROGRAM Revison 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM Aux Steam. Heating Steam. ChBed aM Hot Water DRAWING NOr M-2214. Sheet VALVE CORD FUNCTION CLASS CAT StZE TYPE ACT POS REOMT FREO REMARKS HV@2G3 E2 Aux Steam to Cont 2 A 3 GA MA C SLT-1 2Y VRR-23 Passive l HV@286 C2 Aux Steam Cond 2 A 1.5 GA MA C SLT-1 2Y VRR-23 Ret Passue 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 Passue HV@637 C3 Aux Steam Cond 2 A 1.5 GA MA C SLT-1 2Y VRR-23

, Ret PassNe ,

Page 7 of 50

~'N GOINT BEACH NUCLEAR PLANT INSERVICE TES !NG RAM

- INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPEND!X E UNIT 2 VALVE PROGRAM TABLE SYSTEAt Chemcal and Volume Control DRAWING NO.: 685J175

_- _ 1 VALVE CORD FUNCTION Ci. ASS CAT SIZE ACT POS RECMT FREQ REMARKS CV@112B B6 RWST to Cit " ump 2 B 4 GA MO C BT-O OF PIT 2Y CSJ4 CV-00112C C6 VCT to Chg Pump 2 B 4 GA MO O BT-C CS PIT 2Y CV m142 C8 Charging Flow Cont ! 2 B 3 GL AO O BT-O CS CSJ-5 PST CS PIT 2Y CV-00283A B8 Chg Pump Disc Sat 2 C .75 SRV SA C RVT 10Y CV@283B B8 Chg Pump Disc Saf 2 C 75 SRV SA C RVT 10Y CV@283C A8 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 CVM300A C10 RCP SealIri Thrt! 2 A 1 NE MA T BT-C RR VRR-19 SLT-1 2Y CV-003008 C11 RCP Sea!Inj Thr:I 2 A 1 NE MA T BT-C RR VRR-19 SLT-1 2Y CV 6 C C10 RCP Seal Wtr Sup

1 A/C 2 CK SA O CV-C RR VRR-12 SLT-1 2Y CV@304D C11 RCP Seal Wir Sup 1 A/C 2 CK SA O CV-C RR VRR-12 SLT-1 2Y CV M 13 C8 RCP Seal Wir Ret 2 A 3 GA !.80 O BT-C CS CSJ4 PsT 2Y SLT-1 2Y Page 8 of 50

9OINT BEACH NUCLEAR PLANTN INSERVICE TESTING RAM

- INSERVICE TESTING PROGRAM Redsion 1 May 28,1991 APPENDIX E UNIT 2 V.ALVE PROGRAM TABLE SYSTEM: Chemical and Vdume Con:roi DRAWING NO.: 685J175 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CV40313A C9 RCP Seal Wtr Ret 2 A 3 GL AO O BT-C CS CSJ4 FST CS CSJ-6 PIT 2Y SLT-1 2Y CV40323A A9 Aux Chrging Isol 2 A 2 GL MA C SLT-1 2Y Passhe CV40323B C9 Chg HCV Bypass 2 A 2 GL MA C SLT-1 2Y VRR-23 Passive

'l CV-00331A A3 BA Xfer Pump Disch 2 A/C 2 CK SA C CV-PO OR VRR-26 CV-O RR VRR-26 CV-C CR SLT-5 2Y CV-003338 A3 BA Xfer Pump Disch 2 A/C 2 CK SA C CV-PO OR VRR-26 CV-O RR VRR-26 CVC CR SLT-5 2Y CV-00350 AS Emerg Boration 2 B 2 GA MO C BT-O CR FIT 2Y Page 9 of 50

INSERVICE TESTING RAM OlNT BEACH NUCLEAR PLANT

- INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Chemical ard Volume Control DRAWING NOc 684J741 CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION C 2 CK SA C CV-O RR VRR-24 CV-00351 AS Err.arg Boratkyi Ck 2 B6 HW';T to Chg Pump 2 C 4 CK SA C CV-O OR CV40357 C9 Charging Hdr Ck 2 A/C 3 CK SA O CV-O OR CV-00370 VRR-13 CV-C RR SLT-1 RR 2 A 2 GL AO O BT-C CS CSJ-7 CVOO371 D9 RCS Letdown iso FST CS CSJ-7 PIT 2Y SLT-1 2Y 2 A 2 GL AO O BT-C CS CSJ-7 CV40371A D9 RCS Letdown Iso FST CS CSJ-7 PIT 2Y SLT-1 2Y 2 A 3 GL MA O BT-C CS CSJ-8 CV403848 C8 Chg Line HCV Out SLT-1 2Y VRR-23 Aux Charging Iso i A 2 GL AO C PIT 2Y Passhre CV-01296 AH SLT-t 2Y Page to of 50

OINT BEACil NUCLEAR PLANT O

V INSERVICE TESTING RAM 12 - INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNI' 2 VALVE PROGRAM TABLE SYSTEM; Compnnent Cooling Water ORAWING NO.: 110E029, Sheet 1 I VA,/E CORD FUNCTION Ct_ ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CC-00738A G4 RHR Cooling Wtr .

3 8 10 GA MO C BT-O OR Sup _ ,I PIT 2Y CC 'yJ7388 G3 RHR Cooling W!* $ 3 B 10 GA MO C BT-O OR Sup PIT 2Y Page 11 of 50

INT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Component Cooling Water DRAWING NO.: 110E029. Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREQ REMARKS CC40719 G12 Cont TW Sup 2 B 6 GA MO O BT-C CS CSJ-9 PIT 2Y CC-00754A F13 RCP Og Water Sup 2 A 4 GA MO O BT-C CS CSJ-10 SLT-1 2Y PIT 2Y CC-007548 F10 RCP Og Water Sup 2 A 4 GA MO O BT-C CS CSJ-10 SLT-1 2Y PIT 2Y CC-00755A E13 RCP Og Wtr Sup 2 A/C 4 CK SA O CV-C 2Y VRR-10 Ck SLT-1 2Y VRR-23 CC@755B E10 RCP Og Wir Sup 2 A/C 4 CK SA O CV-C 2Y VRR-10 Ck SLT-1 2Y VRR-23 CC-00759A F11 RCP Og Water Ret 2 A 4 GA MO O BT-C CS CSJ-10 SLT-1 2Y VRR-23 PIT 2Y CCG759B Fe RCP Og Water Ret 2 A 4 GA MO O BTC CS CSJ-10 SLT-1 2Y VRR-23 PIT 2Y CC 00763A E12 RCP Og Wtr Ret 2 C 2 SRV SA C RVT 10Y S/R CC-007638 E8 RCP Og Wir 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 VRR@

Sun SLT-1 RR VRR-30 Page 12 of 50

1 INSERVICE TESTING

' INT BEACH NUCLEAR PLANT Revision 1 INSERVICE TESTING PROGRAM May 28,1991

. APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Component Cooling Water DRAWING NO.: 110E029, Sheet 2 1 ACT POS REOMT FREO REMARKS FUNCTION CLASS CAT S.7E TYPE VALVE CORD A 2 GL AO C BT-C OR F5 Ex LD HX Cfg Wtr 2 CC-00769 FST OR Ret 2Y PIT SLT-1 2Y l

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7_s INT BEACH NUCLEAR PLANT

- INSERVICE TESTING PROGRAM (V ')

INSERVICE TESTING Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Component Cooling Water DRAWING NO.: 110E029, Sheet 3 VALVE CORD FUNCTir 4 CLASS CAT SIZE TYPE ACT POS REOMT FREO REAMRKS CC-00724A G7 CCW Pump Disch 3 A/C 10 CK SA O CV-O OR Check CV-C OR SLT-5 OR CC@724B F7 CCW Pump Disch 3 A/C 10 CK SA O CV-O OR Check CVC OR SLT-5 OR CC-00773 F9 CCW Normal 3 B 2 GL MA C SLT-6 2Y Pass.%

Makeup CC 90779 H9 CCW Surge Tank 3 C 3 SRV SA C RtT 10Y

. Relief CC@773A H9 CCW Surge Tk Vac 3 C 1 CK SA C CV-O OR Breaker CV-C OR CC-00815 F9 CCf Emerg 3 B E GL MO C SLT-6 2Y Passive Makeup PIT 2Y Page 14 of 50

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CINT BEACH NUCLEAR PLANT INSERVICE TESTING A

!NSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SfSTEM: Containment Spray DRAWING NO.: M-110E035, Sheet 3 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI40836A F7 NaOH Supply 2 B 2 GL AO C BT-O CS CSJ-11 FST CS CSJ-11 PIT 2Y _

S140836B E7 NaOH Supply 2 9 2 GL AO C BT-O CS CSJ-11 FST CS CSJ-11 PIT 2Y SI-00840A G5 Spray Add Tank 2 C .75 SRV SA C RVT 10Y Vac Breaker SI40840B G5 Spray Add Tank 2 C .75 SRV SA C RVT 10Y Vac Breaker

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S140847A H9 Spray Add Educt 2 C 2 CK SA C CV-O OR Check SI40847B D8 Spray Add Educt 2 C 2 CK SA C CV-O OR Check SI-00858A 13 RWST to CS Pump 2 C 6 CK SA C CV-PO OR VRR-8 P14A INSP SP VRR-8 SI-008588 C3 RWST to CS Pump 2 C 6 CK SA C CV-PO OR VRR-8 P14B INSP SP VRR-8 SI40860A 11 0 CS Pump 1-P14A 2 B 6 GA MO C BT-O OR Disch PIT OR SIIJ08608 11 0 CS Pump 1-P14A 2 B 6 GA MO C BT-O CR Disch PIT OR Page 15 of 50

JINT BEACH NUCLEAR PLANT INSERVICE TESTING

- INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Containment Spray DRAWING NO.: M-110E035, Sheet 3 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI-00860C C10 CS Pump 1-P148 2 8 6 GA MO C BT-O OR Disch PIT OR SI-00860D C10 CS Pump 1-P14B 2 8 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-9 Disch SLT-1 RR VRR-23, 29 SI-008625 C11 CS Pump 1-P148 2 A/C 6 CK SA C INSP SP VRR-9 Disch SLT-1 RR VRR-23. 29 SI-00864A H11 CS Pump Test 2 A .75 GL MA C SLT-1 2Y Passive Rec!re VRR-23 S8-00864B C11 CS Pump Test 2 A .75 GL MA C SLT-1 2Y >

Passive Recirc VRR-23 SI-00870A 13 RWST to CS Pump 2 A 6 GA MO O BT-O OR P14A BT-C OR Note 3 SLT-6 2Y Note 2 PIT 2Y l SI-00870B C3 RWST to CS Pump 2 A 6 GA MO O BT-O OR i P148 BT-C OR Note 3 l SLT-6 2Y Note 2 PIT 2Y SI-00871A 15 RHR to CS Pump 2 B 6 GA MO C BT-O OR P14A BT-C OR '

l PIT 2Y Page 16 of 50

JINT BEACH NUCLEAR PLANT 'w/ INSERVICE TESTING .MM

- INSERVICE TESTING PROGRAM Revison 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Containtnent Spray DRAWING NO.: M-110E035, Sheet 3 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SIG871B C5 RHR to CS Pump 2 B 6 GA MO C BT-C OR P14B BT-C OR P1T 2Y SI-00872 G6 Spray Add Tank Saf 2 C .75 RV SA C RVT 10Y i

Page 17 of 50

(m INT BEACH NUCLEAR PLANT INSERVICE TESTING flNSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPEND 1X E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Delonized/ Reactor Makeup Water DRAWING NO.: PBM-231. Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REh%RKS DIN E2 DI Water Sup to' 2 A 2 D! MA C SLT-1 2Y Passive CorY; D14)o011 El DI Water Sup to 2 A 2 DI MA C ,

SLT-1 2Y Passive Cont Page 18 of 50

OlNT BEACH NUCLEAR PLANT U INSERVICE TESTING

- INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Heating and Ventiation DRAWING NO.: M-2215, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS VNPSEG212 G3 Cont Purge Exhaust 2 A 36 BTF AO C BT4 CS CSJ-12 FST CS CSJ-12 SLT-1 2Y VRR-23, 29 PIT 2Y VNPSE-03213 G3 Cont Purge Exhaust 2 A 36 BTF AO C BT-C CS CSJ-12 FST CS CSJ-12 '

SLT-1 2Y VP'.-23, 29 PIT 2Y VNPSE-03244 D3 Cont Purge Supply 2 A 36 BTF AO C BT-C CS CSJ-12 FST CS CSJ-12 SLT-1 2Y VRR-23, 29 PIT 2Y VNPSE-03245 D3 Cont Purge Supply 2 A 36 BTF AO C BT-C CS CSJ-12 FST CS CSJ-12 SLT-1 2Y VRR-23, 29 PIT 2Y Page 19 of 50 -

s

,mdlNT BEACH NUCLEAR PLANT INSERVICE TESTING JJ- INSERVICE TESTING PROGRAM Revision 1 May 28,1991 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 3R RM43200A F3 Cont Atmos Samp 2 A 1 GA AO O BT-C OR Retr FST OR SLT-1 2Y PIT 2Y RM43200B F8 Cont Atmos Samp 2 A 1 GA AO O BT-C OR Sup FST OR 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 Page 20 of 50

ulNT BEACH NUCLEAR PLANT b INSERVICE TESTING A f - INSERVICE TESTING PROGRAM Revision 1 i

May 28,1991

{ APPENDIX E UNIT 2 VALVE PROGRAM TABLE l

SYSTEM. Instrument Air DRAWING NO.: M-209 Sheet 7 TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT S!ZE l NC .25 CK SA C CV-O OR J IA40876 E8 Purge Viv 3244 Sup A/C QR CV-C SLT-3 2Y VRR-14 NC .25 CK SA C CV-O OR IA OO877 E8 Purge Viv 3212 Sup A/C OR l CV-C I SLT-3 2Y VRR-14 2 2 CK SA C CV-C OR IA41315 E3 Inst Air to Cont A/C 2Y VRR-23 SLT-1 l MA C SLT-1 2Y VRR-23 IA-01316 E4 inst Air to Cont 2 A 1 GA Passive 2 2 CK SA C CV-C OR IA41324 F3 Inst Air to Cont A/C 2Y SLT-1 2 A 2 GA AO O BTC OR IA-03047 E3 Inst Air to Cont FST OR SLT-1 2Y l 2Y PIT 2 A 2 GA AO O BT4 OR IA 43048 F3 last Air to Cont OR FST SLT-1 2Y PIT 2Y Page 21 of 50

/m V);NT BEACH NUCLEAR PLANT (,-)s l s INSERVICE TESTING INSERVICE TESTING PROGRAM R3 vision 1 '

May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Instrument Air DRAWING NO.: M-209. Sheet 11 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS IA41335 F4 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 IA41338 G4 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 IA-01401 H2 Purge Viv 3245 Sup NC A/C .25 CK SA C CV-O CS CSJ-13 CV-C CS CSJ-13 l SLT-3 2Y VRR-14 IA41402 H1 Purge Viv 3213 Sup NC A/C .25 CK SA C CV-O CS CSJ-13 CV-C CS CSJ-13 l SLT-3 2Y VRR-14 IA41418 F4 Nit Sup to PORV NC A/C CK SA C CV-O CS CSJ-28 CV-C CS CSJ-28 SLT4 2Y Note 1 IA-01419 G4 Nit Sup to PORV NC A/C CK SA C CV-O CS CSJ-28 CV-C CS CSJ-28 SLT4 2Y Ndet IA-01652 F4 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 Page 22 of 50

INT BEACH NUCLEAR PLANT INSERVICE TESTING M INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE .

SYSTEM: Instrument Air DRAW,NG NO.: M-209, Sheet 11 VALVE CORD FUNCTION CLASS 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

~

SLT-3 2Y VRR42 Ndel IA46308 F4 PORV Nlt St,p S/R NC C SRV SA C RVT 10Y Note 1 IA46309 G4 PORV Nit Sup S/R NC C SRV SA C RVT 10Y Note 1 IA 46310 F5 PORV 430 Nit Sup NC C GL SA O/C BT-EE CS CSJ-28 f Reg IA-06311 GS PORV 431C Nit Sup NC C GL SA O/C BT-EE CS CSJ-28 Reg Page 23 of 50

rh INT BEACH NUCLEAR PLANT INSERVICE TESTING DAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Main Feedwater DRAWING NO.: M-2202, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS CSm46GAA C2 S/G 1 A FW Ck 2 A/C 16 CK SA O CV-C RR VRR-21 SLT-6 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 CS-00476AA 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 of 50

e-(d8NT BEACH NUCLEAR PLANT '

INSERVICE TESTING

- INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Main and Reheat Steam DRAWING NO.: M-2201, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS MS-02005 G3 Main Stm Safety 2 C 6 RV SA C RVT SY MS42006 G4 Main Stm Safety 2 C 6 RV SA C RVT SY MS42007 G4 Main Stm Safety 2 C 6 RV SA C RVT SY MS-02008 G4 Main Stm Safety 2 C 6 RV SA C RVT SY MS42010 D3 main Stm Safety 2 C 6 PV SA C RVT SY MS-02011 D4 Main Stm Safety 2 C 6 RV SA C RVT SY MS42012 D4 Main Stm Safety 2 C 6 RV SA C RVT SY MS-02013 D4 Main Stm Safety 2 C 6 . RV SA C RVT SY MS-02015 HS MS Atmos Stm 2 B 6 GL AO C BT-C O Dmp BT-O O PIT 2Y MS-02016 ES MS Atmos Stm 2 B 6 GL AO C BT-C O Dmp BT-O O PIT 2Y MS-02017 G5 Main Stm isolation 2 B 30 SCK AO O BT-C CS CSJ-15 FST CS CSJ-15 PIT 2Y MS42017A G7 Main Stm Nonretum 2 C 30 CK SA O CVC CS CSJ-16 MS-02017C H6 MSIV 2017 Air Pilot NC B 1 AP K_ C BT-PV CS CSJ-17 1 MS42017D H6 MSIV 2017 Air Pilot NC B 1 AP SO C BT-PV CS CSJ-17 Page 25 of 50

INT BEACH NUCLEAR PLANT

- INSERVICE TESTING PROGRAM (V\ INSERVICE TESTING Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE ,

SYSTEM: Main and Reheat Steam DRAWING NO.: M-2201, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT PO3 REOMT FREO REMARKS MS-02018 D5 Main Stm isola!!on 2 B 30 SCX AO O BT-C CS CSJ-19 FST CS CSJ-15 PIT 2Y MS-02018A D7 Main Sten Nonretum 2 C 30 CK SA O CV-C CS CSJ-16 MS42018C E6 MSIV 2018 Air Pilot NC B 1 AP SO C BT-PV CS CSJ-17 MS420180 E6 MStV 2018 Air Pilot NC B 1 AP SO C BT-PV CS CSJ-17 MS-02019 F6 AFW Steam Supply 2 B/C 3 SCK MO C BT-O OR CV-O OR BT-C OR PIT 2Y MS42020 E6 AFW Steam Supply 2 B/C 3 SCK MO C BT-O OR CV-O OR BT-C OR PIT 2Y MS-02082 B8 Main S:eam to AFW 2 B 3 GL SA/ O BT-C OR VRR-1 Pump MA BT-O OR PR 2Y ,

MS-02083 B2 S/G Sample isol 2 A .75 DI AO O BT-C OR FST OR SLT-1 2Y PIT 2Y Page 26 of 50

rm.

INT BEACH NUCLEAR PLANT

- INSERVICE TESTING PROGRAM (d )

INSERVICE TESTING Revisicn i May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Main and Reheat Steam DRAWING NO.: M-2201. Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS MS42084 F2 S/G Sample Isol 2 A .T5 DI AO O BT-C OR FST OR SLT-1 2Y PIT 2Y MS-02090 89 SW to AFW Pump 3 8 1 GL SO O BT-O OR VRR-20 P429 FST OR MS45958 E2 S/G Blordown isol 2 A 2 GA AO O BT-C QR FST OR SLT-1 2Y PIT 2Y MS45959 B2 S/G Blowdown isol 2 A 2 G AO O BT-C OR FST OR SLT-1 2Y PIT 2Y RS-SA-10 F9 Radwaste Steam 2 B 3 GA AO O BT-C OR Supply FST OR PR ] 2Y Page 27 of 50

OlNT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM. Post-Accident Containmert Vent / Monitoring DRAWING NO.: M-224 VALVE CORD FUNCTION Ct. ASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS H2-V-04 D5 Post-Acc Purge 2 A 2 DI MA C BT-O 1Y VRR44 Disch SLT-1 2Y VRR-23 H2-V-05 D5 Post-Acc Purge 2 A 2 DI MA C BT-O 1Y VRR44 Disch SLT-1 2Y VRR-23 H2-V-06 D5 Post-Acc Purge 2 A .75 GA MA C SLT-1 2Y VRR-23 Drain PassNe H2-V-07 DS Post-Acc Purge 2 A .75 GA MA C SLT-1 2Y VRR-23 Drain Passhe H2-V-08 E5 Post-Acc Atmos 2 A .75 DI MA C SLT-1 2Y PassNe Samp H2-V-09 E5 Post-Acc Atmos 2 A .75 DI MA C SLT-1 2Y PassNe Samp H2-V-12 DS Post-Acc Svc Air 2 A 2 DI MA C BT-O 1Y VRR44 Sup SLT-1 2Y VRR-23 H2-V-13 D5 Post-Acc Svc Air 2 A 2 DI MA C BT-O 1Y VRR-34 Sup SLT-1 2Y VRR-23 H2-V-19 D5 Post-Acc Alt Vent 2 A 2 DI MA C BT-O 1Y VRR-34 SLT-1 2Y VRR-23 PassNe H2-V-20 D5 Post-Acc Alt Vent 2 A 2 DI MA C BT-O 1Y VRR44 SLT-1 2Y VRR-23

[ Passhs Page 28 of 50

INSERVICE TESTING M ODINT BEACH NUCLEAR PLANT Revision 1

- INSERVICE TESTING PROGRAM May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAivi TABLE SYSTEM: Post-Accident Corfainment Vent / Monitoring DRAWING NO.: M-224 !

ACT POS REOMT FREO REMARKS FUNCTION CLASS CAT SIZE TYPE VALVE CORD C BTO 1Y VRR-34 Post-Acc Sup Drain 2 A 2 DI MA H2-V-22 D4 2Y VRR-23 SLT-1 Passt e C BT-O 1Y VRR-34 Post-Acc Sup Drain 2 A 2 DI MA H2-V-23 D4 2Y VRR-23 SLT-1 Passte Page 29 of 50

s INT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Primary Samping DRAWING NO.: 541F448 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SC-00951 F9 Press Stm Sampe 1 A .375 GL AO C BT-C OP.

FST OR

SLT-1 2Y L PIT 2Y SC-00953 E9 Press Liq Sampe 1 A .375 GL AO C BT-C OR FST OR SLT-1 2Y PIT 2Y SC-00955 E9 Met Leg Sample 1 A .375 GL AO O/C BT-C OR FST OR SLT-1 2Y PIT 2Y SC-00959 D9 RHR Sampie 2 A _375 GL AO C BT-C OR FST OR SLT-6 2Y PIT 2Y SC-00966A F8 Press Sim Samps 1 A .375 GL AO C BT-C OR FST OR SLT-1 2Y PIT 2Y SC-00906B E8 Press Uq Sampe 1 A .375 GL AO C BT-C OR FST OR SLT-1 2Y PIT 2Y Page 30 of 50

OlNT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDlX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Primary Sampling DRAWING NO.: 541F448 I

VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SC M E E8 Leg Sample 1 A .375 GL AO O/C BT-C OR I FST OR SLT-1 2Y r PIT 2Y i

i Page 31 of 50

INT BEACH NUCLEAh t'LANT INSERVICE TESTING A INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Reactor Coolant DRAWING NO.: 541F445, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS RC-00430 HS Power 4perated Ret 1 B 2 GL AO C BT-C CS CSJ-18 BT-O CS CSJ-18 FST CS CSJ-18 PIT 2Y RC-00431C 15 Power-operated Ret 1 8 2 GL AO C BT-C CS CSJ-18 BT-O CS CSJ-18 FST CS CSJ-18 PIT 2Y RC-00434 17 Pressurizer Safety 1 C 3 SRV SA C RVT SY RC M S 16 Pressurtzer Safety 1 C 3 SRV SA C RVT SY RC-00515 15 PORV Block Valve 1 B 3 GA MO O BT-C OR Note 4 PIT 2Y ,

RC-00516 H5 PORV Block Valve 1 B 3 GA MO O BT-C OR Note 4 PIT 2Y l

Page 32 cf 50

s s

1 OINT BEACH NUCLEAR PLANT (V) INSERVICE TESTING Revision 1

- INSERVICE TESTING PROGRAM May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Reactor Coolant DRAWING NO.: 541F445, Sheet 2 TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CUSS CAT SIZE 2 A 2 DI AO O/C BT-C OR RC-00508 D2 PRT FH1 Line Iso FST OR SLT-1 2Y l PIT 2Y CVC RR VRR-11 f RC@528 D3 PRT Nitrogen Sup 2 A/C .75 CK SA O/C '

SLT-1 RR CV-C RR VRR-18 RC@529 D3 PRT Fai Line O 2 A/C 2 CK SA O/C SLT-1 RR 2 A .375 GL AO O BT-C OR RC-00538 E3 FRT Sample FST OR SLT-1 2Y PIT 2Y 2 A .375 GL AO O BT-C OR RC-00539 E2 FRT Sample l FST OR SLT-1 2Y PIT 2Y SO C - BT-O CS CSJ-19 F5 RX Vess Vent 1 B 1 GL RC-00570A PIT 2Y SO C BT-O CS CSJ-19 F5 RX Vess Vent 1 B 1 GL RC-005708 PIT 2Y GL SO C BT-O CS CSJ-19 F5 RX Vess/ Press Vent 1 B 1 RC-00575A PTT 2Y SO C BT-O CS CSJ-19 F4 1 B 1 GL RC-00575B RX Vess/ Press Vent PIT 2Y J Page 33 of 50

INT BEACH NUCLEAR PLANT INSERVICE TESTING .1AM

, INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Reactor Coolant DRAW 1NG NO.: 541F445, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS RC-00580A GS Pressurizer Vent 1 B 1 GL SO C BT-O CS CSJ-19 PIT 2Y RC-00580B GS Pressurizer Vent 1 B 1 GL SO C BT-C CS CSJ-19 PIT 2Y ,

RC-00595 D3 PRT Nitrogen Sup 2 A .75 DI MA O/C BT-C OR SLT-1 2Y i

Page 34 of 50

JOINT BEACH NUCLEAR PLANT G INSERVICE TESTING RAM

- INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPEND!X E UNIT 2 VALVE PROGRAM TABLE l SYSTEM: Safety injection and Residual Heat Removal DRAW 1NG NO.: 110E035. Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI-00830A J10 SIS Accum Relief 2 C 1 SRV SA C RVT 10Y SI408308 F10 SIS Accum Relief 2 C 1 SRV SA C RVT 10Y SI40834A H7 SIS Accum Vent 2 B 1 GL AO C BT-O CS CSJ-30 FST CS CSJ40 PIT 2Y SI-00834B D7 SIS Accum Vent 2 B 1 GL AO C BT-O CS CSJ40 FST CS CSJ-30 PIT 2Y SI-00841A H10 SIS Accum Disch 2 B 10 GA MO O BT-C CS CSJ-20 PIT 2Y SI-008418 E10 SIS Accum Disch 2 B 10 GA MO O BT-C CS CSJ-20 F1T 2Y Sl40842A H12 SIS Accum Disch 1 A/C 10 CK SA C CV-PO E-CS VRR4 Ck CV-C OR VRR4 CV-PO RR VRR4 INSP SP VRR4 SLT-4 QR VRR4 SI-00842B E12 SIS Accum Disch 1 A/C 10 CK SA C CV-PO E-CS VRR4 Ck CV-C QR VRR4 CV-PO RR VRR4 INSP SP VRR4 SLT-4 OR VRR4 Page 35 of 50

OINT BEACH NUCLEAR PLANT INSERVICE TESTING RAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety injection and Reskfual Heat Removcl DRAWING NO.: 110E035, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREQ REMARKS SI 00845A H12 SIS Cold Leg Ir; 1 A/C 2 CK SA C CV-O RR VRR-2 CV-C RR VRR-2 SLT-2 2Y VRR-22 ,

i SIM845B D12 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 Y

SI 00845C 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 SIG845D D12 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 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@845F 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 J5 Accum Nit Supply 2 A 1 GL AO C BT-C OR FST OR PIT 2Y SLT-1 2Y SI-00850A B7 Cont Sump Hyd Isol 2 B 10 GA HO C BT-O OR -

PIT 2Y Page 36 of 50

,n.

INT BEACH NUCLEAR PLANT k) INSERVICE TESTING M

- INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE 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-00850B B10 Cont Sump Hyd Isol 2 B 10 GA HO C BT-O OR PIT 2Y SI-00851A BS Cont Sump Isol 2 B l 10 GA MO C BT-O OR PIT 2Y SI408518 A5 Cont Sump Isol 2 B 10 GA MO C BT-O OR FIT 2Y SI40852A C11 RHR/LH Core 2 8 6 GA MO C BT-O CS CSJ-21 Delugo BT-C CS CSJ-21 PIT

2Y SI408528 B11 RHR/LH Core 2 8 6 GA MO C BT-O CS CSJ-21 Deluge BT-C CS CSJ-21 PIT 2Y SIC 0853A C12 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 SIf08538 B12 RHR/LH Inj Check 1 A/C 6 CK SA C CV-PO E-CS VRR-3 CV-C E-CS VRR4 CV-O RR VRR-3 CV-C RR VRR-3 SLT-2 2Y VRR-22 l

l Page 37 of 50 t

INT BEACH NUCLEAR PLANT (-)

k INSERVICE TESTING

- INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety injection and Residual Heat Removal DRAWING NO.: 110E035, Sheet 1 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SI40853C C13 RHR/ Core Deluge 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 VRR4 SLT-2 2Y VRR-22 SI-00853D B13 RHR/ Core Deluge 1 A/C 6 CK SA C CVfD E-CS VRR4 CV-C E-CS VRR-3 CV-O RR VRR-3 CV-C RR VRR-3 SLT-2 2Y VRR-22 SI-00861A C8 RHR RX Ves ini b/3 2 C .75 SRV SA C RVT 10Y SI-00866A HS SIS Pump Disch 2 B 4 GA MO O BT-O OR l BT-C OR PIT 2Y SI-00866B H5 SIS Pump Disch 2 B 4 GA MO O BT-O OR BT-C CR PIT 2Y S140867A H13 SIS Cold Leg inj Ck 1 A/C 10 CK SA C CV-PO E-CS VRR-4 CV-C E-CS VRR-4 CV-PO RR VRR-4 CV-C RR VRR-4 INSP SP VRR-4 l

SLT-2 2Y VRR-22 Page 38 of 50

NSERVICE TES11NG RAM OiNT BEACH NUCLEAR PIANT Revision 1

- INSERVICE TESTING PROGRAM May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety friection ard Residual Heat Removal DRAWING NO : 110EG35. Sheet 1 SIZE TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT CK SA C CV-PO CS VRRJ E13 SIS Cold Lg inj ck A/C 10 SI406678 1 CV-PO E-CS VRR4 CVO E-CS VRR4 CV-PO RR VRR4 CVO RR VRR4 i

iNSP SP VRR4 l SLT-2 2Y VRR-22 l 2 75 CK SA C CVO OR SIC 0875A F7 SIS Test Recirc Ck A/C CV-C OR

' SLT-S 2Y SI408758 F7 SIS Test Recire Ck 2 AfC .75 CK ! SA fC CVO OR OR CVO l SLT-5 2f l C BTC CS CSJ22 D12 RX Vessel Safety fri 2 B 2 GL MO

( SIO0878A BTC CS CS322 PIT 2Y B 2 GL MO O BT-O CS CS123 SI-008788 D12 S S Loop inj 2 BT-C CS CS123 PIT 2Y 2 GL UO C BTC CS CSS 22 SI-00878C G12 RX vessel Safety inj 2 B BT-C CS CSJ22 FIT 2Y B 2 GL MO O BT-O CS CS123 SI-00878D H12 SIS Loop snj 2 BT-C CS CS123 P!T 2Y Page 39 of 50

INSERVICE TESTING RAM jO NT BEACH NUCLEAR PLANT Revision 1 INSERV!CE TESTING PROGAAM May 23,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety injection and Residual Heat Removal DRAWING NO_: 110E035. Sheet i TYPE ACT POS REOMT FREO RELMRKS VALVE CORD FUNCTION CLASS CAT S!ZE 2 C .75 SRV SA C RNT 10Y SIGS87 F6 Tes: Une S/R

! STO CS CSJ M N2 Supply Vent / Ret 2 A 1 GL AO C SI@957 16 CS CSJ M FST SLT-1 2Y

- PIT 2Y Page 40 of 50

INSERVICE TESTING M e INT BEACH NUCLEAR PLANT Revisico 1 INSERVICE TESTING PROGHAM 1

May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety injecton and Residual Heat Remcwal DRAWING NO.: 110E035. Sheet 2 CJ7F TYPE ACT POS REOMT FREO REMARKS VALVE CORD FUNCTION CLASS CAT SIS Pump Sucuon 2 B 12 GA MO C BT-O OR SI40825A HS PfT 2Y I

2 B 12 GA MO C BT-O OR SI408258 H5 SIS Pump Sucuan FIT 2Y GA MO C BT-O CS CSJ-24 SI40826B J7 SIS Pump Rendunt 2 B 8 BT-C CS CSJ-24

(

Suct PIT 2Y i

MO C BT-O CS CSJ-24 Slo 0826C 17 SIS Pump Rendunt 2 B 8 GA BT-C CS CSJ-24 1 Suct M W l CK SA C CV-O RR VRR4 ;

SI40854A E4 RHR Pump Suct Ck 2 A/C to RR VRR-6 CV-C SLT4 RR VRR4 CK SA C CV-O RR VRR4 E4 RHR Pump Suct Ck 2 A/C 10 SI40854B CVC RR VRR4 SLT4 RR VRR4 l 2 B to GA MO O BT-C OR Si40856A E4 RHR Pump Suct FIT 2Y OR 2 B 10 GA MO O BT-C SI-008568 E4 RHR PUMP Suct PET 2Y 6 GA MA C BY-O OR SI40857A G8 i's to SIS Pump 2 B Suct RHR te SIS Pump 2 8 6 GA MA C BT-O OR S1408578 G7 Suct 1.

Page 41 cf 50

m INT BEACH NUCLEAR PLANT v } INSERVICE TESTING INSERVICE TESTING PROGRAM Revtscn 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety Irjection ard Residual Heat Remova!

DRAWING NOc 110E035, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS S!40889A 11 0 SIS Pump Dicch Ck 2 C 6 CK SA C CV-PO OR VRR-7 CV-O RR VRR-7 l

S140889B H10 SIS Pump Disch Ck 2 C 6 CK SA C CV-PO OR VRR-7 g CV-O RR VRR-7 SI40891A G9 SIS Pump Mini-rec 2 C 2 CK SA C C/-PO OR VRR-27 Ck INSP SP VRR-27 SI408918 G9 SIS Pump Mini-rec 2 C 2 CK SA C CV-PO OR VRR-27 Ck INSP SP VRR-27 l

SI-00895 MS SIS Pump Mini-Rec 2 C 2 CK SA C C/-O OR Ck SI-00896A 17 SIS Pur p Suction 2 8 6 GA MO O BT-C OR PIT 2Y SI-008968 H7 S!S Pump Suction 2 8 6 GA MO O BT-C OR FIT 2Y SI-00897A 12 SIS Test Line Ret 2 A 2 GL AO O BT-C CS CSJ-25 FST CS CSJ E SLT-5 2Y PIT 2Y SI408978 H2 SIS Test Line Ret 2 A 2 GL AO O BT-C CS CSJ-25 FST CS CSJ-25 SLT-5 2Y Pir n Page 42 of 50

i f INSERVICE TESTING 4

' INT BEACH .'JUCLEAR PLANT Revisicn 1 INSERVICE TESTING PROGRAM May 28,1991 APPENDIX E f UNIT 2 VALVE PROGRAM TABLE SYSTEM: Safety injection and Residual Heat Removal l

DRAWING NO.: 110E029. Shee: 1 t .

REOMT FREO IT REMARKS .

CORD FUNCTION CLASS CAT SIZE TYPE l ACT POS VALVE 2 C 8 CK SA C CV-PO OR I RH@710A E4 RHR Pump Disch '

CSJ-26 I Ck CV4 CS C 8 CK SA C . CV-PO CR RH@710B B4 RHR Pump Disch 2 CSJ-15 CV-O CS Ck 8 GA MA C SLT-5 2Y RH@742 H6 RHR/P.WST Isol 2 A 2 GL MA C SLT-5 2Y H6 RHR/RWST isol 2 A RH-00742A AO O PIT 2Y Note 2 RHR HX Oudet 2 B 8 BTF RH@624 G7 Note 2 RHm625 G7 RHR HX Outlet h2 B 8 BTF l AO O PIT 2Y Page 43 of 50

INT BEACH NUCLEAR PLANT \ INSERVICE TESTING Iw INSERVICE TESTING PROGRAM Reviszon 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGFsAM TABLE SYSTEM. Safety injection ard Residual Heat RemoratSYSTEM Ser. ice Air DRAW NG NO.: M-209, Sheet 2 VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FF.EO REMARKS SA@015 F4 Sennce Air Cont 2 A 4 GA MA C SLT-1 2Y Passive Sup SA m017 F4 Sennce Air Cont 2 A/C 4 CK SA C C/-C OR Sup SLT-1 2Y l

Page 44 of 50

INT BEACH NUCLEAR PLANT INSERVICE TESTING M INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE '

SYSTEM Sennce Water DRAWING NO.: M-207 Sheet i VALVE CORD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SW40112A G7 SW TO AFW PP 3 C 1 CK SA O CV-PO OR VRR-15 P429 INSP RR VRR-15 l

SW-02976 88 Spray PP Room 3 8 2 GL SO O FST OR See Unt 1 T/C H&V System 1

I I,

Page 45 of 50

m w

INT BEACH NUCLEAR PLANT INSERVICE TESTING G INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Serwce Water DRAWING NO2 M-2207 Sheet 1 6

VALVE COrtD FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARKS SW-02S17 C6 WT Service Wtr Irdet 3 8 6 GA MO O BTC OR PIT 2Y SW-02880 CS Turb Hall Crs in 3 8 6 GA MO O BT-C CS CSJ-27 PIT 2Y F

j l h

-l l

Page 46 of 50

'\

INT BEACH NUCLEAR PLANT (d

\ INSERVICE TESTING Revision 1 INSERVICE TESTING PROGRAM May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SY5 TEM: Service Water DRAW 1NG NO.: M-207. Sheet 4 4

ACT POS REOMT FREO REkMRKS FUNCTION 8 A'>S CAT SIZE TYPE VALV2 CORD C 8 CK SA O CV-O CR I SW40015A G8 Cont Or Supply Ck J C 8 CK SA O CV-O OR SW400158 GG Cont Or Supply Ck 3 8 3 C 8 CK SA O CV-O OR SW40015C G7 Cont Or Supply Ck C 8 CK SA O CV-O OR SW40015D G7 Cont Or Supply Ck 3 8 12 GA MO C BT-O OR SW42907 C8 Cont Or Emerg 3 PIT 2Y ,

Flow l B 12 GA MO C BT-O OR SW42908 C7 Cont Or Emerg 3 2Y l

PIT Flow SRV SA C RVT 10Y ,

E8 Cont Or Disch S/R 3 C 1 S'N42959 SRV SA C RVT 10Y SW-02963 E6 Cont or Disch S/R 3 C 1 SRV SA C RVT 10Y E7 Cont Or Disch S/R 3 C 1 SWC2967 SRV SA C RVT 10Y SW42971 E6 Cont Or Disch S/R 3 C 1 SRV SA C RVT 10Y E5 Cavt:y Or Ret S/R 3 C 1 SW44300 SRV SA C RVT 10Y SW-04301 E5 Cavity Or Ret S/R 3 C 1 Page 47 of 50 '

OlNT BEACH NUCLEAR PLANT INSERVICE TESTING INSERVICE TESTING PROGRAM Revtson 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Waste Disposal DRAW 1NG NO.: 684J971, Sheet 1 VALVE CORD FUNCTION CLASS l CATS!ZE TYPE ACT POS REOMT FREO REMARKS SF40816 C6 P-033 RWCP 2 A 2 DI MA C SLT-1 2Y VRR-23 Suction Passive WL-01003A RCDT Pump A 3 DI C6 2 AO O/C BT-C OR Suction FST OR SLT-1 2Y VRR-23 PIT 2Y WL-010038 C6 RCDT Pump 2 A 3 DI AO O/C BT-C OR Suction FST OR SLT-1 2Y VRR-23 PIT 2Y WL-01698 C6 RCDT to B -19' 2 A 2 DI AO C BT-C QR Sump FST OR SLT-1 2Y VRR-23 PIT 2Y WL41721 C6 RCOT Pumps Suct 2 A 3 DI AO O/C BT-C QR Con FST OR SLT-1 2Y PIT 2Y VA-01723 C6 Containment Sump 2 A 3 DI AO O/C BT-C CR Dr FST OR SLT-1 2Y VRR-23 PIT 2Y WL-01728 C6 Contenment Sump 2 A 3 G; AO O/C ST-C OR Dr FST OR SLT-1 2Y VRR-23 PIT 2Y Page 48 of 50

INSERVICE TESTING INT BEACH NUCLEAR PLANT Revision 1 INSERVICE TESTING PROGRAM May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE SYSTEM: Waste Disposal l DRAWING NO.: 684J971. Sheet t POS REOMT FREO REMARKS FU'NCTION CLASS CAT SIZE TYPE ACT VALVE CORD A DI AO O BT-C OR WG-01786 B5 RCDT Vent 2 1 FST OR SLT-1 2Y PIT 2Y A DI AO O BT-C OR WG-01787 85 RCDT Vent 2 1 FST OR SLT-1 2Y PIT 2Y 2 A .75 DI AO O/C BT-C OR WG41788 B5 RCDT Sample FST OR SLT-1 2Y PIT 2Y 2 A .75 DI AO O/C BT-C OR WG-01789 B5 RCDT Sample FST OR SLT-1 2Y P!T 2Y Page 49 of 50 E

INT BEACH NUCLEAR PLANT j INSCRVICE TESTING

~ INSERVICE TESTING PROGRAM Redsion 1 May 28,1991 APPENDIX E UNIT 2 VALVE PROGRAM TABLE NOTES

1. These valves and their respective test requirements are included in the IST Program for information and tracking purposes only. They do not necessarfy meet the rec;urements for inclusion per IW/-1100, but are identfed for testing per NRC Genenc 1.etter 9046. TM the tests specFed must not necessarly satisfy the corresponding requirements of Subsection IW/ or f**RC Generic Letter 8904

2. (11490) Physical modfications are required to aDow testiry Testing wil commence upon compietion d modications.

3. (11-08-90) These valves fa5 in a position opposae of that regured Manual stroke capability win be derr6%.ieri If a PORV is isolated in accordance with Technical Specfcatioins, the associated block valve wiD be exercised at cold shutdown.

l4.

i Fage 50 d 50

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Rsvision 1 MBy 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF i UNITS 1 AND 2 TABLE OF CONTENTS VALVE REUEF REQUESTS VRR NUMBER COMPONENT PAGE NUMBE8 1

1 MS42082 2 2 SI40845, A through F 3 i 3 S140853 A through D 4 :

4 SI 00067 A&B, SI 00842 A&B 5 !

5 All valves tested during cold shutdown conditions 8 ;

6 SI 00854 A&B 9 7 SI 00889 A&B 10 8 SI 00858 A&B 11 9 SI 00862 A&B 12 7 10 CC40755 A&B 13 ,

11 RC-00528 14 12 CV40304 C&D 15 2 13 CV40370 10 14 IA40644,645,1280,1281 (Unit 1) lA40876,877,1401,1402 (Unit 2) 17 15 SW 00112A (Unit 2), SW40135A (Unit 1) 18 16 RM 03200AA 19 17 DA43057 A&B, DA43058 A&B 20 18 RC-00529 21 19 CV40300 A&B,2-CV 00300 A&B 22 1 20 1 MS42090,2 M942090 23 21 CS 00406 AA&BB, CS40476 AA&BB 24 22 SI 00845 A through F S!40853 A through D, S!40807 A&B 20 23 Containtnent isolation Vanes Per Table VR 51 27 24 CV40351 29

' 25 DA40125, DA40126, DA40225, DA40226 DA46316 A&B, l DA-06317 A&B, DA46318 A&B, DA46319A&B 30 26 CV 00333A&B 31 27 S140891 A&B 32 28 AF-4002, AF 4007, AF 4014 33 29 Valves 6' NPS and larger subject to leakage rate testing per 10 CFR 50, Appendix J 34 30 1 CC-00767,2-0040767 35 31 HV 00898A, HV40900A, HV 00914A, HV 00916A 36 32 1 IA41206,1 lA41209,1 IA41600, and 1 IA-01000, 2 IA-01335,21A41338,1 IA 01652, and 1 IA41653 37 33 FO-03940 and F043941 38 34 H2 V44, H2 V 05, H2 V.12, H2 V 19. H2 V 20. H2 V 22, H2 V 23 i for Unit 1 and for Unit 2 39 t

Page 1 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Rcvision 1 May 28,1991 I

O APPENDIX F V VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 1

.61SIEbt Various COMPONENTQ; MS-02082

.CATEGOB'C Various FUNCTION: This is a generic Request for Relief SECTION XI REQUIREMENT:

If, for power operated valves, an increase in stroke time of 50% or more for valves with full. stroke timos loss tien or equal to 10 seconds is observed, the test frequency shall bo increasod to once each month until cort.:tive action is taken, at which time the original test frequency shall be resumod. (IWV 3417(a))

BASIS FOR REllEF:

The stroke time moat.urements takon during testing of fast acting valves (those loss than 2 seconds) are subject to considerable variation due to conditions unrelated to the material condition of the valvo (eg. toat conditions, O operator reaction time). In accordance with Reference 2.0, Position 6, an attemate method of evaluating stroke times is considered acceptable.

ALTERN ATE TESTING:

The stroke time evaluation for those valves designated in the IST Program Valva Tables (Appendices D & E) as

' fast-acting

will not account for successive in:reases of measured stroke time por IWV 3417(a) with the change in test frequency as requirod. In lieu of this, t.he assigned maximum limiting value of stroke time will be establishod at two seconds. Upon exceeding the two-second limit, a valve will be declared inoperable and corrective action taken in accordt.nce with IWV-3417(b).

l O

V Status: IST Program 1980; Submitted as VRR-0 (Approved via Gl. 8944)

Page 2 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR.2 SYSTEM: Safety Injoction (110E017, Sh 1 /110E035, Sh 1)

, COMPONENTS: Sl40845, A through F CATEGORY: A/C FUNCTION:

Those valvos opon with differential pressure to provide flowpaths from the safety injoction pumps to the reactor coolant system for emergency coro coolint They close to provent backtow trom the associated SIS Accumulators and from the low-pressure safety injoction system should portions of a traln becomo f aulted. In the normally closod position, they p'avHo pressure isolation from the reactor coolant system.

,$ECTION XI REQUIREMENT:

Chock valves shall be exeylcod at least onco overy 3 months, except as provided by IWV 3522. (IWV-3521)

BASIS FOR RELIEF:

Full stroke exercising of those valves would require operating a safety injection pump at nominal accident flowrate and injecting into the reactor coolant system r,Ince no full flow rocirculation path exists. During normal operation the safety injection dischargo pressure of 1500 psig is insufficient to evercome reactor coolant system pressure. During shutdown conditions, Injoction v!a the SIS pumps is precluuod by rostrictions related to low-temperature over-pressurization protection concems in accordance with Tochnical Specifications, Soction 15.3.15.B.

The lack of a recirculation flowpath procludos partial stroking during operation and cold shutdown conditions.

These are simple chock valvos with no external means of position indication, thus the only practical means of verifying closure is by performing a leak test or backtow test. Such testing requires that the valve first be taken e out of its safety position whon it may operationally be left undisturbod, i.e., moved sofoly for test purposes. This roduction in plant safoty is not warrantod. Additionally, such testing occurs in radiation areas, thereby incrossing

. personnel radlation exposure.

ALTERNATE TESTING; At each roactor refuol lng outage those valves will be full 4troke exercised to the open position.

Valvo seat leak testing will be performed in accordance with Point Beach Technical Specification 15.3.10,

'Roactor Coolant Syste,m Prossure Isolation Valve Leakage Tests.*

O Status: IST Program 1980; Submittod as VRR.2 (Approved via GL 8944)

Page 3 of 39

POINT BEACH NUCLEAR Pl. ANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R: vision 1 May 28,1991

( APPENDIX F V] VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 3 sy3IDM; Safoty injection (110E017, Sh 1 /110E035, Sh 1)

. COMPONENTS; Sl40853 A through D CATEGORY: A/C FUNCTION; Valvos Sl40853A&B opon with differential pressure to provkje flowpaths from the low hoad safety injection pumps to the toactor vossd for omorgency coro cooling. Valvos SiODB53C&D open with differential pressure to provkfe flowpaths from the low and high hoad safety injection pumps to the roactor vessel for emergency coro cooling. In the closod position, they provkje pressure isolation from the roactor coolant system.

SECTION XI REQUIREMEffl; Chock vatves shall be exorcisod at least once overy 3 months, except as providod by IWV 3572. (lWV 352t)

BASIS FOR REUEF;

('

Full or partial stroking during normal oporation is not possitie because low-hoad safety injoction pump dischargo pressure is insufficiont to overcomo reactor coolant system pressure. Even If pump dischargo pressure were adoquate, any stroking would cause the injection of cold tWated water into the system, resulting in power and thermal transients.

Stroke testing the subject valvos during cold shutdowns is possitdo, however, not destratAo untoss

Evert V* leak testing is also schodulod. The *Evont V* testing assures valve Integrity, thus minimlzing the possibility of an inter-system I.OCA which bypassos containment. Exorcising those valves during ovory cold shutdown may reduce the assurance thr.t a valvo Is, in fact, property soated, as estaldished via the

Event V' testing.

ALTERNATE TESTINQ; Those vatves will be full stroke exorcised during pump full flow testing performod during refueling. In addition, they will bo full stroke exercisod during cold shutdown porlods when periormance of

Event V' valve testing is regul'od.

Soat leakage testing will be performed in accordance with Point Beach Technical Specification 15 3.16, *Roactor Coolant System Pressure Isolation Valve Loakage Tests.*

v Status: IST Program 1900; Submittod as VRR-3 (Approvod via GL 8904)

Pago 4 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R:; vision 1 i

May 20,1991 G APPENDIX F h VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF RLOUEST NO. VRR 4 SYSTEM; Safety injection (1?0E017. Sh 1 /110E035, Sh 1)

COMPONENTS: S140007 A&B SiOOS42 A&B

.CATEGQBL A/C FUNCTION; Theso valves open with differentlat pressure to provida flowpaths from the safety injoction pumps and/or the Si accumulators to the reactor coolant system cold logs during an accident. They are normally closed in the closed position they sorvo as roactor coolant system pressure isolation valves.

ECTION XI REQUIREMENT:

Chock valves sMll be exorcisod at least once every 3 months, except as provided by liW 3522. (LYN 3521)

D ASIS FOR REUEF;

/ During normal operation, neithor safety injection pump d schargo pressure of 1500 psig nor accumutator pressure of 700 psig, are sufficlont to overcome reactor (oolant system pressure. Full or partial stroke testing is, therefore, not possible.

During cold shutdown, partial or full stroke testing of valves SiOO867A, SICOS42A, and SI-00842B via the uso of the accumulators or safety injection pumps is not perm!!tod so as to provent the possibility of a low-tomporature crvor pressurlzation event. Partial stroking of S1408670 is however, possido using the RHR pumps.

A full stroke test by dumping the accumulator to the reactor coolant system could be possible during refueling when the reactor vossol head is removed, but the volumo .ard flowrato required for the test could result in damage to the core internals There is also the potential ci forcing a nitrogon bubblo into the reactor coolant system piping ard refueling cavity resulting in possible safety implications which makes this testing concept inadvisable.

BASIS FOR EXTENDED INSPECTION INTERVAL:

Our response to NRC Gonoric Lotter (GL) 0904 containod a justification of the long frequency surveillanco intervals for 1 SICOS42A8B,1 Slo 0067A, and 2 Sl40&42A&B, ard 2 SICODG7A Valves 1 SICOS42A,1-St.

00067A&B,2 SI 00B42A, and 2 S140007A&B are oponod and inspected every ten (10) years. Valves 1-

$140842B ard 2-Slo 08420 are not porkdically opened and inspected because they require a complete core offload and RCS draindown.

The NRrt in pc$ltion 2 of GL 0944, requestod three items of information to support extension of the valve dis 4 Uy/ inspection Intervals to longer than once every six years. Two of these items, rev'ow of industry

/ erpance ard review of the Installation of each valve, were addressed in the response to th9 generic letter.

(s Since this information is current, no additional response is necessary.

P9ge 5 of 39

POINT DEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R: vision 1 M y 28,1991 APPENDIX F

[

x VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 The third item requires a dir.assomtdy ard Inspection of each valve in the valve group. Valves 2 Slo 0842A ard 2 Sl40067A were disassomtiod in 1987. Valve 2 S1442B was not disassemblod for the reasons presented above in the tusis dlscussion.

In response to NRC Information Notice 8845, in 1989 the retalning tdock stixt: in each of the valvos in Unit 2 wore replacod, ard in the procosa cach of those vatves was disassomtdod and inspoetod for froodom of motion as por the regulromonts of NRC Generic Lottor 8904, Position 2.

During all inspections that have been performod on these valvos to date, no defects have boon discover (d that would signify that they were not fully functional and capatie of performing their requirod function to full stroke.

Those vatves have now performed acceptatdy at Point Beach for over 19 years with no indications of degradation. This is in agreomont with industry experience that shows those valvos to be extremoly rollatdo.

The extended frequency inspection is, therefore, conskjerod to be adoquate with respect to the capability of offectNoly detecting valve degradation.

The above justification satisfies the NRC's guidolinos for exterding the frequency for valvo disassomtWy and inspection. It does not specifically Wdress our nood for exterding this frequoney, however. This nood is based on such factors as man hours required to periorm this work, radiation exposure recotved, offect or potential offect or plant operation, and the cost twnotit value of the additional Inspections.

O I S ALTERNATE TESTING:

U The following attornate testing will be performtd:

1, At a minimum for those valves, partlal open and shut stroke losts will be done at each refueling outage.

For $100867B only, a partlat opon stroke test will be performod during any cold shutdewn which utill20s an RHR pump. In addition for those valves, partial open and shut stroke tests will be conducted at each cold shutdown which toquires an Event V test. (See Technical Spocification 15 3.10.)

2. Seat leakage tests of Sl40807A and S1408670 will be performod in accordance with Point Beach Technical Specification 15.3.16, 'Roactor Coolant System Pressure Isolation Valvo Leakago Tests.'

3 Seat leakage tests of Sto0842A ard S100842B will be performod quartorty coincident with the SI pump tests. A seat leakage rate of 5 gpm or less will be considered acceptatWe.

4, At least once within each 120 month inspection interval, valves 1 Slo 004?A,2 Slo 0042A,1 St-00067A&B, and 2 SICOS67A&B will be opened and their discs will be checkod to verify froodom of movernent. The inspections will be staggered such that one valve from the group of six (including both Unit 1 ard 2 valvos) will be inspected approximately every two to three years.

If a condition is discovered during an inspection of a given valve that would have provented it from stroking full opon, the inspection sample will be exparded. A second identical chock valve In the same unit will be opened and inspected. Also, during the next refueling outage on the opposite unit, the sister vatv :o the InoperatAo valve will be inspoctod. If a socord valve is fourd inoperable in the expand (d sample, all six (6) romalning valves from the group of eight (8) like valves will bo inspected.

If the inspection must be exparded to include all olght valves, the inspections of those valves in the unit which is not in a refueling shutdown condition shall be performed during the next regulariy sch(dulod refueling shutdown. l Page 6 of 39

1 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM i INSERVICE TESTING PROGRAM Revision 1 l May 28,1991 [

i 3

APPENDIX F i VALVE PROGRAM REQUESTS FOR RELIEF 4

UNITS 1 AND 2 FIGURE VRR41 i St ACCUMULATOR CHECK VALVES !

d !

i SArtty INsCC TION !

ACCVMULAfoR 'A' L h

FROM

' SiPUMPS '

l M

-/(

l C L SI 667A SI-8 42A SI-8 41 A l

SAFETY INJECT \ON ACCUMULATOR 'B'

, RHR SUPPLY

, FROM Sl PUMPS M

l Ce"<s '.

/

SI-8678

/

SI-8428 X

St-8418 Status: IST Program 1990 l

Page 7 of 39

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

i POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 e APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO, VRR 5 SYSTEM: Various

, COMPONENTS: All valvos tosttd during cold shutdown corditions.

. CATEGORY: Various FUNCTIOft Various

.SECTION XI REQUIREMENT:

Valves shall be exorcist 4. . unless such operation is not practical during plant operation. If only limited operation is practical during plant operation, the valvo shall bo part stroke oxercisod during plant operation ard full stroke exercisod during cold shutdowns Full stroke exercising during cold shutdowns for all valvos not full-stroke exercised during plant operation shall be on a frequoney determinod by the intervals betwoon shutdowns as follows:

For intervals of 3 months or longer exerciso during each shutdown. (liW 3412 and IWV 3522)

C

( BASIS FOR REllEF:

N.

In many Instancos testing of all valvos designated for testing during cold shutdown cannot o0 completed due to the brevity of an outage or the lack of plant condhlons neodod int testing 6pocific valves. It has been the policy of the NRC that if testing commences in a reasonable time and reasonable effons are mado to tost all valves, l then outage extension or significant changes in plant conditions are not requirod when the only reason is to provide the opportunity for completion of valve testing. l 1

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 bolow.

ALTERNATE TESTINQ; For those valvos designated to be exercisod or testtd durl'ng cold shutdown, exercising shall commence as soon as practical after the plant roaches a stable cold shutdown condition as definod by the applicable Technical Specification but no later than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after roaching cold shutdown. If an outage is sufficiently long enough to provide for testing of all valvos required to be testod during the cold shutdown period, then the 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months requirement nood not apply if all valves are lostod during the outage. Valve testing nood not be performed more often than once overy three (3) months except as provided for in IWP-3417(a) Completion of all valve testing during a cold shutdown outage is not requirod if plant conditions preclude testing of spacific valvos or if the length of the shutdown porlod is insufficient to complete all testing. Testing not completod prior to startup will be rescheduled for the next cold shutdown in a sequence such that the test schodule does not omit nor favor cortain valves or groups of valvos, For the purpose of this toquiremont, the term ' cold shutdowif refers to the respective condition as definod in the Technical Spectications. The program tables identify those valvos to ;

which cold shutdown testing applies.

E ;

k Status: IST Program 1990 Page 8 of 39 l

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM RWsion 1 May 28,1991 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. S1-00854 A&B

.C61E.GDRY.; A/C

_ FUNCTION; Those valvos open with differential prossure to provide flowpaths from the Refueling Wator Storage Tank (RWST) to the suctions of the Rt.sidual Hoat Removal (RHR) Pumps for low head safety injection into the reactor vossol.

During post-LOCA rocirculation, they close to prevent sump water from returning to the RWST.

SECTION XI REQUIREMENT:

Chock valves shall be exorcisod at least once overy 3 months, except as provklod by liW-3522. (liW 3521)

B ASIS FOR REUEF:

(t Valve stroking is not possible during normal operation because the RHR pump discharge pressure la insuff6clent to overcome reactor coolant system pressure during normal operation, During cold shutdown periods, full stroke testing of these vatves is not possible because the reactor coo l ant system does not contain a suff'clont expansion volume and there is no retum flowpath to the refueling water storage tank for recirculation.

ALTERNATE TESTING; At least once during each reactor refueling these vatves will be full. stroke exorcised (open and closod) and their leak tight integrity vertflod by means of a seat leak test.

O Status: IST Program 1980; Submittod as VRR4 (Approvod via GL 8904)

Page 9 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Rsvision 1 May 28,1991 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: S100889 A&B

. CATEGORY: 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.

SECTION XI REQUIREMENT: -

Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)

SASIS FOR REUEF:

F'Jil 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 pump discharge pressure of 1500 psig is insuNicient to overcome reactor coolant system pressure. During cold shutdown conditions, injection via the SIS pumps is precluded by restrictions related to low temperature over pressurization protection coteerna.

ALTERNATE TESTING:

These valves will be part stroke exercised quarterly, At taast once during each reactor refueling outage these valves will be full stroke exercised to the open position.

\

Status: IST Program 1980; Submitted as VRR 7 (Approved via GL 0944)

Page 10 of 39

. POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Rtvision 1 ;

i May 28,1991 APPENDlX F

VALVE PROGRAM REQUESTS FOR RELIEF

UNITS 1 AND 2 i !

RELIEF REQUEST NO. VRR 8 SYSTEM: Containment Spray (110E017, Sh 3 /110E035, Sh 3)

COMPONENTS: Sl40858 A&B i I

, CATEGORY: C FUNCTION:

These valves open whh differential pressure to provkfe flowpaths from the refueling water storage tank to ths ;

suctions of the containment spray pumps.

. SECTION XI REQUIREMENT:

Check valves shall be exercised at least once every 3 months, except as provkfod by liW-3522. (IWV-3521)

JASIS FOR RELIEF:

Full stroke exercising of these valves would require operating the containment spray pumps at nomiral accident flowrate and spraying into the containment building since no full flow recirculation path exists. This is obviously Impractical ard undesirable.

ALTERNATE TESTINQ; These valves will be part. stroke exercised during plant operation.

Each of these valves will be disassembled ard Inspected for operability during refueling shutdowns.

t i

Status: IST Program 1930; Submitted as VRR-8 (Approved via GL 8944)

Page 11 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F Os VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 HEUEF REQUEST NO. VRR 9 SYSTEM; Containment Spray (110E017, Sh 3 /110E035, Sh 3)

COMPONEtflA; SI 00N12 A&D

.QAIEQQRY,; A/C f.utfCIl0E Those valvos open with difforontial pressure to provkio flowpaths from the refueling water stora00 tank to the suctions of the containment spray pumps.

In the closed position, these valvos r,orve as containment isolation valves.

SE.QIlQN XI REQUIREMENT:

Chock valves shall be exercisod at least once every 3 months, except as provided by IWV 3522. (IWV-3521) 3 ASIS FOR REllEF:

Full or part stroke exorcising of those valves would require operating the containment spray pumps at nominal acckler't flowrate and spraying into the containment building since no recirculation path is available. This is obviously impractical and undestratie.

Those are simpio chock valves with no external means of position indication, thus the only practical means of vortfying closure la by performing a leak test or backflow test. Performing such tests of those valvos involves considerable effort ard system realignment such that routlno testing during plant operation or cold shutdown outages is impractical.

ALTEHNATE TESTINQ; During reactor refuoling outagos these valvos will be seat leak tested in accordance with 10 CFR 50, Appendtx J.

Those valvos will be disassembled and inspected for operability at reactor refueling outages.

Status: IST Program 1900; Submittod as VRR 9 (Approved via GL 8904)

Page 12 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 10 SYSTEM: Component Coolbg Water (110E018, Sh 2 /110E029, Sh ?)

COMPONEffIj; CC40755 A&B CATEGORY: t/C FUNCTION:

These valves opon to provide flowpaths for cooling water to the reactor coolant pumps (RCP's are non safety rotated) ard close to provide containment isolation for the component cooling water sy. tem in the event of an accident.

.SECTION XI REQUIREMENI; Chock vatves t. hall be exercised at least once overy 3 mor,ths, except as provklod by IWV 3522 (IWV 3521)

BASIS FOR REUEF:

These are simplo chock valves with no external means of poshion indication, thus the only practical means of verifying closure is by performing a leak test or backflow test. During plant operation, such testing would requiro securing the RCP's which is not practical. Periorming such tests of those valves involvos considerable effort and system to alignment such that routine testing during cold shutdown outages is impractical.

ALTERNATE TESTING:

These *.alves will be exercisod to the closed position during seat loak tests performod in accordance with 10 CFR 50, Appendtx J.

Status: IST Program 1900; Submitted as VRR 10 (Approved via GL 8944) i l

Page 13 of 39

l

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F c VALVE PROGRAM REQUESTS FOR RELIEF i UNITS 1 AND 2 REUEF REQUEST NO. VRR.11 SYSTEM: Reactor Coolant (541F091 Sh 2 / 541E445, Sh 2)

COMPONEN1.$; RC40528 j CATEGORY: A/C l

)

EUNCllON, These valves open to provide flowpaths for nhrogen supply to the pressurizer rollet tanks (PRT's are non safety ,

related) and close to provide containment isolation for the nitrogen system in the event of an accident, i 1

SECTION XI flEQUIREMENT:

Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV 3521)

BASIS FOR REUEF:

Because nKrogen makeup to the PRT is seldom required, these valves are normally closed. These are simple 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 involves considerable effort ard 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 full stroke exercised to the closed position and seat leak tested in accordance with 10 ra ' 50, Appendtx J. .

Status: IST Program 1980; Submitted as Vr'.R 11 (Approved via GL 8944)

Page 14 of 39

4 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Rsvision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 1.

i SYSTEM: Chemical and Volume Control (684J741 / G85J175)

COMPONENTS: CV-00304 C&D 4

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 IVN-3522. (IWV 3521)

BASIS FOR REUEF:

These valves are normally opon. They are simple check valves with no external means of position Indication, thus the only practical means of verifying closure is by porforming a leak test or backtow test. During plant i operation, such testing would require securing the RCP's which is not practical, Performing such tests of those 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 verified shut by means of seat loakago testing performod in accordance with 10 CFR 50, Appendix J.

l t

Status: IST Program 1980; Submitted as VRR 12 (Approved via GL 8944)

Page 15 of 39

POINT DEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991

- APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRP 13

_ SYSTEM: Chemical ard Volume Control (G84J741 / 685J175)

COMPONEN1$.; OV40370

, CATEGORY: A/C FUNCTIOR; These valvos open to provide flowpaths for charging water into the reactor coolant system from the charging pumps. They close to provide containrr'ont isolation for the CVCS system in the event of an accident.

.SECTION XI REQUIREMENT:

Chock valves shall be exercisod at least onco every 3 months, except as provided by liW 3522 (LYN 3521)

.DASIS FOR RELIE; e

f This valve k crmally open. It is a simple chock valve with no external means of posttion indication, thus the only practicai raoans of vorWying closure is by porforming a loak test or backflow test. During plant operation, such testing would requlte securing the charging pumps which is not practical or pndent ard could result in a plant trip if done. Performing such tests of those valves involves considorablo offort and system re alignment such that routine testing during cold shutdown outages is impractical.

ALTERNATE TESTING:

During reactor refueling outages these valvos will be verified shut by means of seat leakage testing performod in accordance with to CFR 50, Appendix J.

( O Status: IST Prograin 1980; Submittod as VRR 13 (Approvod via GL 8944)

Page 16 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 14 SYSTEM: Instrument Air (M 209, Sheets 5,7,11)

COMPONENTS: IA 00644,645,1280,1281 (Unit 1) 4 IA-00876,877,1401,1402 (Unit 2)

.C6lfGORY: A/C

! FUNCTION:

These valves open to provkfe air to inflate the purge valve boot seals. They close on a loss of supply air pressure to maintain the boot seals inflatod.

SECTION XI REQUIREMENTS; Valve leakage shall be determined by one of two methods; measuring inkage directly or measuring feed rate regt!lred to maintain test pressure. (IWV-3424)

Q BASIS FOR REllEF:

There are other acceptable techniques available which demonstrate leak rates through valves. OM Part 10, Section .4.2.2.3 describes such techniques.

ALTERNATE TESTING:

Leakage will be assessed by measuring pressure decay in the test vrlume. All leakage will be assigned to the vajve being tested. Differential pressure will be applied in the sar. , direction as when the valvo is performing its l function.

I l

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Page 17 of 39

ARPF13M POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 RELIEF REQUEST NO. VRR 15

.Qyji1Eht Service Water (M 207 Sh 1)

COMPONENTS; SW-00112A (Unit 2)

SW40135A (Unit 1)

CATEGDBY; C FUNCTION:

These valves open to provide tiowpaths to the steam 4 riven auxilbry feedwater pumps (P429) for bearing cooling water.

SECTION XI REQUIREMENTS:

Check valves shall be exercised to the position required to 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 flow through the valve, or by other positive means. (IWV-3522) Per NRC Generic Letter 8944, if valve exercising is performod with system flow, there must be a quantitative measurement of flow to verify that full accident flow is O attained.

BASIS FOR RELIEF:

There is no practical means of measuring flow through these check valves. in accordance with NRC Generic Letter, an acceptable alternatNe is a program of valve disassembly and inspection to vertfy operability.

ALTERNATE TESTING:

During quarterly testing of the related auxilluy feedwater pumps, the va!ves will be exercised and pump and turbine bearing temperatures will be monitored.

During reach reactor refueling outare, the valve associated with the unit undergoing refueling will be disassembled and inspected to ve 4 operability.

Status. IST Program 1990 Page 18 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1

! May 28,1991 I

I APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 16 SYSTEM: Heating and Ventilation (V 215, Sh 2,M 2215, Sh 2)

COMPONENTS: RM43200AA CATEGORY: A/C F_ UNCTION:

These valves open to provide a retum flowpath to the containment from the ccntainment atmospheric monitoring system. They close for contalnment isolation.

SECTION XI REQUIREMENT:

Check valvos shall be exercised at least onco every 3 months, except as provided by IW\ 3S2?. 6 NVc521)

BASIS FOR RELIEF:

During normal plant operation, gases from a cont!nuws sampling system rotum samps f -w to the J,ntainment i through thece linos /valvos. To test those valves during operation or cold shutdown. It w#) be nocessary to

\ discharge potentially radioactive gases to the Environment. There is no mechanism to partid stroke these valves.

ALTERNATE TESTING:

During refueling outages each of these valves will be exercised to the rlosed position during seat loak tests performed in accordance with 10 CFR 50, Appendix J.

Status: IST Program 1980; Submitted as VRR-16 (Approved via GL 8944)

Page 19 of 39

_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ ____.m ______ ______ __

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 17 SYSTEM: Emergency Diesel Generator Air Start (M 209, Sh 12)

COMPONENTS: DA-03057 A&B DA43058 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.

SECTIORXI 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 frecuency shall be Increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed. (lWV 3417(a))

D}&Q FOR REUEF:

These are enclosed air pilot operated valves with no remote os local position Indication and where the valve daign prohibits visual observation of valve operation or position. Thus, stroke time measurements are not poss!ble.

Failure of a valve to operate properly would result in unacceptable start and operation of the associated diesel generators.

ALTERNATE TESTING; Valve stroke testing v.ill bc pct'ctmed monthly in conjunction with the associated emergency diesel generator start testing. Valve stroking parameters will be considered acceptable !! the diesel generator start is acceptable.

If a diesel generator falls to start, at no fault of the respective valve (s), the valve stroking parameters will be considered acceptable, which will be proven with the restart following diesel generator corrective action.

l l

Status: IST Program 1980; Submitted as VRR 17 (Approved via GL 89-04) l Page 20 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDlX F

\ VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REur.F REQUEST NO. VRR-18 SYSTEM; Reactor Coolant (541F091, Sh 2 / 541E445 Sh 2)

COMPONENTS: R C G)529 CATEGORY: A/C FUNCTION:

These valves open to provide flowcaths for makeup water supply to the Pressurizer Rollef Tanks (PRT's are non-safety related) and close to provide containment isolation in the event of an accident.

SECTION XI REQUIREMENT:

Check valves shall be exercised at least onco every 3 months, except as provkjed by I',W-3522. (IWV-3521)

BASIS FOR RELIEF:

p Those are simple, normally-closed, check valves with no external means of position Indication, thus the only practical means of verifying closure is by performing a leak test or backtiow test. Performing such tests of these valves involves considorable effort and system re-alignment suc.i that routino testing during plant operation or cold shutdown outages is impractical.

ALTERN ATE TESTING:

During reactor refueling outages each of these valves will be exercit d to tha c ased uosition curl'sg sect leak tests performed in acco, dance with 10 CFR 50 Appendix J.

O Status: IST Program 1980; Submitted as VRR-18 (Approved via GL 8904)

Pago 21 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991

/O APPENDIX F

\ VALVE PROGRAM REQUESTS FOR REllEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 19 SYSTEM: Chemical and Volume Control (684J741 / 685J175)

.CD}MPONENTS: 1 CV 00300 A&B 2-CV-00300 A&B CATEGORY: A FUNCTION:

These normally throttled open valves provide seal water to the RCP's during pump operation (RCPs are nonsafety-related.) and are closed upon direction of the operator for containment isolatloa.

SECTION XI REQUIREMENT:

Category A and B valves shall be exercisod at least onco every 3 months, except as provided by IWV-3412(a),

IWV-3415, and IWV-3416. (IWV 3411)

BASIS FOR RELIEF:

V Exercisirg 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 theso valves would result in a considerable operational bucJen. Note that these small manual valves are highly reliable with respect to their capability to close and exercising during refueling outages will adequately demonstrate their operability, ALTERNATE TESTING:

During reactor refueling outages these valves will be exercised to the closed position and seat leak rate tested in accordance with 10CFR50, Appendix J.

Status: IST Program 1990 Page 22 r' S

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 20 SYSTEMS: Main Stearr, (M 201, M 2201)

COMPONENTS: 1-MS42090 2-MS42090 i

CATEGORY: B fUNCIJOtt 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 a': 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 stro.<e 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 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 measurements are impractical.

Failure 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 will be exorcised in conjunction with testing of the associated auxillary 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 8944) i l

Page 23 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Rsvision 1 May 28,1991 APPENDIX F

( VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 21 SYSTEM: Main Feedwater (M 202, Sh 2 / M 2202, Sh 2)

COMPONENTS: CS40466 AA&BB CS40476 AA&BB CATEGORY: C FUNCTION:

The main feedwater line to each 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 auxiliary feedwater flow is unimpaired to at least one of the two steam generators while main foodwater is not available. The series check valves also prevent simultaneous blowdown of both steam generators in the event of a main feed pipeline failure.

SECTION XI RECUIREMENT:

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 manner that proves that the disc travels to the seat promptly on cessation or reversal of flow.

(IWV-522(a))

BASIS FOR RELfEF:

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 between the valves. It is therefore not feasible, with the present plant configuration, to

erify individual valve closure . Closure of at least one of the two series check valves can be verified by measuring the differential pressure across, or leakage past the combination of both valves. This is adequate .o ensure the safety function of the valve combination is maintained and verifled.

Prompt seating 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 available.

Valve testing can be conducted only during unit shutdowns since the flow of main foodwater to the steam generators must be secured in order to perform the tests.

ALTERNATE TESTING:

A valve exercise test of the main feedwater check valves will be conducted once each refueling outage, At least one of the series valves will be vertfled closed after flow la secured by measuring the differential pressure across, or the leakage past, the series combination of valves.

Additionally, once every 10 years, the main feedwater check valves will be opened and Inspected. The O inspections will be distributed so that at least one valve is inspected every two-to-three years, and all valves are inspected within a 10-year interval.

Page 24 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 Sloco the spilt body construction of the socordeil check valves 466AA and 476AA limits access to the valvo intomats, only those portions of the valvo Internals accesslble from a sido access port will be inspectod.

Completo disassembly of these valvos is not practical sinco it would require that largo pipo support structures would have to be cut and piping be moved.

The construction of the first-off check valvos 466BB and 47688 permits access to valvo internals for inspection with no known limitations.

Status: IST Program 1980; Submnted as VRR 21 (Approved via GL 8904)

Page 25 of 39

4 POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO VRR 22 UNITS. 1 and 2 f,JSTEM. Safety injection / Residual Heat Removal (110E017 & 110E035) 9 2ENTS. SI-00845 A through F SI-00853 A through D SI 00867 A&B SI.L WRY: A/C (Check Valves) rU, icTION-These check valysa open to provide for high-pressure and low-pressure safety injection to the RCS. The motor-operated valves open for residual heat removal recirculation during shutdown. Each of these valves is designated as a pressure isolation valve (PlV) and provides isolation of safeguard systems from the RCS, SECTION XI REQUIREMENT:

The leakage rate for valves 6-inches or greater shall be evaluated per Subsection !WV-3427(b). (1WV 3521)

BASIS FOR RELIEF:

Leak testing of these valves is primarily for the purpose of confirming their capability of preventing over-pressurization and catastrophic failure of the safety injection piping and components. In this regard, special leakage acceptance criteria 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 Code acceptance criteria is not warranted and implementation would be difficult and confusing.

( ALTERNATE TESTING:

The leakage rate acceptance criteria for these valves will be established per the Point Beach Technical Specifications, I

1. Leakage rates less than or equal to 1.0 gpm are considered acceptable.

l 2. Leakaga rates greater than 1.0 gpm but less than or equal to 5.0 gpm 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 determined by the previous test by an amount that reduces the margin i 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.

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Page 26 of 39 n

- - - - .- . - - - - . - - _=

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVC PROGRAM REOUESTS 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 FUNCTION: These valves are closed to provide containment isolation.

SECTION XI REQUIREMENT:

Category A valves shall be seat leak tested and a maximum permissible leakage rate shall be spectfled Individual valve leakage rates shall be evaluated per IWV 3426 and IWV-3427 (IWV 3426. IWV-3427, NRC Gencric Letter 89-04)

BASIS FOR REllEF:

Due to the configuration of the system piping and components, in many cases individual leakage rate tests are imp:actical. 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 10CFR50, Appendtx J ALTERNATE TESTING:

In those cases where Individual valves testing is impractical, valves will be leaktested simultaneously in multiple 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.

't i

O Status: GL 8M>4 response submitta! dated 10/3/09, Itam 10 i

Page 27 of 39 l

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM

l. INSERVICE TESTING PROGRAM Revision 1 l

May 28,1991 i APPENDIX F

VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR-23 (Cont.)

TABLE VR-5-1 SYSTEM VALVES Auxiliary Steam HV40632 HV40009 HV 00633 HV40818 HV40808 Chemical & Vol. Control CV-003238 CV 003848 Component Cooling Water CC-00755 A&B CC-00750 A&B Containment Spray SI00862 A&B SI-008G4 A&B O Hoating & Ventilation VNPSE43212 VNPSE-03213 VNPSE-03244 VNPSE43245 Instrument Air IA41182 IA-01184 Post-Acc Containment H2 V-04 H2 V 13 Vent / Monitoring H2 V45 H2 V 19 H2 V-06 H2 V-20 H2 V 07 H2-V-22 H2 V 12 H2 V 23 l Waste Disposal WL-00816 WL-01728

! WL-01698 WL 01003A

! WL41723 WL 010038

\~

O Page 28 of 39

\ . . - _ . - - - - - - -. - - - - -- -

POINT BEACil NUCLEA.R Pl ANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Ruvislcn 1 May 28, ".991 O APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 RELIEF REQUEST NO. VRR 24 1YSTEM. Chomical and Volume Control (604J971)

SQMPQNENTS: CVM351 CATEGORY: C FUNCTION:

Thoco valvos opon to provido a flowpath for omorgency boration from the boric acid transfor pumps to the suction of the charging pumps providing for omorgency boration of the RCS.

SECTION XI REQUIREMENI; Chock valvos shall be oxorcised at least once overy 3 months. except as provklod by IWV 3522. (IWV-3521)

BASIS FOR REllEE Testing those valves in the open direction requires the introduction of hig!Jy concentrated boric acid solution from the boric acid makoup tanks to the suction of the charging pumps. This, in tum, would result in the s

addition of excess boron to the RCS whk.1 would adversdy affect plant power lovel and operational paramotors with the potential for an undesirable plant transiont and a plant trip or shutdown. During cold shutdown, the introduction of excess quantitles of boric acid is undostrable from tho aspect of maintaining proper plant cbomistry and the inhoront difficulties that may be encountered during the subsequent startup.

ALTERNATE TESTING:

These valves will be exercised as requirod during each reactor refueling outago.

Status IST Program 1990 Page 29 of 39

POINT BEACH NUCLEAR Pl. ANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR REllEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 25 UNITSl 1 and 2 SYSTEM: Emergency Diesel Generator Air Start (M-209, Sh 12)

COMPONENTS: DAM 125 DAM 310 A&B DA@t26 DA4317 A&B DA 00225 DA-06318 A&B DA@226 DAM 319 A&B CATEGORY: B/C .

FUNCTIOtt These valves operate as required to supply starting air and to sequence starting operations of the ernorgency diesel generators.

SECTION XI REQUIREMENT:

The stroke time of all power operated valves shall be moasured to the nearest second, ..., whenever such a valve is full-stroke tested. (IWV 3413(b))

Check valves are to be full-stroke tested por Reference 2.8, Position 1 including quantitative measuromonts verifying design flow through a valve.

BASIS FOR REUEF:

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 moasuring the stroke times or flowrates of each Individual valve. If a valve were to fab to stroke as required it would be reflected in an unacceptable starting time and/or performance of the respective diesel generator.

ALTERNATE TESTING:

These valves wul be exercised in conjunction with testing of the emergency diesel generators. Stroke times of Category B valves wul not be measured nor will flowrates through check valves, but the starting timo for each diesel generator wul be verified to be acceptable.

Status: IST Program 1990 Page 30 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R:: vision 1 i

May 28,1991

/m

( APPENDIX F k VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR-20 UNITS: 1 and 2 SYSTEM: Chemical and Volume Control System (684J971)

COMPONENTS: CV-00333 A&B CATEGORY: C FUNCTION:

These valves open to provide a flowpath from the boric acid makeup pumps to the emergency be c.then header and close to prevent recirculation flow 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) p BASIS FOR REUEF:

5

' Full-stroke testing these valves requires operating the boric acid makeup pumps at or near rated flow and verifying full accident flow throagh each valve. This 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 tum, would result in the addition of excess boron to the RCS which would adversely affect plant power level and operationa! 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 difficulties that may be encountered during the subsequent startup.in over-boration of the RCS. In addition to the above, there is no flowrate measurement instrumentaton installed in this flowpath.

ALTERNATE TESTING:

Each of these valves will be pa tlal stroke exercised quarterly.

During testing of the boric acid makeup pumps performed during et.ch reactor refueling, system flowrate will be measured to verify full stroke of these varves.

A Status: IST Program 1990 Page 31 of 39

POINT DEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 O APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 27 SYSTEM: Safety injection (110E017, Sh 2 /110E035, Sh 2)

COMPONENTS: S140891 A&B CATEGORY: C f!)NCTION:

These valves open to provide flowoaths from the safety injection pumps to the refueling water storage tank to provir for minimum flow through the respectivo pumps in the ovent they are operating under low or no flow conditions.

SECTION XI REQUIREMENT:

Check valves shal: be exercisod at least once every 3 months, except as provided by l\W-3522. (M%3521)

BASIS FOR RELIEF:

G There ls no flowrate instrumentation availablo to verify valve full stroke exercising as required by Reference 2.8, Position 1.

ALTERNATE TESTING:

During quarteriy pump testing each of those valves will be partial stroko exorcised via rocirculation through the minimum flow test circuits with no flow measurements.

During each reactor refueling outago at Inast one of these valves will be disassornbled, inspected, and manually stroked to verify operability. Inspections shall be scheduled such that valves will be checked in a rotating sequence such that each valvo is subject to inspection at least once overy six (6) years. Should a valve under inspection be found to be inoperable, then the other valve in that untt will be Inspected during the same outago, after which the rotational Inspection schedule will be re-initiated. This satisfies the requirements of Generic Letter 8944, Position 2.

l O Status: IST Program 1990 (Approved via GL 8944)

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Page 32 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 i May 28,1991

( APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 281 UNITS. I and 2 SYSTEM: Aux 1,lary Foodwater COMPONENTS: AF-4002. AF-4007, AF-4014 CATEGORY: B FUNCTION:

These valvos open to ensure minimum recirculation flow from the pumps to provent pump damago. These valves shut in response to main lino flow increases such that they are fully shut when pump damage due to insufficient flow is no longer a concom. These are alr operated valves.

SECTION XI REQUIREMENT:

Power operated valves shall have their stroke timod in accordance with IWV 3413.

G BASIS FOR REllEF:

These valvos are actually control valves, in that they respond to discharge flow and may actually ond up in a throttled position. As control valvos, cccording to IWV 1200, they could be exempt from test!ng. They do provide an important function, to shut when sufficiently large main lino flows are achieved, thereby ensuring full pump capacity is avaHable to moet any accident requirements. The appropriate acceptance criteria for these valvos is to assure they respond properly to flow.

ALTERNATE TESTING:

Vortfy that the valve is closed when main line flow reachos a value which assures the pump will not be damaged.

This will be performed on a cold shutdown frequency because sufficiently largo main line flow rates of cold foodwater during operation would produce unacceptable thermal stressos of feedwater system piping components.

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Page 33 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 l

May 28,1991 APPENDIX F O(/ VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR-29 UNITS. I and 2 SYSTEM: Primary Containment COMPONENTS: Valves 6-inches NPS and larger subject to loakago rato testing por 10 CFR 50, Appendix J.

CATEGORY: A/C (Chock Valves)

A (Motor-operated valves)

FUNCTION:

Each of these valvos is designated as a containment isolation valvo maintaining the leakrato Integrity of the primary containment in the case of an accident.

SECTION XI REQUIREMENT:

The leakage rate for valves 6-inches or greator shall be evaluated por Subsoction IWV 3427(b). (IWV 0521)

BASIS FOR REllEF:

The usefulness of applying this requiremont does not justify the burdon of compilanco. This position is supported by NRC Generic Lettor, Position 10 ALTERNATE TESTING:

Leakrate test results for valves 6-inches or greator (NPS) will be evaluated por IWV-3426 and IWV-3427(a) however, the requirements of IWV4427(b) will not be appliod. This satisfies the requirements of Genoric Lottor 8944, Position 10.

I Status: IST Program 1990 (Approved via GL 8944)

Pago 34 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM-INSERVICE TESTING PROGRAM Revision 1 May 28,1991 l

O APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 l

REUEF REQUEST NO. VRR 30 UNITS: I and 2 SYSTEM: Component Cooling Water (110E018, Sh 2 /110E029, Sh 2)

COMPONENISI 1-CC40767 2-CC40767 CATEGORY: A/C FUNCTION; These valves open to provide flowpaths for coo l!ng 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.

I SECTION XI REQUIREMENT:

Check valves shall be exercised at least once every 3 months, except as provided by liW-3522. (IWV-3521)

BASIS FOR REUEF:

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.

Status: IST Program 1980; Submitted as VRR-15 (Approved via GL 8944)

Page 35 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REllEF REQUEST NO. VRR 31 SYSTEM: Chilled Water (M 214, Sh 2)

COMPONENTS: HV40898A, HV 00000A, HV40914A, HV40916A CATEGORY: A/C IUNCIIDE These valves open with differential pressure to provide flowpaths frnm the control room and cable spreading room chilled water pumps to the respective cooler units. Each closes to prevent recirculation flow 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)

BASIS FOR RELIEF:

There is no instrumentation available with which to measure system flowrate in order to satisfy the requirements of NRC Generic Letter (GL) 8944, Position 1 for full stroke exercising check valves.

ALTERNATE _TESIjMQ; The following attomate 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 operability at least once every six (6) years, inspections will be scheduled on a staggered basis such that one valve be inspected every two years. If 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 39

RAM INSERVICE TESTING PRO Revision 1 ANT May 28,1991 OGRAM i POINT BEACH NUCLEAR PL i

/

INSERVICE TESTING PR

/

I FOR RELIEF APPENDIX FVALVE PROGRAM REQUESTS UNITS 1 AND 2 REUEF REQUEST NO.VRR 32 I instrument Air (M 209, Sh 11)

.6L91Di A41600, and 1 IA4100641652, and t IA416 SQfLQNQ(($;

1 IA41200,1 IA41209,1 I2 IA41335,2 IA41338,1 IA ir g A/C lt from the plant instrumont a close to provent

$611GQH'(;

ovide flowpaths for operatingV's.a fURGllDR in the instrument air wl'h dsfforential pressure tof pr system theyg Those valves open t of aloss of air pressutoneumatic supply that provk system to PORV's. In the evendNorsion Paragraph IWV 3420 of the nitrogen b QU1BDdENI;

.$1CIl0H.XLBE tod in accordance with Category A valvos shall be loak tes ith no test connection in valvos are installed The function in series wof clo 9 -

The plant configuration alves is suchdthat them that to test two the valvos indNidually.lther could vbe useith ordy one valvo, for those tem. thus if o the common piping betwoonisolation can be accompitshe al functional adequacy of the syses a system ronwins fully function adequaid/d. emonstratosthe f rmation Ard tracking pur Testing two valves in combination in din the testing program for in o Noto thatthethose strictly moot requiremen valves are includetswillof IWV 1100 be assigned to the for asured leaktato ALIIBH61fLII.1M d single in combination valvo.

such that the me Thoso valves will beleak testocombination as though

%47 Progr am 1990

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Rovision 1 May 28,1991 APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR 32 SYSTEM: Instrument Air (M 209, Sh 11)

COMPONENTS: 1 IA 01206,1 IA 01209,1 IA-01600, and 1 IA 01606 2 IA-01335, 2 IA 01338,1 IA41652, and 1 IA-01653 CATEGORY: A/O FUNCTION:

These valves open with differential pressure to provide flowpaths for operating air 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 operation of the PORV's.

SECTION XI REQUIREMENT: I Category A valves shall be leak tested in accordance with Paragraph liW-3420.

BASIS FOR RELIEF:

\

The plant configuration for these valves is such that two Valves 3 re Installed in series with no tett 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 lealdight integrity, then the system remains fully functional.

Testing two valves in combination adequately demonstrates the functional adequacy of the system.

Note that these valves are included in the testing program for information and tracklag purposes and do not strictly meet the requirements of IWV 1100 for inclusion.

ALTERNATE TESTING:

These valves will be leak tested in combination such that the measured leakrate will be assigned to the combination as though it were s single valve.

! O Status: IST Program 1990 Page 37 of 39 i

i POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX F VALVE PROGRAM REOUkSTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR-33 SYSTEM: Emergency Diesel Generator Fuel OR (M 219)

COMPONENTS: FO 03940 and FOC3941 CATEGORY: A/C FUNCTION:

These valves operate to control fuel oR 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 ou back to the Emergency Fuel Tank.

SECTION XI REQUIREMENT:

Valves sha!! be exercised (full stroke) to the position required to fulfill their function. (IWV-3412)

BASIS FOR REUEF:

O

, Since these are essentially back-pressure regulating valves requiring no outside 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 vafve 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 ascertaining the condition of the valves and proving their operability. ,

ALTERNATE TESTING:

These valves will be subjected to an operational test to verify proper operation with respect to limiting and controlilng the fuel oR piping pressure during fuel oil transfer pump operation. During thosc tests, cystcm operating parameters will be monitored to determine valve operability.

O Status: IST Program 1990 P 'a 38 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 f

( APPENDIX F VALVE PROGRAM REQUESTS FOR RELIEF UNITS 1 AND 2 REUEF REQUEST NO. VRR44 SYSTEM: Post-Accident Containment Vent Systems (M-224)

COMPONENTS: H2 V-04, H2 V.05, H2 V 12, H2 V 13, H2 V 19, H2 V-20. H2 V 22, H2-V-23 for Unit 1 and for Unit 2 CATEGORY: A FUNCTIQR These valves would be used should a nood arise to perform a post accident vont of containmont.

SECTION XI REQUIREMENT:

Category A valves shall be exercisod at least once every three months. .(etc). (IWV-3411)

DASIS FOR REUEF:

O These valves are manual valves which remain shut at all times except to perform stroke testing. They are diaphragm-type vatves, thus they do not have a disc which can separato from the stem. Frequent flexing of diaphragms is a failure mechanism. These valvos use stainless steel in their construction, thus they are susceptible to galling. Frequent stroking of these valvos could lead to inoperability rather than improving operability.

ALTERNATE TESTING:

Exercise these valves once por year.

O Status: IST Program 1990 Page 39 of 39

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX G COLD SHUTDOWN JUSTIFICATIONS TABLE OF CONTENTS COLD SHUTDOWN JUSTlFICATIONS CSJ NO. COMPONENT, PAGE NO.

1 AF40100, AF 00101, AF-00102, AF40104, AF-00106 and AF40107 2 2 AF-00108, AF40109 and AF40110 2 3 AF-00111, AF-00112 and AF-00113 2 4 CV40112C 3 5 CV40142 3 6 CV-00313 and CV40313A 3 7 CV40371 and CV-00371 A 3 8 CV 00384B 3 9 CC40719 4 10 CC-00754 A&B and CC-00759 A&B 4 11 SI40836 A&B 4 12 VNPSE-03212, VNPSE43213. VNPSE-03244, and VNPSE43245 4 13 Unit 1 IA41280 and IA41281, Unit 21A41401 and IA-01402 4 15 MS 02017 and MS42018 5 Os 16 17 MS 02017A and MS-02018A MS 02017CS, MS-02017DS, MS-02017CS, and MS 02017DS 5

5 18 RC-00430 and RC-00431C 5 19 RC-00570 A&B, RC-00575 A&B, AND RC-00580 A&B G 20 SI00841 A&B 6 21 SI 00852 A&B 6 22 SI 00878 A&C 0 23 SI 00878 B&D 6 24 SI 00826 B&C 6 25 SI 00897 A&B 6 26 RH-00710 A&B 7 27 SW42880 7 28 Unk 1 IA-01206,01209,01301,01302 and Unit 2 IA 01335,01338,01418,01410 5 30 SI-00957 and SI 00834 A&B 7 31 AF-4002, AF-4007, AF-4014 (Unit 1 & 2) 2 32 SW-00307, SW40315, SW40322 and SW40360 7 O

l Page 1 of 7

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POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Revision 1 May 28,1991 APPENDIX G COLD SHUTDOWN JUSTIFICATIONS This appendix is intended to provide the justification for performing valve exercising ordy at cold shutdown conditions as permitted by IWV-3412(a),3415 and 5322. Specifically included in this category are the iallowing:

A valve whose fauure in a position other than its normal position could jeopardiz* ..ie immerdlate safety of the plant or system components; A valve whose falure in a position other than its normal position could cause all trains of a safeguard

, system to be Inoperable; A valve whose fauure in a position other than its normal position that might cause a transient that could lead to a plant trip; When test requirements or conditions are precluded by system operation or access.

Cold shutdown tecting is performed under conditions outlined in Rollef Request VRR-5.

Auxillarv Feedwater (M 217)

CSJ1 AF-00100, AF@101, AF-00102, AF 00103, AF-00104, AF-00105, AF 00106, and AF 00107 AuxHlary Feedwater 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 p! ping components.

CSJ-2 AF-00108, AF 00109 and AF-00110 AuxHlary Feedwater Pump Discharge Check Valves Fu!I stroke exercising of these valves would require operation of the relateo auxHlary 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 Auxiliary Feedwater Pump Suction Check Valves Full-stroke exercising of these valves would require operation of a related auxHlary feedwate. 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. These vane 3 will be partial stroke tested during quarteriy testing via the minimum flow recirculation tires.

I (./

l l

Page 2 of 7

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Rsvision 1 May 28,1991 APPENDIX G

( COLD SHUTDOWN JUSTIFICATIONS t CSJ-31 AF-4002, AF 4007, AF-4014 (Unit 1 & 2)

Generating a close signal for these valves (which is equivalent to falling the operating alt, see Appendix H) requires a large main line flow rate. The addnion of large quantities of cold feedwater would cause unacceptable thermal stresses on the feedwater piping.

Chemical & Volurr:e Control f684J741)

CSJ-4 CV 00112C Volume Control Tank Outlet Valve Oosing this valve during operation of a charging pump would Isolat6 the VCT from the charging pump suction header damaging any operating charging pumps and Interruptirrg the flow of charging water flow to the RCS with the potential of RCS transient and plant trip.

CSJ-5 CV 00142 Charging Flow Control Valve i Cosing 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 potential 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 RCP Seal Water 9etum Valves Exercising these valves to the closed position when the associated reactor coolant pump (RCP) in operation would irterrupt flow from the respective RCP seals and result in pump damage.

CSJ 7 "N-00371

. a x! CV40371 A Letdown Une Isolation Valves Gosing either of these valves during operation isolates the letdown line from tne RCS and would result in undesirable pressurizer level transients 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 Oharging Une HCV Outlet Valves Cosing these valves during operation will interrupt flow of charging water flow to the RCS with the potential of RCS transient and plant trip.

O Page 3 of 7

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM Rcvision 1 May 28,1991 h

d APPENDIX G COLD SHUTDOWN JUSTIFICATIONS Comoonent Coolino Water (110E018)

CSJ-9 CC40719 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 at a subsequent plant shutdown.

CSJ 10 CC40754 A&B and CC40759 A&D RCP Cooling Water Supply /Retum Isobtlon Valves These valves are required to be open to ensure continued cooling of reactor coolant pump auxiliary components. Closing any of these valvws during plant operation would result in severo RCP damage leading to plant operation in a potentially unsafe mode and a subsequent plant shutdown.

Containment Sorav System (110E017)

CSJ-11 S140836 A&B Sodium Hydroxide (NaOH) Supply Valves in order to exerclse these valves without contaminating the containrnent spray piping with sodium hydroxide would require Isolating the NaOH supply from the containment spray eductors. This, in tum, renders the sodium hydroxide additNe subsystem for both tralns of containment spray InoperatNe during the test period.

Heatino and Ventilation (M-215)

CSJ-12 VNPSE-03212, VNPSE43213, VNPSE-03244, and VNPSE43245 Containment Purge Supply and Exhaust Valves These vanes 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, 10Eritme_n. Lair (M-209)

CSJ 13 Unit 1 IA41280 and IA41281, Unit 2 IA41401 and IA41402 Containment Purge Valve Air Supply Check Valves These valves and other valves required for exercising are located within the containment bu!! ding and, as such, are not readily accessible during plant operation at power.

Page 4 of 7

I POINT REACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R; vision 1 Mey 28,1991 r~

(l APPLNDIX G COLD SHUTDOWN JUSTIFICATIONS CSJ 20 Unti 1 IA 01200,01209,01301,01302 and Unit 21A41335,01338,01410, ii>19, instrument Air ard Nitrogon Supply to PORVs and IA46310 ard IA4G311 Nitrogen Supply P# essure Rogulators PORV Pneumatic Supply Vfdves These valvos nood ordy be testod prior to entering a :ondition where LTOP precautions must 50 administarwi (le crdd Sh e'dc*n) Fua.hermore, exerc!dng thoce vdic: rcqdss contair. ment entri ard opa,ation of the PORV's which is not advisaldo during plant operation at powor, (GL 0040) i l WLn and Rehoat Sicam (MIDM CSJ 15 MS42017 and MS42010 Main Stoam isolation Valves During plant operation at powor, closure of either of those valves la not practical as it would require isolating .; steam generator wh'ch w and result in a severo transient on the steam ard reactor systems and a reactor plant trip.

CCJ 10 MS42017A and MS42018A Main Steam Non Retum Valves

,rm

( Exorcising those valves requires isolating the associated stoam generatnr which is not practical without e plant t hutdown, and, il performed during plant operation. will result in a plant trip.

C$J 1, 42017CS, MS42017DS, MS42017CS, ard MS42017DS tV Air Pilot Valves Testing of thr.,e valves can result in closure of the related MSIV During plant oporation at power, closure of any MSIV la not desirable as it would cause Isdation of a steam gonorator which would result in a e'rvoro trantnt en the steam and roactor systems and a reactor plant trip.

Reactor Coolant (541 FOP / Si1F445)

CSJ 18 RC40430 and RC404310 Power-Operated Rol!of Vatves (PORV's)

Due to the potential impact of the resulting transient should one 6f those valves open prematurely or stick in the open pesillon, it is considered imprudent to cyclo them during plaat operation. In accordance with NRC Genotic Lotter 0040, they will be exercised when practical with the reactor shutdown ard at reduced roactor coolari system pressure.

C!>J 19 RC-00570 A&B, RC40575 A&B, ard RC00500 A&B Roactor Codant System Vents These are isolation valves for the reactor coolant syctom, failure of a valve to close or significaat loakago following closure could result in a loss of coolant in excess of the limits imposed by Technical r Specificailon 16.3.1.0 loading to a plant shutdown. Furthormoro, if a valve were to fall opon or valvo h indication fab in show the valvo rotumod to the fully closed position following exorcising, prudent plant opointion would probaldy likely r9sult in a plant shutdown. Pago 5 of 7

POINT BEAOH NUCLEAR PLANT INSERVICE TESTING PROGRAM 1 INSERVICE TESTING PROGRAM R:; vision 1 i May 28,1991 l 1 l APPENDIX G i COLD SHUTDOWN JUSTIFICATIONS l Safety Inlaction / Residual Heat Reagyal (110E017 /1.1RD10) ; CSJ 20 SI40841 A&B Safety injection Accumulator Discturge Valves During pbnt operation In any mode above cold shutdown these vanes are required to remain open and ;

  ,                                       disabled. Oos!ng one of these valves renders the associated accumulator unavaRatWe for Injection in l                                       the event of a LOCA. Oosing either of these valves during plant operation is considered to be imprudert and unsafe.                                                                                            i CSJ-21 S140852 A&B RHR/LH Core Deluge Motor Operated Vatves Opening these valves with the RCS ct normal pressures could expose the downstream safety injection                i piping to RCS pressure w*h the only protection being the two check valves. This la considered to be               ,

imprudent and an unwarranted challenge to plant safety. CSJ 22 SI 00878 A&C Reactor Vesse, Safety injection Motor-Oparated Valves During plant operatton in any mode above cold shutdown these valves are requireo to remain open and disabled. Oosing one of these valves renders the associated accumulator unavaRable for ',njection in l the event of a LOCA. Cosing either of these valvas 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 wil result in isolation of one of the injection flowpaths to the RCS. This is considered imprudent and an unwarranted compromise of t plant safety, CSJ 24 SI 00826 B&C Si Pump Redundant Suction From the BAST's l I 1 Evercking these valves requires closure of the downstream valve, SI 00826A or the mini flow valve from

i. the RWST to preclude overfilling the BAST's from the RWST. Operation in either configuration would isolate all water sou,*ces from both SI pumps with the potential of the loss of functionality in the event of dn accident.

CSJ 25 SI-00897 A&B Sabty injection Pump Mini-Recirc To RWST Cosing either of these valves isolates the minimum flow recirc lines from both Si pumps and, in the event of SI Initiation at devated RCS pressure, both pumps could sustain damage with the potential of . tendering both safety injection pumps inoperable. l Page 6 of 7 L__ _ _ _ _ -. _ _.

POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM INSERVICE TESTING PROGRAM R: vision 1 May 28,1991 I . APPENDIX G l COLD SHUTDOWN JUSTIFICATIONS I CSJ 76 RH40710 A&B ' RHR Pump Discharge Check Valves j 1 1 During normal plant operation, the RHR Pumps cannot develop sufficient discharge pressure to pump through these vanes to the RCS and tuil kroke exercise them in the open direction. CSJ 30 Sl40967 and SI 00834A&B

 ,                                Accumulator Nitrogen Supply Vent Valve and Accumulator Vent Valve                                                                                                                          !

Stroking these vnNos during operation has the potential for reducing plant safety. If a series valve were , to leak, accumulator nitrogen pressure could drop below that requ! red to maintain the accumulator , operable. Stroke tetting at cold shuidown when accumulators are not required provides a satisfactory < I demonstration of valve operabulty without the possibilty of compromising plant safety.

              ,$grvice Water N 207)

CSJ 27 SW42800 Turbine Plant Service Water Supply Valve ! Closing this valve results in securing cooling wat< t to the turbine plant auxiliarles including the main 1 turbine, main generator, steam generator feedoter pumps, condensate pumps and other supporting equipment. If, during testing, this valve were to fal to reopen for any extended period of time, the associated turbine generator and various support components would sustain significant damage. CSJ 32 SW40307., SW40315, SW40322, SW40360 ' Component Cooling Water Heat Exchanger 12D,120,12A,128. Outlet Vanes Operating these vanes during power operation causes large fluctuations in component cooling water i temperature. The efects of these temperature changes is seen on reactor coolant pump performance parameters, particularly the No.1 seal. The temperature transients are most reticeable when the RCS is ; at normal operating temperatures when a large temperature gradient exists between the RCS and the CCW system, We think that placing temperature transients on the RCP No.1 seal and lube ou systems ; leads to seal and bearing damage and could result in catastrophic failures. ' In cold shutdown the RCS temperature has been reduced by at lust 350'F. This results in a lower , temperature gradient between RCS and CCW and less chance of RCP damage. ; i l \ l Page 7 of 7 i

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i POINT BEACH NUCLEAR PLANT INSERVICE TESTING PROGRAM l lNSERVICE TESTING PROGRAM R3 vision O December 18,1990 9 [V APPENDIX H VALVE FAIL GAFE TEST DESCRIPTION ASME Section XI, Article hW 3415, states the following for valvos having fall sato actuators.

                   Valvon with fau t.afo actuaters t, hall be lostod by observing tho oporation of the valves upon loss of actuator power.'

This type of tost demonstrates that a valve wul go to its roquircd position to fulfill its safoty function upon loss of actuator power. The following doacribes the requirements for lau safe tests for the different types of actuators. AchtatetIyce .EaLSa!e_Tril Motor Valve will fa0 as is. No test requirod. Solenoid Valvo falls to hs safo position upon loss of power to the solenold. Air Valve falls to its safe position upon loss of control air to the actuator and/or loss of contrd power to its associated solenoid valvo. (~ A fall safe test can only be performod on sdenold-operated or air oporated valves. Upon loss of power, a ( motor-operated valve is Incapable of moving trd falls as is. Fall sato testing of motor operators will not be performod. A fall-safe test of solunold operated valvos will be conducted by doonorg!2ing the solenoid and obsery ng that the valve moves to its fall safe position. Doonergization of the sdonold wl!! be performed by operating the valvo control switch to the position that corresponds to the fall safe position (i.e., open or shut). A fall safo test of air operated valves will be conducted by doenergizing the solenoid control valvo, which will, in turn, vont air from the valve actuator and result in the valve moving to its fall sato position. Operation of the AOV control switch to the position corresponding to the fau safe position (i e., open or shut) will deenergize the solenold-operated valve and vent att from the AOV's actuator. In some cases, a controllor,1/P (electric / pneumatic) converter, ard a positioner is used to control alt to the actuator of an AOV. For those cases, one of the following methoos will be used to perform a fall safe test of the AOV.

1. Securo power to the 1/P converter which in tum w!!! socure air to the AOV actuator.

2. With the contr> . er in manual, adjust the valve to its fau safo position. Operation of a controller in this manr'er sends a tinimum contrd signal to the 1/P convertor and causes the 1/P converter to cut off air to the valve actuator. This is similar to securing control power to the 1/P converter, except a e, mall control signal is still present, f

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ML20079B785: Difference between revisions

Latest revision as of 23:50, 19 May 2020

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1.0 INTRODUCTION

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