ML20205S231

Rev 0 to Pump & Valve Inservice Testing Program

ML20205S231
Person / Time
Site:	Nine Mile Point
Issue date:	03/31/1987
From:	NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17054C027	List: ML20205S231
References
PROC-870401, NUDOCS 8704060551
Download: ML20205S231 (172)

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INFORMATION ONLY I l

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 1 PUNP AND VALVE INSERVICE TESTING PROGRAN PLAN DATE AND INITIALS APPROVALS SIGNATURES REVISION O REVISION 1 REVISION 2 Inservice Inspection Superintendent T. A. Nawksley W/El. W -

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'f8N Site Technical Superintendent Nuclear j W. Drews C '

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Operations Superintend n NNPNS Unit 1 J. C. Aldrich _

Station Superinte nt NNPNS Unit 1 T. W. Roman h en,cet AM/~'

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General Superintendent  %/g7 Nuclear Generation T. J. Perkins N PA!4A$o Manager, Nuclear Engineering ,

C. J. Gresock 5' - -

t Manager, Nuclear zek, Jr. &7 .

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< - - y r Summary of Panes Revision O (Effective 4/1/R7 )

"- e e_s gal.g, i,11,1 I-10, 11 II-1-10, 111 III 1 March 1987 NIAGARA MONAWK POWER CORPORATION e

THIS PROCEDURE NOT TO BE 40 USED AFTER April, 1989 0 SUBJECT TO PERIODIC REVIEW.

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PUNP AND VALVE INSERVICE IESTING PROGRAM PLAN .

1 TABLE OF CONTENTS SECTION TITLE PAGE i I.0 OVERVIEW I.1.0 Introduction I : I.2.0 Basis I-3 I.3.0 General Program Plan Concept I-4 1.4.0 Organization I-5 I.5.0 Definitions I-6 I.6.0 General Relief Request for Pumps (PG-1) I-7 I.7.0 General Relief Request for Valves (VG-1) I-8 l I.7.1 General Relief Request for Valves (VG-2) I-9 I.7.2 General Relief Request for Valves (VG-3) I-10 II.0 PUMP IST PROGRAM PLAd 11 r fr.l.0 Introduction II-2 1i42.0 Code Interpretation II-3 11.3.0 Pump List II-4 II.4.0 Pump Table Nomenclature- II-5 II.5.0 Attachment 1: Pump Test Table And Relief Requests II-1-1 11.6.0 Pump Test Table & Notes I1-1 II.7.0 Pump Relief Requests 11-1-5 II.7.1 Emergency Diesel Generator Cooling Water II-1-5 II.7.2 Reactor Core Spray II-1-6 11.7.3 Condensate Transfer 11-1-7 II.7.4 Reactor Liquid Poison II-1-8 II.7.5 Emergency Service Water - Flow Rate II-1-9 II.7.6 Vibration (Submerged Pumps) _ II-1-10 11.7.7 Reactor Building Closed Loop Cooling Water 11-1-11 III.0 VALVE IST PROGRAM PLAN III-1 III .1. 0 Introduction III-2 III.2.0 Code Interpretation III-3 III.3.0 Valve Test Table Nomenclature III-7 III.4.0 Valve Test Table Format III-9 III.5.0 Valve Test Table and Relief Request III-1-1 11I.5.1 Attachment 1: Main Steam System III-1-1 111.5.2 Attacament 2: Reactor. Recirculation III-2-1 III.5.3 Attachment 3: Control Rod Drive III-3-1 11I.5.4 Attacnment 4: Feedwater/HPCI III-4-1 III.5.5 Attachment 5: Core' Spray III-5-1 III.5.6 Attachment 6: Emergency Cooling III-6-1 111.5.7 Attachment 7: Reactor Shutdown Cooling III-7-1 III . S . 8 Attacnnent 8: Containment Spray III-8-1 III.S.9 Attachment 9: Reactor Cleen-up III-9-4 III.5.10 Attachment 10: Inert Gas Purge and Fill III-10-1 I1I.5.11 Attachment 11: Hydrogen-Oxygen Monitoring III-11-1 I11.5.12 Attachment 12: TIP III-12-1

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PUNP AND VALVE INSERVICE TESTING PROGRAN PLM TABLE OF CONTENTS (Cont'd)

SECTION TITLE PAGE III.5.13 Attachment 13: Nitrogen Supply #11 III-13-1 III.5.14 Attachment 14: Nitrogen Supply #12 III-14-1 III.5.15 Attachment 15: Reactor Building HVAC III-15-1 III.5.16 Attachment 16: Liquid Poison III-16-1 III.S.17 Attachment 17: Spent Fuel Storage Pool Filtering & Cooling III-17-1.

III.5.18 Attachment 18: Sample . III-18-1 III.5.19 Attachment 19: Reactor Building Closed Loop Cooling III-19-1 III.S.20 Attachment 20: Condensate Transfer III-20-1 III.5.21 Attachment 21: Torus Vacuum Relief III-21-1 III.S.22 Attachment 22: Emergency Service Water III-22-1 III.S.23 Attachment 23: Emergency Diesel Generator Cooling Water III-23-1 III.5.24 Attachment 24: Waste Disposal III-24-1 III.S.25 Attachment 25: Breathing Air To Drywell III-25-1 l

March 1987

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I 4 PUNP AND VALVE INSERVICE TESTING PROGRAM PLAN i

for l 'NINE MILE POINT j NUCLEAR POWER STATION

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.i SECTIOh I OVERVIEW i Pages i

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l.0 Introduction This document presents the 2nd Ten Year Program Plan for Inservice Testing (IST) of Pumps and Valves at tne Nine Mile Point Nuclear Station Unit 1 (NMP-1) in compliance with the requirements of 10CFR50.55a(g) and Plant Technical Specification 3.2.6. This Program Plan was prepared in accordance with the rules of the ASME Boiler and Pressure Vessel Code,Section XI, 1983 Edition, Summer 19S3 Addenda. As specified in 10CFR50.55a(g) (4)ii, this edition and addenda of the Code will remain in effect for the entire 120-month inspection interval.

Although the 1st ten year inspection interval was not scheduled to end until December 1989, Niagara Mohawk voluntarily revised the program. The revised Inservice Testing Program ten year interval now runs concurrently with the revised Inservice Inspection ten year interval; from June 1986 to June 1996 (Refe renc( C. V. Mangan, NMPC, letter to D. B. Vassello, NRC, dated September 13, 1983).

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4 2.0 Bases In addition to the reference Code edition and addenda, the Program Plan has been prepared in compliance with the NRC guidance (except wnere exemption /

relief has been requested) contained in " Guidance for Preparing Pump and Valve Testing Program Descriptions and Associated- Relief Requests Pursuant to 10CFR50.55a(g)" and the November 1981 Draft Regulatory Guide " Identification of Valves - for Inclusion in Inservice Testing Programs." These three documents provide the basis for selection of components, test requirements, relief I requests, and format.

Regarding the inclusion of certain valves based on their Containment / Reactor Coolant Isolation functions; this program is inclusive of all valves which are categorized as Isolation Valves as specified in both the current Technical Specification tables (3.2.7 & 3.3.4) and the revised Appendix J ' Technical Specification Aasendment request of August 27, 1984 and as Aasended November 13, 1985. Current NMP1 practice (based on interim NRC Concurrence) is to perform leak date Testing in accordance with the . Revised Appendix J submittal. An exemption from Appendix "J" testing requirements is considered an exemption from ASME Section XI code requirements also.

All information except individual valve maximum strote times, requested by the reference documents has been included in this Program Plan. This revision of tne NdP-1 Valve Testing Program includes a number of valves not previously tested and for which maximum stroke times are not yet available. Because of 1 this, tiMP-1 has elected not to include maximum stroke times into tne Program Plan at this time. Maximum stroke times will be determined for all appropriate valves and recorded in a separate NdP-1 document as they are established.

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u 3.0 General Program Plan Concept The Program Plan specifiesSection XI testing requirements for components providing, either by action or position, a safety-related function. By definition, a safety-related function is one that is needed to:

a) Mitigate the consequences of an accident b) Shut down the reactor to the cold shutdown condition Plant Technical Specifications, special manufacturer's tests, system operating conditions, etc., may dictate additional components which should be included in the overall plant testing program, but whose- functions fall outside the criteria above, and are, therefore, not .2ddressed by this Program Plan.

Section XI requires quarterly testing of all components unless it is impractical to do so. This program specifies quartorly testing of Pumps and valves unless it has been determined that such testing would:

a) Be impractical due to system or component design b) Render a safety-related system inoperable

, c)  % se a reactor scram or turbine trip d) Require significant deviations from normal operations e) Require entry into inaccessible plant areas f) Increase the possibility of an inter-system LOCA Each component excluded from quarterly testing has been analyzed to determine when appropriate testing may be performed. If operation of a valve is not practical during plant operation, the Code allows part-stroke exercising during normal plant operation, and full-stroke exercising at cold shutdown.

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Since the Code allows testing at cold shutdown, this program does not request j relief for those valves for which testing is delayed until cold shutdown, The Valve IST Program Plan does provide a justification for the delay of testing-until cold shutdown. These justifications are prepared in a format similar to relief requests, and are included following the Valve Test Tables for each system.

Where it has been determined that testing is not practical during plant operation, or at cold shutdown, a specific relief request has been prepared.

Each specific relief request provides justif* cation for'not performing the Code required testing, and provides appropriate alternative testing.

In addition to specific relief requests, general relief requests which address specific Code requirements found to be impractical for this site have been prepared. Because of the general nature of these relief requests, and the number of components involved, they are presented in separate sections and are not repeated in the individual system sections.

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4.0 Organization j

The Pump and Valve Inservice Testing Program Plan is organized into three I independent sections, each of which can be removed from the Program Plan . for

~j review. Section I presents the general program commitment basis, the conceptual framwork used in developing the Program Plans, and general relief requests for Code requirements found to be impractical for this site.Section II deals specifically with the Pump Test Program, and Section III deals l specifically with the Valve Test Program.

j Section II and III are formatted in a manner to aid review. Each section summarizes the basic and concepts used to formulate the Pump and Valve Test j Tal,les. Pump testing requirements are summarized in a single Pump Test Table i attached to Section II. Valve test requirements are sumanarized in Valve Test

Tables attached to Section III. The Valve Test Tables are arranged into 1 j separate attachments for each system. Where quarterly testing has been found )

to be impractical, either a justification for delay of test to cold shutdown, l j or a relief request, is provided following the appropriate Pump or Valve Test i

> Tables. In those cases where additional discussion of the test requirements for a component is needed, the remarks . column of the Test Table contains a Note Number. These Notes may be found following the Valve Test Tables for each system.

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5.0 Definitions The terms below, when used in the Inservice Testing Program Plan, are defined as follows:

Quarterly: An interval of 92 days for testing components which can be tested during normal plant operation.

Cold Shutdown: Tecting deferred until cold shutdown shall.

cosusence within 48 hours of achieving :old shutdown, and shall continue until all testing is complete or until the plant is ready to return to power. Completion - of cold shutdown testing is not a prerequisite to return to power. Any testing not completed at one cold shutdown will be preferentially scheduled for testing at subsequent cold shutdowns. Cold shutdown testing of a component is not required if less than 92 days have passed since the last cold shutdown test of that component. For scheduled outages greater than 14 days, all cold shutdown tests will be performed; testing does not have to commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Refueling: Testing deferred to refueling will be performed during the normal scheduled refueling shutdown before returning to power operation.

Period: Category C safety and relief valves (IWF-3511).

Category D explosive actuated valves (IWF-3610) and Category D rupture disks (IWF-3620) are periodically tested as defined in the appropriate Code Sections.

Pressure Isolation: Any valve which acts as an isolation boundary j between the high pressure Reactor Coolant System and a system having a lower operating or design pressure.

Containment Isolation: Any valve which performs a containment isolation function and is included in the Appendix J Leak Rate Test program. I l

Active: Any valve which is required to change position to accomplish its safety-related function.

Passive: Any valve which is not required to change position to accomplish a specific function.

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lIl 6.0 General Relief Requests for Pumps This section requests relief from specific requirements of Section XI found to be impractical for this site. Since they are general in nature, and pertain to a number of components, this section requests general relief ss presented below.

General Relief kequest: PG-1 Pumps: All centrifugal pumps Test Requirements: Differential pressure alert and required action ranges (Table IWP-3100-2).

Basis for Relief: Pump overpressure is an indicator of pump clogging or improper maintenance and as such is an important test parameter to measure. However, small positive increases in measured differential pressure across a centrifugal pump are most likely not a significant indicator of pump degradation. Adherence to the Code specified alert and required action ranges could result in unnecessary pump testing and repair. In order to preclude unnecessary testing and repair, pump differential pressure will be measured and expanded alert and required action ranges used.

Alternate Testing: In lieu of the Code specified values, the high i side acceptance range will be 1.05 times the reference pump differential pressure. The high aide alert and required action ranges will be 1.05 to 1.07 and > 1.07 times the reference pump differential pressure respectively, t

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g-7.0 General Relief Requests for Valves This section requests relief from specific requirements of Section XI found to be impractical for this site. Since they are general in nature, and pertain to a number of components, this section requests general relief as presented below.

General Relief Request: VG-1 Component: Rapid actuating power operated valves with stroke times of 5 seconds or less.

Category: A, B Code Requirements: IW-3417 requires corrective action if the measured stroke. time for a valve which normally strokes in ten seconds or less increases by fifty percent from the last measured stroke time. IW-3413 allows measurement to the nearest second for stroke times of ten seconds or less.

Basis for Relief: For rapid actuating power operated valves the application of the above criteria could result in requiring corrective action when the valves are functioning normally. These valves are generally small air and solenoid operated valves which because of their size and actuator types stroke very quickly.

Operating history on this type of valve indicates that they generally either operate isumediately or fall to operate in a reasonable length of time. The intent of the referenced Code sections is to track valve stroke time as a means of detecting valve degradation. This type of valve does not lend itself to this tracking technique.

Alternate Testing: A maximum stroke time of five seconds (or two times the reference stroke . time, '

whichever is greater) will be specified for each rapid actuating valve. If the valve j strokes in five seconds (or two times the i reference stroke time, whichever is greater)

it will be considered as acceptable and no I corrective action will be required. If the

! valve stroke time exceeds five seconds (or j' two times the reference stroke time, i whichever is greater), it will be considered I l inoperable and appropriate corrective action l l will be taken.

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7.1 General Relief Request for Valves General Relief Request: VG-2 Component: Containment Isolation Valves Code Requirements: For Section XI category A valves IWV-3426 requires the establishment of individual valve permissible leaktge rates. Each time leak-rate tests are performed the test results are to be compared with the previous test results and the permissible leakage rates. IWV-3427 establishes test result rejection criteria and specifies corrective actions to be taken.

Category: A, AC j Basis for Relief: IWV-2200(a) defines category A valves as

" valves for which seat leakage is limited to a specified maximum amount in the closed position for fulfillment of their function." The intent of the Code requirement is to verify that valve leakage is limited to an acceptable value. For containment isolation valves an acceptable total allowed leakage rate has been established in compliance with the requirements of 10CFR50 Appendix J.

Appendix J. Type C Local Leak Rate testing is performed in lieu of Section XI Category A individual valve seat leak testing, for containment isolation valves.

Alternato Testing: Containment isolation valves will be local leak rate tested to the requirements of Appendix J. Type C testing in lieu of Section XI Category A individual valve seat leak testing.

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-3 7.2 General Relief Request for Valves General Relief Request: VG-3 Component: Primary Containment Isolation Valves.

Category: A,C Code Requirements: IWV-3420 requires category A valves to be leak tested at least every two years. For primary containment isolation valves this is accomplished in accordance with 10 CFR50, Appenxiz J. (Reference VG-2)

Basis for Relief: Reference " Application for Ammendment to Operating License", submitted to the U.S. Nuclear Regulating Commission for Nine Mile Point Unit 1, Docket No.

50-220, DPR-63, dated August 27, 1984 with ammendment supplement dated November 13, 1985. The following valves are affected:

Valve No. Description Appendix-J Exemption (s) 05-Olk EMC high gaiet vent Type - A Testing 05-04R EMC high pc' nt vent

. Type - A Testing 05-11 EMC high pcint vent Type - A Testing 05-12 EMC high prMnt vent Type - A Testing 38-01 SDC I.V. (Outlet) Type A & C Testing 38-02 SDC I.V. :9utlet) Type A & C Testing 38-12 SDC I.V. (intet) Type A & C Testing 38-13 SDC I.V. (inlet) Type A & C Testing 39-03 EMC return I.V. Type A & C Testing 39-04 EMC return I.V. Type A & C Testing 39-05 EMC return I.V. Type A & C Testing 39-06 EMC return I.V. Type A & C Testing 40-05 Core Spray testline I.V. Type A & C Testing 40-06 Core Spray testline I.V. Type A & C Testing 63.1-01 RCU SRY Discharge Type A & C Testing 63.1-0? RCU SRV Discharge Type A & C Testing 70-92 RBCLC Supply to Recire. Non-Testable Pump Mctor Coolers 70-93 RBCLC Supply to Rectre. Non-Testable Pump Mctor Coolers 70-94 RBCLC Supply to Drywell Non-Testable Air Coolers 70-95 RBCLC Supply to Drywell Non-Testable Air Coolers 301-112 CRD Hydraulic I.V. Type A & C Testing (outnide) 301-113 CRD Hydraulic I.V. Type A & C Testing (inside)

Alternate Testing: For alternate testing, reference the above listed Ammendment to the Operating License.

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1 PUMP AND VA1.VE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION II PUMP IST PROGRAM PLAN Pages II-1 through II-5 II-1 fl

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5 1.0 Introduction This section presents the Program Plan for Inservice Testing of safety-related l,

Pumps at Unit 1 of the Nine Mlle Point Nuclear Station, in compliance with the

requirements of 10CFR50.55a. This Program Plan has . been prepared to the requirements of the ASME Boller and Pressure Vessel Code.Section XI.

Subsection IWP, 1983 Edition through the Summer 1983 Addenda.

The Pump Program Plan specifiesSection XI testing requirements for all ASME Class 1, 2 and 3 pumps provided with an emergency power source, and which are required for safety-related system operation. Test requirements determined to be impractical for a large number of pumps have been addressed in Section I j under General Relief Requests for Pumps. In addition to those General Relief l Requests, this section includes requests for relief from Code requirements j found to be impractical for specific pumps. Each relief request provides justification for deviation from the Section XI specified test, and proposes l appropriate alternate testing.

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lf 2.0 Code Interpretation A number of items in Subsection IWP of the Code are subject to  !

interpretation. 'The interpretations of a number of general items encountered in preparing the Pump Test Program Plan are provided below. I Pump Test Data within the Required Action Range (Table IWP-3100-2)

When test results show deviations greater than allowed by Table IWP-3100-2, the instruments involved may be checked for accuracy and the test rerun. If the second test provides results falling within the required action range, then corrective action must be implemented. This corrective action may be either replacement, repair, or analysis to demonstrate that the condition does not impair pump operability, and that the pump will still fulfill its safety-related function. If the analysis verifles that the pump is operable, -l a new set of reference values will be established. If the instrumentation is checked, and the test terun with results in the acceptable range, the first set of test results will be discarded, and the second set retained.

Analysis of Data within 96 Hours'(IWP-3220) ,

All Code required test pa-ameters will be reviewed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of test to verify that they do not fall within the required action t range. Those that fall within the required action range will be processed as described above. Those that fall within the required action range will be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of the test. This fulfills the intent of the Code to require immediate action on pumps f alling within the required action range and allows orderly reduction of data taken on weekends or holidays, when sufficient staff may not be available to perform the Code required analysis.

Scope of Tests (IWP-3300) i Subarticle IWP-3300 requires that each inservice test measure and observe all the quantitles in Table IWP-3100-1 except bearing temperature, which shall be measured at least once a year. The Code assuces that each pump installation can be instrumented to obtain the specified quantities. In some installations it is not possible to provide instrumentation to obtain Code specified quantitles. For example, submerged pwaps cannot be instrumented to measure inlet pressure and observation of proper lubricant level or pressure is not possible for a greased bearing pump. In some cases it is possible to substitute an alternate method. For example, inlet pressure for a submerged pump can be calculated by measuring the head of water relative to the pump l suction. This program does not request relief from Section XI testing for l those quantitles which cannot be obtained due to pump design or installation.

Explanatory notes have been used in the Pump Test Table when Section XI testing is not possible due to pump design or installation.

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3.0 Pump List Pumps required for safety-related operation for this site are as follows:

SYSTEM DWG. NO. REV. NO. NO. of PUMPS Core Spray C-18007-C 29 4 Core Spray Topping C-18007-C 29 4 Spent Fuel Pool Cooling C-18008-C 11 2 i

containment Spray C-18012-C Sh.2 85-52-C2(2/13/85) 4 Containment Spray Raw Water C-18012-C Sh.1 85-52-C2(2/13/86) 4 Liquid Poison C-18019-C 12 2

.hergency Service Water C-18022-C Sh.3 8 2 RBCLC C-18022-C Sh.3 8 3 Emergency D. G. Cooling C-18026-C Sh.1 4 1 C-18026-C Sh.2 85-27-Cl(1/14/86) 1 i Condensate Transfer C-18048-C 18 2

! HQTX: Revision numbers listed are those current during Program Plan development, and may not reflect the most current drawing revision available.

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0 4.0 Pump Table Nomenclature The following abbreviations have been used in the Pump Test Table:

N = Rotative Speed Pi = Inlet Pressure (Before and after pump start)

AP = Differential Fressure Qf = Flow Rate Y = Vibration Amplitude Tb = Bearin5 Temperature Q = Quarterly C = cold Shutdown X = Measurement / Observation per IWP L = Lubricant Level or Pressure PR = Pump Relief Request II-5 lL

G PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION II.5.0 ATTACHMENT 1 PUMP TEST TABLE AND RELIEF REQUESTS FOR PUMPS Pages II-1-1 through II-1-11 II-1-1

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_ _ _g 6.0 Pump Test Table Notes l

1 In the Pump Test Table, the test parameters to be measured or observed, a.d l the test frequency are identified. Footnotes 1 through 9 refer to amplifications, deviations, and exceptions to the Code requirements and are further discussed below:

(1) Pump with constant speed drive, speed is not measured since test will Le performed at nominal motor nameplate speed as required by Section XI, IWP-3100.

(2) Inlet pressure to be calculated from the inlet 11guld level.

(3) Bearing temperature measurement not required (IWP-4310) since bearings are in the pumped fluid flow path.

(4) Bearing temperatures are measured once a year as stipulated by Section XI, IWP-3300.

(5) Lubricant level or pressure not observed because of bearing lubrication design.

(6) Direct bearing temperature measurements not possible since bearings are an integral part of the pump drive unit. Lubricant temperature shall be measured at a point solected to be responsive to changes in the temperature of the bearings.

(7) Flow rate determined by change in 11guld level.

(8) Two pumps in series, both operating during test with flow and discharge pressure measured at discharge of second pump.

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PUMP TEST TABLE PUMP LIST MEASURED PARAMETRRS PUMP CO- ASME TEST PUMP NAME I.D. P&I.D. NO. ORD. CLASS FREQ. N Pi AP Qg V Th4) L Liquid Poison NP02A C-18019-C H-5 2 Q (1) PR-4 PR-4 (7)PR-4 I (6) X (C11. C12) NP028 H-7 2 Q (1) PR-4 PR-4 (7)PR-4 I (6) I Energ:ncy Service 72-04 C-18022-C B-5 3 Q (1) (2) I PR-5 PR-6 (3) (5) ',

(2) (3) (5) l Water 72-03 sh. 3 D-5 3 Q (1) X PR-5 PR-6 I (C11. 012) l l

Reacter Building 70-01 C-18022-C D-8 3 Q (1) X PR-7 PR-7 I I I C1 ced Cooling 70-02 Sh. 3 D-7 3 Q (1) X PR-7 PR-7 I X X i Water 70-03 D-6 3 Q (1) X PR-7 PR-7 I I X l (C11. C12, #13)

Core Spray 81-23 C-18007-C B-7 2 Q (1) (2) (8)PR-2 (8)PR-2 PR-6 (3) (5)

(C111. #112 81-24 B-8 2 Q (1) (2) (8)PR-2 (8)PR-2 PR-6 (3) (5)

C121 #122) 81-03 L-7 2 Q (1) (2) (8)PR-2 (8)FR-2 PR-6 (3) (5) 81-04 L-8 2 Q (1) (2) (8)PR-2 (8)PR-2 PR-6 (3) (5)

Core Spray 81-50 C-18007-C A-5 2 Q (1) PR-2 (8)PR-2 (8)PR-2 X X X

, Topping 81-49 A-5 2 Q (1) PR-2 (8)PR -2 (8)PR-2 X X X (C111. #112 81-51 M-5 2 Q (1) PR-2 (8)PR-2 (8)PR-2 X X X C121 #122) 81-52 M-5 2 Q (1) PR-2 (8)PR-2 (8)PR-2 I I I II-1-3

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PUNP TEST TABLE PUMP LIST MEASURED PARAMETERS ASME TEST PUNP NAME PUNP I.D. P&I.D. NO. COORD. CLASS FREQ. N Pi AP Qg V Th4) L Energency D. C. 72-62 C-18026-C B-9 3 Q (1) (2) X PR-1 PR-6 (3) X Cooling Sh. 1 Water 72-63 C-18026-C A-9 3 Q (1) (2) X PR-1 PR-6 (3) X (C102. #103) Sh. 2 Spent Fuel Storage 54-01 C-18008-C C-5 3 Q (1) (2) X X X X X Pool cooling 53-02 C-8 3 Q (1) (2) X X X X X (011. #12)

Contclament Spray 93-02 C-18012-C R-8 3 Q (1) (2) X X PR-6 (3) (5)

Raw Water 93-01 Sh. 1 F-8 3 Q (1) (2) X X PR-6 (3) (5)

(0111. #112 93-04 C-8 3 Q (1) (2) X X PR-6 (3) (5)

C121, #122) 93-03 J-9 3 Q (1) (2) X X PR-6 (3) (5)

Contclament Spray 80-04 C-18012-C D-7 2 Q (1) (2) X X PR-6 (3) (5)

(C111. #112 80-24 Sh. 2 J-7 2 Q (1) (2) X X PR-6 (3) (5).

C121, #122) 80-03 D-9 2 Q (1) (2) X X PR-6 (3) (5) 80-23 J-9 2 Q (1) (2) X X PR-6 (3) (5)

Condensate 57-12 C-18048-C I-8 3 Q (1) (2) X PR-3 I I I Tran:fer 57-11 H-8 3 Q (1) (2) X PR-3 I I I (Cll, #12) l II-1-4

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NINE MILE POINT NUCLEAR STATION UNIT 1 7.0 PUMP RELIEF REQUEST 7.1 PR-1 System: Emergency Diesel Generator Cooling Water Pump: 72-62:72-63 Class: 3 Function: Provide cooling water to the Emergency Diesel Generators.

Test Requirements: Measure flow rate (IWP-3100).

Basis for Relief: There are no system design provisions to measurt flow.

Alternate Testing: Pump differential pressure, pump motor vibration, and pump motor current will be used to evaluate pump performance, t

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LT NINE MILE POINT NUCLEAR STATION UNIT 1 7.0 PUMP RELIEF REQUEST 7.2 PR-2 System: Reactor Core Spray Pump: Core Spray 81-03:81-04:81-23:81-24 Core Spray Topping 81-49:81-50:81-51:81-52 Class: 2 Function: To provide cooling to the core in the event of a LOCA.

Test Requirements: Measure flow rate and differential pressure (IWP-3100)

Basis for Relief: The Core Spray and Core Spray Topping pumps are operated simultaneously. The flow from the Core Spray pump is delivered to the suction of the topping pump such that independent pump flow and differential pressure measurement are not possible.

Alternate Testing: The combined flow will be measured downstream of the topping pumps. Differential Pressure will be measured from the suction of the Core Spray pumps to the discharge of the Core Spray Topping pumps.

II-1-6 IT

, u g NINE MILE POINT NUCLEAR STATION UNIT 1 7.0 PUMP RELIEF REQUEST 7.3 PR-3 System: Condensate Transfer

! Pump 57-11:57-12 Class: 3 Function: To provide make-up water to safety-related cooling systems.

Test Requirements: Neasurement and Analysis of flow rate and differential pressure.

8 asis for Relief

This is a normally operating system which provides water to a large number of components.

The demands on the system vary constantly, which consequently maxes flowrate and differential pressure readings meaningless in evaluating pump performance. There is no design provision for testing the pumps. The only direct line back to tne condensate tank is a small (3/4 inch) line with a flow restricting orifice. Without a pump test line, it is lapossible to perform Code required measurements and analysis of flow and differential pressure.

Alternate Testing: Pump vibration measurement will be used to evaluate pump performance. Pump differential, pressure and pump motor currrent will be monitored.

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I NINE MILE POINT NUCLEAR STATION UNIT 1 7.0 PUNP RELIEF REQUEST 7.4 PR-4 System: Reactor Liquid Poison Pump: NP02A:NP028 Class: 2 Function: Provide a method of shutting down the Reactor without use of the Control Rods.

Test Requirements: Neasure flow rate, suction and differential pressure.

Basis for Relief: These pumps are tested by pumping water from a test tank into a 55 gallon barrel foe one minute and calculating flow rate from test barrel water level increase. Pump suction pressure is the head of water in the test tank and test lines which decreases as the tank level drops during testing. Pump discharge pressure and flow rate are established by adjusting a single manual gate valve in the pump discharge test line to the 55 gallon barrel. Because of limited test tank volume and gate valve characteristics, it is not

-possible to establish an exact reference discharge test pressure in the short test time available. Because of the inherent inaccuracy in measuring test barrel water level, decreasing suction pressure during testing and the inability to establish exact discharge pressure, adherence to code allowable ranges in Table IWP-3200-2 could result in unnecessary additional testing and repair.

Alternate Testing: The test tank provides pump suction pressures above minimum pump requirements and will not be i measured or calculated. Because of the variation I in suction pressure and inability to set exact discharge pressures, differential pressure will not be used to monitor pump performance. Pump flow rate and discharge pressure will be measured as follows:

Test Quantity AcceDtance Ranae Flowrate. Q .91 - 1.06Qr Discharge Press., P .894 - 1.057 Pr Alert Ranae Roo'd Action Ranae k9X lilAh k92 fil.1h

.87 .91Qr 1.06-1.070r <.87Qr >1.07Qr

.868 .894Pr- 1.037-1.068Pr <.868Pr >1.068Pr II-1-8 tl

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NINE MILE POINT NUCLEAR STATION UNIT 1 7.0 PUNP RELIEF REQUEST 7.5 PR-5 System: Emergency Service Water Pump: 72-03:72-04 Class: 3 Function: Provide cooling water to safety-related equipment.

Test Requirements: Measure flow rate (IWP-3100).

Basis for Relief: There are no system design provisions to measure flow in the pump test lines.

Alternate Testing: Pump differential pressure, pump motor, vibration, and pump motor current will be used to evaluate pump performance.

II-1-9 q

f NINE MILE POINT NUCLEAR STATIOld UNIT 1 7.0 PUMP RELIEF REQUEST 7.6 PR-6 System: Emergency service water, emergency diesel generator cooling water, core spray, containment spray, raw water, containment spray.

Pump: 72-03, 72-04, 72-62, 72-63, 81-03, 81-04, 81-23, 81-24, 93-01, 93-02, 93-03, 93-04, 80-03, 80-04, 80-23, 80-24 Class: 2,3 Function: Cooling Water Supply Test Requirement: Measure vibration on pump bearing housing (IWP-4500).

Basis for Relief: These pumps are verticle centrifugul submerged process pumps. The pump bearings are not accessible for vibration measurements.

Alternate Testing: Vibration measurements will be taken from points on the pump motors.

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NINE MILE POINT NUCLEAR STATION UNIT 1 7.0 PUMP RELIEF REQUEST 7.7 PR-7 System: Reactor Building Closed Loop Cooling Water Pump: 70-01:70-02:70-03 Class: 3 Function: Provide cooling water to safety-related equipment.

Test Requirements: Measure flow rate and differential pressure (IWP-3100).

B2 sis for Relief: The RBCLC system is not a fixed resistance system and there are no pump test loops installed. The system flow rate and the number of pumps running are a function of '.he system heat loads. In most cases it is not possible to operate the system with a single pump and align the system to achieve Code test conditions without adversely affecting plant operation Alternate Testing: Pump vibration will be used to evaluate pump performance. Pump differential pressure and flow j rate will be monitored for each combination of pumps. (Two pumps run concurrently).

11-1-11

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PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III VALVE IST PROGRAM PLAN Pages III-1 through III-11 i

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1 III-1 4

t 1.0 Introduction

This section presents the Program Plan for Inservice Testing of Valves at Unit 1 of the Nine Mile Point Nuclear Station, in compliance with the requirement of 10CFR50.55a. This Program Plan has been prepared to the requirements of the ASME Boller and Pressure Vessel Code,Section II, subsection IWV, 1983 Edition through the Sussner 1983 Addenda.

l The Valve Test Program Plan was developed to verify the operability of

! safety-related systems. The valves addressed are those whose operability is essential to safety-related system operation. Section II valve testing is

then specified for each of these valves to verify individual velve operability. The Program Plan specifies either Section XI or alternate testing, as appropriate, for all valves which perform a safety-related function.

Valves are selected for inclusion in the test program based on a review of all

plant systems. This review identifies those systems performing safety-related i functions. Each safety-related system is then analyzed to determine which valves are essential to the safety-related operation of the system. These valves are investigated to determine whether Section II testing can be

performed during normal operation. Those valves for which quarterly testing i is determined to be inappropriate are analyzed further to determine if Code allowed cold shutdown testing is possible. If so, a justification for delay j of test to cold shutdown is provided following the appropriate Valve Test i Tables. Relief requests describing appropriate alternative testing, and justifying exclusion from Section II testing, have been prepared for valves which cannot be tested quarterly or during cold shutdown, and are provided following the appropriate Valve Test Tables.

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- - --.-- ,---._..~ - -. - -. _ ,_..-. ,,- - - - , - - . . , , . _ , , - , . . . - - - - - - , . . , , _ - - . __,.,_.-.....-,.-....---,,----...,.n-- , - - , , , - ~ - . ,

- .tn 2.0 Code Interpretation A number of items in Subsection IWV of the Code are subject to interpretation. The interpretations of a number of general items encountered in preparing the Valve Test Program Plan are provided below.

Relief Valves:

The Code requires testing of pressure relief valves in accordance with ASME PTC 25.3-1976. The relief valves designated for test are only those which perform a system pressure relief function. Thermal relief valves, whose only function is to protect components or piping from thermal expansion are not considered to be safety-related and are not addressed in the program. Where a relief valve performs both a system and a thermal relief function it has been included as testable.

Passive Valves:

The reference Code excludes valves used only for operating convenience and/or maintenance testing. Also, the code defines passive valves but specifies no operability test requirements. This program defines as passive power operated valves which do not have to change position to accomplish a specific function.

System Test Valves:

Power operated valves which receive an automatic initiation signal, that are used to align a system for testing purposes, are included for Section XI testing.

Pressure and Flow Control Valves:

The reference Code excludes valves which perform pressure or flow control functions. This program excludes them unless they also perform a system safety-related response function such as automatic closure on system initiation. The program addresses thene valves by specifying testing of the safety-related function, and excluding the normal pressure or flow control functions.

Automatic Power Operated Valves Power operated valves which receive an automatic signal on system initiation are included in the program.

III-3 0

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2.0 Code Interpretation (Cont.)

Remote Power Operated Valses:

The program includes power operated valves activated by remote switches if they are required to change position to align a system for safety-related operation, or provide containment isolation.

Normal vs. Safety-Related System Operation:

Valves in systems which have both normal and safety-related operating modes are incit.ded in the program only if they perform a safety-related function.

Valves which provide normal system operation control and whose position has no effect on safety-related operation are excluded from the program.

Dual Function Valves:

Valves which provide more than one function are tested for their safety-re.ated function only. Valves with multiple safety-related functions-are tested for each function. Examples are the automatic depressurization valves, which open and close in response to either an automatic or remote manual signal, and also act as relief valves. Both are safety-related functions, and testing for both functions is included in the program.

Simple Check Valves:

This Program Plan considers any check valve to be a simple check valve if it has no means of changing position other than by fluid flow. Simple check valves are tested to verify operability in the safety-related flow direction.

Normally closed simple check valves which must open are tested to verify full opening with forward flow. Normally open simple checks which must close on cessation of flow are tested to verify closure on cessation of forward ficw.

Normally closed simple check valves which remain closed on system initiation are tested to verify absence of reverse flow. Normally open simple check valves which are required to remain open, are tested to verify full flow in the forward direction. Simple check valves which are required to cycle open and closed are tested to verify full opening with forward flow and closure on loss of forward flow.

Manual Stop Check Valves Manual stop check valves are tested to verify operability in the safety-related flow direction. If the manual operator is withdrawn, the valve operates as a simple check in the forward flow direction and is tested as a simple check. Reverse flow closure is verified as a slmple check, if possible, or by use of the manual operator.

Testable Check Valves Check valves equipped with manual exercisers will be tested as a simple check, or by exercising using the manual exercising device. Check valves equipped with a power operator installed for the sole purpose of exercising the valve for operability will be tested as a simple check, or by use of the power operator.

III-4 I

9 2.0 Code Interpretation (Cont.)

Power Operated Stop Check Valves:

Testing of power operated stop check valves is based on the function of the operator. If the valve operator is always withdrawn, and the valve operates as a simple check valve except during maintenance, the valve is tested as a simple check. If the operator is normally withdrawn, such that the valve operates as a simple check in the forward direction, and the operator provides positive closure, it is tested as a simple check in the forward direction, and exercised closed usine the operator. In addition to exercising, the operator will be timed an1 tail safe actuation tested as appropriate.

Pump Discharge Check Valves:

As a minimum, pump discharge check valves in safety-related systems will be forward flow exercised. In addition, reverse flow closure will be verified when failure of the valve to close could result in a substantial reduction of system performance. Such a potential exists with parallel pumps connected to common suction and discharge headers. If the check valve on the idle pump falls to close, a significant amount of system flow could be diverted back through the idle pump to the suction header.

System Piping Keep Fill Check Valves:

Keep till lines are those lines attached to gCCS system piping whose function is maintenance of system water inventory to preclude water hammer. Forward flow operability is verified by a system check of water inventory performed at least quarterly. Reverse flow closure verification is performed only if failure of the valve to close could result in a significant reduction of gCCS system operation.

Check Valve Full / Partial Stroke:

In most cases full design flow through a check valve requires less than full mechanical valve movement. As used in this program, the term full stroke refers to the ability of the valve to pass design flow, and not the full mechanical stroking. Forward flow full stroke operability testing will be by any method that verifles the valve is capable of passing design flow. Any test that verifies less than full design flow capability is considered as a l partial stroke test.

Category A (Containment Isolation Valve) Leak Testing:

All valves specified for Appendix J. Type C Local Leak Rate testing are included in the Valve IST Program as Category A valves. A Relief Request (see VG-2) has been included to perform the Appendix J. Type C testing in lieu of testing specified in IWV-3420. The Program Plan reflects the current list of valves receiving Appendix J. Type C Testing. Any future change to that list will be incorporated into the valve test program.

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v tr 2.0 Code Interpretation (Cont.)

Category A (pressure Isolation Valve) Leak Testing:

All valves which perform a pressure isolation function between the Reactor Coolant System and a low pressure system are included in the Valve IST program as Category A valves. These valves will be tested to the requirements specified in IW-3420.

Category A (Containment and pressure Isolation Valve) Leak Testing:

Valves which perform both a containment isolation and a pressure isolation function are included in the Valve IST progen plan as Category A Valves.

These valves will be tested to requirements of both Appendix J and Section XI.

Locked Valves:

This program plan classifies as locked valves only those which are physically restrained from movement (i .e. , chain and padlock), or sealed (i.e., wire and seal) in position. Keylocked valves are not considered to be physically locked. This program plan makes no distinction between locked and non-locked manual valves and considers both to be passive.

Valve Timing:

All required maximum stroke times will be established and incorporated into a separate NNPI document.

Valve position Indicator Verification:

IW-3300 requires that all valves with remote position indicators shall be observed at least once every two years to verify that valve operation is accurately indicated. This program specifies all valves equipped with remote position Indicators for which verification of proper operation will be performed during each refueling outage.

Valve Fall Safe Testing:

IW-3415 requires proper operation of valves equipped with Fall Safe Actuators to be observed. For NMp1, this is accomplished by placing the control to the position which de-energizes the actuator and observing proper valve operation.

I III-6 k

3.0 Valve Test Table Nomenclature The following abbreviations have been used in the Valve Test Table Valve Troe Actuator Tree AGV - Angle Valve APA - Alr/Platon ADA - Air /Diaphram BFV - Butterfly Valve EXA - Explosive BLV - Ball Valve HOA - Nydraulic CHV - Check Valve NAA - Nanual EIV - Explosive Valve NPA - Nitrogen / Piston NDA - Nitrogen /Diaphram GLV - Globe Valve SEA - Self GTV - Cate Valve SOA - Solenoid NDV - Needle Valve REV - Rollef Valve SCV - Stop Check Valve Stroke Direction TPV - Two Port Valve 0 - Closed to Open TWV - Three Way Valve C - Open to Closed PGV - Plug Valve Normal Position Check Valve Test Direction 0 - Open F - Forward Flow C - Closed R - Reverse Flow LO - Locked Open ,

I LC - Locked Closed TH - Throttled DE - Normal position depends on system condition (check valves).

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3.0 Valve Test Table Nomenclature (Cont.)

Test Reeutrements i EX - Explosive Valve toit per IWV-3610.

FE - Full Stroke Exercise test.

FS - Fall Safe test.

LC - Leak Test per both Appendix J. Type C, and Section XI (both pressure and containment isolation function).

LJ - Leak Test per Appendix J. Type C (containment isolation function only).

LK - Leak Test per Section XI (pressure isolation function only).

PE - Partial Stroke Exercise test.

PI - Remote Position Indication Verification.

PV - Passive Valve (no operability tests required).

RD - Rupture Disk test per IWV-3620.

RT - Rollef Valve test.

ST - Stroke Time test.

Test Frequency C - Testing performed during cold shutdown P - Periodically tested during the time period defined int IWV-3511 (safety and relief valves)

IWV-3610 (explosive actuated valves)

IWV-3620 (rupture disks)

Q - Once per 92 days (Quarterly)

R - Once per refueling outage ,

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U 4.0 Valve Test Table Format Valve No. and Description Unique number assigned to each valve, and a description of tne valves function within the systes.

Class and Dws. Coor. The ASME wive classification (Class 1, 2 or 3), and tne valve location on the reference drawing.

Valve Cat. Valve ca tegory as defined in Sub-a rticle IWV-2200.

Size (in.) and Type Valve size is the nominal disseter of the valve in inenes.

Valve type is the specific type of valve, as abbreviated in Section 3.0 " Valve rest Table Nomencia ture".

Actu. Type The type of Actua tor used to opera te the valve.

Nora. Posit. The valve position during norasi plant opera tion.

Test Req. The Section XI test requirement (s) wnich apply to the valve.

Stroke Direct. The direction in whien the valve is required to be Stroke Timed (SI), indicated by "0" for open and "C" for closed. ,

j Check Valve Test Direct. The direction of check valve operability verifica tion, indica ted by "F" for forward flow and "R" for reverse flow.

C.S. Just. or .

Reference number of the cold shutdown detief Aeq. No. justification or relief request. I C.S. or Alt. Test Perf. Cold shutdown or alternate testing which is .

being performed in lieu of the Code specified quarterly testing.

Remarksi Key to notes providing amplifying remarks. l Ihese notes are loca ted lacedia tely I following the Valve Test Tables.

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v s 4.0 Valve Test Table Format (Cont.)

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System Dwn No. Rev. No. Attach ment.No.

Mala steam C-18002-C 21 1 Reactor Recirculation C-18020-C 12 2 control Rod Drive C-18016-C Sh.1 13 3 C-18016-C Sh.2 10 Feedwater/HPCI C-18005-C Sh. 2 13 4 Core Spray C-18001-C 29 5 Emergency Cooling C-18017-C 21 6 Reactor Shutdown Coo 11ng C-18018-C 10 7 Containment Spray C-18012-C Sh.1 9 8 C-18012-C Sh.2 24 Rtactor Clean-up C-18009-C Sh.1 22 9 Inert Ces Purge and F111 C-18014-C Sh.1 17 10 Hydrogen-Onygen Monitoring C-18014-C Sh.2 26 11 C-26939-C 4 C-26949-C 6 TIP C-18014-C Sh.2 26 12 Nitrogen Supply No. 11 C-18014-C Sh.4 19 13 Nitrogen Supply No. 12 C-18014-C Sh.4 19 14 Reactor 81ds. HVAC C-18013-C 15 15 Liquid Polson C-18019-C 12 17 Spent Fuel Storage Pool Piltering & Cooling C-18004 C 11 18 Sample C-18041-C Sh.7 $ 19 I EII: Revision numbers listed are those current during program plan develo nt and may not reflect the most current drawing revision avalla le

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4.0 Valve Test Table Format (Cont.)

I System Dwat . No. Rev. No. &LLachment No.

Ret.ctor Sids. Closed C-18022-C Sh.2 18 20 Loop Cooling C-18022-C Sh.3 3

C-18022-C Sh.4 5 l C-18047-C 13

) C-26939-C 4

C-26949-C 6 l

! Condensate Transfer C-18003-C 22 l C-18007-C 25 i C-18008-C 11 21 l C-18009-C Sh.2 10 j C-18035-C 13 ,

C-18048-C 18 j Torus Vacuum Rollef C-18006-C Sh.2 16 22 l

l Emergency Service Water C-18022-C Sh.3 8 23 C-18027-C Sh.2 6 i

Emergency Diesel Generator C-18026-C Sh.1 4 24 Cooling Water C-18026-C Sh.2 1 i l Weste Disposal C-18045-C Sh.7 3 25 l

C-18045-C Sh.9 7 Sreathing Air to Drywell C-18578-C 2 26 1 i 1  :

i ll911: Revision numbers listed are those current

] during Program Plan development and may not j reflect the most current drawing revision  !

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PUNP AND VALVE INSERVICE TESTING PROGRAN PLAN for WINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION !!!

5.1 ATTACNMENT 1 VALVE TEST TA8LES AND RELIEF REQUESTS FOR NAIN STEAN DWG. NO. C-18002-C SN. 1 Pages l

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111.6.0 SYSTER MAIN STEAM MIME MILE POINT UNIT 1 VALVE TEST TABLE DWG. 30. C-18002-C SE.1 C.S C.S CLASS VALVE SIZE ACTU. NCEN. TEST STROKE CNECE JUST. OR CALnE NUISER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARES DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

01-01 1 A 24 NOA O FE-Q CS-1 FE-C MS-In-IV el (111) R-5 CLv ST-Q C ST-C LJ-R PE Q PI-R 01-02 1 A 24 NOA O FE-Q CS-1 FE-C MS-IN-IY 82 (121) F-5 CLv ST-Q C ST-C LJ-R PE-Q PI-R

, 01-03 1 A 24 APA O FE-Q CS-1 FE-C l C.S. out 17 #3 A-5 GLv ST-Q C ST-C (112) FS-Q C FS-C LJ-R PE-Q PI-R 01-04 1 A 24 APA O FE-Q CS-1 FE-C C.S. Out IV #4 G-5 GLV ST-Q C ST-C (122) FS-Q C FS-C LJ-R PE-Q PI-R 01-05 1 A 2 ADA C PV NOTE 2 U.S. Out IT #3 A-6 GLY LJ-R By-Pass PI-R 01-06 1 1 2 ADA C PY NOTE 2 0.3. Out IV #4 C-6 GLV L2-R PI-R Ry-Pass 1

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MINE MILE POINT IBIIT 1 VALVE TEST TABLE SYSTBt MAIN STEAM DUG. NO. C-18002-C 55.1 I I I I C.S I C.S 1 1 1 I I I I I ruper l JUST. 1 OR l I m" l VALVE I SIZE I ACTU. I NORN. l TEST l STROKE l ALT. l RMM vatyr mensa I aun 1 (cat.) I (IN.) l TYPE I POSIT. I REQ. I DIRECT. I YALVE l OR 1 Dec. I I ano I i l I i TsST l anIEr I TsST I I I I I I nIascr.1 mag. m0.1 rear.1 I I coom.I I Tyre I C FT NOTE 1 34-01 1 A 2 MOA cRn me d Spray n-2 cTT LI-m Outcide IV FI-E 2 SEA C FT NOTE 1 34-02 1 C M D Need Spray F-2 CNT Li-E Inside IT ( Oeck) 37-01 -1 3 2 M0a C FE-Q CS-2 FE-C CTT ST-Q O.C ST-C C:s Beed Test F-2 D.Y. #1 FI-R 1

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SYSTDt MAIN STEAM NINE MILE POINT UNIT 1 VALVE TEST TABLE DWC. NO. C-18002-C SH.1 I I C.S I C.S I i i i i I I I I ICIASS I YALVE I SIZE I ACTU. I NORM. I TEST l STROKE I CHECE l JUST. I OR I l YALVE NUMBER I AND l (CAT.) l (IN.) l TYPE I POSIT. I REQ. I DIRECT. I VALVE I OR I ALT. I RDIARKS I osc. I I AND I I I I I TEST l RELIEF l TEST l l COCR.I l TYPE l l l l l DIRECT.I REQ. NO.I PERF.l MCA C FE-Q CS-2 FE-C l 37-06 1 5 2 ST-Q 0,C ST-C C3 Head Vent F-3 CTV B.V. #2 PI-R 4 SEA DE FE-Q F RR-2 FE-R 66-07 2 C R ,

SRV Vacuum Breaker B-4 CHV 66-C8 2 C 4 SEA DE FE-Q F RR-2 FE-R CHV R SRV Vacuum Breaker B-4 66-09 2 C 4 SEA DE FE-Q F RR-2 FE-R CHV E SRV Vacuum Breaker B-3 C 4 SEA DE FE-Q F RR-2 FE-R 66-10 2 CHV E SRV Vacuus Breaker B-3 C 4 SEA DE FE-Q F RR-2 FE-R 66-11 2 CEV E SKY Yacuum Breaker F-3 4 SEA DE FE-Q F RR-2 FE-R 66-12 2 C CEV R SRV Vacuum Breaker F-3 4 SEA DE FE-Q F RR-2 FE-R 66-13 2 C CHV E SRV Vacuum Breaker F-4 4 SEA DE FE-Q F RR-2 FE-R 66-14 2 C R

SEY Yacous Breaker F-4 CHV 66-15 2 C 4 SEA DE FE-Q F RR-2 FE-R CHV E SRV Vacuum Breaker F-5 I

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SYSTEM MAIM STEAM MIME MILE FOINT UNIT 1 VALVE TEST TABLE DWG. No. C-18002-C 55.1 I I I I I C.S I C.S I I l l I I l ruarv l ,;gST. l OR l l IcIASS I VALVE I SIZE I ACIU. I NORM. I TEST l STROEE VALVE NUMBER l AND l (CAT.) I {IN.) 1 TYFE I FOSIT. I REQ. I DIRECT. I VALVE I DE l ALT. I REMRKS l I muc. I IAW I I I I I TEST I HLIEF l TEST I l I coca.1 1 TTFE I I I I I DIRECT.I REQ. mo.1 FsRF.I i 66-16 2 C 4 SEA DE FE-Q F RR-2 FE-R SOY Vacuum Breaker F-5 CN7 R 66-17 2 C 4 SEA DE FE-Q F RR-2 FE-R SOY Yacuum Breaker B-5 CW R 66-18 2 C 4 SEA DE FE-Q F RR-2 FE4

$2Y Vacuum Breaker B-5 CHY R 66-25 2 C 10 SEA DE FE-Q F BR-2 FE4 SOY Vacuum Breaker B-4 CW R 66-26 2 C 10 SEA DE FE-Q F RR-2 FE4 SEY Yacuum Breaker B-4 CW R 66-27 2 C 10 SEA DE FE-Q F RR-2 FE4 SRY Yacuum Breaker B-3 CW R 66-28 2 C 10 SEA DE FE-Q F RR-2 FE-R SRY Yscuum Breaker B-3 CW R 66-29 2 C 10 SEA DE FE-Q F BR-2 FE-R SOY Vacuum Breaker F-3 CW R 66-30 2 C 10 SEA DE FE-Q F BR-2 FE-R SCY Yacuum Breaker CW R 66-31 2 C 10 SEA DE FE-Q F BR-2 FE-R SEY Yacuum Breaker F-4 CW R 111-1-5 k - .. - . _ _ - - _ _ . .

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SYSTEM MAIN STEAM NINE MI1E FOINT UNIT 1 VALVE TEST TABII IMic. NO. C-18002-C 58.1 I I I i i 1 I I I C.S I C.S I I IcuSS I YALVE l SIZE I ACTU. I NORM. l TEST l STRORE I CMEcK I JcST. I OR I l YALvE ucMan l AuD I (CAT.) I (IN.) i TTrE I POSIT. I REQ. I nIRECr. I VALVE I OR l ALT. I REMARKS I I suc. I I AsD I I I I I TEST I utIEF 1 TEST I I I coat.I I TYPE I I I I  ! DIRECT.I REQ. mO.I enF. I I 66-32 2 C 10 SEA DE FE-Q F RR-2 FE-R SRv vac=== areaker c-4 Cuv R 66-33 2 C 10 SEA DE FE-Q F BR-2 FE-R SRv vac=== areaker F-5 cw E 66-34 2 C 10 SEA DE FE-Q F RR-2 FE-R SRv vac=== nre ker F-5 cuv R 66-35 2 C 10 SEA DE FE-Q F RR-2 FE-R S v vac=== areaker n-5 cue R 66-36 2 C 10 SEA DE FE-Q F BR-2 FE-R SRv v.ce== areaker n-5 car R miceA 1 aC 61s C FE-Q O.C RR-1 FE-R MSERY-3 (#111) C-4 REW SOA RT-P PI-R M1083 1 BC 618 C FE-Q O.C RR-1 FE-R MSERY-1 (#112) C-3 RET SOA RT-P FI-R M108C 1 BC 6I8 C FE-Q O.C RR-1 FE-R MSIRY-2 (#121) E-4 REY SOA RT-P FI-R M100D 1 BC 618 C FE-Q O.C RR-1 FE-R MSERY-4 (#122) E-4 REY SOA RT-P PI-R M108E I BC 618 C FE-Q 0,C RR-1 FE-R MSIRV-5 (#113) C-4 REW SOA RT-P PI-R 111-1-6 O (

NINE NI1E POINT WIT 1 V EVE TEST TAhl2 SYSTEM M&IN STEAM DMG. NO. C-IS002-C SN.1 I I C.S I C.S I I I I I I I I I I run i vnvE I SIZE l ACTU. I NORN. I TEST I STROKE I rurY l JUST. l OR l l l ALT. I annaast ]

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M2SC 1 C 6 SEA C RT-P Cs. Need PST D-1 RN M2SE 1 C 6 SEA C RT-P Ca. Beed PST D-1 RN III-I-7 m--_,_._._.__,_ , _ _._. _ __ _ _ ._ _ _ __ _ _ , . _ _ _ _ _. _. _ _

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I NOTES FOR ATTACNNSNT 1 SYSTSNI MAIN STRAN

& E 1 These valves are in the head spray line which 49 not used during any mode of normal operation or sold shutdown.

2 These valves are in the closed peeltlon during normal plant operations and are currently under engineering evaluation for removal from the system due to their design configuration and possive operational l function. (Def. Ned. Control No. N1444M2011)

I 1

111 1-9 0

COLD SNUT00tdW TEST JUST!PICAf!0N CS-1 l

l Systemi Nain and Aus. Steam-Valvel 01-01:01-02:01-03:01-04 Cate6ery A Clasel 1 Funetton Main steam line isolation valves.

ASME Section XI Quarterly feet poquirements: Eserelse and time.

Cold Shutdown feet Justifteetient Full stroke esercisins results in loss of steam flow from one main steam Inne to the turbine. Also, recent industry information indleates that closing these valves with high steam flow in the line may be a 1erse contributing f actor in observed seat degradation. The valves are designed for partial stroke esereising with full steam flow durins plant operation. The partial stroke test will verify operability of the valve and operator without the potentist for seat damate which could result from full stroke esereisins.

Quarterly Part 8troke festinal Partial Stroke close esereise.

Cold shutdown festingi Full stroke eserstee and time.

til l=10

_ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . .O

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COLD SHUTDOWN TEST JUSTIFICATION CS-1 Sfstem Reactor Head Vent Component Valves: 31-01 (RHV-BY-1) & 37-06 (RHV-bV-2)

Category: 8 Clasel 1 ASHE 8ection XI Quarterly Req'mts: Full esercise and stroke time quarterly.

, Cold Shutdown Test l Justification The design function of these valves is to provide a vent path to primary containment for uso during reactor vessel water level changes. This vent path is only utilised during cold shutdowns and for long-term post-LOCA reactor vessel flooding. There is no design basis which would require these valves to be cycled during reactor power operation. In addition, cycling these valves during full power operation would significantly reduce the margin of safety of the Reactor Coolant pressure Roundry since these valves provide a Reactor Coolant / primary Containment boundary. Failure of the adjacent valve during cycling would introduce a t.0CA within the drywall which would affect operation of equiteent necessary for safe shutdown.

Quarterly part Stroke Testingi The above justification also applies for partial esercising.

Cold Chutdown Testing: Valves will be full esercised aid stroke timed during cold shutdowns.

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RELIEF REQUEST l

l RR-1 System Main Steam  ;

l Valve: NR108A.B.C.D.E & F Category: BC I

Class:

1 Function: ADS Valves.

ASME Section XI Quarterly Test Requirements: Eserciso quarterly.

Basis for Rolleft If the valves were to fall to reclose af ter testing, the plant would be placed in a LOCA condition. In addition, a recent study (BWR Owners Group Evaluation of NUREG-0737 Item II.E.3.16 Reduction of Challenges and Failures of Relief Valves) recomunends that the number of ADS valve openings be reduced as much as possible. Based on this study and the potentist for causing a possible LOCA condition esercise testing of the ADS valves will be delayed to refueling.

Alternate Testing: Esercise at refueling.

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RELIEF REQUEST RR-2 System: Main Steam Valve: 66-07:66-08:66-09:66-10:66-11 66-12:66-13:66-14:66-15:

66-16:66-17:66-18:66-25:66-26:66-27:66-28:66-29:66-30:

66-31:66-32:66-33:66-34:66-35:66-36 Category: C Class: 2 Function: Vacuum Relief check valves on the lines from the ADS l

valves to the Torus.

(

l ASME Section XI f Quarterly Test Requirements: Exercise.

Basis for Reitef: Valves are simple check valves located inside the drywell. The only e.vthod possible to verify operability is by exercising by hand. This requires entry into the drywell which is not possible during normal operation or cold shutdown.

Alternate Testing: Operability of these valves will be verified by hand exercising during refueling.

l l

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v -

l PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN

. for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.2 ATTACHMENT 2 VALVE TEST TABLES AND RELIEF REQUESTS FOR REACTOR RECIRCULATION DWG. NO. C-18020-C Pages III-2-1 througn III-2-2

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=

III-2-1 c

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SYSTEM REACTOR RECIRC. NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18020-C l l l l l l l l l C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l DWG. l l AND l l l l l TEST l RELIEF l TEST l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.I 110-127 1 A 1 MOA C FE-Q React. Recire. K-1 GLV ST-Q C Simple IV LJ-R PI-R 110-128 1 A 1 MOA C FE-Q React. Recire. L-1 GLV ST-Q C S:mple IV LJ-R PI-R c III-2-2 R_ _ ___-----_____-_-_____

1 PUMP AND VALVE INSERVICE TEST 1'JG PROGRAM PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.3 ATTACHMENT 3 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONTROL ROD DRIVE DWG. No. C-18016-C SH.1 C-18016-C SH.2 Pages III-3-1 enrougn III-3-7 111-3-1 0

SYSTEM CRD NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. N0. C-18016-C SH.1 C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR ,

VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS >

DWG. AND TEST , RELIEF TEST COOR. TYPE DIRECT.' REQ. NO.!, PERF.

106 2 C O.5 MAA DE FE-Q R RR-1 NOTE 1 Chtrging Water B-4 SCV SEA F Isolation Valve 2 C .75 MAA DE FE-Q F RR-1 NOTE 1,2 108 Scram Discharge A-4 SCV SEA ,

Icolation Valve 2 .75 ADA C FE-Q RR-1 NOTE 1,3 126 B C-3 GLV ST-Q O Scram Inlet valve FS-Q O PI-R 127 2 B .75 ADA C FE-Q RR-1 NOTE 1,3 Scram Discharge A-3 GLV ST-Q O Valve FS-Q O PI-R 138 2 C O.5 SEA DE FE-Q R RR-1 NOTE 1 Croling Water D-2 CHV Inlet Check 301-112 1 C 3 SEA DE LJ-R VG-3 R turn Water L-7 CHV Outside Ck. V1v.

YG-3 3 SEA DE LJ-R 301-113 1 C M-7 CHV R2 turn Water Inside Ck. Vlv.

111-3-2 P - .5

SYSTEM CRD NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18016-C SH.2 C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS VALVE NUMBER DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

44.2-15 2 A 2 ADA O FE-Q Scram Discharge A-4 GLV ST-Q C RR-2 ST-R Vol. H1d. Tk. IV KEEO C 44.2-16 2 A 2 ADA O FE-Q Scram Discharge B-7 GLV ST--Q C

• Vol. Hld. Tk. IV FS-Q C LJ-R PI-R 44.2-17 2 A 2 ADA O FE-Q Scram Discharge I-7 GLV ST-Q C Drain IV FS-Q C LJ-R PI-R 44.2-18 2 A 2 ADA O FE-Q Scram Discharge J-7 GLV ST-Q C RR-2 ST-R Drain IV FS-Q C LJ-R PI-R III-3-3

v . _ ,

NOTES FOR ATTACHMENI 3 SYSTEM: CRD NO. NOTE 1 Typical of 129 Control Rod Drive Hydraulic Units.

2 Proper operation of the Control Rod during Rod Insertion Time tating verifies forward flow operability.

3 Proper operation of the Control Rod during Rod Insertion time testing verifies valve operability and adequate valve stroke time.

l III-3-4

_ ., S

)

1 RELIEF REQUEST RR-1 System: Control Rod Drive Valve: 108:126:127:106:138 (To be done for all 129 HCU's)

Category: B (126:127)

C (108:106:138)

Class: 2 Function: Reactor shutdown.

ASME Section XI Quarterly Test Requirements: Exercise, time and fail (126:127)

Verify forward flow operability (108:106)

Verify reverse flow operability (106:138)

Basis for Relief: The Hydraulic Control Units (HCU) are integrally designed systems (GE) for controlling rod drive movements. Individual valve testing is not possible without causing a control rod scram with a resulting enange in core reactivity. Quarterly testing of these valves would violate plant Technical Specifications wnica govern tne methods and frequet y of reactivity changes. The Technical Specification Control Rod Scram Insertion Time testing meets the intent of Section XI testing requirements.

Alternate Testing: Technical Specification Control Rod Scram Insertion Time testing serves to verify proper operation of each of these valves. Following eacn reactor scram from rated pressure, the mean 90% Insertion time shall be determined for eight selected rods. If tne mean 90%

insertion time of the selected control rod drives does not fall within the range of 2.4 to 3.1 seconds or the ceasured scram time of any one drive for #0% insertion does not fall witnin tne range of 1.9 to 3.b seconds, an evaluation shall be made to provide reasonable assurance tnat proper control rod drive performance is maintained. After each major refueling outage and prior to power operation with reactor pressure above 800 psig, all operable control rods shall be scram tested from tne fully witndrawn position. Following any outage not initiated by a reactor scram, eight rods anall be scram tested with reactor pressure above 800 psig.

l 111-3-5 i

s.

. g RELIEF REQUEST RR-2 System: Control Rod Drive Valve: 44.2-15,44.2-18 Category: A Class: 2 Function: Scram Discharge Volume Vent Isolation Valve ASME Section KI Quarterly Test Requirements: Exercise and Time (IWV-3510)

Basi:: for Relief: Solenoid air pilot valves control the air supply to the air actuators for valves 44.2-15 and 44.2-18. The solenoid valves utilize two different exhaust paths; one reverse venting path for testing purposes (valve exercising) and one path for normal valve operation (reactor scram conditions). These solenoids have internal pilots and are not designed for universal operation. That is, they are not designed to accept dual inlet and exhaust flows. When reverse venting occurs during testing, the air flow is restricted.

Consequently, the stroke times obtained during valve testing are much longer than those for normal valve operation (approximately 140 seconds versus approximately 5 seconds), and do not represent normal valve operation.

Alternate Testing: These valves will be full stroke exercised quarterly using the testing path. ' Valve stroke times will be measured whenever a reactor scram occurs and during refueling using computer points and/or chart recorders, whereby stroke time obtained will represent normal valve operation.

III-3-6

_ _ _ _ _ - - _ . _ d

• o; RELIEF REQUEST RR-3 System:

Control Rod Drive Valve: 44.2-15,44.2-18 Category: A Class: 2 Function:

Scram Discharge Volume Vent Isolation Valve ASME Section XI Quarterly Test Requirements:

Exercise and Time (IWV-3510)

Basis for delief:

Solenoid air pilot valves control the air supply to the air actuators for valves 44.2-15 and 44.2-18. The solenoid valves utilize two different exhaust paths; one reverse venting path for testing purposes (valve exercising) and one path for normal valve operation (reactor scram conditions). These solenoids have internal operation.

pilots and are not designed for universal That is, they are not designed to accept dual inlet and exhaust flows. When reverse venting occurs during testing, the air flow is restricted.

Consequently, the stroke times obtained during valve testing are much longer than those for normal valve operation (approximately 140 seconds versus approximately valve operation.5 seconds), and do not represent normal Alternate Testing:

Thesetne using valves willpath.

testing be full stroke exercised quarterly Valve stroke times will be measured refueling whenever using a reactor scram occurs and during computer points and/or chart recorders, wnereby normal valve operation.stroke time obtained will represent III-3-7 d

e-- _,

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.4 ATTACHMENT 4 VALVE TEST TABLES AND RELIEF REQUESTS FOR FEEDWATER/HPCI DWG. NO. C-18003-C C-18005-C SH.1, SH.2 C-18033-C Pages III-4-1 through III-4-4 III-4-1 b

SYSTEM FEEDWATER/HPCI NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18005-C SH.2 - - - - --

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

e. ------- - - _ _ - _ _.

C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND ( C.4T . ) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

31-01 1 AC 18 SEA DE FE-Q R RR-1 FE-R 011 FW Riser C-4 CHV LJ-R Icclation Check Valve 31-02 1 AC 18 SEA DE FE-Q R RR-1 FE-R c 012 FW Riser C-4 CHV LJ-R Icolation Check Valve 31-07 1 A 18 MOA O FE-Q CS-1 FE-C C11 FW Isolation C-4 GTV ST-Q C ST-C Valve LJ-R PE-Q PI-R 31-08 1 A 18 MOA O FE-Q CS-1 FE-C C12 FW Isolation C-4 GTV ST-Q C ST-C Valve LJ-R PE-Q PI-R III-4-2 fa 9

u l

COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: FEEDWATER/HPCI Valve: 31-07:31-08 Category: A Class: 1 Function: Feedwater inlet isolation valves.

ASME Section XI Quarterly Test Requirements: Exercise and time.

Cold Snutdown Test Justification: Exercising these valves closed during normal operation would require a significant reduction in power and stopping one line of feedwater flow. Isolation of one line of feedwater flow during normal operation introduces undesireable operational transients and could result in a reactor trip.

Quarterly Part Stroke Testing: Partial stroke close exercise.

Cold Snutdown Testing: Full strone exercise and time.

III-4-3 b

D RELIEF REQUEST RR-1 System FEEDWATER/HPCI Valves 31-01:31-02 Category: AC Class: 1 Function: Feedwater isolation check valves.

ASME Section XI Quarterly Test Requirements: Verify reverse flow closure.

Basis for Relief: Verification of reverse flow closure during normal operation would require a significant reduction in power and stopping one line of feedwater flow.

Isolation of one line of feedwater flow during normal operation introduces undesirable operational transients and could result in a reactor scras.

Verification of reverse flow closure during cold shutdown would require entry into the drywell, which is not normally accessible during cold shutdown outages. The only method available to verify reverse flow closure is by valve leak testing during Appendix J Type C, testing at refueling.

Alternate Testing: Verify reverse flow closure at refueling during Appendix J, Type C, testing. '

l l

III-4-4 b

_g PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT l NUCLEAR POWER STATION UNIT 1 SECTION III 5.5 ATTACHMENT 5

, VALVE TEST TABLES AND RELIEF REQUESTS FOR CORE SPRAY DWG. NO. C-18007-C Pages a

III-5-1 through III-5-9 4

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III-5-1 l

SYSTEM CORE SPRAY NINE MILS POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18007-C __

C.S C.S SIZE ACTU. NORM. TEST STROKE CHECK JUST. CR CLASS VALVE REMARKS TYPE POSIT. REQ. DIRECT. VALVE OR ALT.

VALVE NUMBER AND (CAT.) (IN.)

TEST AND TEST RELIEF DWG.

DIRECT. REQ. NO. PERF.

COOR. TYPE 40-01 1 B 12 MOA C FE-Q C:ro Spray Sys #12B H-4 GTV ST-Q O PI-R Iol t to Reactor Vessel 12 MOA O PI-R NOTE 3 40-02 1 B CRS #12 Inlet J-4 GTV Outside IV 12 SEA DE FE-Q F 40-03 1 AC CRS #12 Inlet K-4 CHV LK-R R Outoide Check Valve 6 MOA C LJ-R VG-3 NOTE 3 40-05 1 B Tcct IV #12 to Torus K-5 GTV PI-R 1 B 6 MOA C LJ-R VG-3 NOTE 3 40-06 Tact IV #11 to Torus C-5 GTV PI-R 40-09 1 B 12 MOA C FE-Q C:ra Spray Sys #12 A H-3 GTV ST-Q O IOlst to Reactor PI-R Vessel 111-5-2 R ___ ___ _____ ___

- - - 9

SYSTEM CORE SPRAY NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18007-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

40-10 1 B 12 MOA C FE-Q Cero Spray Sys F-3 GTV ST-Q O Cll A Inlet to PI-R Rocctor Vessel 40-11 1 B 12 MOA C FE-Q Ciro Spray Sys F-4 GTV ST-Q O 011 B Inlet to PI-R .

Racetor Vessel 40-12 1 B 12 MOA O PI-R NOTE 3 CRS #11 Inlet E-4 GTV Outoide IV 40-13 1 AC 12 SEA DE FE-Q F Check Valve C-4 CHV LK-R R 40-20 2 AC 2 SEA DE FE-Q F NOTE 1 lot Check #11 C-4 CHV LC-R R RR-1 FE-R Keep-fill System 40-21 1 AC 2 SEA DE FE-Q F NOTE 1 2nd Check Valve - C-4 CHV LC-R R RR-1 FE-R C11 Keep-fill System 40-22 1 AC 2 SEA DE FE-Q F NOTE 1 2nd Check Valve - K-4 CHV LC-R R RR-1 FE-R 612 C.S. Keep-fill System 111-5-3 P ._ 3

SYSTEM CORE SPRAY NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18007-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

40-23 2 AC 2 SEA DE FE-Q F NOTE 1 let Check Valve - K-4 CHV LC-R R RR-1 FE-R 012 C.S. Keep-fill System 40-30 1 A 1 MOA C FE-Q C ro Spray 11 E-3 CLV ST-Q C Test IV LJ-R PI-R ,

40-31 1 A 1 MOA C FE-Q Ctro Spray 12 H-3 CLV ST-Q C Test IV LJ-R PI-R 40-32 2 A 1 APA C FE-Q Coro Spray 11 E-3 CLV ST-Q C Test IV FS-Q C LJ-R PI-R 40-33 2 A 1 APA C FE-Q C:ro spray 12 I-3 CLV ST-Q C Test IV FS-Q C LJ-R PI-R 81-07 2 C 12 SEA DE FE-Q F Trpping Pump 121 M-5 CHV R Diccharge Check Valve III-5-4 P _b

SYSTEM CORE SPRAY CICE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18007-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR AND (CAT.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS VALVE NUMBER (IN.)

DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

81-08 2 C 12 SEA DE FE-Q F Tapping Pump 122 M-5 CHV R Diccharge Check Valve 81-11 2 C 2 SEA DE RT-P Loop #12 L-4 REV Diccharge PSV 81-27 2 C 12 SEA DE FE-Q F c Tepping Pump 111 A-5 CHV R Diccharge Check Valve 81-28 2 C 12 SEA DE FE-Q F-Tcpping Pump 112 A-5 CHV R Diccharge Check Valve 81-31 2 C 2 SEA C RT-P Loop #11 A-4 REV Dic harge PSV 81 77 2 C .75 SEA C RT-P Tipping Pump PRV K-2 REV 81-78 2 C .75 SEA C RT-P T pping Pump PRV K-2 REV 81-79 2 C .75 SEA C RT-P Tepping Pump PRV K-2 REV III-5-5 E-__-------_________-.___--- _ - _ _ _ _

, 3

l SYSTEM CORE SPRAY NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18007-C ,.

C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS VALVE NUMBER DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

81-80 2 C .75 SEA C RT-P Trpping Pump PRV K-2 REV 2 AC 12 SEA DE PV NOTE 2 93-58 12" Testable B-2 CHV MAA LJ-R Check Valve 93-64 2 AC 12 SEA DE PV NOTE 2 l 12" Testable M-2 CHV MAA LJ-R I

Check Valve l

93-71 2 A 12 MOA C PV l

12" Flow Control B-2 PGV LJ-R Valve PI-R 93-74 2 A 12 MOA C PV 12" Flow Control L-2 PGV LJ-R Valve PI-R 1

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- - -5

NOTES FOR ATTACHMENT 5 SYSTEM: CORE SPRAY NO. M9.T.E

1. Forward flow operability is verified by a system check to verify water inventory (Core Spray keep fill system).

2. Testable check valve, with manual exerciser.

(Opening handwheel forces disk open, closing handwheel frees disk up for normal operation.)

3. These valves are only used for Core Spray Testing purposes to Align the Core Spray flow to the torus. During all other periods, these valves are placed in their normal position; the electrical circuit breakers opened and then locked in the open position such that valve l operation is not possible, i

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III-5-7 l

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9 RELIEF REQUEST RR-1 System: Core Spray Valve: 40-21:40-22:40-20:40-23 Category: AC Class: 1 Function: Containment and pressure isolation simple check valves (reverse flow closure fer containment and pressure isolation only).

ASME Section XI Quarterly Test Requirements: Verify reverse flow closure.

Basis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J.

Type C, testing at refueling.

Alternate Testing: Reverse flow closure will be verified during Appendix J. Type C, testing at refueling.

I l

III-5-8 0

v c RELIEF REQUEST RR-2 System: Core Spray Valve: 93-58:93-64 Category: AC Class: 2 Function: Containment Spray Raw Water cross-tie to Core Spray System check valves.

ASME Section XI Quarterly Test Requirements: Verify reverse flow operability.

Basis for Relief: The only method available to verify reverse f+ow closure is by valve leak testing during Appendix J, Type C testing at refueling.

Alternate Testing: Since there is no possible way to verify reverse flow operability by flow testing, these valves will be Appendix J. Type C tested at refueling.

l i

I III-5-9 l

• r PUNP AND VALVE INSERVICE TESTING PROGRAN PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.6 ATTACHMENT 6 VALVE TEST TABLES AND RELIEF REQUESTS FOR ENERGENCY COOLING DWG. NO. C-18017-C Pages III-6-1 through III 10 III-6-1 IL

STSTEN ENERGENCY COOLING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18017-C C.S C.S CLASS VALVE SIZE ACTU. NORN. TEST STROKE CHECK JUST. OR VALVE NUISER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. annamEs DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF. j 05-01R 2 B 1 APA O FE-Q CS-2 FE-C Emerg. Cond. F-3 GLY ST-Q C,0 ST-C Loop all Vent FS-Q C FS-C B.V. LJ-R VG-3 PI-R 05-02R 2 A 1 APA O FE-Q CS-2 FE-C Baerg. Cond. Vest C-1 GLV ST-Q C ST-C IV 11 to Mais FS-Q C FS-C Steam Line LJ-R PI-R 05-03R 2 A 1 APA O FE-Q CS-2 FE-C Beers. Cond. Vent F-1 CLV ST-Q C ST-C IV 12 to Naia FS-Q C FS-C Cteam Line LJ-R PI-R 05-04R 2 3 1 APA O FE-Q CS-2 FE-C Emers. Cond. M-3 CLY ST-Q C.O ST-C l loop #12 Vent FS-Q C FS-C R.V. LJ-R VG-3 PI-R 05-05 2 3 1.5 NOA C FE-Q CS-2 FE-C C-4 GLV ST-Q O.C ST-C Emers. Cond. Vest to Torus B.V. 811 PI-R NOA C FE-Q CS-2 FE-C 05-07 2 8 1.5 ST-C C-5 GLY ST-Q O.C Emerg. Cond. Vest PI-R to Torus B.V. 812 III-6-2

I STSTEM EIERCENCY COOLING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18017-C C.S C.S i I

CLASS VALVE SIZE ACTU. NORM. TEST STROKE CNECE JUST. OR POSIT. DIRECT. VALVE OR ALT. massaars CALVE NUMBER AND (CAT.) (IN.) TYPE REQ.

DWG. AND TEST RELIEF TEST COOR. TYPE l g DIRECT. REQ. NO. PERF.

, a 05-11 2 3 1 APA O FE-Q CS-2 FE-C Esmerg. Coad. F-3 GLV ST-Q C,0 ST-C Loop all Vent FS-Q C FS-C B.V. LJ-R VC-3 PI-R 05-12 2 B 1 APA O FE-Q CS-2 FE-C N-3 CLV ST-Q C,0 ST-C Busers. Cond.

Loop #12 Yeat FS-Q C FS-C 3.V. LJ-R VC-3 PI-R 39-03 1 C 10 SEA DE FE-Q F RR-1 FE-C Loop #11 Cond. F-8 CMV LJ-R VG-3 Retura Inlet Check l

39-04 1 C 10 SEA DE FE-Q F RR-1 FE-C l l

Loop #12 Coed. N-S CMV LJ-R VC-3 Retura Inlet Check 39-05 1 3 10 APA C FE-Q CS-1 FE-C Loop all Cond. E-3 CLV TT-Q O.C ST-C Betura I.V. FS-Q O FS-C l

LJ-R VG-3 l PI-R 39-06 1 3 10 APA C FE-Q CS-1 FE-C Imop #12 Cond. I-S CLV ST-Q O.C ST-C 1

FS-Q O FS-C l Retura I.V. VG-3

! LJ-R PI-R III-6-3

. _ . _ - - - - . . - _ . _ . . . . - - _ . - _ _ - . - _ _ _ - - _ . - _ _ - . _ _ _ - - - . - - _ - - - _ ~__-_ _

l SYSTEN INERGENCY COOLING NINE MILE POINT UNIT 1 VALVE TEST Tant r DWG. NO. C-18017-C C.S C.S CLASS VALVE SIZE ACTU. NORN. TEST STROKE CHECE JUST. OR POSIT. DIRECT. VALVE OR ALT. Rggnaert VALVE NUENbER AND (CAT.) (IN.) TYPE REQ.

DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. N0. PERF.

l l 39-07 1 A 10 NOA O FE-Q l Loop #11 Steam F-6 GTV ST-Q O.C Out10t outside I.V. LJ-R (Emers. Cond. Sta. PI-R I.U. #112) 39-08 1 A 10 NOA O FE-Q l

Loop #12 Steam M-6 GTV ST-Q O.C l LJ-R l Out10t Outside IV (Beers. Cond. Stm. PI-R l

j I.T. #122) 39-09 1 A 10 NOA O FE-Q l Loop #11 Steam F-6 GTV ST-Q O.C l Outlet Inside IV LJ-R (BnerE. Cond. Ste. PI-R I.T. #111) l 39-10 1 A 10 NO& O FE-Q j Loop #12 Steam N-6 GTV ST-Q O.C Outlnt Inside IV LJ-R (Emers. Cond. Ste. PI-R I.V. #121) 39-11 2 A 1 ADA O FE-Q Loop all Sta. D-6 GTV ST-Q C FS-Q C Line Drala 1st I.V. LJ-R PI-R III-6-4 P_ _ _ , _ . _

SYSTEM EMERGENCY COOLING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. N0. C-18017-C I C.S C.S CLASS VALVE SIZE ACTU. NORN. TEST STROKE CHECK JUST. OR VALVE NUINRER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

39-12 2 A 1 ADA O FE-Q Loop #11 Sta. C-6 GTV ST-Q C Line Drain 2nd FS-Q C I.V. LJ-R PI-R 39-13 2 A 1 ADA O FE-Q Loop #12 Sta.. J-6 GTV ST-Q C Line Drain 1st FS-Q C '

I.V. LJ-R PI-R 39-14 2 A 1 ADA O FE-Q Loop #12 Ste. E-6 GTV ST-Q C FS-Q C Line Drain 2nd I.V. LJ-R PI-R 60-03 3 B 4 ADA C FE-Q Line from Cond. E-1 GLV ST-Q O.C Trans. Pump to FS-Q- 'C Emer. Cond. M.U. PI-R Tank #12 60-04 3 8 4 ADA C FE-Q Line from Cond. C-1 GLV ST-Q O.C Trans. Pump to FS-Q C Emerg. Cond. M.U. PI-R Tank #11 F

3 C 4 ' SEA DE FE-Q 60-05 CHV Check Valve on B-1 C:nd. Supply to ECMU Tank #11 III-6-5

- - - - - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ = - _ _

SYSTEM EMERGENCY COOLING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18017-C C.S C.S CLASS VALVE SITE ACTU. NORM. TEST STROKE CHECK JUST. OR AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS VALVE NUMBER DWG. AND TEST RELIEF TEST TYPE DIRECT. REQ. NO. PERF.

COOR.

4 SEA DE FE-Q F 60-06 3 C Check Vavle on L-1 CHV C:nd. Supply to ECMU Tank #12 60-13 3 8 4 ADA O FE-Q ,

GLV ST-Q C Tio Valve Between I-3 FS-Q C Einers. Cond. M.U.

T:nks PI-R 4 ADA DE FS-Q O NOTE 1 60-17 3 B Einerg. Cond. D-3 GLV PI-R 111-112 Level Cmtrol Valve 4 ADA DE FS-Q O NOTE 1 60-18 3 B Einers. Cond. J-3 GLV PI-R 121-122 Level Control Valve III-6-6 C - - _------ _ ___ ________ _ _______ ____ _ - - - __ --_.-__4

.. , 3 nu-.* , .1 - s c. -- - . --- - - - _ _ - -

.4 a h /[a

\

v6 NOTES FOR ATTACHMENT 6' SYSTEM: EMERGENCY COOLING NO. M 1 ,

4

• Level control valve to maintain emergency condenser water level.

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I 1

f

'I h

+

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1 4

4 111- 0 1 i

i

RELIEF REQUEST RR-1 Systext: Emergency Cooling-Valve: 39-03:39-04 Category: C Class: 1 J ASME Section XI Quarterly Test Requirements: Verify forward flow operability.

Cold Shutdown Test Justification: To verify forward flow operability would require placing the Emergency Cooling System into operation.

These valves are normally maintained closed by Reactor Recirculation System operating pressure and to initiate flow through the valves requires initiation of the Emergency Cooling System. The Emergency Cooling System is not initiated unless the plant is bein5 shut down and initiation during normal operation would result in shutting the plant down.

Quarterly Part Stroke Testing: Valves are simple check valves and cannot .be part stroke exercised.

Alternate Testing: Verify forward flow operability once every 5 years when Emergency Cooling System is tested.

111-6-8 L. _ _

k

COLD SHUTDOWN TEST JUSTIFICATION CS-1 l

System: Emergency Cooling Valve: 39-05:39-06 Category: B Class: 1 Function: Emergency Cooling System discharge to Reactor Recirculation System air operated blocking valves.

ASME Section II Quarterly Test Requirements: Exercise, time and fall.

Cold Shutdown Test Justification: To verify operability would require placing the Emergency Cooling System into operation. The system is normally aligned such that opening these valves initiates Emergency Cooling,. The Emergency Cooling System is not initiated unless the plant is being shut down and initiation during normal operation would result in shutting tha plant down.

Quarterly Part Stroke Testing: Partial exercising of these valves would initiate Emergency Cooling.

Cold Shutdown Testing: Valves will be exercised, time and failed at cold shutdown when the Emergency Cooling System is used.

III-6-9 k

COLD SHUTDOWN TEST JUSIIFICATION CS-2 l

System: Emergency Cooling Valve: 05-01R:05-02R:05-03R:05-04R:05-11:05-12:05-05:05-07 Category: A (05-02R,05-03R)

B (05-01R,05-04R,05-11,05-12,05-05,05-07)

Class: 2 Function: Emergency Condenser Vent Valves.

, ASME Section XI Quarterly Test Requirements: Exercise, time and fail.

Cold Shutdown Test Justification: The NRC " Safety Evaluation Nine Mlle Point Nuclear Station, Unit 1 Niagara Mohawk Power Corporation" finds the modified vent system to be acceptable and in conformance with the requirements of 10CFR50.44 paragraph (c)(3)(111), and the guidelines of NUREG-0737 item II.B.1 and NUREG-0800 section 5.4.12.

As part of this Safety Evaluation, the vent valves are to be included in the Inservice Test Program and the frequency of testing changed from "every three months" to "during cold shutdown or each refueling outage".

Cold Shutdown Testing: Exercise, time and fail, as applicable.

III-6-10

• tr PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.7 ATTACHMENT 7 VALVE TEST TABLES AND RELIEF REQUEST FOR REACTOR SHUTDOWN COOLING DWG. NO. C-18018-C Pages III-7-1 through III-7-4 l

l III-7-1 ,

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SYSTEM SHUTDOWN COOLING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18018-C ---

- = - - _

CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR ,

VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS l 1 '

DWG. AND i TEST RELIEF , TEST COOR. TYPE DIRECT. REQ. NO. f PERF.

38-01 1 B 14 MOA C FE-Q CS-1 FE-C SC Outlet Inside M-5 GTV ST-Q C ST-C LJ-R VG-3 Icelation Valve PI-R 38-02 1 B 14 MOA C FE-Q CS-1 FE-C '

SC Outlet Outside L-5 GTV ST-Q C ST-C Icelation Valve LJ-R VG-3 PI-R 38-12 1 B/C 14 SEA DE FE-Q R RR-1 FE-R SC Inlet Outside B-5 CHV LJ-R VG-3 Ioslation Check valve 38-13 1 B 14 NOA C FE-Q CS-1 FE-C ,

SC Inlet Inside A-5 GTV ST-Q C ST-C Icclation Valve LJ-R VG-3 l PI-R i

l III-7-2 l

l N _______ _ __ _ ____ _____ _ _ 1

v ,

COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Shutdown Cooling Componenc: Isolation Valves: 38-01, 38-02, 38-13 Category: B Class 1 ASME Section XI Quarterly Requirements: Full Exercise and Stroke Time.

Cold Shutdown Test Justification: These are motor operated gate valves which normally function (cycle) at a service temperature of 1350*F and pressure of 1120 psig (designed interlocks). These valves were not designed to cycle with such a high differential pressure as would be experienced if cycled at full power, (up to 1030 psig). In addition, failure of any of these valves to reclose during full power operation could result in the plant being placed in an L.C.O. and possibly subjecting the shutdown cooling system to temperatures above that for which it was designed.

Quarterly Part Stroke Testing: None Cold Shutdown Testing Requirements: Full Exercise and Stroke Time During Cold Shutdowns.

1 i

III-7-3 i

RELIEF REQUEST RR-1 System: Shutdown Cooling Component: 38-12 Category: BC Class: 1 Function: Shutdown cooling system supply check valve to prevent reverse circulation of Rx. water.

Basis for Relief: This valve is normally closed during power operation and only open during operation of the Shutdown Cooling System.

The Shutdown Cooling System is normally in operation during cold shutdowns and not comoved from service until the plant is ready to startup. Therefore plant startup would most likely be delayed in order to perform reverse flow testing due to the complexity of the test method. (Venting /

draining SDC piping, hydropump pressurization and possibly radiographing the valve disk.)

Alternate Testing: Reverse flow testing will be performed during scheduled refueling outages when the Shutdown Cooling System is out of service for an extended period of time.

III-7-4 k

7 i

l PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINI NUCLEAR POWEd STATION ONIT 1 SECTION III 5.8 ATTACHMENT 8 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONTAINMENT SPRAY DWG. NO. C-18012-C SH.1 C-18012-C SH.2 Pages III-8-1 through III-8-12 l

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III-8-1

NINE MILE POINT UNIT 1 VALVE TEST TABLE SYSTEM CONTAINMENT SPRAY DWG. No. C-18012-C SH.2 l l C.S l C.S I l l l CIASS VALVE SIZE ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR I VALVE NUMBER l AND l (CAT.) I (IN.) l TYPE l POSIT. I REQ. I DIRECT. l VALVE I OR I ALT. lI REMARKS l l DWG. l l AND l l l l l TEST l RELIEF l TEST l l l COOR.l l TYPE l ] l l l DIRECT.l REQ. NO.l PERF.l SEA DE FE-Q F 80-05 2 C 12

1. 121 CTN-SP Pump C-9 CHV Discharge CK Valve 12 SEA DE FE-Q F 80-06 2 C fill CTN-SP Pump C-7 CHV Discharge Chack Valve 80-114 2 A 4 MOA C FE-Q PCV ST-Q C C.S. to Radwaste L-4 I.V. LJ-R PI-R 80-115 2 A 4 MOA C FE-Q L-3 PGV ST-Q C Cont. Spray to IJ-R Rad. Waste I.V.

l PI-R 80-118 2 B 6 MOA C FE-Q CLV ST-Q O C.S. Test Line J-6 PI-R to T:rus FCV l

III-8-2 l

l 2 --- - -- _ _ _ _ _ _ _ _ - _

NINE MILE POINT UNIT 1 VALVE TEST TABLE SYSTEM CONTADetENT SPRAY DWG. No. C-18012-C SH.2 l 1 1 I I C.S I C.S I I I I l 1 l CIASS l VALVE l SIZE I ACTU. l NORM. I TEST l STROKE l CHECK I JUST. l OR l {

VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE I POSIT. l REQ. I DIRECT. I VALVE I OR l ALT. l REMARKS l DWG. l l AND l l l 1 l TEST l RELIEF l TEST l l I COOR.I I TYPE l l l l l DIRECT.l REQ. NO.l PERF.i 80-15 2 B 12 APA O FE-Q

1. 12 CTN-SP Inlet D-3 CTV ST-Q 0,C to Drywell FS-Q 0 PI-R 80-16 2 B 12 APA 0 FE-Q

1. 111 CTN-SP HT D-4 GTV ST-Q 0,C Exch. Inlet IV FS-Q 0 PI-R 80-17 2 C 12 SEA DE FE-Q F RR-1 FE-R

1. 12 CTN-SP Loop F-3 CHV Check Valve to trywell Sparger 80-18 2 C 12 SEA DE FE-Q F RR-1 FE-R -

1. 111 CTN-SP Icop F-4 CHV Check Valve to Drywell Sparger 80-19 2 C 3 SEA DE FE-Q F RR-1 FE-R

1. 112 CTN-SP Icop I-4 CHV Check Valve to Torus Sparger III-8-3 P- ___ . _ _ _ _ _ _ _ _

_q

STSTEM CONTAIIAIENT SPRAT NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18012-C SH.2 C.S C.S CLASS VALVE SIZE ACTU. NORN. TEST STROKE CHECE JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. RENARES DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

m 80-25 2 C 12 SEA DE FE-Q F C122 CTM-SP Pump E-9 CMV Ciccharge Check Valve

.~

S0-26 2 C 12 SEA DE FE-Q F ,

C112 CTM-SP Pump E-7 CHV Eiccharge Check Valve 80-35 2 8 12 APA O FE-Q C122 CTN-SP Inlet I-3 CTV ST-Q O.C I.V. to Drywell FS-Q O Sparger PI-R 80-36 2 R 12 APA O FE-Q l C112 CTM-SP Inlet I-4 GTV ST-Q O.C l I.V. to Drywell FS-Q O Sparter PI-R 80-37 2 C 12 SEA DE FE-Q F RR-1 FE-R C122 CTM-SP Loop N-3 CMV i

Check Valve to Drywell 80-38 2 C 12 SEA DE FE-Q F RR-1 FE-R C112 CTM-SP Loop H-4 CMY Check Valve to Drywell Sparger 111-8-4 P- _ _ _ _ _ _ .-- 9

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

SYSTEM CONTAIISENT SPRAY NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-ISO 12-C SN.2 C.S C.S CLASS VALVE SIZE ACTU. NORft. TEST STROEE CHECE JUST. OE VALVE NUISER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AIID TEST RELIEF TEST COOR. TYPE DIRECT. REQ. 100. PERF.

80-39 2 C 3 SEA DE FE-Q F RR-1 FE-R C111 CTM-SP Loop E-5 CMV Check Valve to Torus Sparger  ;

80-40 2 B 6 APA C FE-Q '

Bypass to Torus D-4 GTV ST-Q C.O for Loop #111 FS-Q C PI-R 80-41 2 5 6 APA C FE-Q Bypass to Torus C-3 GTV ST-Q C.O for Loop 8121 FS-Q C PI-R 80-44 2 B 6 APA C FE-Q Bypass to Torus J-4 GTV ST-Q C.O for Loop #112 FS-Q C PI-R 80-45 2 B 6 APA C FE-Q Bypass to Torus J-3 GTV ST-Q C.O for Loop #122 FS-Q C PI-R 80-65 2 C 3 SEA DE FE-Q F RR-1 FE-R C12 Coat. Spray F-5 CMV StrOimer Outlet Check to Torus SEA DE FE-Q F RR-1 FE-R 80-66 2 C 3 G121 CTM-SP Loop E-3 CMV Check Valve to l

T:rus Sparger git-g $

STSTEM CONTAIINIENT SPRAT NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18012-C SH.2 - - - .

C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

80-67 2 C 3 SEA DE FE-Q F RR-1 FE-R C11 Cost. Spray N-5 CMV Straiser Outlet Check to Torus 80-68 2 C 3 SEA DE FE-Q F RR-1 FE-R c C122 CTN-SP Loop I-3 CNY Check Valve to Torus 93-60 2 AC 12 SEA DE PV NOTE 1 Testable Check L-2 CNV MAA LJ-R Ylv. on Raw Water Tio in from Raw Water Loop 8112 93-62 2 AC 12 SEA DE PV NOTE 1 Ter; table Check R-3 CNV MAA LJ-R Ylv. in Tie in free Raw Water Loop #121 93-72 2 A 12 MOA C PV FCV on Raw Water E-2 PCY PI-R Tio la free Raw LJ-R Water Loop 8112 93-73 2 A 12 MOA C PV PCy P FCV on Raw Water C-3 Tio in from Raw Water Loop s121 III-8-6

- _ _ _ _ _E

SYSTEM CONTAlleIENT SPRAY NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18012-C SH.1 --

C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT, VALVE OR ALT. REMARKS VALVE NUMBER DWG. AND TEST RELIEF TEST COOR. TYPE .

DIRECT. REQ. NO. PERF.

L_ _ .

93-09 3 C 12 SEA DE FE-Q F C121 CTM-SP Raw B-7 CMV Watcr Pump Cischarge Ck. Valve 93-10 3 C 12 SEA DE FE-Q F c C111 CIN-SP Raw D-7 CMV Water Pump l Cischarge Ck. Valve 93-11 3 C 12 SEA DE FE-Q F C122 CTM-SP Raw N-7 CNV Water Pump Cischarge check Valve 93-12 3 C 12 SEA DE FE-Q F C112 CTN-SP Raw F-7 CMV Watcr Pump Ciccharge Check Valve 93-25 3 8 12 MOA FE-Q C111 Cont. Spray C-4 GTV O ST-Q O.C Heat Exch. Raw PI-R Water Discharge to Tunnel 93-26 3 8 12 MOA FE-Q GTV O ST-Q 0,C C121 CTN-SP Heat A-4 PI-R Exch. Raw Water Ciccharge to Tunnel III-8-7 3  %

l SYSTEN CONTAllSEENT SPRAY MINE MILE POINT UNIT 1 VALVE TEST TABLE DWG, NO. C-18012-C SH.1

-- r-C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE REQ. NO. PERF.

. . _ _ _ . L DIRECT.

93-27 3 8 12 MOA FE-Q C122 Cont. Spray F-4 GTV O ST-Q O.C RW Cisch. to PI-R Tunnel 93-28 3 8 12 NOA FE-Q C122 Cont. Spray E-4 GTV O ST-Q O.C Ct. Exch. RW PI-R Ciccharge to Tunnel 93-57 3 A/C 12 SEA DE FE-Q F Ciceh. Testable D-6 CMV LK-R R RR-2 Ck. Viv. RW Pump 8111 93-63 3 A/C 12 SEA DE FE-Q F Cicch. Testable H-5 CNV LK-R R RR-2 Ck. V1v. RW Pump

1. 122 93-59 3 A/C 12 SEA DE FE-Q F Cicch. Testable E-5 CHV LK-R R RR-2 Ck. V1v. RW Pump 8112 93-61 3 A/C 12 SEA DE FE-Q F B-6 LK-R R RR-2 Cicch. Testable CHV Ck. Viv. RW Pump

1. 121 III-8-8 m

u "

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NOTES FOR ATTACHMENT 8 SYSTEM: CONTAINMENT SPRAY No. NOTE 1 Testable check valve with manual exerciser (opening handwheel forces disk open, closing handwheel frees disk up for normal operation).

1 III-8-9 l

RELIEF REQUEST RR-1 System: Containment Spray Valve: 80-17:80-18:80-19:80-37:80-38:80-39:80-65:80-66:

80-67:80-68 Category: C Class 2 Function: Containment Spray System simple check valves.

ASME Section XI Quarterly Test Requirements: Verify forward flow.

Basis for Relief: To verify forward flow operability would require spraying torus water into the containment. This would result in permanent damage to equipment located inside the containment.

Alternate Testing: Permanently installed compressed air test lines have been included in the system design. These compressed air lines are used to verify operability of these check valves as well as freedom of flow from the primary and secondary '

loops located inside the containment. This test is performed at refueling when the containment is de-inerted and entry can be made to perform testing.

III-8-10 l

. -f RELIEF REQUEST RR-2 System: Containment Spray Valve: 93-57,93-59,93-61,93-63 Category: A/C Class 3 Function: Prevent reverse flow through the raw water system.

ASME Section XI Quarterly Test Requirements: Verify reverse flow closure operability quarterly.

Basis for Relief: The only method available to verify reverse flow closure operability is by Section XI Leak Testing which is performed each refueling outage.

Alternate Testing: Acceptable Leak Testing during refueling outages will be used to verify reverse flow closure operability.

1 III-8-11 1

= v RELIEF REQUEST RR-3 System: Containment Spray Valve: 93-60:93-62 Category: AC Class 2 Function: Containment Spray Raw Water cross-tie to Containment Spray System check valves.

ASME Section XI Quarterly Test Requirements: Verify reverse flow operability.

Basis for Rollef: The only method available to verify reverse flow closure is by valve leak testing during Appendix J. Type C testing at refueling.

Alternate Testing: Since there is no possible way to verify reverse flow operability by flow testing, these valves will be Appendix J. Type C tested at refueling.

l l

III-8-12 k

" tr PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.9 ATTACHMENT 9 VALVE TEST TABLES AND RELIEF REQUESTS FOR REACTOR CLEAN-UP DWG. NO. C-18009-C SN.1 Pages III-9-1 through III-9-5 I

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111-9-1 l

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SYSTEN RCU NINE MILE POINT UNIT 1 VALVE TEW TABLE DWG. NO. C-18009-C SH.1 C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROEE CHECE JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST <

COOR. TYPE DIRECT. REQ. NO. PERF.

33-01 1 A 6 MOA O FE-Q CU Betura D-1 GTV ST-Q C Isolation Yalve LJ-R (Inside) PI-R 33-02 1 A 6 MOA O FE-Q ,

CU Supply A-2 GTV ST-Q C Isolation Yalve LJ-R 11 (Inside) PI-R  ;

I 33-03 1 AC 6 SEA DE FE-Q R RR-1 FE-R CU Retura D-1 CNV LJ-R Isolation Yalve (outside) 33-04 1 A 6 MOA O FE-Q Cu Supply A-2 GTV ST-Q C Isolation valve LJ-R 12 (outside) PI-R 63-04 2 A 2 APA C FE-Q Post Acc. Sample E-2 GLY ST-Q C Line Retura IV FS-Q C LJ-R PI-R l

l l III-9-2 l- _ _ _ ____ _ _ _

STSTEN RCU NINE MILE POINT UNIT 1 VALVE TEST TABLE DMG. NO. C-18009-C SN.1 C.S C.S tratt VALVE SIZE ACTU. NORN. TEST STROKE CNECE JUST. OR (CAT.) POSIT. DIRECT. VALVE OR ALT. RussanES UALVE amaname AND (IN.) 'g ' ripe REQ.

! DWG. AIS I TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

l 63-05 2 A 2 APA C FE-Q Post Acc. Sample E-2 GLV ST-Q C Line Betura IT FS-Q C LJ-R PI-R 63.2-01 2 AC .75 SEA DE FE-Q R RR-1 FE-R f

l C.O. Relief Line M-2 CNY LJ-R j Vac. Brkr.

63.2-02 2 AC .75 SEA DE FE-Q R RR-1 FE-R C.U. Relief Line M-2 CNY LJ-R Yac. Bekr.

63.1-01 2 C 20 SEA DE LJ-R VG-3

RCU Relief to M-1 CNY Toinas I.T. ,

63.1-C2 2 C 20 SEA DE LJ-R VG-3 BCU Belief to E-1 CMV Torus I.T.

111-9-3 p- - - -- -

_ _ _ _ _ __ _ _ _ _ g

RsL!sr Raquest RR-1 .

l System: Reactor Clean-Up i

Valve: 33-03:63.2-01863.2-02 Category: AC Class: 1 (33-03) 2 (63.2-01:63.2-02) j i

Function: Containment isolation simple check valve (reve.se flow closure for containment isolation only).  !

l ASMs section XI [

Quarterly Test  !

Requirements: Verify reverse flow closure i Basis for Relief: The only method evallable to verify reverse flow closure is by valve leak testing during Appendia J.

Type C, testing at refueling.  ;

Alternate testing: Reverse flow closure will be vertfled during Appendis i J. Type C testing at refueling. '

i I

i l

{

6 h

t i

I t

l t

!!!-9-4 l

_______._________]

o y NOTE 3 FOR ATTACHMENT 9 SYSTEMI REACTOR Ct.EAN-UP UL. N91K 1 Reactor Vessel deeln valve. Maintalnad closed during all modes of operation.

l l

!1I-9-S

_ - - _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Q

l l

PUNP AND VALVE INSERVICE TESTING PROGRAN PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION 111 S.10 ATTACHNENT 10 VALVE TEST TABLES AND RELIEF REQUESTS l

FOR INERT CAS PURCE AND FILL DWO. NO. C-18014-C SN.1 Pages

!!!-10-1 through !!!-10-6

!!I-10-1

SYSTM INRT CAS FORCE AND FILL NINE MIII POINT UNIT 1 ' VALVE TEST TABLE BMG. NO. C-18014-C 55.1 1 I l I I I I I l C.S I C.S I I l CIASS I VALVE I SIZE I ACTU. I NORM. l TEST l STROKE CHECK l JUST. OR VALVE NUMBER I AND I (CAT.) l (IN.) l TYPE I POSIT. l REQ. l DIRECT. , VALVE l OR ALT. REMARKS l DuC. I I AND I l l l l TEST l REMEF l TEST l COOR.I I TYPE l l l l l DIRECT.I REQ. NO.l PRF. l 201-07 2 A 20 MOA C FE-Q Torus Air Vent & B-8 BFV ST-Q C Purge I.V. #12 U-R PI-R 201-08 2 A 20 APA C FE-Q Torus Air Vent & B-8 BFV ST-Q C Purge I.V. #11 FS-Q C 5

U-R PI-R 201-09 2 A 24 MOA C FE-Q Drywell Air Vent B-6 BFV ST-Q C

& Purge I.V. #12 U-R PI-R 201-10 2 A 24 APA C FE-Q Drywell Air Vent C-7 BFV ST-Q C

& Purge I.V. #11 FS-Q C U-R FI-R 201-16 2 A 20 APA C FE-Q

- K-7 BFV ST-Q C Tarus N2 Vent

& Purge Inside I.V. FS-Q C U-R PI-R C

III-10-2 m .-_ _ _ _

3

SYSTEN INERT CAS PURCE AND FILL NINE MILE POINT UNIT 1 VALVE TEST TAh!.P.

DWG. NO. C-18014-C SH.1 --------..

C.S C.S CLASS VALVE SIZE ACTU. NORN. TEST STROKE CHECE JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. R EM A t<K;;

DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF7 201-17 2 A 20 NOA C FE-Q Vent L-7 BFV ST-Q C Torus N2 LJ-R

& Purge Outside I.V.

PI-R 201-18 3 B 12 APA C FE-Q BFV ST-Q C Eners. Vent from L-2 Drywell & Torus B.V. FS-Q C PI-R 201-22 3 B 30 APA C FE-Q RR-1 FE-R Discharge B.V. of K-1 BFV ST-Q C ST-R Emerg. Vent & FS-Q C FS-R Purge Fan PI-R 201-31 2 A 24 NOA C FE-Q Drywell N2 Vent J-2 BFV ST-Q C

& Purge Outside I.V. LJ-R PI-R 201-32 2 A 24 APA C FE-Q Drywell N2 Vent I-2 BFV ST-Q C

& Purge Inside I.V. FS-Q C LJ-R PI-R 201.1-09 2 A 1 NPA C FE-Q Post Loca AOV I-3 CLV ST-Q C FS-Q C Inside I.7.

LJ-R

• PI-R III-10-3 P__.______-._____..______________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

q

SYSTEM INERT CAS PURGE AND FILL NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.1 l l l l l l l l l C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF l TEST l l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l l 201.1-11 2 A 1 NPA C FE-Q P ct Loca A0V J-3 CLV ST-Q C Outcide I.V. FS-Q C LJ-R PI-R 201.1-14 2 A 1 APA C FE-Q Psct Loca Vent E-2 GLV ST-Q C A0V Inside I.V. FS-Q C LJ-R PI-R 201.1-16 2 A 1 APA C FE-Q P:ct Loca Vent D-2 GLV ST-Q C A0V Outside I.V. FS-Q C LJ-R PI-R 201.2-02 2 B 1 ADA C FE-Q Drywell N2 I-4 CLV ST-Q 0,C Blied B.V. FS-Q C PI-R 201.2-03 2 A 4 ADA 0 FE-Q Drywell N2 .

I-3 GLV ST-Q C,0 Mskrup & Bleed FS-Q C Outeide I.V. LJ-R PI-R 201.2-04 2 B 1 ADA C FE-Q Torus N2 I-6 CLV ST-Q 0,C Hektup B.V. FS-Q C PI-R III-10-4 m _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 8

I SYSTEM INERT CAS PURGE AND FILL NINE MILE POINT UNIT 1 VALVE TEST TABLE DWC. NO. C-18014-C SH.1 l l l l l l l l l C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. I NORM. l TEST l STROKE l CHECK l JUST. l OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF l TEST l l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l l 201.2-06 2 A 3 NDA C FE-Q Terus N2 I-6 GLV ST-Q C,0 Mikzup & Bleed FS-Q C Outcide I.V. LJ-R PI-R 201.2-136 3 B 3 APA C FE-Q Rzcetor Bldg. L-3 PCV ST-Q C

+

Emerg. Vent B.V. FS-Q C PI-R 201.2-32 2 A 4 ADA 0 FE-Q Drywell N2 I-2 GLV ST-Q C,0 Mxksup & Bleed FS-Q C Incide I.V. LJ-R PI-R 201.2-33 2 A 3 ADA C FE-Q Teru3 N2 I-7 GLV ST-Q C,0 Mikeup & Bleed FS-Q C Innide I.V. LJ-R PI-R 201.9-46 2 B 1.5 APA C Fh-Q Nitrogen B.V. to H-4 GTV ST-Q C,0 Torus FS-Q C PI-R 201.9-47 2 B 1.5 NPA C FE-Q N2 B.V. to H-5 GTV ST-Q C,0 Drywell FS-Q C PI-R III-10-5

_ _ ______________1

RELIEF REQUEST 4 RR-1 Pa5e III-10-6 SYSTEM: Reactor Containment Vent & Purge COMPONENT: 201-22 CATEGORY: B CLASS: 3 FUNCTION: Emergency Vent & Purge Fan Discharge Blocking Valve.

ASME SECTION XI QUARTERLY REQ'MTS: Exercise, Time and Failsafe BASIS FOR RELIEF: This valve is electrically interconnected to the Vent &

Purge Fan such that valve operation is only possible by operating the fan. This fan is only used for inerting/ purging the containment. Operation of the fan durin5 any other period could damage the fan since no flowpath exists.

ALTERNATE TESTING: Valve exercising, timing and failsafe testing will be performed whenever the :ontainment is inerted and at refueling outages as a minimum to coincide with Vent &

Purge fan operation.

1 III-10-6 I

3 I

l PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 1 SECTION III I

5.11 ATTACHMENT 11 VALVE TEST TABLES AND RELIEF REQUESTS FOR 4 HYDROGEN-OKYGEN NONITORING DWG. NO. C-18014-C Pages III-11-1 through III-11-6 III-11-1 l'

l SYSTEM HYDROGEN-0XYGEN MONITORING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.2 l l l l l l l l l C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. I REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF l TEST l l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l l 201.2-109 2 A .75 ADA 0 FE-Q H022 Sys. #11 C-7 GLV ST-Q C Rsturn to Torus FS-Q C In,ide I.V. IJ-R PI-R l

201.2-110 2 A .75 ADA 0 FE-Q ,

H022 Sys. #11 C-6 GLV ST-Q C Tcrus Sample FS-Q C Inside I.V. LJ-R PI-R 201.2-111 2 A .75 ADA 0 FE-Q H022 Sys. #11 C-7 GLV ST-Q C Tcrus Sample FS-Q C Outside I.V. LJ-R PI-R 201.2-112 2 A .75 ADA 0 FE-Q H022 Sys. #11 B-7 GLV ST-Q C Raturn to Torus FS-Q .C Outcide I.V. LJ-R PI-R III-11-2 W_--____-_-_- _ - _ _ _ _

SYSTEM HYDROGEN-0XYGEN MONITORING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.2 l l 1 I I I I I I C.S l C.S I l CLASS l VALVE SIZE l ACTU. I NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER l AND l (CAT.) 1 (IN.) l TYPE l POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS l DWG. l l AND 1 TEST RELIEF TEST l COOR.I l TYPE l DIRECT., REQ. NO. PERF.

201.2-23 2 A .50 SOA 0 FE-Q H022 Sys. #12 H-8 GLV ST-Q C Tcrus Sample LJ-R Inside I.V. PI-R 201.2-24 2 A .50 SOA 0 FE-Q H022 Sys. #12 H-7 GLV ST-Q C Torus Sample LJ-R Outside I.V. PI-R 201.2-25 2 A .50 SOA 0 FE-Q H022 Sys. #12 G-7 GLV ST-Q C Drywell Sample LJ-R Inside I.V. PI-R 201.2-26 2 A .30 SOA 0 FE-Q H022 Sys. #12 H-7 GLV ST-Q C Drywell Sample LJ-R Outside I.V. PI-R 201.2-27 2 A .50 SOA 0 FE-Q H022 Sys. #12 0-6 GLV ST-Q C Drywell Sample LJ-R Inside I.V. PI-R 201.2-28 2 A .50 SOA 0 FE-Q H022 Sys. #12 H-6 GLV ST-Q C Drywell Sample LJ-R Outside I.V. PI-R 201.2-29 2. A 0.5 SOA 0 FE-Q H022 #12 G-6 GLV ST-Q C Drywell Sample LJ-R Inside I.V. PI-R III-11-3

SYSTEM HYDROCEN-0XYCEN MONITORING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.2 l l l l l 1 l l 1 C.S l C.S I l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. I OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF l TEST , l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF. ,

201.2-30 2 A 0.5 SOA 0 FE-Q H022 #12 H-6 CLV ST-Q C Drywell Sample LJ-R Outside I.V. PI-R 201.2-67 2 AC .75 SEA DE FE-Q R RR-1 FE-R H022 Sys. #12 H-7 CHV LJ-R Sccple Return to Drywell IN I.V.

201.2-68 2 AC .75 SEA DE FE-Q R RR-1 FE-R H022 Sys. #12 I-7 CHV LJ-R Ss.cple Return to Drywell OUT I.V.

201.2-70 2 AC .75 SEA DE FE-Q R RR-1 FE-R H022 Sys. #12 J-8 CHV LJ-R Sciple Return to Terus Inside I.V.

201.2-71 2 AC .75 SEA DE FE-Q R RR-1 FE-R H022 Sys. #12 J-8 CHV LJ-R Srple Return to T:rus Outside I.V. ,

201.7-01 2 A 1 ADA 0 FE-Q H022 Sys. #11 E-4 GLV ST-Q C Socple Stream B FS-Q C In ide I.V. IJ-R PI-R 201.7-02 2 A 1 ADA 0 FE-Q H022 Sys. #11 D-4 GLV ST-Q C Serple Stream B FS-Q C Outside I.V. LJ-R PI-R III-11-4 2_ - - _ _ _ _ _ - - -____. -- _._.

SYSTEM HYDROGEN-0XYGEN MONITORING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.2 l l l l l l l l 1 C.S l c.S l 1 l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR I VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. I REQ. l DIRECT. l VALVE l OR I ALT. l REMARKS l DWG. l l AND l l l l l TEST l RELIEF TEST I C00R.l l TYPE l l l l l DIRECT.I REQ. NO.i PERF.

==

201.7-03 2 A 1 ADA 0 FE-Q H022 Sys. #11 E-5 GLV ST-Q C Drywall Sample FS-Q C Stru a A Inside I.V. LJ-R PI-R 201.7-04 2 A 1 ADA 0 FE-Q H022 Sys. #11 D-5 GLV ST-Q C Drywall Sample FS-Q C .

Strera A Outside I.V. LJ-R PI-R 201.7-08 2 B 1 ADA 0 FE-Q Drywell Can G-4 GLV ST-Q C Srple Line Inside FS-Q C I.V. LJ-R PI-R 201.7-09 2 B 1 ADA 0 FE-Q Drywell Can H-4 GLV ST-Q C Sarple Line Outside FS-Q C I.V. LJ-R PI-R 201.7-10 2 A 1 ADA 0 FE-Q H022 Sys. #11 G-5 GLV ST-Q' C Rzturn to Drywell FS-Q C Inside I.V. LJ-R PI-R 201.7-11 2 A 1 ADA 0 FE-Q H022 Sys. #11 H-5 GLV ST-Q C-Return to Drywell FS-Q- C Outside I.V. LJ-R PI-R III-11-5 =

E _ _ . _ _ _ _ _ _ _ __ _ _

ms, RELIEF REQUEST RR-1 System: Hydrogen-Oxygen Monitoring Valve: 201.2-67:201.2-68:201.2-70:201.2-71 Category: AC Class 2 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).

ASME Section XI Quarterly Test Requirements: Verify reverse flow closure.

Basis for Relief: Ine only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.

Alternate Testing: Reverse flow closure will- be verified during Appendix J, Type C, testing at refueling.

4 III-11-6 b

g PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.12 ATTACHMENT 12 VALVE TEST TABLES AND RELIEF REQUESTS FOR TIP DWG. No. C-18014-C SH.2 Pages III-12-1 through III-12-5 l

I I

I l

l III-12-1 t b

SYSTEM TIP NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.2 i~ 1 l l l l l l ~i C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. I RFr; ARKS ,

l DWG. l l AND l l l' l l TEST RELIEF TEST l C00R.l l TYPE l l l l l DIRECT., REQ. NO. PERF.

201.2-39 2 AC .75 SEA DE FE-Q R RR-1 FE-R N2 Purge TIP H-2 CHV LJ-R Indsxers 5563 201.2-40 2 AC .75 SEA DE FE-Q R RR-1 FE-R N2 Purge TIP G-2 CHV LJ-R Indrxers 5563 ,

TIP-1 (BALL) 2 A .50 SOA C FE-Q NOTE 1

1. 1 Tip Machine F-3 BLV ST-Q C Drive & Control FS-Q C LJ-R TIP-2 (BALL) 2 A .50 SOA C FE-Q NOTE 1

1. 2 Tip Machine F-3 BLV ST-Q C Drive & Control FS-Q C LJ-R TIP-3 (BALL) 2 A .50 SOA C FE-Q NOTE 1

1. 3 Tip Machine F-3 BLV ST-Q C Drive & Control FS-Q C LJ-R TIP-4 (BAI1) 2 A .50 SOA C FE-Q NOTE 1

1. 4 Tip Machine F-3 BLV ST-Q C Drive & Control FS-Q C LJ-R III-12-2 F=' . ___ -?

SYSTEM TIP NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.2 l l l l l l l l l C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l DWG. l l AND l l l l l TEST l RELIEF l TEST l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.

TIP-1 (SHEAR) 2 D .50 EXA -

0 EX-P NOTE 1,2 F-3 EXV TIP-2 (SHEAR) 2 D .50 EXA 0 EX-P NOTE 1,2 F-3 EXV TIP-3 (SHEAR) 2 D .50 EXA 0 EX-P NOTE 1,2 F-3 EXV TIP-4 (SHEAR) 2 D .50 EXA 0 EX-P F-3 EXV NOTE 1,2 III-12-3 2-___--___-________ _  %

. u NOTES FOR ATTACtiMENT 12 SYSTEM: Tip NO. NOTE 1 Tip Ball and Shear Valves are not shown on the P&ID.

2 The Tip Shear Valves are explosive actuated valves wnich are used to provide a containment isolation barrier should the Ball Valves fail to operate properly.'

111-12-4 f}.

. u-RELIEF REQUEST RR-1 System: TIP Valve: 201.2-39:201.2-40 Category: AC Class 2 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).

ASME Section XI Quarterly Test Requirements: Verify reverse flow closure.

Basis for Relief: The only metnod available to verify reverse flow closure is by valve leak testing during Appendix J, Type C testing at refueling.

Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C, testing at refueling.

I l

1 l

III-12-5 l

01

. y.,

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.13 ATTACHMENT 13 VALVE TEST TABLES AND RELIEF REQUESTS FOR NITROGEN SUPPLY #11 DWG. NO. C-18014-C SH.3 Pages III-13-1 through III-13-4 III-13-1

. . _ _ , . - . - ._. . . -._ - k

SYSTEM N2 SUPPLY #11 NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.3

=

l l 1 l l l l l 1 C.S l C.S l 1 l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l DWG. l l AND l l l l l TEST l RELIEF l TEST l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l 201.9-17 3 C 0.5 SEA C RT-P fil N2 Storage G-5 REV Tenk Liquid With-drawal 140 #PSV 201.9-19 3 B 1 NDA C FS-Q 0 fil N2 Storage H-5 GTV P1-R Tank Liquid With-drtwal B.V.

c 201.9-24 3 C 0.5 SEA C RT-P 140 #PSV Af ter J-4 REV Anbient Vaporizer 201.9-25 3 C 0.5 SEA C RT-P fil N2 Storage H-4 REV Tcnk 140 iPSV After B.V. 201.9-19 201.9-49 3 B 1 NDA 0 FS-Q 0 NOTE 1 N2 FCV L-5 GLV 201.9-69 3 C 1 SEA C RT-P 33 #F0V After L-4 REV 201.0-48 201.9-70 3 C 1 SEA C RT-P 33 #PSV After M-3 REV FCV 201.9-49 201.9-94 3 C 1 SEA DE FE-Q F NOTE 2 N2 Supply to I-7 CHV CAD Valve Actuators III-13-2 D. - - = = -

_ __ . . _ __ _ _ _ __ _ _ A

SYSTEM N2 SUPPLY #11 NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.3

. ___- __- -= - - -

r_ - -

C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST

! TYPE '

j j

DIRECT. REQ. NO. PERF.

COOR.l____

_ ----________.L_________.-- m ___ _________

201.9-10 3 C 1x1" SEA C RT-P N2 Storage Tank E-2 REV PSV 201.9-11 3 C 1x1" SEA C RT-P N2 Storage Tank F-2 REV ,

PSV 201.9-40 3 C .5x.25" SEA C RT-P N2 Press. E-6 REV Build. Coil PSV 201.9-38 3 B 1.5" NDA O FS-Q O F-6 GTV N2 Press.

Build. Coil PCV 201.9-48 3 B 1" NDA O FS-Q O K-5 CLV PI-R NOTE 1 C2 PCV III-13-3

- e

.o _ _ _ _ _ - _ _ _ _ _ _ __-____

NOTES FOR ATTACHMENT 13 SYSTEM: NITROGEN SUPPLY No. 11 NO. NOTE 1 Fall open flow control valva.

2 Forward flow operability verified by proper operation of the nitrogen supplied CAD valves.

l l

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111-13-4

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1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 e

SECTION III 5.14 ATTACHMENT 14 i

VALVE TEST TABLES AND RELIEF REQUESTS FOR

. NITROGEN SUPPLY NO. 12

.I l DWG. NO. C-18014-C SH.4 Pages III-14-1 through III-14-4 4

1 i

111-14-1

_ _ _ _ __ - _ . - . . . . . , . - . _ - _ _ _ _ _ _ . . ._. _ _ _ , _ - _ _ . _ _ _ , . _ _ . . _ _ _ _ . _ . . __ __ .l

1 SYSTEM N2 SUPPLY #12 NINE MILE POINT UNIT 1 VALVE TEST TABLE DWC. NO. C-18014-C SH.4 l l l l l l l l l C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. I VALVE l OR I ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF l TEST l COOR.I l TYPE l l l l l DIRECT.l REQ. NO.l PERF. ,

201.8-01 3 B 1.0 ADA DE FS-Q O N2 PCV G-6 GLV 201.8-02 3 B 1 ADA DE FS-Q 0 NOTE 1-J-6 GLV N2 FCV 201.8-03 3 B 1.5 NDA C FE-Q Liquid N2 B.V. C-2 PGV ST-Q C to Stean Vaporizer FS-Q C .

& Control Cabinet PI-R 201.8-04 3 B 1 NDA C FE-Q B.V. to 6000 SCFN F-3 GTV ST-Q C,0 Ambient Vaporizer FS-Q 0 PI-R 201.8-10 3 C 0.5 SEA C RT-P PSV cn Inlet Side F-3 REV of 201.8-04 201.8-11 3 C 0.5 SEA C RT-P PSV on Outlet F-3 REV Sid2 of 201.8-04 201.8-12 3 C 0.5 SEA C RT-P PSV cn Discharge F-5 REV Sida of 6000 SCFH Ambirnt Vaporizer 201.8-13 3 C 1 SEA C RT-P PSV After PCV I-5 REV 201.8-01 111-14-2

m. - -- - - _ _ _ _ _ _ _ - _ _ _ _ _ _ s

SYSTEM N2 SUPPLY #12 NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.4 l l l l l l l l l C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. I VALVE l OR l ALT. I REMARKS l l DWG. l l AND l l l l l TEST l RELIEF l TEST l l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.!

l 201.8-14 3 C 1 SEA C RT-P PSV After PCV K-5 REV 201.8-02 201.8-39 3 C 0.5 SEA C RT-P P.S.V. to S.O.V.s E-2 REV 201.8-03B to 201.8-04B PSV SSI-40 3 C 1.0 SEA C RT-P

1. 12 N2 Tank C-2 REV Pr203 Build. Coil PSV 8 250#

III-14-3 i => _ _ - - - _ _ _ _

. u NOTES FOR ATTACHMENT 14

)

SYSTEM: NITROCEN SUPPLY NO. 12 NO. NOTE 1 Fall open flow control valve.

111-14-4 k

. r I

I PUNP AND VALVE INSERVICE TESTING PROGRAN PLAN FOR NINE NILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.15 ATTACHMENT 15 VALVE TEST TABLES AND RELIEF REQUESTS FOR REACTOR BUILDING HVAC DWG. No. C-18013-C Pages III-15-1 through III-15-3 l

l l

111-15-1 j

SYSTEM R5NVAC NINE MILE POINT UNIT 1 VALVE TEST TABLE  ;

DhiC. NO. C-18013-C l 1 l l 1 I l l l C.S I C.S I l l CLASS l VALVE l SIZE I ACTU. 1 NORM. l TEST l S11t0KE I CHECK l JUST. l OR VALVE NUMBER I AND l (CAT.) l (IN.) I TYPE l POSIT. l REQ. I DIRECT. I VALVE l OR l ALT. I REMARKS I DWG. l l AND l l l l l TEST l RELIEF l TEST l l C00R.l l TTPE I l l l l DIRECT.] REQ. NO.l PERF. I l 202-15 3 5 54 ADA 0 FE-Q Supply Isolation C-4 BFV ST-Q C Valve FS-Q C PI-R 202-16 3 B 54 ADA O FE-Q S:pply Isolation C-4 BFV ST-Q C Valve FS-Q C PI-R 202-31 3 5 54 _ ADA 0 FE-Q Exhaust Isolation J-2 BFV ST-Q C Valve FS-Q C PI-R 202-32 3 B 54 ADA O FE-Q Exhaust Isolation J-2 BFV ST-Q C Valve PS-Q C i PI-R 202-34 2 B 12 ADA C FE-Q Es. Exh. Fan #11 M-5 BFV ST-Q 0,C Outlet FS-Q 0 PI-R l 202-35 2 B 12 ADA C FE-Q l Es. Exh. Fan #12 M-6 BFV ST-Q 0,C l Outlet FS-Q O PI-R 202-36 2 B 12 ADA O FE-Q Ro. Vent Sys. I-3 BFV ST-Q 0,C Inlet FS-Q 0 ,

PI-R III-15-2 i p_ _

SYSTEM R&BVAC NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18013-C I l l l l l l l 1 C.S l C.S 1 I l CIASS l VALVE l SIZE l ACTU. l NORM. I TEST l STROKE l CHECK l JUST. I OR I VALVE NUMBER l AND l (CAT.) I (IN.) l TYPE l POSIT. l REQ. l DIRECT. I VALVE l OR l ALT. I REMARKS 1 DWG. l l AND I l l l l TEST l RELIEF l TEST l l l COOR.l l TTPE l 1 l 1 l DIRECT.l REQ. NO.I PERF.l l 202-37 2 5 12 ADA C FE-Q i I

Loop #11 Inlet I-5 BFV ST-Q 0,C FS-Q O PI-R 202-38 2 B 12 ADA C FE-Q Loop #12 Inlet I-6 BFV ST-Q 0,C FS-Q O PI-R 202-74 3 B 2 ADA C FE-Q Loop #11 Cooling I-5 BFV ST-Q C,0 -

FS-Q C l PI-R 202-75 3 5 2 ADA C FE-Q Loop #12 Cooling I-7 BFV ST-Q C,0 FS-Q C PI-R 202-47 3 B 2 ADA C FE-Q i Cross-tie Valve L-6 BFV ST-Q 0,C l FS-Q O I PI-R 1

l 202-50 3 B 12 ADA O FS-Q 0 Exh. Fan #11 L-5 BFV PI-R l

Inlet l

202-51 3 5 12 ADA O FS-Q O Exh. Fan #12 L-6 BFV PI-R Inlet III-15-3 D _ _ _ _ _

7 i

PUMP AND VALVE INSERVICE TESTING PROGRAN PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.17 ATTACHMENT 16 VALVE TEST TABLES AND RELIEF REQUESTS FOR LIQUID POISON DWG, NO. C-18019-C Pages III-16-1 throuEh III-16-4 1

11I- 16-1

[

SYSTEM LIQUID POISON NINE MILE POINT UNIT 1 VALVE TEST TABLE DWC. NO. C-18019-C l l l 1 l l l l l C.S I C.S l 1 l CIASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l VALVE NUMBER I AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT.  !' VALVE l OR _ l ' ALT. l REMARKS l DWG.'l l AND l l TEST RELIEF TEST l C00R.l l TYPE l l DIRECT. REQ. NO. PERF.

42-19 2 C 1.5 SEA DE FE-Q F Pump #11 Disch. F-5 CHV Check 42-20 2 C 1.5 SEA DE FE-Q F Pump #12 Disch. F-7 CHV Check C

42.1-02 1 C 2 SEA DE FE-Q F RR-1 FE-R CIV Inside B-6 CHV LJ-R R RR-2 42.1-03 1 C 2 SEA DE- FE-Q F RR-1 FE-R CIV Outside C-6 CHV LJ-R R RR-2 NPO4A 2 C IX2 SEA DE- RT-P Icop #11 PSV F-4 REV NPO4B 2 C IX2 SEA DE RT-P Icop #12 PSV. F-6 REV NP05A 2 D 1.5 EXA C EX-P Liquid Poison D-5 EXV Explosive Valve #11

~

.NPO58 2 -D 1.5 EXA C- EX-P Liquid Poison D-7 EXV Explosive Valve #12 III-16-2 P ------- _- _ ----_ - - _ _ _ _ _ - _ . . _ .

. n\

l RELIEF REQUEST RR-1 System: Liquid Poison Valve: 42.1-02:41.2-03 Category: C Class 1 Function: Liquid poison injection line check valves.

ASME Section II Quarterly Test Requirements: Verify forward flow operability.

Basis for Relief: To verify forward flow operability during normal operation would require firing a squib valve and injection water into the reactor vessel using the 11guld poison pumps.

Injection water during operation could result in adverse plant conditions such as changes in reactivity, power transients, thermal shock induced cracking and a possible plant trip.

Alternate Testing: Verify forward flow operability during refueling during the liquid ' poison system injection test, which fires at least one squib valve and pumps domineralized water into the reactor vessel.

111 ~16-3 I

l RELIEF REQUEST RR-2 System: Liquid Poison Valve: 42.1-02:42.1-03 Category: C Class 1 i

Function: Containment and pressure isolation simple check valves l (reverse flow closure for containment and pressure  !

isolation only) j l

ASME Section KI Quarterly Requirements: IW-3520 l Verify reverse flow closure.

Basis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J. Type C. Testing at Refueling.

Alternate Testing: Reverse flow closure will be verified during Appendix J.

Type C. Testing at Refueling.

l l

l l

111'16-4

\

l c)

-?

ig

+

1 l

I s

,T t.

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.18 ATTACHMENT 17 VALVE TEST TABLES AND RELIEF REQUESTS FOR SPENT FUEL STORAGE POOL FILTERING & COOLING DWG. NO.'C-18008-C Pages III-17-1 through III-17 -4 III- 17-1 k

SYSTEM SFSPFC NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18008-C .______

.____ =

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

=- _

C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS VALVE NUMBER DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

___ ___ J__. ______ _ _______ __

54-12 3 B 6 ADA DE FE-Q Filter #12 Loop G-8 BFV ST-Q O.C Inlet B.V. FS-Q C PI-R 54-13 3 B 6 ADA DE FE-Q

• Filter #11 Loop C-5 BFV ST-Q 0,C Inlet B.V. FS-Q C PI-R 54-45 3 C 6 SEA DE FE-Q F H3ct Exchanger L-8 CHV 012 - Outlet -

Chsck Valve 54-46 3 C 6 SEA DE FE-Q F H;st Exchanger L-5 CHV C11 - Outlet -

Ch:ck Valve 54-71 3 C 6 SEA DE FE-Q F Fusi Pool Loop F-1 CHV R RR-1 Intcke Check Valve 54-72 3 C 6 SEA DE FE-Q F Fual Pool Loop E-1 CHV R RR-1 I:tcke Check Valve SEA DE FE-Q F FP-308 3 C 2 Fugl Pool Loop C_1 CHV Rsturn - Chect Valve to Siphon BRKR III-17-2 F=. N

SYSTEM SFSPFC NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18008-C

(_

i C.S C.S CLASS VALVE SIZE ACTU. , NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND . TEST RELIEF TEST i COOR. TYPE I

DIRECT. REQ. NO. PERF.

--_ b - _ _ _ _

.. .1 J FP-310 3 C 2 SEA DE FE-Q F Fu21 Pool Loop E-1 CHV R; turn - Check Vcive to Siphon BRKR 57-25 3 8 3 ADA C FS-Q O .,

Fusi Pool Make-up E-2 GLV Normal LCV 57-58 3 B 3 SOA C FS-Q O Strge Tank - G-2 GLV Maka-up Back-up LCV 57-03 3 C 3 SEA DE FE-Q F Faol Pool Level E-2 CHV Cmtrol Check III-17-3 P__.________________ __ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _

q

7 .,

RELIEF REQUESf RR System: Spent Fuel Storage Pool Filtering & Cooling.-

Valve (s): 54-71,54-72 Category: C Class: 3 Function: Si ent Fuel Pool intake check valves to prevent siphoning of j fuel pool water.

J.SME Section XI

Quarterly Requirements

Verify reverse flow closure operability i Basis for Relief: Due to the system configuration, there is no means to attempt to introduce a reverse flow through these check valves. Ihe design function of these valves is to prevent water from being drained out of the fuel pool in the event

. . that a vacuum should be created witnin the piping system.

In addition to check valves 54-71 & 72, the system has been provided witn sipnon breamers (FP-308 & FP-310) between tne check valves and the fuel pool which are designed to

maintain tne system of atmospheric pressure. Proper i operation of the siphon breakers insures that a vacuum will not be created and that no reverse flow will occur enrough either check valve.

Alternate Testing: Ihe fuel pool siphon breaker check valves (FP-308 & 310) i will be tested for forward flow operability once per quarter by manual exercising of the disk.

1 i

111-17-4

_ _ _ . . . _ . . _ I

f PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.19 ATTACHMENT 18 VALVE TEST TABLES AND RELIEF REQUESTS FOR SAMPLE DWG. NO. C-18041-C SH.7 Pages III-18-1 through III-18-2 III- 18-1

- .b.

~ .. . . - -

SYSTEM SAMPLE NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18041-C SH.7 i l l l l l l l l C.S I C.S I l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE' l CHECK l JUST. l OR l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. I VALVE l OR l ALT. l REMARKS l DWG. l l AND l l l l l TEST l RELIEF l TEST l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l

=

122-03 2 A 1 ADA C FE-Q Pozt Accident A-3 CLV ST-Q C Simple IV FS-Q C LJ-R PI-R III 'J8-2 m _ _ _ .

I l

l PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.20 ATTACHMENT 19 VALVE TEST TABLES AND RELIEF REQUESTS FOR REACTOR BUILDING CLOSED LOOP COOLING DWG. NO. C-18022-C SH.2 C-18022-C SH.3 C-18022-C SH.4 C-18034-C SH.1 Pages III-19-1 through III-19-8 III- 19 1 1

SYSTEM RBCLCW NINE MILE POINT UNIT 1 VALVE TEST TABLE DWC. NO. C-18022-C SH.3

~ '

l l l 1 l l l l l C.S I c.S I l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JGST. I OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR I ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF . l TEST l l l COOR.l l TYPE l l l l l DIRECT.1 REQ. NO.1 PERF. l l 70-04 3 C 12 SEA DE FE-Q F Pump #11 E-8 CHV R Dicch. Check 70-05 3 C 12 SEA DE FE-Q F Pump #12 E-7 CHV R Dicch. Check 70-06 3 C 12 SEA DE FE-Q F .

Pump #13 E-6 CHV R Dicch. Check 70-94 2 B 8 MOA 0 FE-Q RR-1 FE-R RBCLC Return I-8 GTV ST-Q C ST-R from DW Air Coolers LJ-R VG-3 PI-R 70-95 2 C 8 SEA DE FE-Q F RBCLC DW Air K-5 CHV R RR-2 Coolor Supply IV- LJ-R VG-3 III- 19-2 P . _ _ - ---______ _ _ _ _ _ _ _ _ J

SYSTEM RBCLCW llINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18022-C SH.2 C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE , , DIRECT.j REQ. NO. PERF.  ;

i

-._ - - - 4_ ---A-_ & _

70-MU-7 3 C 1.5 SEA DE FE-Q F NOTE 1 CLC Make-up Check M-5 CHV 71-127 3 B 2 ADA O FS-Q O Mako-up Domin. L-6 CLV 71-MU-11 3 C 2 SEA DE FE-Q F NOTE 1 Make-up Domin. L-6 CHV Supply Check III-19-3 P A

SYSTEM RBCLCW NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18022-C SH.4 l l l l l l l l l C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF l TEST l l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l l' 70-92 2 B 4 MOA 0 FE-Q RR-1 FE-R RBCLC Return from E-6 GTV ST-Q C ST-R RX Recire Pump LJ-R VG-3 Cooler Header PI-R 70-93 2 C 4 SEA DE FE-Q F Recire Pump E-5 CHV R RR-3 Motcr Cooler I.V. LJ-R VG-3 III-19-4 m - _ _ _ - -- _ __

NOTES FOR ATTACHMENT 19 SYSTEM: RBCLCW

& NOTE 1 This valve is in the line from the R8CLCW make-up tank to the system and assures adequate NPSH for the RBCLCW pumps.

This system is in operation during all modes of plant operation, including cold shutdown and refueling. Proper operation of the valve is verified by proper system operation.

III- 19-5 b

v

-,e RELIEF REQUEST RR-1 System: RBCLCW Valve: 70-92:70-94 Category: B Class: 2 Function: Inlet and outlet bock valves to the recirculation pump coolers and drywell air coolers.

ASME Section XI Quarterly Test Requirements: Exercise and time.

Basis For Relief To test these valves would require interruption of cooling water to the recirculation pump coolers and the drywell air coolers. Loss of cooling water for more than a few minutes could cause dunt.go to the recirculation pumps. Also, loss of drywell coolers could cause a reactor tip due to high drywell temperature or pressure. Failure of these valves to reopen could cause ~ extensive damage to the equipment being cooled.

Alternate Testing: Exercise and time during scheduled refueling outage.

l l

1 1

I III.19-6 I

- r RELIEF REQUEST RR-2 System: Reactor Building Closed Loop Cooling Component: 70-95 Category: C Class: 2 Function: Isolation check valve for cooling water supply line to drywell air coolers and recirculation pump coolers.

ASME Section XI Quarterly Requirements: Reverse flow operability.

Basis for Relief: The only method available to reverse flow test these valves would be to remove the drywell air cooler from service for an extended period of time such that each cooling loop could be pressurized using a suitable water source. This is considered unreasonable consequences to the drywell if required during every refueling, since these cooling loops are normally inservice throughout refueling activities for purposes of plant and personnel safety.

Alternate Testing: Due to system design configuration, the check valve will be reverse flow tested once every ten years to coincide with the 10 year ISI Hydrostatic Test which is performed at the end of each ten year inspection interval.

III- 19-7 k

• x RELIEF REQUEST RR-3 System: Reactor Building Closed Loop Cooling Component: 70-93 Category: C Class: 2 Function: Isolation check valve for cooling water supply line to drywell air coolers and recirculation pump coolers.

ASME Section II Quarterly Requirements: Reverse flow operability Basis for Relief: The only method available to reverse flow test these valves would be to remove the recirc. pump coolers from service for an extended period of time such that each cooling loop could be pressurized using a suitable water source. This is considered unreasonable consequences to the drywell if required during every refueling, since these cooling loops are normally inservice throughout refueing activities for purposos of plant and personnel safety.

Alternate Testing: None. Due to system design configuration.

1 I

1 III '19-8 k

_ . . . . . _ ~ .

l 4

PUNP AND VALVE INSERVICE TESTING PROGRAN PLAN FOR NINE MILE POINT 1

NUCLEAR POWER STATION i

i UNIT 1 SECTION III 5.21 ATTACHMENT 20 VALVE TEST TABLES AND RELIEF REQUESTS FOR 1 CONDENSATE TRANSFER 1

DWG, NO. C-18003-C

C-18007-C C-18008-C

! C-18048-C i

}

Pages III-20-1 through III-20-2 I

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III- 20-1 ,

l

.- ,-,.,--,--.-,.,.--...---,-,,----.--<-------,--------.-,..-----,--n- -

l l

SYSTEM CONDENSATE TRANSFER NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18048-C l l l l l l l l l C.S l C.S I l l CIASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l l VALVE NUMBER l AND l (CAT.) l (IN.) _ l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF l TEST l l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l l 57-13 3 C 4 SEA DE FE-Q F Cond. Transfer H-8 CHV R Syst. Pump #12 Cischarge 57-14 3 C 4 SEA DE FE-Q F Cond. Transfer I-8 CHV R Syst. Pump #11 Discharge ,

57-57 3 C 3X4 SEA C RT-P Cond. Transfer I-5 REV Syst. Safety Valve Pump at Cond. Surge

& Sterage Tanks.

III 20-2

=;>

• PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT i NUCLEAR POWER STATION UNIT 1 SECTION III 5.22 ATTACHMENT 21 VALVE TEST TABLES AND RELIEF REQUESTS FOR TORUS VACUUM RELIEF DWG. NO. C-18006-C SH.2 Pages III-21-1 through III-21-3 l

l r

III 21-1 jj

SYSTEM TORUS VACUUM RELIEF NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18006-C SH.2 l l l l l l l l l C.S l C.S l -l l CIASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF -l TEST l l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l l 68-01 2 BC 30 SEA C FE-Q F Terus Vacuum F-4 CHV APA PI-R Reliof Check 68-02 2 BC 30 SEA C FE-Q F Tirus Vacuum H-4 CHV APA PI-R R211gf Check 68-03 2 BC 30 SEA C FE-Q F c Terus Vacuum H-4 CHV APA PI-R Ralisf Check 68-04 2 BC 30 SEA C FE-Q F T:rua Vacuum H-4 CHV APA PI-R Reliaf Check 68-05 2 AC 30 SEA C FE-Q F Tarus Vacuum J-3 CHV APA LJ-R R Ucli f I.V. PI-R 68-06 2 AC 30 SEA C FE-Q F Terus Vacuum J-3 CHV APA LJ-R R Relicf I.V. PI-R III- 21-2 3 - - - -

_ __q

SYSTEM TORUS VACUUM RELIEF NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18006-C SH.2 i i 1 l 1 l l l l C.S l C.S l l l CLASS l VALVE l SIZE I ACTU. l NORM. l TEST l STROKE l CHECK l JUST. I OR l l VALVE NUMBER ! AND l (CAT.) l (IN.) l TYPE I POSIT. l REQ. I DIRECT. l VALVE l OR l ALT. l REMARKS l l DWG. I I AND l l l l l TEST l RELIEF l TEST l l l C00R.] l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l l 68-07 2 AC 30 SEA C FE-Q F Terus Vacuum J-3 CHV APA U-R R l Relief I.V. PI-R 68-08 2 A 30 APA C FE-Q T:rus Vacuum I-3 BFV ST-Q 0,C i

R211 f I.V. FS-Q 0 i U-R PI-R ,

68-09 2 A 30 APA C FE-Q Terus Vacuve I-3 BFV ST-Q 0,C Relief I.V. FS-Q O l U-R l PI-R l

l 68-10 2 A 30 APA C FE-Q Tsrus Vacuum I-3 BFV ST-Q 0,C i Relisf I.V. FS-Q 0 U-R PI-R i

{

III- 21 't m_______-..___. _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

t 1

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PUNP AND VALVE INSERVICE TESTING PROGRAN PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.23 ATTACHMENT 22 VALVE TEST TABLES AND RELIEF REQUESTS FOR ENERGENCY SERVICE WATER DWG. NO. C-18022-C SN.3 C-18027-C SN..'

Petes III-22-1 throuth III-22-6 a

III- 22-1 h

t SYSTEM EMERC D CT SERVICE WATER NINE MILE POINT UNIT 1 VALVE TEST TABIE Duc. NO. C-Is022-c Sn.3 l i I I I l l 1 i C.S I C.S I I l CUSS I vnVE I SIZE I ACTU. 1 NORM. l TEST I STRORE I CHECK l JUST. I OR l l VALVE NUMBER I AND I (CAT.) I (IN.) i TTPE l POSIT. I REQ. I DIRECT. I VALVE l OR I ALT. l R MARRS l I Duc. I I AND l l l 1 1 TEST I RELIEF l TEST l l 1 000R.I I TTPE l l 1 I I DIRECT.I REQ. NO.I PERF.l l 72-11 3 C 14 DE FE-R F RR-1 Emer(). S.W. Pump B-3 CNV SEA R

1. 12 Disch. Check 72-12 3 C 14 DE FE-R F RR-1 EmerR. S.W. Pump D-3 CEV SEA R

1. 11 Disch. Check 72-21 3 C 20 MAA DE FE-Q R CS-1 .

Servo Utr. Supply 3-1 CHV SEA Check 72-22 3 C 20 MAA DE FE-Q R CS-1 Servo Utr. Supply B-2 CHY SEA Check l

l l

III- 22-2 m 8

i SYSTDI EMERCDICT SERVICE WATEE MINE MILE POINT UNIT I VnVE TEST TABLE BMC. NO. C-18027-C 58.2 I I I I I I I I l C.S I C.S I I I CIASS I vnvE I SIZE I ACTU. I NORM. I TEST l STROKE I CHECK I JUST. 1 OE l l vnvE NoMnEm i ann I (CAT.) 1 (1x.) I TTPE I POSIT. I EEn. I DIu CT. I vatvr i Om i ALT. I RIMARKS l 1 nWc. I I ann I I I I I TEST I utIEr l TEST I i l COOR.! l TYPE I I I I I DIRECT.I req. NO.I PERF.l I SU-121 2 A 1 MAA C PV SEE NOTE 1 Servo Utr. to E-6 CTV IJ-R Dry ext I.T.

Detside SU-122 2 B 1 MAA C PV SEE NOTE 1 Servo Utr. to D-6 GTV IJ-R Drywell I.T.

Inside c III- 22-3 a -_- _ _ _ _ _ _ . - _ _

- - - . - - (

l l

NOTES FOR ATTACHIIENT 22 SYSTE31: INERGENCY SERVICE WATER Es. EIE 1 The valve shall be locked close by cheln &

lock and/or other approved method.

t i

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!!!- 22-4 l I

. _ - _ _ _ _ . ll

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

i RELIEF REQUEST RR-1

( Systemt knergency Service Water i

Component 72-11:72-12  !

Category: C Class: 3 Function: Emergency Service Water pump Discharge check Valves.

ASME Sectica XI Quarterly Requirements: IWA-352, verify forward flow & reverse flow closure.

Basis For Rolleft To verify forward flow and reverse flow closure would require the interruption of normal plant operatlon and placing the emergency service water system in service.

V Alternate Testing: To disassemble the check values, inspect and verify integrity during refueling outage, l

i h

111- 22-5

__-____________--_--______-_____-___-___----_------------S

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

3 __.- __

l.

i AELIEF REQUEST i

j, CS-1

).

! Systems Service Water Systes

.l Component 72-21:72-22

• l Category: C i

Class: 3 i

1 Function Isolate emers. serv. water header from normal service water ,

supply headers.

! ASME Section XI i Quarterly i daquirements: IWA-3522, verify reverse flow closure.

I assis For deliefs to verify reverse flow closure for each valve requires the i isolation the appropriate pung and its discharge header j wnile tne two pumps are in service. Sotn pumps need to be

! operating when ever the lake temperature is 60*F or above.

i 1 Alternate festing: Valves exercised for reverse flow operability at cold j shutdown when the heat load is low and handled by one j service water pump.

I s 4

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111-22-6 i

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t PUNP AND VALVE INSERVICE TESTING PROGRAN PLAN FOR NINE MILE POINT NUCLEAR POWER STATION l

l' NIT 1 SECTION III 5.24 ATTACHNENT 23 VALVE TEST TABLES AND RELIEF REQUESTS FOR ENERGENCY DIESEL GENERATOR COOLING WATER DWG. NO. C-18026-C SN.1 C-18026-C SN.2 PaBes III-23-1 throuRh III-23-4 1

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l l III- 23-1 l

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SYSTEM EM. DIESEL CEN. COOLING WTR. NINE MILE POINT UNIT 1' VALVE TEST TABLE DWG. NO. C-18026-C SH.1 1 I I I I l l l l C.S I C.S I I l CIASS I VALVE l SIZE I ACTU. I NORM. l TEST l STROKE l CHECK 'JUST. OR VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE I POSIT. I REQ. I DIRECT. l VALVE OR ALT. REMARKS '

l DWC. l l AND I l l TEST RELIEF TEST l COOR.l -l TYPE I I I DIRECT. REQ. NO. PERF.

72-67 3 C 4 SEA DE FE-Q F NOTE 1

1. 102 Diesel F-6 CHV FE-R R Cooling Water Imop Discharge Check 72-69 3 C 4 SEA DE FE-Q F NOTE 2 Es. DCCW Pump C-8 CHV 9

1. 102 Disch. Check I

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l 6

111-23-2 E_-__._________________________ _ _ _ _ _ _ _ _ _ _ _ _

_ 1$

'J SYSTEM EN. DIESEL GEN. COOLING WTR. NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18026-C SH.2 l l l l l l l l l C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. I REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF- l TEST l l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l 1 G

72-66 3 C 4 SEA DE FE-Q F NOTE 1

1. 103 Diesel F-6 CHV FE-R R Cccling Water Loop Diccharge Check 72-68 R 3 C 4 SEA DE FE-Q F NOTE 2 Fa. DGCW Pump C-8 CHV

1. 103 Disch. Check III- 23-3 P __ ___!

y NOTES FOR ATTACHMENT 23 NO. NOTE 1 As a result of I.E. Bulletin 83-03, Niagara Mohawk has committed to performing a reverse flow test of these check valves during refueling outages.

(See Note 2 below).

2 As a result of I.E. Bulletin 83-03, Niagara Mohawk has committed to disassembling and inspecting these valves during refueling outages. (See Note 1 above).

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111-323-4 l

PUMP AND VALVE INSERVICE TESTING PROGRAN PLAN FOR 1

NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.25 ATTACHNENT 24

, VALVE TEST TABLES AND RELIEF REQUESTS FOR WASTE DISPOSAL DWG. NO. C-18045-C SH.7 C-18045-C SH.9 Pages III-24-1 through III-24-3 l

l l

1 l

1 III-24-1 l 2

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SYSTEM WASTE DISPOSAL NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18045-C SH.7 l l l l l l l l l C.S l C.S l l l CLASS l VALVE l SIZE l ACTU. l NORM. l TEST l STROKE l CHECK l JUST. l OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. l REMARKS l l DWG. l l AND l l l l l TEST l RELIEF l TEST l l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l l 83.1-09 2 A 3 MOA 0 FE-Q Drywall Equip. D-1 GTV ST-Q C Drain I.V. LJ-R PI-R 83.1-10 2 A 3 ADA* O FE-Q Drywall Equip. H ,2 GLV ST-Q C Drain I.V. FS-Q C LJ-R PI-R i

i III- 24-2

=D - _ - - - - - _ _ _ - - - - _ _ _ _ _ _ _ _ . _ _ - - _ _ _ _ _ _ _ __ _

SYSTEM WASTE DISPOSAL NINE MILE POINT UNIT 1- VALVE TEST TABLE DWG. NO. C-18045-C SH.9 I l 1 l l 1 l l l C.S I C.S I I l CLASS l VALVE I SIZE l ACTU. I NORM. l TEST l STROKE l CHECK l JUST. I OR l l VALVE NUMBER l AND l (CAT.) l (IN.) l TYPE l POSIT. l REQ. l DIRECT. l VALVE l OR l ALT. I REMARKS l l DWC. l l AND l l l l 1 TEST l RELIEF l TEST l l l C00R.l l TYPE l l l l l DIRECT.l REQ. NO.l PERF.l l 83.1-11 2 A 4 MOA 0 FE-Q Drywell Floor H-1 GTV ST-Q C Drain I.V. LJ-R PI-R 83.1-12 2 A 4 ADA 0 FE-Q Drywell Floor G-1 GLV ST-Q C Drain I.V. FS-Q C IJ-R PI-R III- 24-3

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l 1

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN l l

FOR  ;

NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.26 ATTACHMENT 25 i

VALVE TEST TABLES AND RELIEF REQUESTS FOR BREATHING AIR TO DRYWELL DWG. NO. C-18578-C Pages a

III-25-1 through III-25-2 i

l I

III- 25-1

SYSTEM BREATHING AIR TO DRYWELL NINE MILE POINT UNIT 1 VALVE TEST 7ABLE DWG. NO. C-18578-C

-=. -

C.S C.S VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR CLASS AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS VALVE NUMBER AND TEST RELIEF TEST DWG.

TYPE DIRECT. REQ. NO. PERF.

COOR.

114-BA-lO2 2 B 4 MAA LC PV Crosthing Air GLV LJ-R Supply to Drywell E1.237 ll4-BA-103 2 B 4 MAA LC PV CrOcthing Air GLV LJ-R Supply to Drywell El.237 .

4 III-25-2 m __ -____ - - . _ _ _ _ _ _ _ - _ _ - _ _ _ ____ -__________