ML17055E477

Second 10-Yr Interval Inservice Testing Program.

ML17055E477
Person / Time
Site:	Nine Mile Point
Issue date:	01/16/1989
From:	NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17055E478	List: ML17055E477 ML18038A434
References
PROC-890116, NUDOCS 8901310374
Download: ML17055E477 (470)

Text

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT 1 ATTACHMENT A SECOND TEN YEAR INTERVAL INSERVICE TESTING PROGRAM 6515G 890i310374 890ii8 PDR ADOCK 05000220 P PDC

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 1 SECOND TEN YEAR INTERVAL PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN INITIALS AND DATE APPROVALS SIGNATURES REVISION 1 REVISION 2 REVISION 3 Station Superintendent, NMPNS Unit 1 I.frs K. A. Dahlberg LC~

Manager, Nuclear Engineering, G. J. Gresock Manager, Nuclear Technology D. Greene (Acting) ~Qlg I Ie Summary of Pa es

.Revision 1 (Effective

~Pa es Date i, III-30-5 January 1989 THIS PROGRAM PLAN IS A GENERAL REWRITE NIAGARA MOHAWK POWER CORPORATION

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN TABLE OF CONTENTS SECTION TITLE PAGE I.O OVERVIEW I-l I. 1.0 Introduction I-2 I.2.0 Basis I-3 I.3.0 General Program Plan Concept I-4 I.4.0 Organization I-5 I.5.0 ti Def ini ons I-6 I.6.0 General Relief Request for Pumps I-7 I.7.0 General Relief Request for Valves I-12 I.8.0 References I-19 II.O PUiMP IST PROGRAM PLAN II-1 II.1.0 Introduction II-2 II.2.0 Code Interpretation II-3 II.3.0 Pump List Ij-4 II.4.0 Pump Table Nomenclature II-5 II.5.0 Pump Test Table II-1-1 II.6.0 Pump Test Table Notes II-1-5 II.7.0 Pump Relief Requests II-1-6 III.O 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 Tables and Relief Requests III-I I I I.5. 1 Attachment 1: Main Steam System III-1-1 I I I.5. 2 Attachment 2: Reactor Recirculation III-2-1 III.5.3 Attachment 3: Control Rod Drive III-3-1 III.5.4 Attachment 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 III.5.7 Attachment 7: Reactor Shutdown Cooling III-7-1 III.5.8 Attachment 8: Containment Spray III-,8-1 III.5.9 Attachment 9: Reactor Cleanup III-9-4 I I I.5.10 Attachment 10: Inert Gas Purge and Fill III-10-1 I I I.5.11 Attachment 11: Hydrogen-Oxygen Monitoring III-11-1 III.5.12 Attachment 12: TIP III-12-1 I I I.5.13 Attachment 13: Nitrogen Supply 811 III-13-1 III.5.14 Attachment 14: Nitrogen Supply 812 I I I-14-1 I I I.5.15 Attachment 15: Reactor Building HVAC III-15-1 III.5.16 Attachment 16: Liquid Poison III-16-1 III.5.17 Attachment 17: Spent Fuel Storage Pool Filtering 5 Cooling III-17-1

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN TABLE OF CONTENTS (Cont'd)

SECTION TITLE PAGE I I I.5.18 Attachment 18: Sample III-18-1 III.5.19 Attachment 19: Reactor Building Closed Loop Cooling III-19-1 I I I.5. 20 Attachment 20: Condensate Transfer III-20-1 III.5.21 Attachment 21: Torus Vacuum Relief III-21-1 III.5.22 Attachment 22: Emergency Service Water III-22-1 III.5.23 Attachment 23: Emergency Diesel Generator Cooling Water III-23-1 I I I.5. 24 Attachment 24: Emergency Diesel Generator Air Start III-24-1 III.5.25 Attachment 25: Emergency Diesel Generator Fuel Oil Transfer III-25-1 III.5.26 Attachment 26: Waste Di sposal III-26-1 III.5.27 Attachment 27: Breathing Air To Drywell III-27-1 III.5.28 Attachment 28: Control Room Chilled Water, III-28-1 III.5.29 Attachment 29: Control Room HVAC III-29-1 III.5.30 Attachment 30: Instrument Air III-30-1

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION I OVERVIEW Pages I-l through I-20 I-1 January 1989

1.0 Introduction This document presents the 2nd Ten Year Program Plan for Inservice Testing

( IST) of Pumps and Valves at the Nine Mile Point Nuclear Station Unit 1 (NMPS-1) in compliance with the requirements of 10CFR50.55a(g) and Station 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 1983 Addenda.

Although the 1st ten year inspection interval was not scheduled to end until December 1989, Niagara Mohawk voluntarily revised the program. The revi sed Inservice Testing Program ten year interval now runs concurrently with the revised Inservice Inspection ten year interval; to June 1996 (Reference C. V.

Mangan, NMPC, letter to D. B. Vassello, NRC, dated September 13, 1983).

I-2 January 1989

2.0 Basis In addition to the reference Code edition and addenda, the Program Plan has been prepared in compliance with the NRC guidance (except where 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)", the November 1981 Draft Regulatory Guide "Identification of Valves for Inclusion in Inservice Testing Programs" and the August 1988 Draft Generic Letter "Inservice Testing for Pumps and Valves." These four documents provide the basis for selection of components, test requirements, relief .

requests, and format.

Regarding the inclusion of certain valves based on their Containment/Reactor Coolant Isolation functions; this program is inclusive of valves which are categorized as Isolation Valves as specified in the latest NMPC NMPl Appendix J Program.

Current NMP1 practice is to perform Leakage Rate Testing in accordance with the NMPl Appendix J Program. Any changes to the Appendix J Program shall be incorporated into the IST Program Plan as applicable.

The information except individual valve maximum stroke times, requested by the reference documents has been included in this Program Plan. Maximum stroke times are determined for the appropriate valves and recorded in a separate NMP-1 document as they are established.

I-3 January 1989

~ 'Y Np

3.0 General Program Plan Concept The Program Plan specifiesSection XI testing requirements for pumps and valves providing a safety-related function. The document which delineates safety-related components is titled Nine Mile Point Unit "g-List". By 1 definition, a safety-related function is one that is required to assure:

a) Integrity of the reactor coolant pressure boundary; b) Capability to achieve and maintain safe shutdown; c) Capability to prevent or mitigate the consequences of postulated the accidents which could result in off-site exposures comparable to guidelines of '10CFR Part 100.

The selection criteria used for components included in this Program Plan are safety-related active components as delineated in the "Nine Mile Point Unit 1 g-List." Safety-related passive components have no operability test requirements and are not included in the Program Plan. Only those safety-related passive components which have leakage requirements shall be included in the Program Plan.

Station Technical Specifications, special manufacturer's tests, system operating conditions, etc., may dictate additional components which should be included in the overall station testing program, but whose functions fall outside the criteria above, and are, therefore, not addressed by this Program Plan.

Section XI requires quarterly testing of components unless it is a burden to do so. This program specifies quarterly testing of pumps and valves unless it has been determined that such testing would:

a) Render a safety-related system inoperable; b) Cause a reactor scram or turbine trip; c) Require significant deviations from normal operations; d) Require entry into inaccessible station areas; e) 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 station operation, the Code allows part-stroke exercising during normal station operation, and full-stroke exercising at cold shutdown.

Since the Code allows testing at cold shutdown, this program does not request 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 station operation, or at cold shutdown, a specific relief request has been prepared.

Each specific relief request provides justification 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 a burden for this station 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.

I<<4 Januar y 19S9

4.0 Organi zation The Pump and Valve Inservice Testing Program Plan is organized into three sections.Section I presents the general program commitment basis, the conceptual framework used in developing the Program Plan, and general relief requests for Code requirements found to be a burdeh for this station.Section II deals specifically with the Pump Test Program, and Section III deals specifically with the Valve Test Program.

Section II and III are formatted in a manner to aid review. Each section summarizes the bases and concepts used to formulate the Pump and Valve Test Tables. Pump testing requirements are summarized in a single Pump Test Table attached to Section II. Valve test requirements are summarized in Valve Test Tables attached to Section III. The Valve Test Tables are arranged into separate attachments for each system. Where quarterly testing has been found to be impractical, either a justification for delay of test to cold shutdown, or a relief request, is provided following the appropriate Pump or Valve Test 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.

I-5 January 1989

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

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

Cold Shutdown: Testing deferred until cold shutdown shall commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown, and shall continue until 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 shall 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 shall 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 ( IWV-3511),

Category 0 explosive actuated valves (IWV-3610) and Category 0 rupture disks ( IWV-3620) are periodically tested as defined in the appropriate Code Sub-Sections.

Pressure Isolation: Any valve which acts as an isolation boundary 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 Leakage Rate Test program.

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.

I-6 January 1989

6.0 General Relief Requests for Pumps This section requests relief from specific requirements of Section XI found to be a burden for Nine Mile Point Unit 1. Since they are general in nature, and pertain to a number of components, this section requests general relief as presented below. The relief requests do not appear in the Pump Test Table except for bearing temperature and for vibration relief requests.

General Relief Request: PG-1 Pumps: Al 1 Test Requirements: Table IWP-3100-2, Acceptance Criteria Basi s For Rel i ef: Standard Industry practice is to use vibration velocity as a basis for the establishment of vibration reference values for pumps operating at normal speeds. Vibration velocity is used because it is independent of frequency in this RPM range. Thus yielding a simple reliable measure of the severity of the vibration.

Alternate Testing: In lieu of the code specified criteria, Nine Mile 1 will use the following Table:

RANGES OF TEST PARAMETERS PUMP PUMP TEST ACCEPTANCE ALERT REQUIRED TYPE SPEED PARAMETER RANGE RANGE ACTION RANGE Centri fugal <600 rpm Vd <2.5 Vr >2.5vr to 6Vr >6Vr and Vertical or Vv but not but not Line Shaft >10.5 mi1s >22 mils

>600 rpm Vv <2.5 Vr >2.5vr to 6Vr >6V or Vd but not but not

>0.325 in/sec >0.70 in/sec Reciprocating Vd <2.5 Vr > 2.5Vr to 6Vr > 6Vr or Vv NOTE: 1) Vr is vibration reference value in the selected units.

2) Vv is vibration value in velocity.

3) Vd is vibration value in displacement.

I-7 January 1989

6.0 General Relief Requests for Pumps General Relief Request: PG-2 Pumps: Emergency Service Water, Reactor Building Closed Loop Cooling Water, Core Spray, Emergency DG Cooling Water, Containment Spray, Containment Spray Raw Water, Condensate Transfer and Emergency Diesel F.O. Transfer Test Requirements: Measure pump suction pressure, Table IWP-3100-1 Basis for Relief: Instrumentation is not installed for measuring pump suction pressure. However, the suction pressure can be calculated by measuring the level of the applicable supply, (eg., torus water level, condensate storage tank level, diesel F.O.

storage tank level or lake level) and the elevation of the pump suction and taking the difference. The difference is the suet>on pressure in feet of head, which is then converted to pressure in pounds per square inch.

Alternate Testing: Calculate suction pressure from the level of the suction supply.

I-8 January 1989

6.0 General Relief Requests for Pumps General Relief Request: PG-3 Pumps: Emergency Service Water, Reactor Building Closed Loop Cooling Water, Core Spray, Emergency Oiesel Generator Cooling Water, Spent Fuel Pool Cooling, Containment Spray Raw Water, Containment Spray, Condensate Transfer, and Emergency Oiesel Generator Fuel Oil Transfer Test Requirements: Neasure pump inlet pressure before pump startup and during the test, Table IWP-3100-1 Basis for Relief: These pumps use lake water or applicable tank contents as a fluid medium, and the change in supply level is negligible throughout the duration of testing.

Alternate Testing: Inlet pressure shall only be measured or calculated once.

I-9 January 1989

6.0 General Relief Requests for Pumps General Relief Request: PG-4 Pumps: All Test Requirements: Measure pump bearing temperature yearly, Table IWP-3100-1 Basis for Relief: The measuring of bearing temperatures, along with vibration monitoring are both means of determining the mechanical condition of a pump.

However, the condition of a pump bearing would have to seriously degrade to cause a detectable rise of temperature on the bearing housing. With the improved vibration monitoring program employed at NMPl, the ability to detect very small changes in the mechanical condition of a pump exists. Therefore, any degradation of a bearing would be detected before an increase of temperature on the bearing housing occurred.

Alternate Testing: Pump mechanical condition will be determined by the enhanced vibration monitoring program.

Bearing temperatures will not be measured.

I-10 January 1989

6.0 General Relief Requests for Pumps General Relief Request: PG-5 Pumps: All Test Requirements: Table IWP-4110-1, Acceptable instrument accuracy requires a pressure instrument accuracy of + 2X of full scale Basis for Relief: NNPl uses pressure sensing instrumentation which meets the acceptable instrumentation accuracies defined in Table IWP-4110-1. The total loop accuracy from the sensing device to the final readout device will not meet the instrumentation accuracies of Table IWP-4110-1. A threshold loop accuracy value of + 3X shall be established which does not significantly exceed Section XI limits and should be sufficiently repeatable from test to test to allow for evaluation of the pump hydraulic condition and for the detection of pump degra- dation. For instruments that exceed this threshold loop accuracy value, temporary test instrumentation will be used. An engineering evaluation shall be made to add permanent pressure instrumentation for the individual pumps.

Al ternate Testing: Permanent and temporary pump pressure instrumen-tation shall be used until a permanent modifica-tion (1991) is performed.

I-11 January 1989

7.0 General Relief Requests for Valves This section requests relief from specific requirements of Section XI found to be a burden for Nine bile Point Unit 1. Since they are general in nature, and pertain to a number of components, this section requests general relief as presented below. These relief requests do not appear in the applicable system valve test tables.

General Relief Request: VG-1 Valves: Rapid actuating power operated valves with stroke times of 4 seconds or less Category: A, 8 Test Requirements: IWV-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. IWY-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 immediately or fail 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: Historical valve stroke time results for rapid acting valves has been collected and analyzed. Based on the results of this analysis, two separate acceptance criteria will be established. Rapid acting solenoid valves will be those that operate in 2 seconds or less. Rapid acting piston and diaphragm valves will be those that operate in 4 seconds or less. If stroke times fall within these limits, the results will be acceptable. If stroke times exceed these limits, the valves will be considered inoperable and corrective action initiated in accordance with IWV-3417(b).

I-12 January 1989

7.0 General Relief Request for Valves General Relief Request: VG-2 Valves: Containment Isolation Valves Category: A, AC Test Requirements: Leak rate test in accordance with Subsection IWV-3421 through 3425 and IWV-3427(b).

Basis for Relief: Containment isolation valves are required to be leakage rate tested in accordance with 10CFR50, Appendix J. The leakage rate requirement is based on a total allowable leakage rate for all valves instead of an individual valve leakage rate. IWV-2200(a) defines Category A as "valves for which seat leakage is limited to a specified maximum amount in the closed position of fulfillment of their function." Although, leakage r ates for containment isolation valves are not limited on an individual basis, they have been determined to be Category A valves.

Since containment isolation valves are Category A, the leakage rate testing requirements of IWV-3420 must be satisfied.

The leakage rate testing performed per Appendix J satisfies the intent of IWV-3421 through 3425, however, it does not satisfy the individual valve leakage r ate analysis and corrective actions of IWV-3426 and 3427. In order to prevent duplicate leakage testing of these valves, individual leakage rate will be obtained during Appendix J testing and the requirements of IWV-3426 and 3427(a) wi 11 be applied via separate procedure. The usefulness of IWV-3427(b) does not justify the burden of complying with this requirement.

Alternate Testing: Containment isolation valves will be leak rate tested in accordance with the 10CFR50 Appendix J testing program. In addition, individual valve leakage rates will be obtained by test or analysis and the requirements of IWV-3426 and 3427(a) will be applied via a separate procedure for those valves that are Appendix J Type C tested.

I-13 January 1989

7.0 General Relief Request for Valves General Relief Request: VG-3 Valves: Excess Flow Check Valves; (Identified by instrument line below)

Recirculation 'A'ifferential Pressure 18020 18020 X-29R X-29L Recircu1 ati on Pump Pump 'A'ifferenti al Pressure 18020 X-30R Recirculation Pump 'B'ifferential Pressure 18020 X-30L Recirculation Pump 'B'ifferential Pressure 18020 X-31R Recirculation Pump 'C'ifferential Pressure 18020 X-31L Recirculation Pump 'C'ifferential Pressure 18020 X-32R Recirculation Pump 'O'ifferential Pressure 18020 X-32L Recirculation Pump 'O'ifferential Pressure 18020 X-28R Recirculation Pump 'E'ifferential Pressure 18020 X-28L Recirculation Pump 'E'ifferential Pressure 18020 X-43R Recirculation Pump 'A'low 18020 X-43L Recirculation Pump 'A'low 18020 X-37R Recirculation Pump 'B'low 18020 X-37L Recirculation Pump 'B'low 18020 X-36R Recirculation Pump 'C'low 18020 X-36L Recirculation Pump 'C'low 18020 X-35R Recirculation Pump 'O'low 18020 X-35L Recirculation Pump 'O'low 18020 X-34R Recirculation Pump 'E'low 18020 X-34L Recirculation Pump 'E'low 18020 X-41R Recirculation Pump 'A'eal Water Pressure 18020 X-41L Recirculation Pump 'A'eal Water Pressure 18020 X-44R Recirculation Pump 'B'eal Water Pressure 18020 X-44L Recirculation Pump 'B'eal Water Pressure 18020 X-42R Recirculation Pump 'C'eal Water Pressure 18020 X-42L Recirculation Pump 'C'eal Water Pressure 18020 X-38R Recirculation Pump 'O'eal Water Pressure 18020 X-38L Recirculation Pump 'D'eal Water Pressure 18020 X-47R Recirculation Pump 'E'eal Water Pressure 18020 X-47L Recirculation Pump 'E'eal Water Pressure 18015 X-82R Total Recirculation Flow 18015 X-82L Total Recirculation Flow 18015 X-71A Reactor Vessel Water Level 18015 X-71B Reactor Vessel Water Level 18015 X-71D Reactor Vessel Instrumentation 18015 X-71E Reactor Vessel Instrumentation 18015 X-71F Reactor Vessel Instrumentation 18015 X-720 Reactor Vessel Instrumentation 18015 X-72E Reactor Vessel Instrumentation 18015 X-133 Reactor Vessel Instrumentation 18015 X-72F Reactor Vessel Level 18015 X-53 Reactor Vessel Level 18015 X-72A Reactor Vessel Level 18015 X-72B Reactor Vessel Level I-14 Janu ar y 1989

I 0

General Relief Request (Cont'd)

General Relief Request: VG-3 (Cont'd)

Valves: Excess Flow Check Valves; (Cont'd)

PE ID Penetration Oescription 18002 X-75R Mainstream Loop ll Flow 18002 . X-75L Mainstream Loop ll Flow 18002 X-81R Mainstream Loop 12 Flow 18002 X-81L Mainstream Loop 12 Flow 18017 X-51 Emergency Condenser Loop 11 Steam Flow 18017 X-71C Emergency Condenser Loop ll Steam Flow 18017 X-54 Emergency Condenser Loop 12 Steam Flow 18017 X-72C Emergency Condenser Loop 12 Steam Flow 18007 XS-348 Torus Water Level Category: AC Test Requirements: Required testing procedure (IWV-3522), and quarterly oper ability testing (IWV-3521).

Basis for Relief: Excess flow check valves differ in design from conventional swing check valves in that there is no valve 'disk'ut rather a ball which functions to block flow upon initiation. Consequently, code test requirements are impractical. The valves are used for containment isolation purposes in the event of an instrument line break outside containment.

These valves are located on instrument lines which function to provide signals relating reactor vessel conditions to station operations personnel as well as automatic trip systems for normal and emergency operation of the station. These instruments are typically required to operate during cold shutdown conditions as well as during normal operation. Testing the excess flow check valves requires valving the corresponding instrumentation out of service. This could cause spurious instrument signal fluctuations to occur resulting in the inadvertent automatic initiation or trip of certain systems. Testing the excess flow check valves during normal operation or cold shutdown conditions imposes undue risk to plant operations and personnel since the test medium is high pressure (normally greater than 800 psig), high temperature (approximately 200-300'F) and highly contaminated reactor coolant. Testing during scheduled refueling outages provides adequate assurance of proper operation and satisfies the intent of Appendix J requirements associated with containment iso1ation.

I-15 January-1989

General Relief Request (Cont'd)

General Relief Request: VG-3 (Cont'd)

Valves: Excess Flow Check Valves; (Cont'd)

Alternate Testing: At NMP1, excess flow check valves are tested during scheduled refueling outages with the reactor pressure at least 200 psig. The test method consists of simulating a line break downstream from the check valves by opening a manual drain valve which initiates flow due to reactor pressure. Verification of proper valve closure is by an audible indication (when check valve closes, a noticeable noise is generated by the hydraulic surge within the piping) as well as temperature sensing in the drain piping (if the valve fails to close, a rapid increase in drain pipe temperature is detectable due to high temperature reactor water flowing through it). Visual observation of any flow from the drain piping is not possible since the drain line is hard piped directly to the equipment drain tank.

I-16 January 1989

7.0 General Relief Request For Valves General Relief Request: VG-4 Valves: Valves equipped to fai 1 open or closed Category: A,B Test Requirements: Observe the operation of the valves upon loss of actuator power, IWV-3415.

Basis For Relief: Certain valves are equipped with remote position indication which provides a positive means of verifying valve position.

Alternate Testing: Valves equipped with remote position indicators shall have their fail safe actuation verified using control room indicating lights.

I-17 January 1989

7.0 General Relief Request For Valves General Relief Request: VG-5 Valves: All Control Valves Category: A, B Test Requirements: IWV-3412 and IWY-3413, Exercising and Stroke Time Requirements.

Basis For Relief: Exercising these valves at any periodic frequency is impractical. They respond to signals generated by flow, pressure, level, or temperature. Valve degradation will be indicated by the inability to perform a system control function. The operability of these valves is demonstrated continuously by virtue of it performing its control function. The control valves are included in the inservice test program because of their fail safe feature only.

Alternate Testing: Operability of these control valves will be assessed during normal system operation and during individual valve calibration tests.

I-18 January 1989

8.0 References 0 ASME Boiler and Pressure Vessel Code,Section XI, Rules For Inservice Inspection of Nuclear Power Plant Components, 1983 Edition, Summer 1983 Addenda.

8.2 Nine Mile Point Unit 1,Section XI Pump and Valve Inservice Testing Program Plan, 1st Interval.

8.3 Technical Specifications, Niagara Mohawk Power Corporation, Nine Mile Point Nuclear Station Unit 1, Section 3.2.6, 3.2.7, 3.3.4, Table 3.2.7, 3.2.7.1, 3.3.4.

8.4 Final Safety Analysis Report (Updated), Nine Mile Point Nuclear Station Unit l.

8.5 10CFR50.55a(g), Inservice Inspection Requirements, Guidance For Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests.

8.6 Nine Mile Point Station Unit 1 "Q-List".

8.7 Nine Mile Point Station Unit 1 "Q-Boundary Drawings".

IE Bulletin No. 83-03, Check Valve Failure in Raw Water Cooling Systems of Diesel Generators.

IE Bulletin No. 88-70, Check Valve Inservice Testing Program Deficiencies.

8. 10 Nl-ISP-R-201-550, Local Leak Rate Test-Summary (Type B and C Tests).

8. 11 Nl-ST-M4, Emergency Diesel Generators Manual Start and 1 Hour Rated Load Test.

8.12 NMPl Letter, Log No. 6777, dated June 14, 1983, from T. E. Lempges to R. C. OeYoung, "IE Bulletin No. 83-03 Response."

8.13 NMPl Letter, Log No. 7947, dated December 10, 1984, from T. E. Lempges to R. C. OeYoung, "IE Bulletin No. 83-03 Response, Rev. l."

8. 14 NRC Letter, TAC 65888, dated March 29, 1988, from R. A. Capra to C. V.

Mangan, "Relief Request Transmitted by Letter Dated July 8, 1987 for Nine Mile Point Unit 1."

8.15 NRC Letter, TAC 54152, dated May 6, 1988, from R. A. Capra to C. V.

Mangan, "Proposed Technical Specifications and Exemption Requests Related to Appendix J."

8.16 NRC Letter, TAC 68462, dated October 17, 1988, from R. A. Capra to C.

V. Mangan, "Schedular Exemption from the Requirements of Appendix J to 10CFR50 for the Emergency Condenser Condensate Return Line Valves."

8.17 NRC Letter, TAC 54152, dated November 9, 1988, from M. F. Haughey to C.

V. Mangan, "Review of the July 28, 1988 Letter on Appendix J Containment Leakage Rates Testing at Nine Mile Point Unit l."

I-19 January 1989

8.18 SER 26-88, INPO: Failure of Safety Valve due to Bonding of the Valve Disc and Seat.

8.19 USNRC Oraft Inservice Testing Generic Letter.

8.20 IE Notice No. 85-84, Inadequate Inservice Testing of Main Steam Isolation Valves.

I-20 January 1989

PUMP AND VALVE 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 January 1989

1.0 Introduction This section presents the Program Plan for Inservice Testing of safety-related Pumps at Unit 1 of the Nine Mile Point Nuclear Station, in compliance with the requirements of lOCFR50.55a. This Program Plan has been prepared to the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWP, .1983 Edition through the Summer 1983 Addenda.

The Pump Program Plan specifies Section XI testing requirements for all pumps provided with an on site emergency power source, and which are required for safety-related system operation. The pump, the test circuit, and the associated instrumentation were investigated to determine whether Section XI testing could be performed. For pumps where Code requirements are determined to be inappropriate, a specific relief request has been prepared. The specif ic relief requests fol low the Pump Test Table. Each specif ic relief request provides justification for deviation from the Section XI specified testing, and proposes appropriate alternate testing.

II-2 January 1989

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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.

Analysis of Oata - Time Frame All Code required test parameters will be reviewed at the time of performance for acceptability. If during this review, the test results show deviations greater than allowed (See Section XI Table IWP-3100-2 and NMPl General Pump Relief Request PG-l), an analysis shall be conducted to determine the cause of the deviation. If the cause of the deviation cannot be determined and corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the original test performance, the pump shall be declared inoperable. This position is more conservative than the Code (See Section XI IWP-3220) but less conservative than in the USNRC's Or aft Generic Letter, Supplement 1, Item 10. This time frame is needed due to the NMPl plant technical specifications which requires an immedi ate test of the redundant component(s) or system(s). This additional testing delays the investigation of the initial test deviation which could have been caused by a misaligned system, a human error in data recording or reduction, or by a malfunctioning or out of tolerance instrument loop, etc.

Scope of Tests (IWP-3300)

Subarticle IWP-3300 requires that each inservice test measure and observe all the quantities in Table IWP-3100-1. The Code assumes 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 quantities. For example, submerged pumps 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 suction. Explanatory notes and/or relief requests are included in the Pump Test Table when Section XI testing is not possible due to pump design.

II-3 January 1989

3.0 Pump List Pumps required for safety-related operation for NMP1 are as follows:

SYSTEM DWG. NO. REV. NO. NO. of PUMPS Core Spray C-18007-C 33 Core Spray Topping C-18007-C 33 Spent Fuel Pool Cooling C-18008-C Containment Spray C-18012-C Sh.2 26 Containment Spray Raw Water C-18012-C Sh. 1 Liquid Poison C-18019-C 12 Emergency Service Water C-18022-C Sh.3 10 RBCLC C-18022-C Sh.3 10 Emergency D. G. Cooling C-18026-C Sh.l C-18026-C Sh.2 Emergency D.~ G.~ C-18040-C Fuel Oil Transfer C.~ R.~ Chilled Water C-18047-C Condensate Tr ansfer C-18048-C 19 NOTE: Revision numbers listed are those current during Program Plan development, and may not reflect the most current drawing revision available.

II-4 January 1989

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)

P = Differ ential Pressure Qf = Flow Rate V = Vibration Amplitude Tb = Bearing Temperature Q

= Quarterly X = Measurement/Observation per IWP L = Lubricant Level or Pressure PR = Pump Relief Request NA = Not Applicable I I-5 January 1989

PUMP ANO VALVE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION II.5.0 PUMP TEST TABLE Pages II-1-1 through II-1-16 I I-1-1 January 1989

0 PUMP ABLE PUMP LIST MEASURED PARAMETERS PUMP CO- ASME TEST

-. PUMP NAME I.D. PLI.D. NO. ORD. CLASS FREQ. N Pi V L PG-1)

Liquid Poison NP02A C-18019-C H-5 Q (1) PR-4 PR-4 PR-4 PG-4 X (Ill, f12) NP02B H-7 Q (1) PR-4 PR-4 PR-4 PG-4 X Emergency Service 72-04 C-18022-C B-5 3 PR-5 (1) (3) (4) PR-5 PR-6 PG-4 (2)

Water 72-03 Sh. 3 D-5 3 PR-5 (1) (3) (4) PR-5 PR-6 PG-4 2)

(Ill, 812)

Reactor Building 70-01 C-18022-C D-8 3 PR-3 (1) (3)PR-3 (4)PR-3 PR-3 PG-4 Closed Loop 70-02 Sh. 3 0-7 3 PR-3 (1) 3)PR-3 (4)PR-3 PR-3 PG-4 Cooling Water 70-03 D-6 3 PR-3 (1) 3)PR-3 (4 PR-3 PR-3 PG-4 (Ill, 812, 813)

Core Spray 81-23 C-18007-C B-7 2 (1) . (3 PR-2,7 PR-6 PG-4 81-24 B-8 (4 PR-2,7 PR-6 PG-4 (8111, 8112 2 (1) 3) 8121, 8122) 81-03 L-7 2 3) PR-2,7 PR-6 PG-4 2) 81-04 L-8 2 (1) (3 (4) PR-2,7 PR-6 PG-4 (2 Core Spray 81-50 C-18007-C A-5 2 PR-2,7 PG-4 Topping 81-49 A-5 2 PR-2,7 PG-4 (8111, 8112 81-51 M-5 2 PR-2j7 PG'-4 8121, 8122) 81-52 M-5 2 (4) PR-2,7 PG-4 II-1-2 January 1989

PUMP T ABLE PUMP LIST MEASURED PARAMETERS ASME TEST PUMP NAME PUMP I.D. PEI.D. NO. COORD. CLASS FREQ. N Pi V Tb PG-1 Emergency D. G. 72-62 C-18026-C B-9 (1) (3) (4) PR-1 PR-6 PG-4 X Cooling Sh. 1 Water 72-63 C-18026-C A-9 (1) (3) (4) PR-1 PR-6 PG-4 X (8102, 8103) Sh. 2 Spent Fuel 54-01 C-18008-C C-5 PR-7 X PG-4 X Pool Cooling 53-02 C-8 PR-7 X PG-4 X (ill, 812)

'ontainment Spray 93-02 C-18012-C E-8 (1) (3) (4) PR-7 PR-6 PG-4 (2)

Raw Water 93-01 Sh. 1 F-8 (1) (3) (4) PR-7 PR-6 PG-4 (2)

'Pill, 8112 93-04 93-03 C-8 J-9 (1) (3 (4 PR-7 PR-7 PR-6 PR-6 PG-4 PG-4 (2)

-

8121, 8122) (2)

'fill,

.

.

Containment Spray 8112 8121, 8122) 80-04 80-24 80-03 C-18012-C Sh. 2 D-7 J-7 0-9 (1)

(1) 1)

(3)

(3)

(3)

(4) 4)

4)

PR-7 PR-7 PR-7 PR-6 PR-6 PR-6 PG-4 PG-4 PG-4 (2)

(2) 2)

80-23 J-9 (1) (3) (4) PR-7 PR-6 PG-4 (2)

Condensate 57-12 C-18048-C I-8 (1) (3) (4) PR-1 X PG-4 Transfer 57-11 H-8 (1) (3) (4) PR-1 X PG-4

. (Ill, 812)

II-1-3 January 1989

PUMP TABLE PUMP LIST MEASURED PARAMETERS ASME TEST i PUMP NAME PUMP I.D. P&I.D. NO. COORD. CLASS FREQ. N Pi Qf V Tb PG-1)

Emergency D. G. 82-40 C-18040-C B-7 NA PR-9 (1) (3) (4) PR-8 X PG-4 (2)

'uel Oil Transfer (8102, 8103) 82-41 C-7 NA PR-9 (1) (3) (4) PR-8 X PG-4 (2)

'..'ater R. Chilled C-18047-C I-2 3 (1) X (4) PR-10 X PG-4 (2)

(t>>, >12) 12 I-2 3 (1) X (4) PR-10 X PG-4 (2)

II-1-4 January 1989

6.0 Pump Test Table Notes In the Pump Test Table, the test parameters to be measured or observed, and the test frequency are identified. Footnotes 1 through 5 refer to amplifications, deviations, and exceptions to the Code requirements and are further discussed below:

(1) For pumps with constant speed drive, the speed is not measured since the test wi 11 be performed at nominal motor nameplate speed as required by Section XI, IWP-3100.

(2) Lubricant level or pressure not observed because of bearing lubrication design, (e.g., submerged pumps, sealed bearings).

(3) Inlet pressure measurement is satisfied by monitoring various levels such as torus, tank, pit, or lake level (Reference General Relief Request for Pumps PG-2).

(4) Differential pressure wi 11 be determined by using inlet (or level information) and discharge pressure measurements as opposed to measuring it directly from differential pressure instrumentation. (Reference Section XI, IWP-4240).

I I-1-5 January 1989

IP 7.0 PUMP RELIEF REQUEST PR-1 System: Emergency Diesel Generator Cooling Water Condensate Transfer Pump: Emergency Diesel Generator Cooling Water 72-62:72-63 Condensate Transfer 57-11:57-12 Class:

Function:- Provide cooling water to the Emergency Diesel Generators.

To provide make-up water to safety related cooling systems.

Test Requirements: Acceptable flowrate instrument accuracy of + 2X of full scale (IWP-4110-1).

Basis for Relief: The system currently does not have instrumentation installed to measure flow rate.

Temporary flow instruments shall be used in determining indi vidual pump f low rates. It i s anticipated that the allowable instrument accuracy wi 1 1 exceed Section XI requirements

( IWP-4110-1), however, a small reduction in accuracy should not provide a significant reduction in the ability to determine pump degradation.

Alternate Testing: Temporary test equi pment shal be uti 1 i zed in 1

determining individual pump flow rates. An engineering evaluation shall be made to add permanent flow instrumentation.

I I-1-6 January 1989

7.0 PUNP RELIEF REQUEST 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:

Function: To provide cooling to the core in the event of a LOCA.

Test Requirements: Neasure flow rate (INP-3100-1).

Basis for Relief: These pumps are designed to operate in series to meet Total Core Spray System flow requirements.

There are no system design provisions to measure flow between these pumps. The discharge from the Core Spray pump is delivered to the suction of the associated topping pump such that independent pump flow measurements are not meaningful.

Alternate Testing: The combined flow will be measured downstream of the topping pumps.

II-1-7 January 1989

0 7.0 PUMP RELIEF REQUEST PR-3 Reactor Building Closed Loop Cooling Water Pump: 70-01:70-02:70-03 Class:

Function: Provide cooling water io safety-related equipment.

Test Requirements: Measure inservice test quantities ( IWP-3100-1) quarterly ( IWP-3400) .

Basis 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 the 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: Differential pressure, flow rate and pump vibration shall be measured for each individual pump during cold shutdown. Pump vibration wi 1 1 be measured for each indi vidual pump on a quarterly basis.

II-1-8 January 1989

7.0 PUMP RELIEF REQUEST PR-4 System: Reactor Liquid Poison Pump: NP02A:NP02B Class:

Function: Provide a method of shutting down the Reactor without use of the Control Rods.

Test Requirements: Measure flow rate, inlet and di fferenti al pressure ( IMP-3100-1).

Basi s for Rel i ef: These pumps are tested by pumping water from a test tank into a 55 gallon barrel for one minute and calculating flow rate from the change of test tank water level. Pump suction pressure is the head of water in the test tank and test lines which decreases as the tank level drops during testing. These positive displacement pumps are designed to provide a constant quantity of fluid (flow rate) at a relatively high discharge pressure (approximately 1500 psig) regardless of the suction pressure. In addition, the suction head is so small in comparison to the discharge pressure during testing of these pumps (2 psig vs 1275 psig), that measurement of suction pressure would provide no useful information in assessing pump performance.

Alternate Testing: Pump discharge pressure, calculated flow rate and vibration wi1 1 be used in determining pump degradation.

I I 9 January 1989

7.0 PUMP RELIEF REQUEST PR-5 System: Emergency Service Water Pump: 72-03:72-04 Class:

Function: Provide cooling water to safety-related equipment.

Test Requirements: Measure f ow 1 rate ( IWP-3100-1) quarterly

( IWP-3400). Acceptable instrument accuracy (IWP-4110-1).

Basis for Relief: The test line piping configuration does not allow for temporary test or permanent flow instrumentation to be installed. System heat loads prevent removing an entire service water header from service during operations or even during cold shutdowns. Since the ESW pumps operate at a lower pressure than the normal service water header pressure, testing at quarterly or cold shutdown intervals is not possible. Flow instrumentation can be utilized on the Service Water System inter-tie piping to test the Emergency Service Water pumps during ref ue ing.

1 Alter nate Testing: Pump di fferent i al pressure, and pump motor vibration wi 1 1 be used to evaluate pump performance quarterly. Pump di fferenti al pressure, flow rate, and pump motor vibration will be measured for each individual pump a'

refueling.

Temporary test equipment shall be uti i zed in 1 determining individual pump flow rates. It is anticipated that the allowable instrument accuracy will exceed Section XI requirements

( IWP-4110-1), however, a small reduction in accuracy should not provide a significant reduction in the ability to determine pump degradation. An engineering evaluation shall be made to add permanent flow instrumentation on the individual pump discharge.

II-1-10 January 1989

7.0 PUMP RELIEF REQUEST PR-6 System: Emergency Service Water, Emergency Diesel Generator Cooling Water, Core Spray, Containment Spray Raw Water, Containment Spray.

Pump: Emergency Service Water 72-03:72-04 Emergency Diesel Generator Cooling Water 72-62:72-63 Core Spray 81-03:81-04:81-23:81-24 Containment Spray Raw Water 93-01:93-02:93-03:93-04 Containment Spray 80-03:80-04:80-23:80-24 Class: 23 Function: Various Test Requirements: Measure vibration on pump bearing housing (IWP-4600).

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

Alternate Testing: Vibration measurements will be taken on the pump motors. Since these are vertical line shaft pumps, any change in the vibration characteristics of the pump will be transmitted to the motor. The PG-1 criteria will be applied to these readings.

II-l-ll January 1989

7.0 PUMP RELIEF REQUEST PR-7 System: Core Spray, Core Spray Topping, Spent Fuel Pool, Containment Spray Raw Water, Containment Spray Pump: Core Spray 81-03: 81-04: 81-23: 81-24 Core Spray Topping 81-51: 81-52: 81-49: 81-50 Spent Fuel Pool 54-01: 54-02 Containment Spray Raw Water 93-01: 93-02: 93-03:

93-04 Containment Spray 80-03: 80-04: 80-23: 80-24 Class:

Function: Various Test Requirements: Table IWP-4110-1 acceptable instrument accuracy requires a flow rate instrument accuracy of + 2/

of full scale.

Basis For Relief: NMPl uses flow measuring instrumentation which meets the acceptable instrumentation accuracies defined in Table IWP-4110-1. The total loop accuracy was calculated from the flow device to the final readout device. The loop accuracies do not meet the instrumentation accuracies of Table IWP-4110-1 for flow rate (see the following table for flow instrument accuracies):

I I-1-12 January 1989

PUMP FLOW MEASUREMENT INSTRUMENT ACCURACIES INSTRUMENT SYSTEM ACCURACY< LOOP ACCURACY (1)

Core Spray System 0.25 2.08 (Core Spray Topping)

Spent Fuel Pool System 2.00 2.12 Containment Spray Raw 0. 94 2. 07 Water System Containment Spray 0.25 2.08 (1) X of Full Scale The flow transmitter is well within or meets the accuracy limits of Section XI. The loop accuracies do not significantly exceed Section XI limits and should be sufficiently repeatable from test to test to allow for an evaluation of the pump hydraulic condition and for the detection of pump degradation.

Alt'ernate Testing: Use the installed instruments.

II-1-13 January 1989

7.0 PUMP RELIEF REQUEST PR-8 Emergency Diesel Generator Fuel Oil Transfer Pump: 82-40: 82-41 Class: NA Function: Provide fuel oil to the Diesel Generator Day Tank.

Test Requirements: Measure flow rate IHP-3100-1.

Basis For Relief: The piping conf i gurat i on (underground, mu1 t i pl e bends) as such does not support itself to allow for temporary test or permanent flow instrumentation to be installed, (See PR-9).

Alternate Testing: The change in level of the Diesel Generator Oay Tank shall be used in calculating flow rate for determining pump degradation.

II-1-14 January 1989

7.0 PUMP RELIEF REQUEST PR-9 System: Emergency Diesel Generator Fuel Oil Transfer Pump: 82-40: 82-41 Class: NA Function: Provide fuel oil to the Diesel Generator Day Tank.

Test Requirements: Frequency of inservice tests IWP-3400.

Basis For Relief: The Diesel Generator Fuel Oil Transfer Pumps are skid mounted components and are assessed during monthly Technical Specification Emergency Diesel Generator operability tests. The power for these pumps comes from their associated Diesel Generator. The pumps have no means of operating unless their associated engine is running.

Alternate Testing: Inservice Testing of these pumps shall be performed during refuel when a temporary power supply can be provided to operate the pumps without running their associated engine. In addition, pump degradation assessments shall be performed during monthly Technical Specification Emergency Diesel Generator operability tests.

II-1-15 January 1989

14* HO \ ~ - ~

7.0 PUMP RELIEF REQUEST PR-10 System: Control Room Chilled Water Pump: 11:12 Class:

Function: Provide cooling water for control room HVAC.

Test Requirements: Acceptable flowrate instrument accuracy of + 2'A of full scale (IWP-4110-1).

Basis For Relief: The system currently has inadequate instrumentation installed to measure flowrate.

Temporary flow instruments shall be used in determining individual pump flow rates. It is anticipated that the allowable instrument accuracy will exceed Section XI requirements

( IWP-4110-1), however, a small reduction in accuracy should not provide a significant reduction in the ability to determine pump degradation.

Alternate Testing: Temporary test equipment shall be utilized in determining individual pump flow rates. An engineering evaluation shall be made to replace the permanent flow instrumentation.

II-1-16 January 1989

'4, M g

~

~ t wl ~ 6 0 ~ 4 CA ~ 44 I lA 4hA % ~

PUMP ANO 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-ll I I I-1 Januar y 1989

0 f"

'gF

1.0 Introduction This section presents the Program Plan for Inservice Testing of Valves at Unit 1 of the Nine Nile Point Nuclear Station, in compliance with the requirements of 10CFR50.55a. This Program Plan has been prepared to the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWV, 1983 Edition through the Summer 1983 Addenda.

This Test Program Plan was developed to assess the operational readiness of valves in safety-related systems. The valves addressed are those whose operability is essential to safety-related system operation. Section XI testing is then specified for each of these valves to verify individual valve operational readiness. 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 station systems. This review identifies those systems performing safety-related functions. Each safety-related system was then analyzed to determine which valves are essential to the safety-related operation of the system. These valves are investigated to determine whether Section XI testing can be performed during normal operation. Those valves for which quarterly testing is determined to be inappropriate are analyzed further to determine if Code allowed cold shutdown testing is possible. If so, a justification for delay of testing to cold shutdown is provided following the appropriate Valve Test Tables. Relief requests describing appropriate alternative testing have been prepared for valves which cannot be tested quarterly or during cold shutdown, and are provided following the appropriate Valve Test Tables.

III-2 January 1989

a ~~

2.0 Code Interpretation I

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

Corrective Action - Time Frame If a valve fails to exhibit the required change of valve stem or disk position or exceeds its specified limiting valve of full-stroke time, the corrective action shall be initialed immediately. If the condition is not, or cannot be, corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the valve shall be declared inoperable. This position is in accordance with the Code (see IWV-3417b), but not with the USNRC's Draft Generic Letter, Supplement 1, Item 10. This time frame is needed due to the NNP1 plant technical specification action statement which requires an immediate test of the redundant component in other loop(s) upon declaring the first component inoperable. This additional testing delays the investigation of the initial test deviation which could have been caused by an electrical problem, additional load on the instrument air system, system loading conditions, etc.

Relief Valves:

The Code requires testing of safety and relief valve set points in accordance with ASNE PTC 25.3-1976. The relief valves designated for test are those which perform a system pressure relief function.

, Passive Valves:

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

Control Valves:

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

Automatic Power Operated Valves:

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

III-3 January 1989

2.0 Code Interpretation (Cont.)

Remote Power Operated Valves:

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.

Dual Function Valves:

Valves which provide more than one function are tested for their safety-related function only. Val ves 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 si gnal, and al so act as rel i ef val ves. Both are safety-rel ated 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 reverse flow. Normally closed simple check valves which are considered active and 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 simple check, if possible, or by use of the manual operator.

Testable Check Valves:

Check valves equipped with manual exercisers wi 11 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'heck, or by use of the power operator.

III-4 January 1989

~ ~

II

f

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 using the operator. In addition to exercising, the operator will be timed and fail safe actuation tested as appropriate.

Pump Discharge Check Valves:

As a minimum, pump discharge check valves in safety-related systems wi 11 be forward flow exercised. In addition, reverse flow closure will be verified when failure of the valve to close could result in a 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 fails to close, system flow could be diverted back through the idle pump to the suction header.

System Piping Keep Fill Check Valves:

Keep fill lines are those lines attached to ECCS 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 ver ifi cati on i s performed only if failure of the valve to close could result in a. reduction of ECCS operation.

Check Valve Full/Partial Stroke:

In most cases maximum accident condition 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 maximum accident condition flow, and not the full mechanical stroking. Forward flow full stroke operability testing wi 11 be by any method that verifies the valve is capable of passing maximum accident condition flow. Tests that verify less than maximum accident condition flow capability is considered as a partial stroke test.

Category A (Containment Isolation Valve) Leak Testing:

Valves specified for Appendix J Type C leakage 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 testing. Future changes to the Appendix J Type C Program will be incorporated into the Valve IST Program.

III-5 January 1989

2.0 Code Interpretation (Cont.)

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 IWV-3420.

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

Valves which perform both a containment isolation and a pressure isolation function (Event Y only) are included in the Valve IST Program Plan as Category A Valves. These valves will be tested to requirements of both Appendix J and Section XI.

Valve Timing:

The required maximum stroke times have been established and incorporated into a separate NNPl document.

Valve Position Indicator Verification:

IWV-3300 requires that valves with remote position indicators shall be observed at least once every two years to verify that valve operation is accurately indicated. This program tests active valves equipped with remote position indicators in accordance with IWV-3300. Verification of proper remote position indicator operation will be performed during each refueling outage.

Valve Fail Safe Testing:

IWV-3415 requires proper operation of valves equipped with Fail Safe Actuators to be observed. For NNPl, thi s i s general ly accomp1 i shed by pl acing the control to the position which de-energizes the actuator and observing proper valve operation (See VG-4). In cases where operation of normal valve controls does not de-energize the valve actuator, alternate means will be adopted to simulate loss of actuator power.

Skid Mounted Testing - Valves:

The Instrument Air System Air Compressor Inlet Cooling Water valves, the Emergency Diesel Generator Air Start valves, and the Diesel (Fire Pump) Air Start valves are skid mounted valves that cannot be readily tested as a component. Valve operability will be verified by monitoring the system performance during continuous operation ( IAS), weekly operability tests (Fire Pump), or by monthly operability tests (EDG).

III-6 January 1989

3.0 Valve Test Table Nomenclature The following abbrevi ations have been used in the Valve Test Table Value Tyae Actuator T e AGV - Angle Val ve APA - Air/Piston ADA - Air/Diaphragm BFV - Butterfly Val ve EXA - Explosive BLV - Ball Valve HOA - Hydraulic CHV - Check Valve MAA - Manual MOA - Motor EXV - Explosive Valve NPA - Nitrogen/Piston NDA - Nitrogen/Diaphragm GLV - Globe Valve SEA - Self GTV - Gate Valve SOA - Solenoid NDV - Needle Valve PGV - Plug Valve REV - Relief Valve SCV - Stop Check Valve Stroke Direction TPV - Two Port Valve 0 - Closed to Open TMV - Three Way Valve C - Open to Closed Normal Position Check Valve Test Direction 0 - Open F - Forward Flow C - Closed R - Reverse Flow LO - Locked Open LC - Locked Closed TH - Throttled DE - Normal position depends on system condition I II-7 January 1989

3.0 Valve Test Table Nomenclature (Cont.)

Test Re uirements EX - Explosive Valve test per IWV-3610.

FE - Full Stroke Exercise test.

FS - Fail Safe test.

LA - Leak Test per Section XI (leakage function only).

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 Oisk test per IWV-3620.

RT - Relief Valve test.

ST - Stroke Time test.

Test Frequenc C - Testing performed during cold shutdown P - Periodically tested during the time period defined in:

IWV-3511 (safety and relief valves)

IWV-3610 (explosive actuated valves)

IWV-3620 (rupture disks) g - Once per 92 days (quarterly)

R - Once per refueling outage III-8 January 1989

4.0 Valve Test Table Format Unique number assigned to each valve, and a description of the valves function within the system.

Class and Owg. Coor. The ASME valve classification (Class 1 2 or

3) or Non-ASNE valve classification (NI, and the valve location on the reference drawing.

Valve Cat. Valve category as defined in Sub-article IWV-2200.

Size (in.) and Type Valve size is the nominal diameter of the valve in inches.

Valve type is the specific type of valve, as abbreviated in Section 3.0 "Valve Test Table Nomenclature".

Actu. Type The type of Actuator used to operate the valve.

Norm. Posit. The valve position during normal plant operation.

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

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

Check Valve Test Direct. The direction of check valve "F"

operabi lity verification, indicated by for forward flow and "R" for reverse flow.

C.S. Just. or Reference number of the cold shutdown Relief Req. No. justification or relief request.

C.S. or Alt. Test Per f. Cold shutdown or alternate testing which is being performed in lieu of the Code specified quarterly testing.

Remarks: Key to notes providing ampl i fying remarks.

These notes are located immediately following the appropriate Valve Test Tables.

III-9 January 1989

4.0 Valve Test Table Format (Cont.)

~Sstem ~Dw . No. Rev. No. Attachment No.

Main Steam C-18002-C 21 Reactor Rec i rcul at i on C-18020-C 12 Control Rod Drive C-18016-C Sh.l 14 C-18016-C Sh.2 15 Feedwater/HPCI C-18005-C Sh. 2 15 Core Spray C-18007-C 33 Emergency Cooling C-18017-C 32 Reactor Shutdown Cooling C-18018-C 13 Containment Spray C-18012-C Sh.l 9 C-18012-C Sh.2 26 Reactor Cleanup C-18009-C Sh.l Inert Gas Purge and Fill C-18014-C Sh.l 40 10 Hydrogen-Oxygen Monitoring C-18014-C Sh.2 31 C-26939-C 5 C-26949-C 7 TIP C-18014-C Sh.2 31 12 Nitrogen Supply No. 11 C-18014-C Sh.3 12 13 Nitrogen Supply No. 12 C-18014-C Sh.4 22 14 Reactor Sldg. HVAC C-18013-C 16 15 Liquid Poison C-18019-C 12 16 Spent Fuel Storage Pool Filtering E Cooling C-18008-C 17 Sample C-18041-C Sh.2 10 18 NOTE: Revision numbers listed are those current during program plan development and may not reflect the most current drawing revision avai 1 ab1 e.

III-10 January 1989

4.0 Valve Test Table Format (Cont.)

~Sstem ~ow . No. Rev. No. Attachment No.

Reactor Bldg. Closed C-18022-C Sh.2 19 19 Loop Cooling C-18022-C Sh.3 10 C-18022-C Sh.4 7 C-18047-C 15 C-26939-C 5 C-26949-C 7 C-18008-C 11 C-18041-C Sh. 7 5 Condensate Transfer C-18048-C 19 20 Torus Vacuum Relief C-18006-C Sh.2 17 21 Emergency Service Water C-18022-C Sh.3 10 22 C-18027-C Sh.2 7 Emergency Diesel Generator C-18026-C Sh.l 23 Cooling Water C-18026-C Sh.2 Emergency Di esel Generator C-18026-C Sh.l 24 Air Start C-18026-C Sh.2 Emergency Diesel Generator C-18040-C 25 Fuel Oil Transfer Waste Disposal C-18045-C Sh.7 26 C-18045-C Sh.9 Breathing Air to Drywell C-18578-C 27 Control Room Chilled Water C-18047-C 15 28 Control Room HVAC C-18047-C 15 Instrument Air C-18011-C Sh.l 16 30 C-18011-C Sh.2 10 C-18030-C Sh.3 14 NOTE: Revision numbers listed are those current during Program Plan development and may not reflect the most current drawing revision available.

III-11 January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.0 VALVE TEST TABLES AND RELIEF REQUESTS Pages III-I through III-30-5 I I I-I January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION I II 5.1 ATTACHMENT 1 VALVE TEST TABLES AND RELIEF REQUESTS FOR MAIN STEAM OWG. NO. C-18002-C Pages III-l-l through III-1-14 III-1-1 January 1989

I SYST N STEAM NI N f POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18002-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.

01-01 1 24 MOA 0 FE-Q CS-1 FE-C MS-IN-IV ¹1 B-5 GLV ST-Q ST-C (111) LJ-R PE-Q PI-R 01-02 1 24 MOA 0 FE-Q CS-1 FE-C MS-IN-IV ¹2 F-5 GLV ST-Q ST-C (121) LJ-R PE-Q PI-R 01-03 1 24 APA 0 FE-Q CS-1 FE-C NOTE 3 MS-Out-IV ¹3 A-5 GLV ST-Q ST-C (112) FS-Q FS-C LJ-R PE-Q PI-R 01-04 1 24 APA 0 FE-Q CS-1 FE-C NOTE 3 MS-Out-IV ¹4 G-5 GLV ST-Q ST-C (122) FS-Q FS-C LJ-R PE-Q PI-R III-1-2 January 1989

SYST N STEAM NIN POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18002-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REO. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. RE/. NO. PERF.

34-01 1 2 MOA C PV NOTE 1 CRD Head Spray H-2 GTV LJ-R Outside IV 34-02 1 A,C 2 SEA C PV NOTE 1 CRD Head Spray F-2 CHV LJ-R Inside IV (Check) 37-01 1 2 MOA C FE-C} CS-2 FE-C Rx Head Vent F-2 GTV ST-0 O,C ST-C B.V. 81 PI-R III-1-3 January 1989

SYST N STEAM NIN POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18002-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.

37-06 1 2 MOA C FE-Q CS-2 FE-C Rx Head Vent F-3 GTV ST-Q O,C ST-C B.V. 82 PI-R 66-07 2 SEA DE Ff-Q F,R RR-2 FE-R SRV Vacuum Breaker B-4 CHV 66-08 2 4 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker B-4 CHV 66-09 2 4 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker B-3 CHV 66-10 2 4 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker B-3 CHV 66-11 2 4 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker F-3 CHV 66-12 2 4 SEA DE FE-Q RR-2 FE-R SRV Vacuum Breaker f-3 CHV 66-13 2 4 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker F-4 CHV 66-14 2 4 SEA DE FE-Q RR-2 FE-R SRV Vacuum Breaker F-4 CHV 66-15 2 4 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker F-5 CHV I I I-1-4 January 1989

SYST IN STEAM NI E POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18002-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.

66-16 2 4 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker f-5 CHV 66-17 2 4 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker 8-5 CHV 66-18 2 C 4 SEA DE FE-Q RR-2 FE-R SRV Vacuum Breaker 8-5 CHV 66-25 2 10 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker B-4 CHV 66-26 2 C 10 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker 8-4 CHV 66-27 2 10 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker B-3 CHV 66-28 2 10 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker B-3 CHV 66-29 2 10 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker F-3 CHV 66-30 2 10 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker F-3 CHV 66-31 2 10 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker F-4 CHV II I-1-5 January 1989

SYSTEM MAIN STEAM NINE MILE POINT UNIT 1 VALVE TfST TABLE DHG. NO. C-18002-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.

66-32 2 10 SEA DE Ff-Q F,R RR-2 FE-R SRV Vacuum Breaker G-4 CHV 66-33 2 10 SEA DE F,R RR-2 Ff-R SRV Vacuum Breaker F-5 CHV 66-34 2 10 SEA DE FE-Q F,R RR-2 Ff-R SRV Vacuum Breaker F-5 CHV 66-35 2 10 SEA Df FE-Q F,R RR-2 FE-R SRV Vacuum Breaker 8-5 CHV 66-36 2 10 SEA DE FE-Q F,R RR-2 FE-R SRV Vacuum Breaker B-5 CHV NR108A 1 B,C 6XB FE-Q RR-1 FE-R NOTE 2,4 MSERV-3 (Pill) C-4 REV SOA ST-Q O,C FS-Q RT-P PI-R NR108B 1 B,C 6X8 Ff-Q RR-1 FE-R NOTE 2,4 MSERV-1 (8112) C-3 REV SOA ST-Q O,C FS-Q RT-P PI-R NR108C 1 B,C 6XB FE-Q RR-1 FE-R NOTE 2,4 MSERV-2 (8121) E-4 REV SOA ST-Q O,C FS-Q RT-P PI-R NR108D 1 B,C 6X8 FE-Q RR-1 FE-R NOTE 2,4 MSERV-4 (8122) E-4 REV SOA ST-Q O,C FS-Q

-P R

III nuary 1989

SYSTEM MAIN STEAM NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18002-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.

NR108E 1 8 C 6X8 FE-Q RR-1 FE-R NOTE 2,4 MSERV-5 (¹113) C-4 REV SOA ST-Q O,C FS-Q RT-P P I-R NR108F 1 B,C 6XB FE-Q'T-Q RR-1 FE-R NOTE 2,4 MSERV-6 (¹123) E-5 REV SOA O,C FS-Q RT-P PI-R NR28A 1 6 SEA RT-P Rx. Head PSV D-1 REV NR288 1 6 SEA RT-P Rx. Head PSV D-1 REV NR28C 1 6 SEA RT-P Rx. Head PSV 0-1 REV NR28D 1 6 SEA RT-P Rx. Head PSV 0-1 REV NR28E 1 6 SEA RT-P Rx. Head PSV 0-1 REV NR28F 1 6 SEA RT-P Rx. Head PSV D-1 REV NR28G 1 6 SEA C RT-P Rx. Head PSV 0-1 REV NR28H 1 6 SEA RT-P Rx. Head PSV D-1 REV I I 1-1-7 January 1989

SYSTEM MAIN STEAM NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18002-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.

NR28J 1 6 SEA C RT-P Rx. Head PSV 0-1 REV NR28K 1 6 C RT-P Rx. Head PSV D-1 REV NR28M 1 6 SEA C RT-P Rx. Head PSV 0-1 REV NR28N 1 6 SEA C RT-P Rx. Head PSV D-1 REV NR28R 1 6 SEA C RT-P Rx. Head PSV D-1 REV NR28S 1 6 SEA C RT-P Rx. Head PSV D-1 REV NR28T 1 6 SEA C RT-P Rx. Head PSV D-1 REV NR28U 1 6 SEA C RT-P Rx. Head PSV 0-1 REV III-1-8 January 1989

SYSTEM MAIN STEAM NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18002-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.

37-02 1 2 MOA C FE-Q CS-2 FE-C Rx Head Vent F-3 GTV ST-Q O,C ST-C B.V. 83 PI-R III-1-9 January 1989

NOTES FOR ATTACHMENT 1 SYSTEM: MAIN STEAM NO. NOTE These valves are in the head spray line which is not used during any mode of normal operation or cold shutdown.

IST requirements satisfy SER 26-88.

MSIV's 01-03 and 01-04 receive two fail safe tests each cold . shutdown. One test is performed for loss of electrical signal; the second test is performed for loss of air (Ref. IEN 85-84).

The setpoint test for the ADS valves consists of a two part process. During the first part, the pressure switch which actuates these valves is subjected to setpoint pressure using a deadweight tester. This verifies that the relay logic picks up at the required setpoint. The second part, consists of manually operating each ADS valve at low power during plant startup following refueling outages. The valves are subjected to reactor steam and verifies that the valve disk opens and steam blowdown to the torus occurs.

III-1-10 January 1989

COLD SHUTDOWN TEST JUSTIFICATION MS-CS-1 Main Steam Valve: 01-01: 01-02: 01-03: 01-04 Category:

Class:

Function: Main Steam Line Isolation Valves ASME Section XI quarterly Test Requirements: Exercise, time and fail safe test (01-03: 01-04)

Exercise and time (01-01: 01-02)

Cold Shutdown Test Just ificati on: Full stroke exercising results in loss of steam flow from one main steam line to the turbine causing a reactor trip. Also, recent industry information indicates that closing these valves with high steam flow in the line may be a large contributing factor in observed seat degradation. The valves are designed for partial stroke exercising with full steam flow during plant operation. The partial stroke test will verify operability of the valve and operator without the potential for seat damage which could result from full stroke exercising.

quarter ly Part Stroke Testing: Partial stroke close exercise.

Cold Shutdown Testing: Full stroke exercise, time and fail safe test.

I I I 11 Janu ary 1989

COLD SHUTDOWN TEST JUSTIFICATION MS-CS-2 System: Main Steam Valve: Val ves: 37-01 (RHV-BV-1): 37-02 (RHV-BV-3): 37-06 (RHV-BV-2)

Category:

Class:

Function: Reactor Head Vent ASME Section XI Quarterly Test Requirements: Exercise and time Cold Shutdown Test Justification: The design function of these valves is to provide a vent path to primary containment for use during reactor vessel water level changes. Thi s vent path i s only utilized during startup, 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 Boundary since these valves provide a Reactor Coolant/Primary Containment boundary. Failure of the adjacent valve during cycling would introduce a LOCA within the drywell which would affect operation of equipment necessary for safe shutdown.

Quarterly Part Stroke Testing: The above justification also applies for partial exerci sing.

Cold Shutdown Testing: Full stroke exercise and time.

I I I-1-12 January 1989

t' RELIEF RE(VEST MS-RR-1 System: Main Steam Valve: NR108A,B,C,D,E 8( F Category:

Cl ass:

Function: ADS Val ves ASME Section XI quarterly Test Requirements: Exercise IWV-3412, time IWV-3413 and fail safe test IWV-3415 quarterly IWV-3411 Basis for Relief: Opening the ADS valves during power operation causes a discharge of steam into the torus. If the valves failed to reclose after testing, the plant would be placed in a loss of coolant transient condition. In addition, a recent study (BWR Owners Group Evaluation of NUREG-0737 Item II.K.3.16 Reduction of Challenges and Failures of Relief Valves) recommends that the number of ADS valve openings be reduced as much as possible. Based on this study and the potential for causing a possible loss of coolant transient condition, exercise testing of the ADS valves will be delayed to refueling. Concerning valve stroke timing during exercising, the position indication in the Control Room only indicates ADS Relief Valve pilot position; there is no direct means for detecting the actual position of the valve disk. Actuation of a relief valve is verified by acoustic monitoring of the SRV line discharge to torus. Measuring the time from the initiation signal for the valve and the acoustic monitoring detection provides no meaningful data for predicting valve degradation. Also, de-energizing the solenoid valve has the same effect as loss of electrical power or loss of control air. Therefore, exercising the valve to it's fail-safe position constitutes a fail-safe test.

Alternate Testing: Exercise at refueling.

III-1-13 January 1989

~ 4

• Cl 4 - 1 y

• I* J'

• I ~

RELIEF REQUEST MS-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:

Class:

Function: Vacuum Relief Check Valves on the lines from the AOS Valves to the Torus ASME Section XI, Quarterly Test Requirements: Exercise, observe force or torque limitations of PAV-3522(b) quarter ly IWV-3521 Basis for Relief: The val ves are vacuum breaker check val ves located inside the drywell. The system and valves provide no means for observing operability of the valves other than manually exercising. This requires entry into the drywell which is not possible during normal operation or cold shutdown because of radiation levels and drywell atmosphere being inert. Also, the valves have no provision for installation of a torque wrench or other device for the purpose of measuring the torque or force needed to operate the valve.

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

III-1-14 January 1989

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 OWG. NO. C-18020-C Pages I

III-2-1 through III-2-2 I I I-2-1 January 1989

SYSTEM REACTOR RECIRC. NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18020-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) ( I N. ) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. P ERF.

110-127 1 A 1 MOA C FE-Q React. Recirc. K-1 GLV ST-Q C Sample IV LJ-R PI-R 110-128 1 1 MOA C 'E-Q React. Recirc. L-1 GLV ST-Q Sample IV LJ-R PI-R III-2-2 January 1989

PUMP AND VALVE INSERVICE TESTING 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 through III-3-7 III-3-1 January 1989

SYSTEM CRD NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18016-C SH.l 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 0.5 MAA DE FE-Q F,R RR-1 NOTE 1,5 Charging Water 8-4 SCV SEA Isolation Valve 108 2 .75 MAA DE FE-Q RR-1 NOTE 1,2 Scram Discharge A-4 SCV SEA Isolation Valve 126 2 .75 ADA C FE-Q RR-1 NOTE 1,3 Scram Inlet Valve C-3 GLV ST-Q FS-Q

. PI-R 127 2 .75 ADA C FE-Q RR-1 NOTE 1,3 Scram Discharge A-3 GLV ST-Q Valve FS-Q P I-R 138 2 0.5 SEA DE FE-Q f,R RR-1 NOTE 1,4 Cooling Water D-2 CHV Inlet Check 301-112 1 A,C 3 SEA DE fE-Q RR-3 FE-R Cont. Isol. L-7 CHV LA-R Valve 301-113 1 A,C 3 SEA DE fE-Q RR-3 fE-R Cont. Isol. M-7 CHV LA-R Valve III-3-2 January 1989

. ~

0

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 VALVE NUMBER AND (CAT. ) ( IN. ) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

44.2-15 2 2 ADA 0 FE-Q Scram Discharge A-4 GLV ST-Q RR-2 ST-R Vol. Hld. Tk. IV FS-Q LJ-R Vol. PI-R 44.2-16 2 2 ADA 0 FE-Q Scram Discharge B-7 GLV ST-Q Hl d. Tk. IV FS-Q LJ-R P I-R 44.2-17 2 2 ADA 0 FE-Q Scram Discharge I-7 GLV ST-Q Drain IV FS-Q LJ-R P I-R

44. 2-18 2 2 ADA 0 FE-Q J-7 ST-Q RR-2 ST-R Scram Discharge GI V Drain IV FS-Q LJ-R PI-R I II-3-3 January 1989

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

Proper operation of the Control Rod during Rod Insertion Time testing verifies forward flow opening.

Proper operation of the Control Rod during Rod Insertion time testing ver if i es val ve opening and adequate val ve stroke time.

Normal control rod motion verifies that these check valves move to their closed position. Each partially or ful ly withdrawn control rod is exercised at least once per week per plant Technical Specifications while at operating conditions. When fully inserted control rods are withdrawn to a new value, this also has the same effect. Rod motion may not occur if these check valves were to fail in the open position. Also, during refueling, Technical Specification control rod scram insertion time testing verifies proper operation of each of these valves.

Proper operation of the control rod during rod insertion time testing verifies proper reverse flow closure of these valves.

III-3-4 January 1989

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

Category: B (126:127)

C (108:106:138)

Class:

Function: Reactor Shutdown ASME Section XI Exercise IWV-3412, time IWV-3413 and fail safe test Quarterly Test IWV-3415 quarterly IWV-3411 position indication IWV-3300 Requirements: (126:127)

Verify forward flow opening IWV-3522 quarterly IWV-3521 (108:106:138)

Verify reverse flow closure IWV-3522 quarterly IWV-3521 (106)

Basis for Relief: The Hydr aulic 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 change in core reactivity. Scram testing rods at power also introduces degrading wear and tear on control rod drive mechanisms and to the lower region of the reactor vessel due to both thermal and hydraulic shock. In addition, there is high probability that control rod scram testing results in accelerated deterioration of the CRO stub tube area (cracking) due to this thermal and hydraulic shock, a problem identified at NMPl during the 1984 refueling outage and for which a major engineering effort is underway in search of a long term permanent. repair.

Therefore, Niagara Mohawk believes that performing scram time testing during power operation for the sole purpose of verifying proper scram inlet and outlet valve (126,127) stroke times is very undesirable and unwarranted based on these considerations. 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 each reactor scram from rated pressure, the mean 90K Insertion time shall be determined for eight selected rods. If the mean 90%%d insertion time of the selected control rod drives does not fall within the range of 2.4 to 3.1 seconds or the measured scram time of any one drive for 90K insertion does not fall within the range of 1.9 to 3.6 seconds, an evaluation shall be made to provide reasonable assurance that 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 the fully withdrawn position. Following any outage not initiated by a reactor scram, eight rods shall be scram tested with reactor pressure above 800 psig.

III-3-5 january 1989

RELIEF REQUEST CRD-RR-2 System: Control Rod Dr ive Valve: 44.2-15:44.2-18 Category: A Class:

Function: Scram Discharge Volume Vent and Drain Isolation Valves ASME Section XI quarterly Test Requirements: Exercise IWV-3412 and time IWV-3413 quarterly IWV-3411 Basis for Relief: Solenoid air pi lot val ves control the air supply to the air actuators for valves 44.2-15 and 44.2-18. The solenoid valves uti i ze two different exhaust paths; 1

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 (test mode) operation are much longer than those for valve (safety mode) operation (approximately 140 seconds versus approximately 5 seconds). The test mode operation is not repeatable nor does it represent the safety mode of the valve. Also due to the design of the electrical circuitry, it is not possible to de-energize the solenoid valves and vent via the normal path without causing a reactor scram.

Alternate Testing: These valves will be full stroke exercised quarterly using the testing path. Valve stroke times wi 11 be measured whenever a reactor scram occurs using computer points and/or chart recorders, whereby stroke time obtained will represent normal valve operation.

III-3-6 January 1989

~ ~

RELIEF RE(VEST CRO-RR-3 System: Control Rod Drive Valve: 301-112:301-113 Category: A,C Class:

Function: Containment Isolation ASME Section XI guar ter ly Test Requirements: Verify reverse flow closure IWV-3522 quarterly IWV-3521 Basis For Relief: During al 1 modes of operation, the CRO pumps are normally inservice which discharges to the reactor vessel through these valves at a pressure above reactor pressure.

Al ternate Testing: These valves will have reverse flow closure verified during ASNE XI Leakage Testing at refueling.

e III-3-7 January 1989

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-18005-C SH.2 Pages III-4-1 through III-4-4 III-4-1 January 1989

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

31-01 1 AC 18 SEA DE FE-Q R CS-2 FE-C

¹11 FW Riser C-4 CHV LJ-R Isolation Check Valve 31-02 1 A,C 18 SEA DE Ff-Q CS-2 Ff-C

¹12 FW Riser C-4 CHV LJ-R Isolation Check Valve 31-07 1 18 MOA 0 FE-Q CS-1 FE-C

¹11 FW Isolation C-4 GTV ST-Q ST-C Valve LJ-R PE-Q PI-R 31-08 1 18 MOA 0 FE-Q CS-1 FE-C

¹12 FW Isolation C-4 GTV ST-Q ST-C Valve LJ-R PE-Q PI-R III-4-2 Jan ry 1989

0 COLD SHUTDOWN TEST JUSTIFICATION FW/HPCI-CS-1 System: FEEDWATER/HPCI Valve: 31-07:31-08 Category: A" Class:

Function: Feedwater I so 1 ation Va1 ves ASNE Section XI quarterly Test Requirements: Exercise and time Cold Shutdown Test

• Justification: Exercising these valves closed during normal operation would require; a significant reduction in power, isolating one loop of feedwater flow (which also constitutes entering an LCO on HPCI since it would be removing one of two redundant trains), introduces undesirable operational transients which could result in a reactor trip and introduces degrading feedwater nozzle temperature transients which could cause cracking. (Ref. NUREG 0619) quarterly Part Stroke Testing: Partial stroke close exercise.

Cold Shutdown Testing: Full stroke exercise and time.

III-4-3 January 1989

COLD SHUTDOWN TEST JUSTIFICATION FW/HPCI-CS-2 System: FEEDWATER/HPCI Valve: 31-01:31-02 Category: A,C Class:

Function: Feedwater Isolation Check Valves ASME Section XI quarterly Test Requirements: Verify reverse flow closure Cold Shutdown Test Justification: Exercising these valves closed during normal operation would require; a significant reduction in power, isolating one loop of feedwater flow (which also constitutes entering an LCO on HPCI since it would be removing one of two redundant trains), introduces undesirable operational transients which could result in a reactor trip and introduces degrading feedwater nozzle temperature transients which could cause cracking. (Ref. NUREG 0619)

Cold Shutdown Testing: Reverse flow testing wi 1 1 be performed during cold shutdowns by pressur izing across the valve with water. Reverse flow testing during refueling outages will be verified through Appendix J, type C testing.

III-4-4 January 1989

~ ~ C ~ M PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT 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 III-5-1 through III-5-13 III-5-1 January 1989

SYSTEM CORE SPRAY NINE MILE POINT UNIT 1 VALVE TfST 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.

40-01 1 A 12 MOA C FE-Q Core Spray Sys 8128 H-4 GTV ST-Q Inlet to Reactor PI-R Vessel LA-R 40-02 1 8 12 MOA FE-Q CRS 812 Inlet J-4 GTV ST-Q Outside IV PI-R 40-03 1 AC 12 SEA DE FE-Q RR-2 NOTE 3 CRS 812 Inlet K-4 CHV LK-R Outside Check Valve 40-05 1 A 6 MOA C FE-Q NOTE 3 Test IV 812 to Torus K-5 GTV ST-Q PI-R LK-R 40-06 1 A ~ 6 MOA C FE-Q NOTE 3 tl Test IV 1 to Torus C-5 GTV ST-Q P I-R LK-R 40-09 1 A 12 MOA C FE-Q Core Spray Sys 812 A H-3 GTV ST-Q Inlet to Reactor PI-R Vessel LA-R III-5-2 January 1989

SYSTEM CORE SPRAY NINE NILE 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 12 MOA FE-Q Core Spray Sys F-3 GTV ST-Q

¹ll A Inlet to PI-R LA-R Reactor Vessel 40-11 1 12 HOA FE-Q Core Spray Sys F-4 GTV ST-Q

¹ll 8 Inlet to PI-R LA-R Reactor Vessel 40-12 1 12 HOA FE-Q CRS ¹11 Inlet E-4 GTV ST-Q Outside IV P I-R 40-13 1 A,C 12 SEA DE FE-Q F,R RR-2 NOTE 3 Check Valve C-4 CHV LK-R 40-20 2 A,C 2 SEA DE FE-Q F,R RR-1 FE-R NOTE 1,3 1st Check ¹ll C-4 CHV LK-R Keep-fill System 40-21 1 A,C 2 SEA DE FE-Q F,R RR-1 FE-R NOTE 1,3 2nd Check Valve - C-4 CHV LK-R

¹11 Keep-f il 1 System 40-22 1 A,C 2 SEA DE FE-Q F,R RR-1 FE-R NOTE 1,3 2nd Check Valve - K-4 CHV LK-R

¹12 C.S. Keep-fill System 111-5-3 January 1989

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

40-23 2 A,C 2 SEA DE FE-Q F, R RR-1 FE-R NOTE 1,3 1st Check Valve K-4 CHV LK-R 812 C.S. Keep-fill System 40-30 1 1 MOA FE-Q Core Spray ll f-3 GLV ST-Q LJ-R Test IV PI-R 40-31 1 1 MOA FE-Q Core Spray 12 H-3 GLV ST-Q Test IV LJ-R PI-R 40-32 2 1 APA FE-Q Core Spray ll E-3 GLV ST-Q Test IV FS-Q LJ-R P I-R 40-33 2 1 APA FE-Q Core Spray 12 I-3 GLV ST-Q Test IV FS-Q LJ-R PI-R 81-07 2 12 SEA FE-Q F,R RR-2 Topping Pump 121 M-5 CHV Discharge Check Valve III-5-4 January 1989

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.

81-08 2 12 SEA DE FE-Q F,R RR-2 Topping Pump 122 M-5 CHV Discharge Check Valve 81-11 2 2 SEA DE RT-P NOTE 5 Loop f12 L-4 REV Discharge PSV 81-27 2 12 SEA DE FE-Q RR-2 Topping Pump ill A-5 CHV Discharge Check Valve 81-28 2 12 SEA DE FE-Q F,R RR-2 Topping Pump 112 A-5 CHV Discharge Check 4 Valve 5 81-31 2 2 SEA C RT-P NOTE 5 Loop Ill A-4 REV Discharge PSV 81-77 2 .75 SEA C RT-P Topping Pump PRV K-2 REV 81-78 2 .75 SEA C RT-P Topping Pump PRV K-2 REV 81-79 2 .75 SEA C RT-P Topping Pump PRV K-2 REV III-5-5 J uary 1989

i SYSTEM CORE SPRAY NINf MILf 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 Al T. REMARKS OWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

81-80 2 .75 SEA C RT-P Topping Pump PRV K-2 REV 93-58 2 A,C 12 SEA OE FE-Q F,R NOTE 2 Cont. Spray B-2 CHV MAA LJ-R 12" Testable Check Valve 93-64 2 A,C 12 Of FE-Q F,R NOTE 2 Cont. Spray M-2 CHV LJ-R 12" Testable Check Valve 93-71 2 - A 12 MOA C FE-Q Cont. Spray B-2 PGV ST-Q O,C 12" Flow Control PI-R Valve LJ-R 93-74 2 12 MOA C FE-Q Cont. Spray L-2 PGV ST-Q O,C 12" Flow Control PI-R Valve LJ-R 81-73 2 .75 SEA C RT-P Core Spray Pump B-7 REV ill Motor Cooler Relief Valve

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81-74 .75 SEA C RT-P Core Spray Pump B-8 REV 112 Motor Cooler Relief Valve III-5-6 January 1989

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.

81-75 2 .75 SEA C RT-P Core Spray Pump K-7 REV 121 Motor Cooler Relief Valve 81-76 2 .75 SEA C RT-P Core Spray Pump K-8 REV 122 Motor Cooler Relief Valve CRS-10 2 .75 SEA DE FE-Q F,R RR-4 FE-R C.S. Topping Pumps L-4 CHV

¹121 & ¹122 PSV Check Valve CS-C-3 2 .75 SEA DE FE-Q F,R RR-4 FE-R C.S. Topping Pumps A-4 CHV

¹lll & ¹112 PSV Check Valve CS-C-2 2 0.5 SEA DE FE-Q RR-3 NOTE 4 C.S. Topping Pumps J-1 CHV Seal Cooling & Lub Check Valve's CS-C-2 2 0.5 SEA DE FE-Q RR-3 NOTE 4 C.S. Topping Pumps J-1 CHV Seal Cooling & Lub Check Valve's CS-C-3 2 .75 SEA DE FE-Q NOTE 4 C.S. Topping Pumps J-1 CHV Seal Cooling & Lub Check V e's III-5-7 ary 1989

SYSTEM CORE SPRAY NINE MILE POINT UNIT 1 VALVE TEST TABLE

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D>JG. 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 DHG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

81-01 2 A . 14 MOA 0 FE-Q Core Spray Pump I-7 GTV ST-Q Suction Valve PI-R LA-R 81-02 2 14 MOA 0 FE-Q Core Spray Pump I-7 GTV ST-Q Suction Valve PI-R LA-R 81-21 2 14 MOA 0 FE-Q Core Spray Pump 0-7 GTV ST-Q Suction Valve PI-R LA-R 81-22 2 14 MOA 0 FE-Q Core Spray Pump D-7 GTV ST-Q Suction Valve PI-R LA-R III-5-8 January 1989

NOTES FOR ATTACHMENT 5 SYSTEM: CORE SPRAY NO. NOTE Forward flow opening is verified by a system check to verify water inventory (Core Spray keep fill system).

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Testable check valve, with manual exerciser.

(Opening the handwheel by torque measurement forces disk open, closing handwheel frees disk up for normal operation.)

Reference Technical Specification 4.2.7.1 for pressure isolation valve testing during refuel outages and cold shutdowns.

These valves are on each of the four Core Spray Topping Pumps and are provided for pump seal cooling and lubrication.

IST requirements satisfy INPO SER 26-88.

III-5-9 January 1989

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RELIEF REQUEST CS-RR-1 System: Core Spray Valve: 40-21:40-22:40-20:40-23 Category: A,C Class:

Function: Containment and Pressure Isolation Check Val ves (reverse flow closure for containment and pressure isolation only)

ASME Section XI Quarterly Test Requirements: Verify reverse flow closure !WV-3522 quarterly IWV-3521 Basis for Relief: The only method available to verify individual reverse flow closure is by valve leak testing during pressure i sol ation testing at refueling and during cold shutdowns.

Alternate Testing: Reverse flow closure will be verified individually for each valve during pressure isolation testing at ref uel ing and during cold shutdowns of at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless testing has been performed within the last 9 months. (Ref. Technical Specification 4.2.7.1). In addition, reverse flow closure of series check valves 40-20, 21 and series check valves 40-22, 23 will be performed quarterly in series.

III-5-10 January 1989

RELIEF REQUEST CS-RR-2 System: Core Spray Valve: 40-03:40-13:81-07:81-08:81-27:81-28 Category: A,C (40-03: 40-13)

C (81-07: 81-08: 81-27: 81-28)

Cl ass: 1 (40-03: 40-13) 2 (81-07: 81-08: 81-27: 81-28)

Function: Core Spray Inlet Check Valve (40-03, 40-13)

Core Spray Topping Pump Oischarge Check Valves (81-07, 81-08, 81-27, 81-28)

ASME Section XI Quarterly Test Requirements: Veri fy forward flow opening IWV-3522 Basis for Relief: These val ves are tested quarterly during the survei 1 1 ance tests of the core spray system pumps.

The val ves have no provi sion for determining di sk position. The required system flow rate is 3400 gpm.

In order to minimize system vibration the test flow rate is limited to approximately 2200 gpm by the size of the test line. From manufacturer's published information, valves 40 03 and 40 13 should be fully open at a flow rate of about 1600 gpm. Valves 81-07, 81-08, 81-27 and 81-28 should be fully open at a flow rate of about 2200 gpm. In addition, pressure readings are recorded during the test and compared to acceptance limits of subsection IWP.

Alternate Testing: As described above, the val ves are tested at close to full design flow r ate. At the test flow r ate, the val ve i s expected to be ful ly open. Pressure indications in the system are observed. In addition, full flow testing to the reactor vessel through these valves is performed every refueling.

III-5-11 January 1989

RELIEF REQUEST CS-RR-3 System: Core Spray Val ve: CS-C-2:CS-C-2:CS-C-3(Typical of 4)

Category:

Class:

Function: Provide Core Spray Topping Pump Seal Cooling and Lubrication ASNE Section XI Quarterly Test Requirements: Veri fy forward f ow 1 opening IWV-3522 Basis for Relief: These valves are integral to the Core Spray Topping Pumps and are tested quarterly during the pump surveillance tests. The valves have no provision for determining disc position.

Alternate Testing: As described above, the valves shal 1 be tested and observed at design flow rate and determined operable during pump testing.

III-5-12 January 1989

RELIEF REQUEST CS-RR-4 System: Core Spray Valve: CRS-10: CS-C-3 Category:

Class:

Function: Core Spray Topping Pumps Header Orain Line Valves ASHE Section XI Quarterly Test Requirements: Verify forward flow opening and reverse flow closure IWV-3522 quarterly IWV-3521 Basis for Relief: The only method avai 1 able to veri fy opening and closure of these val ves is by di sassembly and inspection.

Alternate Testing: Full flow exercising shall be verified individually for each valve by disassembly and inspection on an alternate basis during each refueling outage.

I I I-5-13 January 1989

0 PUMP ANO VALVE INSERVICE TESTING PROGRAM PLAN for NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.6 ATTACHMENT 6 VALVE TEST TABLES AND RELIEF RE(UESTS FOR EMERGENCY COOLING OWG. NO. C-18017-C Pages III-6-1 through III-6-9 III-6-1 January 1989

SYSTEM EMERGENCY COOLING NINE MILE POINT UNIT 1 VALVE TEST TABLE OWE NO. C-18017-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.05-01R 2 1 APA FE-Q Emerg. Cond. f-3 GLV ST-Q C,O Loop ¹11 Vent FS-Q C B.V. PI-R 05-02R 2 1 APA FE-Q Emerg. Cond. Vent G-1 GLV ST-Q IV ll to Main FS-Q PI-R Steam Line LJ-R 05-03R 2 1 APA FE-Q fmerg. Cond. Vent F-1 GLV ST-Q IV 12 to Main FS-Q Steam Line PI-R LJ-R 05-04R 2 1 APA FE-Q Emerg. Cond. H-3 GLV ST-Q C,O Loop ¹12 Vent FS-Q C B.V. PI-R 05-05 2 1.5 MOA FE-Q Emerg. Cond. Vent G-4 GLV ST-Q O,C to Torus B.V. ¹11 PI-R 05-07 2 1.5 MOA C . FE-Q Emerg. Cond. Vent G-5 GLV ST-Q O,C to Torus B.V. ¹12 P I-R III-6-2 January 1989

SYSTEM EMERGENCY COOLING NINE MILE POINT UNIT 1 VALVE TEST TABLE DMG. NO. C-18017-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.

05-11 2 1 APA 0 FE-Q Emerg. Cond. F-3 GLV ST-Q C,O Loop 811 Vent FS-Q C B.V. PI-R 05-12 2 1 APA 0 FE-Q Emerg. Cond. H-3 GLV ST-Q C,O Loop tl2 Vent FS-Q C B. V. PI-R 39-03 1 A,C 10 SEA DE FE-Q F,R RR-1 FE-R Note 2 Loop 811 Cond. F-8 CHV LJ-R Return Inlet Check 39-04 1 A,C 10 SEA DE FE-Q F,R RR-1 FE-R Note 2 Loop 8'12 Cond. H-8 CHV LJ-R Return Inlet Check 39-05 1 10 APA C FE-Q CS-1 FE-C Note 2 E-8 GLV ST-Q O,C ST-C Loop 811 Cond.

Return I.V. FS-Q 0 FS-C PI-R LJ-R 39-06 1 10 APA C FE-Q CS-1 FE-C Note 2 I-8 GLV ST-Q O,C ST-C Loop 812 Cond.

0 FS-C Return I.V. FS-Q PI-R LJ-R III-6-3 January 1989

SYSTEM EMERGENCY COOLING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18017-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VAI VE NUMBER AND (CAT. ) (IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST'ELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.39-07R 1 10 MOA FE-Q Loop 811 Steam F-6 GTV ST-Q O,C Outlet outside I.V. LJ-R (Emerg. Cond. Stm. PI-R I.V. 0112)39-08R 1 10 MOA 0, FE-Q Loop 812 Steam H-6 GTV ST-Q O,C Outlet Outside IV LJ-R (Emerg. Cond. Stm. PI-R I.V. 8122)39-09R 1 10 MOA FE-Q Loop 811 Steam F-6 GTV ST-Q O,C Outlet Inside IV LJ-R (fmerg. Cond. Stm. PI-R I.V. 8111)39-10R 1 10 MOA FE-Q Loop 812 Steam H-6 GTV ST-Q O,C Outlet Inside IV LJ-R (Emerg. Cond. Stm. PI-R I.V. 8121)39-11R 2 1 ADA FE-Q Loop 811 Stm. D-6 GTV ST-Q Line Drain 1st FS-Q I.V. P I-R LJ-R III-6-4 January 1989

SYSTEM EMERGENCY COOLING NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18017-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.39-12R 2 A 1 ADA FE-Q Loop 811 Stm. C-6 GTV ST-Q Line Drain 2nd FS-Q I.V. PI-R LJ-R 39-13R 2 1 ADA FE-Q Loop f12 Stm. J-6 GTV ST-Q Line Drain 1st FS-Q I.V. PI-R LJ-R 39-14R 2 1 ADA FE-Q Loop 812 Stm. K-6 GTV ST-Q Line Drain 2nd FS-Q I. V. PI-R LJ-R 60-03 3 4 ADA FE-Q Line from Cond. K-1 GLV ST-Q O,C Trans. Pump to FS-Q C Emer. Cond. M.U. PI-R Tank 812 60-04 3 4 ADA 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 Ill 60-05 3 4 SEA DE FE-Q Check Valve on B-1 CHV Cond. Supply to FCMU Tank 811 III-6-5 January 1989

SYSTEM EMERGENCY COOLING NINE MILE POINT UNIT 1 VALVE TfST TABLE DWG. NO. C-18017-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TfST 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. RfQ. NO. PERF.

60-06 3 4 SEA DE FE-Q Check Valve on L-1 CHV Cond. Supply to ECMU Tank 812 60-13 3 4 ADA 0 FE-Q Tie Valve Between I-3 GLV ST-Q Emerg. Cond. M.U. FS-Q Tanks P I-R 60-17 3 4 ADA DE FS-Q NOTE 1 fmerg. Cond. 0-3 GLV P I-R 111-112 Level Control Valve 60-18 3 4 ADA DE FS-Q NOTE 1 Emerg. Cond. J-3 GLV P I-R 121-122 Level Control Valve III-6-6 January 1989

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• NOTES FOR ATTACHMENT 6 SYSTEM: EMERGENCY COOLING NO. NOTE Level control valve to maintain emergency condenser water level.

These valves are currently under a schedular exemption from leakage testing (Appendix J, lOCFR50) this outage. They will be Type C tested next outage (1991) prior to startup.

III-6-7 January 1989 0

COLD SHUTDOWN TEST JUSTIFICATION EC-CS-1 System: Emergency Cooling Valve: 39-05:39-06 Category:

Class:

Function: Emergency Cooling System discharge to Reactor Recirculation System air operated blocking valves ASME Section XI Quarterly Test Requirements: Exercise, time and fail safe test Cold Shutdown Test Justification: Operation (opening) of these valves during power operations would place the system into service, resulting in a slug of cold water being delivered to the reactor primary system. The cold water injection would result in a neutron spike and corresponding increase in the Average Power Range Monitors (APRM).

Depending on the initial plant condition, a reactor scram could occur.

a Quarterly Part Stroke Testing: Partial exercising of these valves could sequence of events.

pose the same Cold Shutdown Testing: Valves will be exercised, timed and fail safe tested at cold shutdowns when the reactor temperature is low and the potential problems associated with cold water injection are minimized.

III-6-8 January 1989

RELIEF REQUEST EC-RR-1 Emergency Cooling Valve: 39-03:39-04 Category: A,C Class:

Function: Containment I so 1 at i on ASNE Section XI Quarterly Test Requirements: Verify forward flow opening IWV-3522 quarterly IWV-3521 Basis for Relief: To verify forward flow operabi 1 ity would r equi re 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 being shut down under emergency conditions and initiation during normal operation would result in shutting the plant down. The Emergency Cooling System e is only placed in service for testing once every five years. The test frequency is limited to once every five years in an attempt to limit the fatigue (thermal and hydraulic) on the system which is experienced during these tests.

Alternate Testing: Ful 1 flow exerci sing shal 1 be veri f i ed indi vidual ly for each val ve by di sassemb ly and inspecti on on an alternate basis during each refueling outage starting next refuel outage (1991).

III-6-9 January 1989

PUMP ANO VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.7 ATTACHMENT 7 VALVE TEST TABLES ANO RELIEF RE(VEST FOR REACTOR SHUTOOWN COOLING OWG. NO. C-18018-C Pages III-7-1 through III-7-4 III-7-1 January 1989

REACTOR SHUTDOWN COOLING L'YSTEM NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18018-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) ( IN. ) TYPE POSIT. Rf Q. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

38-01 1 14 MOA C FE-Q CS-1 FE-C Note 1 SC Outlet Inside M-5 GTV ST-Q ST-C Isolation Valve PI-R LC-R 38-02 1 14 MOA C FE-Q CS-1 FE-C Note 1 SC Outlet Outside L-5 GTV ST-Q ST-C Isolation Valve PI-R LC-R 38-12 1 A,C 14 SEA DE FE-Q CS-1 FE-C Note 1 SC Inlet Outside B-5 CHV LC-R Isolation Check Valve 38-13 1 14 MOA FE-Q CS-1 FE-C Note 1 SC Inlet Inside A-5 GTV ST-Q ST-C Isolation Valve PI-R LC-R

NOTES FOR ATTACHMENT 7 SYSTEM: REACTOR SHUTDOWN COOLING NO. NOTE These valves are presently pressure isolation valves. They are being reclassified as containment isolation valves. A schedular exemption for leakage rate testing of these valves in accordance with Appendix J, 10CFR50 has been requested for this outage. When approved, the test requirement wi 11 be changed to LJ for Appendix J, 10CFR50 testing versus LC for both Appendix J, 10CFR50 and pressure isolation valve testing. They will be Type C tested next outage (1991) prior to startup.

III-7-3 January 1989

COLD SHUTDOWN TEST JUSTIFICATION RSC-CS-1 System: Reactor Shutdown Cooling Valve: 38-01: 38-02: 38-13: 38-12 Category: A (38-01: 38-02: 38-13)

A, C (38-12)

Class:

Function: Isolation Valves ASME Section XI quarterly Test Exercise and time (38-01: 38-02: 38-13)

Requirements: Verify reverse flow closure (38-12)

Cold Shutdown Test Justification: The Reactor Shutdown Cooling System i s designed to cool reactor coolant below temper atures and pressures at which the main condenser may be used as a heat sink. The motor operated gate valves which normally function (cycle) at a service temperature of approximately 350'F and pressure of less than 120 psig (designed interlocks) were not designed to cycle at the higher differential pressure that would be experience if cycled at full power.

Sequenced with the motor operated valve (38-13) stroking, the reverse flow closure verification on check valve 38-12 shall be performed.

quarterly Part Stroke Testing: None Cold Shutdown Testing: Full stroke exercise and time.

Verify reverse flow closure.

III-7-4 January 1989

0 PUMP ANO VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III

5. 8 ATTACHMENT 8 VALVE TEST TABLES AND REI IEF REQUESTS FOR CONTAINMENT SPRAY OWG. NO. C-18012-C SH.1 C-18012-C SH.2 Pages III-8-1 through III-8-12 III-8-1 January 1989

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SYSTE NTAINMENT SPRAY NINE E POINT UNIT 1 VALVE TES 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.

80-05 2 12 SEA DE FE-Q F RR-2 8121 CTN-SP Pump C-9 CHV Discharge Check Valve 80-06 2 12 SEA DE FE-Q 8111 CTN-SP Pump C-7 CHV Discharge Check Valve 80-114 2 4 MOA C FE-Q C.S. to Radwaste L-4 PGV ST-Q I.V. LJ-R PI-R 80-115 2 4 MOA C FE-Q Cont. Spray to L-3 PGV ST-Q Rad. Waste I.V. LJ-R PI-R 80-118 2 6 MOA C FE-Q C.S. Test Line J-6 GLV ST-Q to Torus FCV PI-R III-8-2 January 1989

SYSTEM CONTAINMENT SPRAY NINE E POINT UNIT 1 VALVE TEST f 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.

80-15 2 12 APA 0 FE-Q NOTE 1 f12 CTN-SP Inlet D-3 GTV ST-Q O,C to Drywell FS-Q 0 PI-R 80-16 2 12 APA 0 FE-Q NOTE 1 Pill CTN-SP HT D-4 GTV ST-Q O,C Exch. Inlet IV FS-Q 0 PI-R 80-17 2 12 SEA DE FE-Q RR-1 Pf-R 812 CTN-SP Loop F-3 CHV Check Valve to Drywell Sparger 80-18 2 12 SEA DE FE-Q RR-1 PE-R fill Check CTN-SP Loop Valve to F-4 CHV Drywell Sparger 80-19 2 3 SEA DE FE-Q RR-1 PE-R 8112 CTN-SP Loop I-4 CHV Check Valve to Torus Sparger III-8-3 January 1989

SYSTEM ONTAINMENT SPRAY NINE E POINT UNIT 1 VALVE TEST E 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.

80-25 2 12 SEA DE FE-Q F RR-2 3I'122 CTN-SP Pump K-9 CHV Discharge Check Valve 80-26 2 12 SEA OE ff-Q RR-2 8112 CTN-SP Pump K-7 CHV Discharge Check Valve 80-35 2 12 APA 0 FE-Q NOTE 1 8122 CTN-SP Inlet I-3 GTV ST-Q O,C I.V. to Orywell FS-Q 0 Sparger PI-R 80-36 2 12 APA 0 FE-Q NOTE 1 8112 CTN-SP Inlet I-4 GTV ST-Q O,C I.V. to Drywell FS-Q 0 Sparger PI-R 80-37 2 12 SEA DE FE-Q RR-1 PE-R 8122 CTN-SP Loop H-3 CHV Check Valve to Orywell 80-38 2 12 SEA DE FE-Q RR-1 PE-R 8112 CTN-SP Loop H-4 CHV Check Valve to Drywell Sparger III-8-4 January 1989

SYSTEM ONTAINMENT SPRAY NINE E POINT UNIT 1 VALVE TEST E 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.

80-39 2 3 SEA DE FE-Q F RR-1 PE-R till CTN-SP Valve Loop to E-5 CHV Check Torus Sparger 80-40 2 6 APA C FE-Q Bypass to Torus D-4 GTV ST-Q C,O for Loop till FS-Q PI-R C

80-41 2 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 6 APA C FE-Q Bypass to Torus J-4 GTV ST-Q C,O for Loop 8112 FS-Q C PI-R 80-45 2 6 APA C FE-Q Bypass to Torus J-3 GTV ST-Q C,O for .Loop 8122 FS-Q C PI-R 80-65 2 3 SEA DE FE-Q RR-1 PE-R 812 Cont. Spray F-5 CHV Strainer Outlet Check to Torus 80-66 2 3 SEA DE FE-Q RR-1 PE-R f121 CTN-SP Loop E-3 CHV Check Valve to Torus Sparger III-8-5 January 1989

SYSTEM CONTAINMENT SPRAY NINE E POINT UNIT 1 VALVE TEST E 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 R EL IEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

80-67 2 3 SEA DE FE-Q F RR-1 PE-R ifll Cont. Spray H-5 CHV Strainer Outlet Check to Torus 80-68 2 3 SEA DE FE-Q RR-1 PE-R 8122 CTN-SP Loop I-3 CHV Check Valve to Torus 93-60 2 A,C 12 SEA DE FE-Q Note 2 Testable Check L-2 CHV MAA LJ-R Vl v. on Raw Water Tie in from Raw Water Loop k'112 93-62 2 A,C 12 SEA DE FE-Q F,R Note 2 Testable Check 8-3 CHV MAA LJ-R Vlv. in Tie in from Raw Water Loop 8121 93-72 2 12 MOA C FE-Q FCV on Raw Water K-2 PGV ST-Q O,C Tie in from Raw PI-R Water Loop 8112 LJ-R 93-73 2 12 MOA C FE-Q FCV on Raw Water C-3 PGV ST-Q O,C Tie in from Raw PI-R Water Loop 8121 LJ-R III-8-6 January 1989

SYST CONTAINMENT SPRAY NI ILE POINT UNIT 1 VALVE TES BLE DWG. NO. C-18012-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.

93-09 3 12 SEA DE FE-Q 8121 CTN-SP Raw B-7 CHV Water Pump Discharge Ck. Valve 93-10 3 12 SEA FE-Q 8111 CTN-SP Raw D-7 CHV Water Pump Discharge Ck. Valve 93-11 3 12 SEA DE FE-Q 8122 CTN-SP Raw H-7 CHV Water Pump Discharge Check Valve 93-12 3 12 SEA DE FE-Q 8112 CTN-SP Raw f-7 CHV Water Pump Discharge Check Valve 93-25 3 12 MOA FE-Q 8111 Cont. Spray C-4 GTV 0 ST-Q O,C Heat Exch. Raw P I-R Water Discharge to Tunnel 93-26 3 12 MOA Ff-Q 8121 CTN-SP Heat A-4 GTV 0 ST-Q O,C Exch. Raw Water PI-R Discharge to Tunnel III-8-7 January 1989

4 l

SYSTEM CONTAINMENT SPRAY NIN MILE POINT UNIT 1 VALVE TES ABLE DWG. NO. C-18012-C SH. 1 C.S C.S CLASS VAI VE 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.

93-27 3 12 MOA FE-Q

¹122 Cont. Spray F-4 GTV 0 ST-Q O,C RW Oisch. to PI-R Tunnel 93-28 3 12 MOA FE-Q

¹122 Cont. Spray E-4 GTV 0 ST-Q O,C Ht. Exch. RW PI-R Discharge to Tunnel 93-57 3 12 SEA DE FE-Q Disch. Testable 0-6 CHV Ck. Vlv. RW Pump

¹lll 93-63 3 12 SEA OE FE-Q Disch. Testable H-5 CHV Ck. Vlv. RW Pump

¹122 93-59 3 12 SEA DE FE-Q Di sch. Testable E-5 CHV Ck. Vlv. RW Pump

¹112 93-61 3 12 SEA DE FE-Q Oisch. Testable B-6 CHV Ck. Vlv. RW Pump

¹121 80-102A 2 0.5 SEA C RT-P CTN SP Pump Motor K-4 REL Cooler Relief Valve III-8-8 January 1989

pi J 17.

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SY CONTAINMENT SPRAY RILE POINT UNIT 1 VALVE T ABLE DWG. NO-. C-18012-C SH. 1 C.S C.S CLASS VALVE S IZE 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.

80-102B 2 0.5 SEA C RT-P CTN SP Pump Motor K-4 REL Cooler Relief Val ve 80-102C 2 0.5 SEA C RT-P CTN SP Pump Motor K-4 REL Cooler Relief Val ve 80-1020 2 0.5 SEA C RT-P CTN SP Pump Motor K-4 REL Cooler Relief Val ve 80-01 2 12 MOA FE-Q CTN SP Pump F-7 GTV ST-Q Suction Valve PI-R LA-R 80-02 2 12 MOA FE-Q CTN SP Pump F-9 GTV ST-Q Suction Valve PI-R LA-R 80-21 2 12 MOA FE-Q CTN SP Pump H-7 GTV ST-Q Suction Valve PI-R LA-R 80-22 2 12 MOA FE-Q CTN SP Pump H-9 GTV ST-Q Suction Valve PI-R LA-R III-8-9 January 1989

NOTES FOR ATTACHMENT 8 SYSTEM: CONTAINMENT SPRAY No. NOTE Valves 80-15: 80-16: 80-35: 80-36 fail open on loss of electrical power but fail as is on loss of air. These val ves are normal ly open during pl ant operation and only closed for surveillance testing, torus cooling, or maintenance operations. Hecause these functions only isolate one loop at any one time and leave the other three loops available for service, these valves will be tested to fail to the proper position on loss of electrical power only. The fail as is on loss of air is not a safety related function and will not be tested.

Testable check valve, with manual exerciser. (Opening the handwheel by torque measurement forces disk open, closing handwheel frees disk up for normal operation.)

III-8-10 January 1989

RELIEF RE(}VEST CTS-RR-1 System: Containment Spr ay Valve: 80-17:80-18:80-19:80-37:80-38:80-39:80-65:80-66:

80-67:80-68 Category:

Cl ass Function: Containment Spray System Check Valves ASME Section XI quarterly Test Requirements: Verify forward flow opening IWV-3522 quarterly IWV-3521 Basis for Relief: Verification of forward flow operability would, require spraying torus water into the containment. This would result in damage to equipment located inside the containment. Disassembly of the valves for inspection of integrity is not feasible since the valves are welded in place and no removable valve Bonnett/Inspection cover exists. In addition, the valves are designed with stationary hinge pins such that external observation during exercising or attachment of external exerciser is not feasible.

Alternate Testing: Permanently installed compressed air test lines have been included in the system design. These compressed air lines are used to partially exercise these check valves as well as verify 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 witness testing.

The air flow test wi 11 be used until a permanent plant modification (1991) to permit full exercising is completed.

I II-8-11 January 1989

RELIEF REQUEST CTS-RR-2 System: Containment Spray Valve: 80-05: 80-06: 80-25: 80-26 Category:

Class Function: Containment Spray Pump Discharge Check Valves ASNE Section XI Quarterly Test Requirements: Verify forward flow opening IWV-3522 8asis for Relief: These valves are tested quarterly during the surveillance tests of the containment spray pumps. The valves have no provision for determining disk position. The required system flow rate is 3000 gpm. The test flow rate is limited to approximately 2900 gpm by the size of the test line. From manufacturers published information, these valves should be fully open at a flow rate of about 2200 gpm.

Alternate Testing: As described above, the valves are tested at close to full design flow r ate. At the test flow rate the valve is expected to be fully open.

III-8-12 January 1989

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PUMP ANO VALVE INSERV ICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.9 ATTACHMENT 9 YAI VE TEST TABLES AND RELIEF REQUESTS FOR REACTOR CLEAN-UP OWG. NO. C-18009-C SH.1 Pages III-9-1 through III-9-4 III-9-1 January 1989

SYSTEM RCU NINE MILE POINT UNIT 1 VALVE TEST TABLE DHG. NO. C-18009-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.

33-01 1 6 MOA 0 FE-Q CU Return D-1 GTV ST-Q Isolation Valve LJ-R (Inside) PI-R 33-02 1 6 MOA 0 FE-Q CU Supply A-2 GTV ST-Q Isolation Valve LJ-R ll (Inside) PI-R 33-03 1 A,C 6 SEA DE FE-Q RR-1 FE-R CU Return D-l CHV LJ-R Isolation Valve (outside) 33-04 1 6 MOA 0 FE-Q Cu Supply A-2 GTV ST-Q Isolation Valve LJ-R 12 (outside) PI-R 63-04 2 2 APA C FE-Q Post Acc. Sample K-2 GLV ST-Q Line Return IV FS-Q PI-R LJ-R III-9-2 January 1989

0 SYSTEM RCU NINE MILE POINT UNIT 1 VALVE TEST TABLE DHG. NO. C-18009-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.

63-05 2 2 APA C FE-Q Post Acc. Sample K-2 GLV ST-Q Line Return IV FS-Q PI-R LJ-R 63.2-01 2 A,C .75 SEA C FE-Q F,R Torus Sample M-3 CHV LJ-R Vacuum Breaker 63.2-02 2 A,C .75 SEA C FE-Q Torus Sample M-3 CHV LJ-R Vacuum Breaker III-9-3 January 1989

RELIEF REQUEST RCU-RR-1 System: Reactor Clean-Up Valve: 33-03 Category: A,C Class:

Function: Containment Isolation Check Valve (reverse flow closure for containment isolation only)

ASHE Section XI Quarterly Test Requirements: Verify reverse flow closure IWV-3522 quarterly IWV-3521 Basis for Relief: Thi s check val ve i s on the cleanup return to reactor line and located in a relatively high radiation area (100-150 mR/hr at contact to val ve, 100-500 mR/hr general area). In order to adequately reverse flow test, this valve would require pressurizing the down stream side of the valve using a hydro pump set-up.

This procedure would generally take 1-2 hours to perform using a minimum of 3, possibly 4 technicians.

Potential exposures could be as high as 1000 mR total dose received each time the test is performed which is in conflict with the NMPC ALARA Program. In addition, opening the drain valve downstream of this check valve introduces a personnel safety concern with the reactor at pressure since there exists only 1 valve boundary from reactor coolant. Reverse flow testing at refueling is performed with this line drained which consequently makes the test much shorter. (This test i s performed by Appendix J, Type C testing using simple air leak rate monitors.) In addition, testing thi s val ve during col d shutdowns would requi re the removal of the Cleanup system from service which is undesirable since reactor water chemistry is adversely affected from the scram and cleanup is normally inservice to return water quality to normal. Testing this valve quarterly or during cold shutdowns is therefore extremely undesirable.

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

III-9-4 January 1989

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

5. 10 ATTACHMENT 10 VALVE TEST TABLES AND RELIEF REQUESTS FOR INERT GAS PURGE AND FILL DWG. NO. C-18014-C SH.l Pages III-10-1 through III-10-6 I I I-10-1 January 1989

SYh INERT GAS PURGE AND FILL NINE MILE POINT UNIT 1 VALVE EST TABLE DWG. NO. C-18014-C SH. 1 C.S C.S CLASS VALVE SIZE ACTO. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT. ) ( IN- ) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TfST COOR. TYPE DIRECT- REQ. NO. PERF.

201-07 2 A 20 MOA FE-Q Torus Air Vent & B-8 BFV ST-Q Purge I.V. 812 LJ-R P I-R 201-08 2 20 APA Ff-Q Torus Air Vent E B-8 BFV ST-Q Purge I.V,. 811 FS-Q LJ-R PI-R 201-09 2 24 MOA FE-Q Drywell Air Vent B-6 BFV ST-Q E Purge I.V. 812 LJ-R PI-R 201-10 2 24 APA FE-Q Drywell Air Vent C-7 BFV ST-Q 5 Purge I.V. 811 FS-Q LJ-R P I-R 201-16 2 20 APA FE-Q Torus N2 Vent K-7 BFV ST-Q 8 Purge Inside I.V. FS-Q LJ-R PI-R III-10-2 January 1989

SYS NERT GAS PURGE AND FILL NINE MILE POINT UNIT 1 VALVE TEE BLE DWG. NO. C-18014-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.

201-17 2 A 20 MOA FE-Q Torus N2 Vent L-7 BFV ST-Q 8 Purge Outside I.V. LJ-R PI-R 201-18 3 12 APA FE-Q fmerg. Vent from L-2 BFV ST-Q Drywell 8 Torus B.V. FS-Q PI-R 201-31 2 24 MOA FE-Q Drywell N2 Vent J-2 BFV ST-Q 5 Purge Outside I.V. LJ-R PI-R 201-32 2 24 APA FE-Q Drywell N2 Vent I-2 BFV ST-Q 8 Purge Inside I.V. FS-Q LJ-R PI-R 201.1-09 2 1 NPA FE-Q Post Loca AOV I-3 GLV ST-Q O,C Inside I.V. FS-Q C LJ-R PI-R III-10-3 January 1989

SY NERT GAS PURGE AND FILL NINE MILE POINT UNIT 1 VALVE TE BLE DWG. NO. C-18014-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.

201. 1-11 2 A 1 NPA FE-Q Post Loca AOV J-3 GLV ST-Q O,C Outside I.V. FS-Q C t LJ-R PI-R 201. 1-14 2 1 APA FE-Q Post Loca Vent E-2 GLV ST-Q O,C AOV Inside I.V. FS-Q C LJ-R PI-R 201. 1-16 2 1 APA C FE-Q Post Loca Vent D-2 GLV ST-Q O,C AOV Outside I.V. FS-Q C LJ-R PI-R 201.2-02 2 1 ADA FE-Q Drywell N2 I-4 GLV ST-Q O,C Bl eed B.V. FS-Q C PI-R 201.2-03 2 4 ADA ff-Q Drywel 1 N2 I-3 GLV ST-Q C,O Makeup 5 Bleed FS-Q C Outside I.V. LJ-R PI-R 201.2-04 2 1 ADA C FE-Q Torus N2 I-6 GLV ST-Q O,C Makeup B.V. FS-Q C PI-R III-10-4 January 1989

SYS INERT GAS PURGE AND FILL NINE MILE POINT UNIT 1 VALVE TE ABLE DWG. NO. C-18014-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.

201.2-06 2 A 3 NDA FE-Q Torus N2 I-6 GLV ST-Q C,O Makeup E Bleed FS-Q C Outside I.V. LJ-R PI-R 201 . 2-136 3 3 APA FE-Q Reactor Bldg. L-3 PGV ST-Q Emerg. Vent B.V. FS-Q PI-R 201.2-32 2 4 ADA FE-Q Drywell N2 I-2 GLV ST-Q C,O Makeup L Bleed FS-Q C Inside I.V. LJ-R PI-R 201.2-33 2 3 NDA Ff-Q Torus N2 I-7 GLV ST-Q C,O Makeup 5 Bleed FS-Q C Inside I.V. LJ-R PI-R 201.9-46 2 1.5 APA FE-Q Nitrogen B.V. to H-4 GTV ST-Q C,O Torus FS-Q C PI-R 201.9-47 2 1.5 NPA FE-Q N2 B.V. to H-5 GTV ST-Q C,O Drywell FS-Q C PI-R III-10-5 January 1989

SYST ERT GAS PURGE AND FILL INE MILE POINT UNIT 1 VALVE TES LE DWG. NO. C-18014-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 DHG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

201.2-531 3 4 ADA 0 FS-Q Emerg. Vent J-3 GLV Sys. PCV's 201.2-532 3 ADA 0 FS-Q fmerg. Vent 0-2 GLV Sys. PCV's 201.2-05 3 3 ADA C FE-Q N2 Supply I-6 GLV ST-Q Valve FS-Q PI-R 201.2-08 3 4 ADA C FE-Q N2 Supply J-6 GLV ST-Q Valve FS-Q PI-R III-10-6 January 1989

11 4 ~ 1 '" I ~ ' 0 ~ '

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION I II 5.11 ATTACHMENT 11 VALVE TEST TABLES AND RELIEF REQUESTS FOR HYDROGEN-OXYGEN MONITORING DWG. NO. C-18014-C SH.2 C-26939-C C-26949-C Pages III-11-1 through III-11-9 III-ll-lJanuary 1989

SYST ROGEN-OXYGEN MONITORING E MILE POINT UNIT 1 VALVE TEST E DWG. NO. C-18014-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.

201.2-109 2 .75 ADA Ff-Q H202 Sys. 811 C-7 GLV ST-Q O,C Return to Torus FS-Q C Inside I.V. LJ-R PI-R 201.2-110 2 .75 ADA FE-Q H202 Sys. Ill C-6 GLV ST-Q FS-Q O,C Torus Sample C Inside I.V. LJ-R PI-R 201.2-111 2 .75 ADA FE-Q H202 Sys. Oil C-7 GLV ST-Q O,C Torus Sample FS-Q C Outside I.V. LJ-R PI-R 201.2-112 2 .75 ADA FE-Q H202 Sys. 5'll 8-7 GLV ST-Q O,C Return to Torus FS-Q C Outside I.V. LJ-R PI-R 201.2-23 2 0.5 SOA f E-Q H202 Sys. 812 H-8 GLV ST-Q O,C Torus Sample FS-Q C Inside I.V. LJ-R P I-R 201.2-24 2 0.5 SOA FE-Q H202 Sys. 812 H-7 GLV ST-Q O,C Torus Sample FS-Q C Outside I.V. LJ-R PI-R III-11-2 January 1989

0 0

SYST ROGEN-OXYGEN MONITORING IE MILE POINT UNIT 1 VALVE TEST E DHG. NO. C-18014-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.

201.2-25 2 0.5 SOA FE-Q H202 Sys. 812 G-7 GLV ST-Q O,C Drywell Sample FS-Q C Inside I.V. LJ-R PI-R 201.2-26 2 0.5 SOA 0 FE-Q H202 Sys. 812 H-7 GLV ST-Q O,C Drywell Sample FS-Q C Outside I.V. LJ-R PI-R 201.2-27 2 0.5 SOA FE-Q H202 Sys. 812 G-6 GLV ST-Q O,C Drywell Sample FS-Q C Inside I.V. LJ-R P I-R 201.2-28 2 0.5 SOA FE-Q H202 Sys. 812 H-6 GLV ST-Q O,C Drywell Sample FS-Q C Outside I.V. LJ-R PI-R 201.2-29 2 0.5 SOA FE-Q H202 812 G-6 GLV ST-Q O,C Drywell Sample FS-Q C Inside I.V. LJ-R PI-R 201.2-30 2 0.5 SOA 0 FE-Q H202 812 H-6 GLV ST-Q O,C Drywell Sample FS-Q C Outside I.V. LJ-R P I-R III-11-3 January 1989

SYST ROGE N-OXYGEN MONITORING lE NILE POINT UNIT 1 VALVE TEST E DWG. NO. C-18014-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.

201.2-67 2 A,C .75 SEA Df ff-Q F,R H202 Sys. dl2 H-7 CHV LJ-R Sample Return to Drywell IN I.V.

201.2-68 2 A,C .75 SEA DE FE-Q F,R H202 Sys. 812 I-7 CHV LJ-R Sample Return to Drywell OUT I.V.

201.2-70 2 A,C ,75 SEA DE FE-Q F,R H202 Sys. 812 J-8 CHV LJ-R Sample Return to Torus Inside I.V.

201.2-71 2 A,C .75 SEA DE FE-Q F,R H202 Sys. 812 J-8 CHV LJ-R Sample Return to Torus Outside I.V.

201.7-01 2 1 ADA 0 FE-Q H202 Sys. Ill E-4 GLV ST-Q O,C Sample Stream B FS-Q C Inside I.V. LJ-R PI-R 201.7-02 2 1 ADA 0 FE-Q H202 Sys. 811 D 4 GLV ST-Q O,C Sample Stream B FS-Q C Outside I.V. LJ-R PI-R III-11-4 January 1989

SYST ROGE N-OXYGEN MONITORING E MILE POINT UNIT 1 VALVE TES E DMG. NO. C-18014-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.

201.7-03 2 1 ADA FE-Q H202 Sys. Ill E-5 GLV ST-Q O,C Drywell Sample FS-Q C Stream A Inside I.V. LJ-R PI-R 201.7-04 2 1 ADA FE-Q H202 Sys. 811 D-5 GLV ST-Q O,C Drywell Sample FS-Q C Stream A Outside I.V. LJ-R PI-R 201.7-08 2 1 ADA FE-Q Drywell Cam G-4 GLV ST-Q O,C Sample Line Inside FS-Q C I.V. LJ-R PI-R 201.7-09 2 1 ADA FE-Q Drywe1 1 Cam H-4 GLV ST-Q O,C Sample Line Outside FS-Q C I.V. LJ-R PI-R 201.7-10 2 1 ADA FE-Q H202 Sys. 811 G-5 GLV ST-Q O,C Return to Drywell FS-Q C Inside I.V. LJ-R PI-R 201.7-11 2 1 ADA 0 Ff-Q H202 Sys. Ill H-5 GLV ST-Q O,C Return to Drywell FS-Q C Outside I.V. LJ-R PI-R III-11-5 January 1989

SYST ROGEN-OXYGEN MONITORING NE MILE POINT UNIT 1 VALVE TES E DMG. NO. C-26939-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.

201.2-251 3 0.5 ADA C FE-Q H202 812 B-l BLV ST-Q O,C Stream FS-Q 0 B.V.

'A'ample 201.2-252 3 0.5 ADA C FE-Q H202 812 B-2 BLV ST-Q O,C Stream FS-Q 0 B.V.

'B'ample 201.2-253 3 0.5 ADA C FE-Q H202 f12 B-3 BLV ST-Q O,C Stream FS-Q 0 B.V.

'C'ample 201.2-254 3 0.5 ADA C FE-Q H202 812 B-4 BLV ST-Q O,C Stream FS-Q 0 B.V.

'D'ample 201.2-282 3 0.5 ADA 0 FE-Q H202 H-4 GLV ST-Q 812 B.V FS-Q I I I-11-6 January 1989

SY HYDROGEN-OXYGEN MONITOR ING INE I'lILE POINT UNIT 1 VALVE T BLE DWG. NO. C-26939-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUNBER AND (CAT.) ( IN.) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

201.2-283 3 .25 ADA C FE-Q H20( ¹12 H-4 GLV ST-Q Caleb. FS-Q Gas Supply B.V.

201.2-305 3 0.5 SEA DE FE-Q H202 ¹12 L-4 CHV Ret. Check Valve 201. 2-413 3 0' ADA C FE-Q H202 ¹12 Sample L-4 TWV ST-Q O,C Return to Cont. FS-Q C III-11-7 January 1989

SY YDROGEN-OXYGEN MONITORING NINE MILE POINT UNIT 1 VALVE T BLE DWG. NO. C-26949-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 DHG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

201.2-141 3 0.5 ADA C FE-Q H202 ¹11 B-1 BLV ST-Q O,C Stream FS-Q 0 B.V.

'A'ample 201. 2-142 3 0.5 ADA C FE-Q H202 ¹ll B-2 BLV ST-Q FS-Q O,C 0

Stream B.V.

'B'ample 201.2-143 3 0.5 ADA C FE-Q H202 ¹ll B-3 BLV ST-Q FS-Q O,C 0

Stream B.V.

'C'ample 201.2-169 3 0.5 ADA 0 FE-Q H202 ¹11 H-4 GLV ST-Q B.V. FS-Q 201.2-170 3 .25 ADA C FE-Q H20( ¹11 H-4 GLV ST-Q Caleb. Gas FS-Q Supply B.V.

201. 2-192 3 0.5 SEA DE FE-Q H202 ¹11 L-4 CHV Ret. Check Valve I II-11-8 January 1989

SYSTE OGEN-OXYGEN MONITORING E MILE POINT UNIT 1 VALVE TEST DWG. NO. C-26949-C C.S C.S CLASS VAI VE 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.

201.2-414 3 0.5 ADA C FE-Q H202 811 Sample L-4 TWV ST-Q O,C Return to Cont. FS-Q C I I I-11-9 January 1989

0 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-12-4 I I I-12-1 January 1989

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

201.2-39 2 A,C .75 SEA DE FE-Q N2 Purge TIP H-2 CHV LJ-R Indexers 5563 201.2-40 2 A,C .75 SEA DE FE-Q N2 Pur ge TIP G-2 CHV LJ-R Indexers 5563 TIP-1 (BALL) 2 0.5 SOA FE-Q NOTE 1 fl Tip Machine F-3 BLV ST-Q Drive E Control FS-Q LJ-R TIP-2 (BALL) 2 0.5 SOA FE-Q NOTE 1 f2 Tip Machine F-3 BLV ST-Q Dri ve E Control FS-Q LJ-R TIP-3 (BALL) 2 0.5 SOA f E-Q NOTE 1 83 Tip Machine F-3 BLV ST-Q Drive 5 Control FS-Q LJ-R TIP-4 (BALL) 2 0.5 SOA FE-Q NOTE 1 84 Tip Machine F-3 BLV ST-Q C Drive 8 Control FS-Q C LJ-R III-12-2 January 1989

0 SYSTEM TIP NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-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.

TIP-1 (SHEAR) 2 D 0.5 EXA 0 EX-P NOTE 1,2 F-3 EXV TIP-2 (SHEAR) 2 ~

D 0.5 EXA 0 EX-P NOTE 1,2 F-3 EXV TIP-3 (SHEAR) 2 0.5 EXA 0 EX-P NOTE 1,2 F-3 EXV TIP-4 (SHEAR) 2 0.5 EXA 0 EX-P F-3 EXV NOTE 1,2 III-12-3 January 1989

-0 NOTES FOR ATTACHMENT 12 SYSTEM: TIP NO. NOTE Tip Ball and Shear Valves are not shown on the PAID.

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

III-12-4 January 1989

PUMP ANO 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 011

'OWG. NO. C-18014-C SH.3 Pages III-13-1 through III-13-5 III-13-1 January 1989

SYSTEM N2 SUPPLY 811 NINE MILE POINT UNIT 1 VALVE 1EST TABLE DWG. NO. C-18014-C SH.3 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.

201.9-17 3 0.5 SEA C RT-P Ill N2 Storage G-5 REV Tank Liquid With-drawal 140 8PSV 201. 9-19 3 1 NDA C FE-Q 811 N2 Storage H-5 GTV ST-Q O,C Tank Liquid With- FS-Q 0 drawal B.V. PI-R 201.9-24 3 0.5 SEA C RT-P 140 8PSV After J-4 REV Ambient Vaporizer 201.9-25 3 0.5 SEA C RT-P Pl 1 Np Storage H-4 REV Tank T40 4PSV After B.V. 201.9-19 201.9-49 3 1 0 FS-Q N2 FCV L-5= GLV 201.9-69 3 1 SEA C RT-P 33 8PSV After L-4 REV 201.9-48 201.9-70 3 1 SEA C RT-P 33 8PSV After M-3 REV FCV 201.9-49 201.9-94 3 1 SEA DE FE-Q NOTE N2 Supply to I-7 CHV CAD Valve Actuators III-13-2 January 1989

SYSTEM N2 SUPPLY 811 NINE MILE POINT UNIT I VALVE TEST TABLE DWG. NO. C-18014-C SH.3 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.

201.9-17 3 0.5 SEA C RT-P 811 N2 Storage G-5 REV Tank Liquid With-drawal 140 SPSV 201.9-19 3 1 NDA C FE-Q Ill N2 Storage H-5 GTV ST-Q O,C Tank Liquid With- FS-Q 0 drawal B.V. PI-R 201.9-24 3 0.5 SEA C RT-P 140 fPSV After J-4 REV Ambient Vaporizer 201.9-25 3 0.5 SEA C RT-P 811 N2 Storage H-4 REV Tank 140 8PSV After B.V. 201.9-19 201.9-49 3 1 NDA 0 FS-Q N2 FCV L-5 GLV 201.9-69 3 1 SEA C RT-P 33 8PSV After L-4 REV 201.9-48 201.9-70 3 1 SEA C RT-P 33 8PSV After M-3 REV FCV 201.9-49 201.9-94 3 1 SEA DE FE-Q NOTE 1 N2 Supply to I-7 CHV CAD Valve Actuators III-13-2 January 1989

SYSTEM N2 SUPPLY 411 NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.3 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.

201-14 N2 Press Amb Vap 3 0.5x.25 SEA C RT-P PSV F-3 REV 201.9-33 N2 Press Amb 3 0.5x.25 SEA C RT-P Vap PSV F-3 REV 201.9-16 3 .25 ADA 0 FS-Q Amb Vap. N2 F-4 GTV Supply FCV 201.9-35 3 .25 ADA 0 FS-Q Amb Vap. N2 F-6 GTV Supply FCV III-13-4 January 1989

0 NOTES FOR ATTACHMENT 13 SYSTEM: NITROGEN SUPPLY 70 11 NO. NOTE Forward flow opening verified by proper operation of the nitrogen supplied CAD valves.

III-13-5 January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.14 ATTACHMENT 14 VALVE TEST TABLES AND RELIEF REQUESTS FOR NITROGEN SUPPLY 4 12 DWG. NO. C-18014-C SH.4 Pages III-14-1 through III-14-3 I I I-14-1 Jaruary 1989

SYSTEM N2 SUPPLY 812 NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.4 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.

201.8-01 3 1 ADA DE FS-Q NZ PCV G-6 GLV 201.8-02 3 1 ADA DE FS-Q N2 FCV J-6 GLV 201. 8-03 3 1.5 C FE-Q Liquid N2 B.V. C-2 PGV ST-Q to Steam Vaporizer FS-Q 8 Control Cabinet PI-R 201.8-04 3 1 NDA C FE-Q B.V. to 6000 SCFH F-3 GTV ST-Q C,O Ambient Vaporizer FS-Q 0 PI-R 201.8-10 3 0.5 SEA C RT-P PSV on Inlet Side F-3 REV of 201.8-04 201.8-11 PSV on Outlet 3

F-3 C 0.5 REV SEA C RT-P Side of 201.8-04 201. 8-12 3 0.5 SEA C RT-P PSV on Discharge F-5 REV Side of 6000 SCFH Ambient Vaporizer 201. 8-13 3 1 SEA C RT-P PSV After PCV I-5 REV 201. 8-01 III-14-2 January 1989

SYSTEM N2 SUPPLY 0'12 NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18014-C SH.4 C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) (IN.) TYPE POSIT. REO. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. RE/. NO. PERF.

201.8-14 3 1 SEA C RT-P PSV After PCV K-5 REV 201.8-02 201.8-39 3 0.5 SEA C RT-P P.S.V. to S.O.V.s E-2 REV 201.8-03B to 201.8-04B SSI-40 3 1 SEA C RT-P 812 N2 Tank C-2 REV Press Build. Coil PSV 8 2508 SSI-35 3 0.5 SEA C RT-P N2 Press Amb C-5 REV Vap. PSV SSI-37 3 .25 SEA C RT-P N2 Press Amb D-5 REV Vap. PSV 201. 8-57 3 0.5 ADA 0 FS-0 0 N2 Press Amb E-4 GLV Vap. PCV III-14-3 January 1989

0 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE 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-15-4 III-15-1 January 1989

SYSTEM RBHVAC NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18013-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.

202-15 3 B 54 ADA FE-Q Supply Isolation C-4 BFV ST-Q Valve FS-Q PI-R 202-16 3 54 ADA FE-Q Supply Isolation C-4 BFV ST-Q Valve FS-Q PI-R

. 202-31 3 54 ADA FE-Q Exhaust Isolation J-2 BFV ST-Q Valve FS-Q PI-R 202-32 3 54 ADA 0 FE-Q Exhaust Isolation J-2 ST-Q Valve FS-Q PI-R 202-34 2 12 ADA FE-Q Em. Exh. Fan 811 M-5 BFV ST-Q O,C Outlet FS-Q 0 P I-R 202-35 2 12 ADA FE-Q Em. Exh. Fan 812 M-6 BFV ST-Q O,C Outlet FS-Q 0 PI-R 202-36 2 12 ADA 0 FE-Q Rm. Vent Sys. I-3 BFV ST-Q O,C Inlet FS-Q 0 PI-R III-15-2 January 1989

SYSTEM RBHVAC NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18013-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.

202-37 2 12 ADA C FE-Q Loop 811 Inlet I-5 BF.V ST-Q O,C FS-Q 0 PI-R 202-38 2 12 ADA Ff-Q Loop 812 Inlet I-6 BFV ST-Q O,C FS-Q 0 PI-R 202-74 3 2 ADA FE-Q Loop 811 Cooling I-5 BFV ST-Q C,O FS-Q C PI-R 202-75 3 2 ADA FE-Q Loop 812 Cooling I-7 BFV ST-Q C,O FS-Q C PI-R 202-47 3 2 ADA Ff-Q Cross-tie Valve L-6 BFV ST-Q O,C FS-Q 0 PI-R 202-50 3 12 ADA FS-Q Exh. Fan 811 L-5 BFV PI-R Inlet FCV 202-51 3 12 ADA FS-Q Exh. Fan f1 2 L-6 BFV PI-R Inlet FCV III-15-3 January 1989

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PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.16 ATTACHMENT 16 VALVE TEST TABLES AND RELIEF REQUESTS FOR LIQUID POISON DWG. NO. C-18019-C Pages III-16-1 through III-16-6 Iii-16-1 January 1989

0 SYS i LIQUID POISON NINE MILE POINT UNIT 1 VALVE T ABLE DHG. NO. C-18019-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.

42-19 2 1.5 SEA DE FE-Q F,R RR-3 FE-R Pump Ill Disch. F-5 CHV Check 42-20 2 1.5 SEA DE FE-Q F,R RR-3 FE-R Pump 812 Disch. F-7 CHV Check 42.1-02 1 A,C 2 SEA DE FE-Q RR-l, 2 FE-R CIV Inside B-6 CHV LJ-R 42.1-03 1 A,C 2 SEA DE FE-Q F,R RR-1,2 FE-R CIV Outside C-6 CHV LJ-R NP04A 2 1X2 SEA DE RT-P NOTE 1 Loop 811 PSV F-4 REV NP04B 2 C 1X2 SEA DE RT-P NOTE 1 Loop 812 PSV F-6 REV NP05A 2 1.5 EXA C EX-P Liquid Poison D-5 EXV Explosive Valve 811 NP05B 2 1.5 EXA C EX-P Liquid Poison D-7 EXV Explosive Valve 812 h

III-16-2 January 1989

NOTES FOR ATTACHMENT 16 SYSTEM: LIQUID POISON NO. NOTE IST requirements satisfy INPO SER 26-88.

III-16-3 January 1989

RELIEF RE(UEST LP-RR-1 System: Liquid Poison Valve: 42.1-02:41.2-03 Category: A,C Class:

Function: Liquid Poison Injection Line Check Valves ASME Section XI quarterly Test Requirements: Verify forward flow opening IWV-3522 quarterly IWV-3521 Sasis for Relief: Veri fication of forward flow operabi ity during normal 1

operation would require firing a squib valve and injecting cold demineralized water into the reactor vessel using the liquid poison pumps. Injecting 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.

Verification of forward flow operability during cold shutdowns would also require firing a squib valve and injecting demineralized water into the vessel. Firing a squib valve during cold shutdowns requires a whole series of tests in itself (testing a charge from a new batch of explosive charges, installation/replacement of old fired charge, leak testing following reassembly, etc.). The scope of this type of test would also most likely delay start up.

Alternate Testing: Verify forward flow opening during refueling during the liquid poison system injection test, which fires at least one squid val ve and pumps demineral i zed water into the reactor vessel.

III-16-4 January 1989

RELIEF REQUEST LP-RR-2 System: Liquid Poison Valve: 42.1-02:42.1-03 Category: A,C Class:

Function: Containment Isol ation Check Valves (reverse flow closure for containment isolation)

ASME Section XI Quarterly Test Requirements: Verify reverse flow closure IWV-3522 quarterly IWV-3521 Basis for Relief: These valves are normally closed and are only opened during refueling outages when the simulated injection test of liquid poison is performed. The valves are then verified closed by performing an Appendix J, Type C leak test. A containment entry is required to perform this leak test.

Since the containment is normally inerted, it is not feasible to perform the test during normal operation or cold shutdowns.

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

III-16-5 January 1989

~ ~ << i ~ . ~ ~ a ~ . <<t ~ ',4 "' .w,r'w RELIEF REQUEST LP-RR-3 System: Liquid Poison Valve: 42-19:42-20 Category:

Class:

Function: Liquid Poison Pumps Discharge Check Valves ASNE Section XI Quarterly Test Requirements: Verify reverse flow closure IWV-3522 quarterly IWV-3521 Basis for Relief: The Liquid Poison Pumps are positive displacement pumps and wi 11 not permit flow through them in the reverse direction. Test connections were not provided between the discharge of the Liquid Poison pumps and pump discharge check valves. Therefore, the only means to establish a vent path is by removing a component (ie, accumulator or relief valve).

In addition, the system lineup required to establi sh a reverse flow condition on these valves requires both LP.

loops to be cross-connected. This lineup would render both pumps inoperable which is not permitted during power operation.

Alternate Testing: Reverse flow closure will be verified at refueling at the next refueling outage (1991), a modi f ication wi 1 1 be performed to add the necessary test connections to permit quarterly testing.

I II-16-6 January 1989

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

5. 17 ATTACHMENT 17 VALVE TEST TABLES AND RELIEF REQUESTS FOR SPENT FUEL STORAGE POOL FILTERING 5 COOLING DWG. NO. C-18008-C Pages III-17-1 through III-17-6 III-17-1 January 1989

SYST SPFC NINE. E POINT UNIT 1 VALVE TES LE DWG. NO. C-18008-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.

54-12 3 8 6 ADA DE FE-Q Filter ¹12 Loop G-8 BFV ST-Q O,C Inlet B.V. FS-Q C P I-R 54-13 3 6 ADA DE FE-Q Filter ¹ll Loop G-5 BfV ST-Q O,C Inlet B.V. FS-Q C P I-R 54-45 3 6 SEA DE FE-Q Heat Exchanger L-8 CHV

¹12 - Outlet-Check Valve 54-46 3 6 SEA DE FE-Q Heat Exchanger L-5 CHV

¹11 - Outlet Check Valve 54-71 3 6 SEA DE FE-Q fuel Pool Loop F-1 CHV Intake Check Valve 54-72 3 6 SEA DE FE-Q fuel Pool Loop E-1 CHV Intake Check Valve FP-308 3 2 SEA DE fE-Q RR-2 Fuel Pool Loop G-l CHV Return Check Valve to Siphon BRKR III-17-2 January 1989

SYSTE SPFC NIN E POINT UNIT 1 VALVE TES LE DHG. NO. C-18008-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.

FP-310 3 2 SEA DE FE-Q RR-2 Fuel Pool Loop E-1 CHV Return - Check Valve to Siphon BRKR 57-25 3 3 ADA C FS-Q Fuel Pool Make-up f-2 GLV Normal LCV 57-58 3 3 SOA C FS-Q Surge Tank- G-2 GLV Make-up Back-up LCV 57-03 3 3 SEA DE FE-Q Fuel Pool Level E-2 CHV Control Check III-17-3 January 1989

0 SYSTE SPFC NINE E POINT UNIT 1 VALVE TES E DWG. NO. C-18008-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; 54-49 3 8 SEA DE FE-Q F RR-1 FE-R Pump Suc. Ck. Vlv. A-7 CHV 54-14 3 6 ADA DE FS-Q Filter 812 FCV I-8 BFV PI-R Outlet Valve 54-15 3 6 ADA DE FS-Q Filter Ill FCV I-6 BFV PI-R Outlet Valve 85-160 3 6 SOA C FE-Q Waste Disposal M-3 GLV ST-Q Block Valve FS-Q P I-R FP-312 3 2 SEA DE FE-Q RR FE-R Rx Head Cavity- D-l CHV Check Valve to Siphon BRKR FP-314 3 2 SEA DE FE-Q RR-2 FE-R Rx Head Cavity- D-l .CHV Check Valve to Siphon BRKR 54-18 3 10 APA C FE-Q SP Fuel Pump A-7 GTV ST-Q O,C Suction Valve P I-R 54-17 3 10 APA 0 FE-Q SP Fuel Pump B-7 GTV ST-Q O,C Suction Valve PI-R III-17-4 January 1989

RELIEF REQUEST SFSPFC-RR-1 System: SFSPFC Valve: 54-49 Category:

Class Function: Reactor Internal s Stor age Pit and Reactor Head Cavity Outlet Check Valve ASME Section XI Quarterly Test Requirements: Verify forward flow opening IWV-3522 quarterly IWV-3521 Basis for Relief: The reactor internals storage pit and reactor head cavity are empty during normal plant operation. The storage pit and head cavity are filled during refueling outages and emptied at the end of the outage to either the condenser, waste disposal system, or reactor building equipment drain tank.

Alternate Testing: Verify forward flow opening during scheduled refueling outage.

I II-17-5 January 1989

RELIEF REQUEST SFSPFC-RR-2 System: Spent Fuel Storage Pool Filtering 5 Cooling Valve: FP-308:FP-310:FP-312:FP-314 Category:

Class Function: FP-308:FP-310 Fuel Pool Siphon Breaker FP-312:FP-314 Reactor Head Cavity Siphon Breaker ASNE Section XI Quarterly Test Requirements: Exercise, observe force or torque limitations of IWV-3522(b) quarterly IWV-3521.

Basic for Relief: FP-312 and FP-314 break siphon on the Reactor Head Cavity and Reactor Internals Storage Pit when these areas are filled and when the header valves to these pools are open.

These valves do not provide a safety function when these pools are drained and the header valves are closed.

The system and valves provide no means for observing the opening of these valves other than manually exercising.

Also, the valves have no provisions for installation of a torque wrench or other device for the purpose of measuring the torque or force needed to operate the valve.

Alternate Testing: Exercising of these valve wi 11 be verified by hand exercising at quarterly intervals for FP-308 and FP-310 and at refueling intervals for FP-312 and FP-314.

III-17-6 January 1989

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

5. 18 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 January 1989

SYSTE PLE NIN f POINT UNIT 1 VALVE TfS DWG. NO. C-18041-C SH.7 C.S C.S CLASS VALVf SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT. ) ( IN. ) TYPE POSIT. REQ. DIRECT. VALVE OR ALT. RfMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

122-03 2 1 ADA C FE-Q Post Accident A-3 GLV ST-Q Sample IV FS-Q LJ-R PI-R III-18-2 January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.19 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-26949-C C-26939-C C-18047-C C-18008-C C-18041-C SH.7 Pages III-19-1 through III-19-15 III-19-1 January 1989

SYSTE CLCW NIN E POINT UNIT 1 VALVE TEST E DWG. NO. C-18022-C SH.3 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.

70-04 3 12 SEA DE FE-Q F,R CS-2 FE-C Pump Ill E-8 CHV Disch. Check 70-05 3 12 SEA DE FE-Q F,R CS-2 FE-C Pump 812 E-7 CHV Disch. Check 70-06 3 12 SEA DE FE-Q F,R CS-2 FE-C Pump 813 E-6 CHV Disch. Check 70-94 2 8 MOA 0 FE-Q CS-1 FE-C RBCLC Return I-8 GTV ST-Q ST-C from DW Air Coolers PI-R LA-R 70-95 2 A,C 8 SEA DE FE-Q RR-3 FE-R RBCLC DW Air K-5 CHV LA-R Cooler Supply IV 72-146 3 12 APA DE FS-Q NOTE 1 Disch. Manifold F-4 GLV TCV I I I-19-2 January 1989

0 SYSTE CLCW NINE, E POINT UNIT 1 VALVE TEST LE DWG. NO. C-18047-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TfST 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.

70-26 3 4 APA DE FE-Q CLC To CR Chiller K-1 PGV ST-Q 0 12 FS-Q 0 70-25 3 4 APA DE FE-Q CLC To CR Chiller H-1 PGV ST-Q 0 ll FS-Q 0 I II-19-3 January 1989

SYSTEM CLCW NINL E POINT UNIT 1 VALVE TES DWG. NO. C-18008-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.

70-68 3 B 6 APA DE FE-Q CLC To SF HX tl 1 L-5 GLV ST-Q 0 FS-Q 0 PI-R 70-69 3 6 APA DE FE-Q CLC To SF HX 812 L-8 GI V ST-Q 0 FS-Q 0 PI-R III-19-4 January 1989

SYSTE CLCW NINE E POINT UNIT 1 VALVE TES 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. REQ. NO. PERF.

70-MU-7 3 1.5 SEA DE ff-Q R RR-2 Ff-R CLC Make-up Check M-5 CHV (Normal)70-257 3 6 SEA DE FE-Q RR-2 FE-R CLC Make-up Check M-5 CHV (Emerg)

I I I-19-5 January 1989

SYSTE CLCH NIN E POINT UNIT 1 VALVE TES DWG. NO. C-18022-C SH.4 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 DHG. AND TEST RELIEf TEST COOR. TYPE DIRECT. REQ. NO. PERF.

70-92 2 A 4 MOA 0 FE-Q RR-1 FE-R RBCLC Return from E-6 GTV ST-Q ST-R RX Recirc Pump PI-R Cooler Header LA-R 70-93 2 4 SEA DE FE-Q RR-3 FE-R Recirc Pump E-5 CHV LA-R Motor Cooler I.V.

III-19-6 January 1989

SYSTEM CLCW NINE E POINT UNIT 1 VALVE TEST E DWG. NO. C-26949-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.70-209 3 0.5 SEA DE FE-Q H202 811 F-6 CHV Sample Cooler Supply Check Valve 70-229 3 0.5 SEA DE FE-Q H20( Ill F-6 CHV Cab>net Cooler Supply Check Valve 70-208 3 0.5 SEA DE FE-Q H202 811 F-3 CHV Sample Cooler Return Check Valve 70-212 3 0.5 ADA C FE-Q H202 811 D-5 GLV ST-Q Sample Cooler FS-Q B.V.

I I I-19-7 January 1989

SYST CLCW NIN E POINT UNIT 1 VALVE TES LE DWG. NO. C-26939-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.70-218 3 0.5 SEA DE FE-Q H202 812 F-6 CHV Sample Cooler Supply Check Val ve 70-219 3 0.5 SEA DE FE-Q H202 f12 F-3 CHV Sample Cooler Return Check Valve 70-234 3 0.5 SEA DE FE-Q H202 812 E-6 CHV Cab>net Cooler Supply Check Valve 70-222 3 0.5 ADA C FE-Q H202 812 0-5 GLV ST-Q Sample Cooler FS-Q B.V.

I I I-19-8 January 1989

SYSTE CLCW NINE E POINT UNIT 1 VALVE TES DWG. NO. C-18041-C SH.7 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.70-272 3 .75 SEA DE FE-Q PASS Sample J-8 CHV Cooler Return Check Valve 70-274 3 .75 SEA DE FE-Q PASS Sample J-8 CHV Cooler Return Check Valve III-19-9 January 1989

NOTES FOR ATTACHMENT 19 SYSTEM: RBCLCM NO. NOTE The function of TCV-70-137 is associated with TCV-72-146.

TCV-70-137 shall have its function verified when TCV-72-146 is fail safe tested.

III-19-10 January 1989

COLO SHUTOOWN TEST JUSTIFICATION RBCLCW-CS-1 System: RBCLCW Valve: 70-94 Category:

Cl ass:

Function: Outlet Blocking Valve for Orywell Air Coolers ASHE Section XI quarterly Test Requirements: Exercise and time Cold Shutdown Test Justification: Testing this valve during normal operation requires interruption of the cooling water to the drywell air coolers. Loss of these coolers could result in a reactor scram due to higher drywell temperature causing higher drywell pressure.

quarterly Part Stroke Testing: None Cold Shutdown Testing: Exercise and time during cold shutdowns when interruption of cooling water to the drywell air coolers does not pose any operational concerns.

'I III-19-11 January 1989

0 COLD SHUTDOWN TEST JUSTIFICATION RBCLCW-CS-2 System: RBCLCW Valve: 70-04:70-05:70-06 Category:

Class:

Function: Pump Discharge Check Valves ASME Section XI quarterly Test Requirements: Verifiy forward flow opening Cold Shutdown Test Justification: Oue to system heat loads, in most cases it is not possible to operate the system to achieve Code test conditions without adversely affecting plant operation.

quarterly Part Stroke Testing: Forward flow operability shall be assessed during normal system operation.

Cold Shutdown Testing: Forward flow operability shall be verif ied during cold shutdowns when the Reactor Building Closed Loop Cooling Water Pumps are tested individually. .

III-19-12 January 1989

r RELIEF RE(UEST RBCLCW-RR-1 System: RBCLCW Valve: 70-92 Category: A Class:

Function: Outlet Blocking Valve for Recirculation Pump Coolers ASNE Section XI quarterly Test Requirements: Exercise IWV-3412 and time IWV-3413 quarterly IWV-3411 Basis For Relief: To test this valve would require interruption of cooling water to the recirculation pump coolers. Loss of cooling water for more than a few minutes could cause damage to the recirculation pumps. Failure of these val ves to reopen could cause extensive damage to the equipment being cooled, Since some recirculation'umps are n'ormally inservice (running) during cold shutdowns, testing during this period is not feasible either, as the reactor building closed loop cooling is a. common line for the reactor recircul a tion p um ps Alternate Testing: Exercise and time during scheduled refueling outages.

III-19-13 January 1989

RELIEF REQUEST RBCLCW-RR-2 System: RBCLCW Valve: 70-MU-7:70-257 Category: C Class:

Function: Provide Makeup to the RBCLCM System ASME Section XI Quarterly Test Requirements: Verify reverse flow closure IWV-3522 quarterly IWV-3521 Basis For Relief: Oue to the system piping configuration, these valves cannot be tested on a quarterly basis.

Alternate Testing: These val ves shall be disassembled and inspected during refueling. A modification (1991) shall be evaluated to add test connections to allow quarterly testing.

III-19-14 January 1989

0 RELIEF REQUEST RBCLCW-RR-3 System: RBCLCW Valve: 70-93:70-95 Category: A,C Class:

Function: Pr ovide RBCLCW to the Orywel 1 Air Coolers and Reactor Recirculation Pump Motor Coolers ASME Section XI Quarterly Test Requirements: Verify reverse flow closure IWV-3522 quarterly IWV-3521 Basis For Relief: Testing these valves during normal operation or cold shutdown requires interruption of the cooling water to the drywell air coolers and reactor recirculation pump motor coolers for a long time period. Loss of the drywell air coolers could result in a reactor scram due to higher drywell temperature causing higher drywell pressure. Loss of cooling water to the recirculation pump water coolers for more than a few minutes could cause damage to the recirculation pumps. Testing during these periods is not feasible, as the reactor building closed loop cooling is a common line for the reactor recirculation pumps.

Alternate Testing: Reverse flow closure of these val ve f shal 1 be veri i ed during ASME XI leakage testing at scheduled refueling outages.

III-19-15 January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.20 ATTACHMENT 20 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONDENSATE TRANSFER DWG. NO. C-18048-C Pages III-20-1 through III-20-3 III-20-1 January 1989

SYSTEM CONDENSATE TRANSFER NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18048-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.

57-13 3 SEA DE FE-Q F,R Cond. Transfer H-8 CHV Syst. Pump 812 Discharge 57-14 3 4 SEA DE FE-Q F,R Cond. Transfer I-8 CHV Syst. Pump 811 Discharge 57-57 3 3X4 SEA C RT-P NOTE 1 Cond. Transfer I-5 REV Syst. Safety Valve Pump at Cond. Surge 5 Storage Tanks.

CT-9 3 .75 SEA DE FE-Q Cond. Transfer J-9 CHV Syst. Pump Ill Min. Flow To CST CT-10 3 .75 SEA DE FE-Q Cond. Transfer I-8 CHV Syst. Pump 812 Min. Flow to CST III-20-2 January 1989

NOTES FOR ATTACHMENT 20 SYSTEM: CONOENSATE TRANSFER NO. NOTE 1 IST requirements satisfy INPO SER 26-88.

III-20-3 January 1989

PUMP AND VALVE INSERYICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III .

5.21 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 III-21-1 January 1989

SYSTEM TORUS VACUUM RELIEF NINE MILE POINT UNIT 1 VALVE TEST TABLE DllG. NO. C-18006-C SH.2 C.S C.S CLASS VAL SIZE ACTU. NORM. TESl 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.

68-01 2 30 SEA C FE-Q F,R Torus To Drywell F-4 CHV APA PI-R Vacuum Relief Check 68-02 2 30 SEA C FE-Q Torus To Drywell H-4 CHV APA PI-R Vacuum Relief Check 68-03 2 30 SEA C FE-Q Torus To Drywell H-4 CHV APA PI-R Vacuum Relief Check 68-04 2 B,C 30 SEA C FE-Q F,R Torus To Drywell H-4 CHV APA PI-R Vacuum Relief Check 68-05 2 A,C 30 SEA C FE-Q F,R Reactor Building J-3 CHV APA LJ-R To Torus Vacuum PI-R Relief I.V.

68-06 2 A,C 30 SEA C FE-Q F,R Reactor Building J-3 CHV APA LJ-R To Torus Vacuum PI-R Relief I.V.

III-21-2 January 1989

SYSTEM TORUS VACUUM RELIEF NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18006-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.

68-07 2 AC 30 SEA FE-Q F,R Reactor Building J-3 CHV APA LJ-R To Torus Vacuum PI-R Relief I.V.

68-08 .2 30 APA FE-Q Reactor Building I-3 BFV ST-Q O,C To Torus Vacuum FS-Q Relief I.V. LJ-R PI-R 68-09 2 30 APA FE-Q Reactor Building I-3 BFV ST-Q O,C To Torus Vacuum FS-Q 0 Relief I.V. LJ-R PI-R 68-10 2 30 APA FE-Q Reactor Building I-3 BFV ST-Q O,C To Torus Vacuum FS-Q 0 Relief I.V. LJ-R PI-R III-21-3 January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION I II 5.22 ATTACHMENT 22 VALVE TEST TABLES AND RELIEF REQUESTS FOR EMERGENCY SERVICE WATER DWG. NO. C-18022-C SH.3 C-18027-C SH.2 Pages III-22-1 through III-22-6 III-22-1 January 1989

SYSTfM EMfRGENCY SfRVICE WATfR NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18022-C SH.3 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 DIRfCT. REQ. NO. PERF.

72-11 3 14 MAA DE Ff-Q F RR-1 FE-R Emerg. S.W. Pump B-3 CHV SEA

¹12 Disch. Check 72-12 3 14 MAA DE FE-Q RR-1 Emerg. S.W. Pump 0-3 CHV SEA

¹ll Disch. Check 72-21 3 20 MAA Df FE-Q RR-2 FE-R Serv. Wtr. Supply B-1 CHV SEA Check 72-22 3 20 MAA DE FE-Q RR-2 FE-R Serv. Wtr. Supply B-2 CHV SEA Check I II-22-2 January 1989

SYSTEM EMERGENCY SERVICE WATER NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18027-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.

SW-121 2 1 MAA C PV NOTE 1 Serv. Wtr. to E-6 GTV LJ-R Drywell I.V.

Outside SW-122 2 1 C PV NOTE 1 Serv. Wtr. to D-6 GTV LJ-R Drywell I.V.

Inside I I I-22-3 January 1989

NOTES FOR ATTACHMENT 22 SYSTEM: EMERGENCY SERVICE MATER NO. NOTE The valve shall be locked close by chain 8 lock and/or other approved method.

III-22-4 January 1989

RELIEF REQUEST ESW-RR-1 System: Emergency Service Water Valve: 72-11:72-12 Category:

Class:

Function: Emergency Service Water Pump Discharge Check Valves ASME Section XI Quarterly Test Requirements: Verify forward flow opening IWV-3522 quarterly IWV-3521 Basis For Relief: The emergency service water pumps are normally in standby during all modes of plant operation. Since the regular service water system is in service during all modes of plant operation including cold shutdown and normal service water pressure is above the shutoff pressure of the emergency ser vice water pumps, no flow path exists for flow through these check valves without removing the normal service water system from service. Use of the manual exerciser is not possible due to the service water pressure on the downstream side of these check valves at all times.

(Since the service water system is a raw water system, and the ESW lines are stagnant during normal operation, it is difficult to maintain the adjacent manual blocking valve leak-tight enough to isolate service water pressure.) The test loop provided for pump testing is also upstream from the check valve.

Alternate Testing: The inspection covers for these valves will be removed during refueling outages on an alternate basis and the integrity of the valve internals verified. Also during disassembly, the valve will be manually exercised using the external exercising arm. A modification shall be evaluated to permit quarterly exercising of these valves. This modification shall be performed next refueling cutage (1991).

III-22-5 January 1989

RELIEF REQUEST ESW-RR-2 System: Emergency Service Water Valve: 72-21:72-22 Category:

Class:

Function: Isolate Reactor Building Service Water Supply from Turbine Building Service Water Supply ASNE Section XI Quarterly Test Requirements: Verify reverse flow closure IWV-3522 quarterly IWV-3521 Basis For Relief: There is no method to simulate reverse flow closure of these valves due to the system design configuration.

Alternate Testing: These valves will be disassembled and inspected on an alternate basis during refueling outages for verification of integrity.

III-22-6 January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.23 ATTACHMENT 23 VALVE TEST TABLES AND RELIEF REQUESTS FOR EMERGENCY DIESEL GENERATOR COOLING WATER DWG. NO. C-18026-C SH.1 C-18026-C SH.2 Pages III-23-1 through III-23-4 III-23-1 January 1989

SYSTEM EH. DIESEL GEN. COOLING WTR. NINE NILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18026-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.

72-67 3 4 SEA DE FE-Q f102 Diesel F-6 CHV FE-R NOTE 1 Cooling Water Loop Discharge Check 72-69R 3 4 SEA DE FE-Q Em. DGCW Pump C-8 CHV FE-R NOTE 2 8102 Disch. Check I I I 2 January 1989

SYSTEM EN. DIESEL GEN. COOLING WTR. NINE NILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18026-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 TfST COOR. TYPE DIRECT. REQ. NO. PERF.

72-66 3 4 SEA DE FE-Q

~

8103 Diesel F-6 CHV FE-R NOTE 1 Cooling Water Loop Discharge Check t

72-68R 3 4 SEA DE FE-Q Em. DGCW Pump C-8 CHV FE-R NOTE 2 4103 Disch. Check III-23-3 January 1989

NOTES FOR ATTACHMENT 23 e SYSTEM: EMERGENCY OIESEL GENERATOR COOLING WATER NO. NOTE 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.

As a result of I.E.Bulletin 83-03, Niagara Mohawk has committed to di sassembling and inspecting these valves during refueling outages.

Reference NMPSl Letters dated 6/14/83 (Log NMP6777) and dated 12/10/84 (Log NMP7947)

III-23-4 January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.24 ATTACHMENT 24 VALVE TEST TABLES AND RELIEF REQUESTS FOR EMERGENCY DIESEL GENERATOR AIR START DWG. NO. C-18026-C SH.1 C-18026-C SH.2 Pages III-24-1 through III-24-4 III-24-1 January 1989

SYSTEM EN. DIESEL GENERATOR AIR START NINE NILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18026-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.

96-11 N A,C .75 SEA DE FE-Q D.G. 102 E-1 SCV LA-R NOTE 1,2 Compressor Stop Ch. Vlv.

96-12 N A,C .75 SEA DE FE-Q F,R D.G. 102 E-4 SCV LA-R NOTE 1,2 Compressor Stop Ch. Vlv.

96-15 N 0.5 SEA C RT-P NOTE 1 D.G. 102 Air G-2 REV TK. 5'1 PSV 96-16 N 0.5 SEA C RT-P NOTE 1 D.G. 102 Air H-2 REV TK 82 PSV 96-17 N 0.5 SEA C RT-P NOTE 1 D.G. 102 Air I-2 REV TK 83 PSV

. 96-18 N 0.5 SEA C RT-P NOTE 1 D.G. 102 Air J-2 REV TK 84 PSV 96-19 N 0.5 SEA C RT-P NOTE 1 D.G. 102 Air K-2 REV TK. 85 PSV 96-20 N 0.5 SEA C RT-P NOTE 1 D.G. 102 Air K-5 REV Start PSV III-24-2 January 1989

SYSTEM EM. DIESEL GENERATOR AIR START NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18026-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.

96-38 N A C .75 SEA DE FE-Q F,R NOTE 1,2 D.G. 103 E-1 SCV LA-R Compressor Stop Ch. Vlv.

96-39 N A,C .75 SEA DE FE-Q NOTE 1,2 D.G. 103 f-4 SCV LA-R Compressor Stop Ch. Vlv.

96-44 N 0.5 SEA C RT-P NOTE 1 D.G. 103 Air G-2 REV TK. tl PSV 96-45 N 0.5 SEA C RT-P NOTE 1 D.G. 103 Air H-2 REV TK. 82 PSV 96-46 N 0.5 SEA C RT-P NOTE 1 D.G. 103 Air I-2 REV TK. f3 PSV 96-47 N 0.5 SEA C RT-P NOTE 1 D.G. 103 Air J-2 REV TK. i4 PSV 96-48 N .0.5 SEA C RT-P NOTE 1 D.G. 103 Air K-2 REV TK. g5 PSV 96-49 N 0.5 SEA C RT-P NOTE 1 D.G. 103 Air K-5 REV STart PSV III-24-3 January 1989

NOTES FOR ATTACHMENT 24 SYSTEM: EMERGENCY DIESEI GENERATOR AIR START NO. NOTE The Emergency Diesel Generator Air Start System is Non-ASME Code classed per Reg. Guide 1.26. This system performs a safety-related function and the appropriate valves are in the IST Program and are tested in accordance with the code.

The leakage rate test for these valves in reality is a system pressure decay test since system leakage is a concern and not just the valves. For the purpose of this Program Plan the system leakage shall be assigned to these valves.

III-24-4 January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.25 ATTACHMENT 25 VALVE TEST TABLES ANO RELIEF REQUESTS FOR EMERGENCY OIESEL GENERATOR FUEL OIL TRANSFER OWG. NO. B-18040-C Pages III-25-1 through III-25-4 III-25-1 January 1989

SYSTEM EM. D.G. F.O. X-FER NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18040-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 DHG. AND TEST RELIEF TEST COOR. TYPE DIRECT. REQ. NO. PERF.

PSV-GM-102 N .25 SEA C RT-P NOTE 1 EDG 102 Fuel Oil A-5 REV XFER PSV PSV-GM-103 N .25 SEA C RT-P NOTE 1 EDG 103 Fuel Oil C-5 REV XFER PSV 82-03 N 1.5 SEA C FE-Q F,R RR-1 NOTE 1 EDG Storage Tank H-7 CHV 102 Foot Valve 82-04 N 1.5 SEA C FE-Q F,R RR-1 NOTE 1 EDG Storage Tank L-7 CHV 103 Foot Valve I I I-25-2 January 1989

NOTES FOR ATTACHMENT 25 a SYSTEM:

NO.

EMERGENCY DIESEL GENERATOR FUEL NOTE The Emergency OIL TRANSFER Diesel Generator Fuel Oil Transfer System is Non-ASME Code classed per Reg. Guide 1.26. The system performs a safety-related function and the appropriate valves are in the IST Program and are tested in accordance with the Code.

III-25-3 January 1989

RELIEF REQUEST EDGFO-RR-1 System: Emergency Diesel Generator Fuel Oil Transfer Valve: 82-03:82-04 Category:

Class:

Function: Diesel Fuel Oil Storage Tank Foot Valves ASME Section XI quarterly Test Requirements: Verify forward flow opening and reverse flow closure IMV-3522 Basis For Relief: The Diesel Fuel Oil Storage Tank foot valves are submerged inside the Diesel Fuel Oil Storage Tanks and thus are inaccessible.

Alternate Testing: Technical Specification Emergency Diesel Generator monthly start and operability tests are performed for a minimum time of one hour. Since the Diesel Fuel Oil Day Tanks are filled during the Emergency Diesel Generator operability test, these valves are verified operable when the tanks are filled.

III-25-4 January 1989

0

~ 0 'c .v 0 << ~

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.26 ATTACHMENT 26 VALVE TEST TABLES AND RELIEF REQUESTS FOR WASTE DISPOSAL DWG. NO. C-18045-C SH.7 C-18045-C SH.9 Pages III-26-1 through III-26-3 I II 1 Janu ary 1989

SYS ASTE DISPOSAL NI ILE POINT UNIT 1 VALVE TE ABLE DWG. NO. C-18045-C SH.7 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.

83.1-09 2 A 3 MOA 0 FE-Q Drywell Equip. D-l GTV ST-Q Drain I.V LJ-R PI-R 83.1-10 2 3 ADA 0 FE-Q Drywell Equip. H-2 GLV ST-Q C Drain I.V. FS-Q C LJ-R PI-R III-26-2 January 1989

SYS ASTE DISPOSAL NI LE POINT UNIT 1 VALVE TEb BLE DWG. NO. C-18045-C SH.9 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.

83.1-11 2 4 MOA 0 FE-Q Drywell Floor H-1 GTV ST-Q Drain I.V. LJ-R PI-R 83-1-12 2 4 ADA 0 FE-Q Drywel 1 Floor G-1 GLV ST-Q Drain I.V. FS-Q LJ-R PI-R III-26-3 January 1989

0 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UiVIT 1 SECTION I II 5.27 ATTACHMENT 27 VALVE TEST TABLES AND RELIEF RE(jUESTS FOR BREATHING AIR TO DRYWELL DWG. NO. C-18578-C Pages III-27-1 through III-27-2 I I I 1 Janu ary 1989

SYSTEM BREATHING AIR TO DRYWELL NINE MILE POINT UNIT 1 VALVE TEST TABLE DLJG. NO. C-18578-C C.S C.S CLASS VALVE SIZE ACTU. NORM. TfST 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.

114-BA-102 2 4 LC PV Breathing Air E-3 GLV LJ-R Supply to Drywell E1.237 114-BA-103 2 4 MAA LC PV Breathing Air f-3 GLV LJ-R Supply to Drywell E1.237 I I I 2 January 1989

PUMP AND VALVE INSERYICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.28 ATTACHMENT 28 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONTROL ROOM CHILLED WATER DWG. NO. C-18047-C Pages III-28-1 through III-28-2 III-28-1 January 1989

SYSTEM C.R. CHILLED WATER NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18047-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.

WTR-1 3 2.5 SEA 0 FE-Q Circ. Pump 811 I-2 CHV Disch. CV WTR-2 3 2.5 SEA 0 FE-Q F,R Circ. Pump 812 I-2 CHV Disch. CV 210.1-01 3 3 APA DE FE-Q Cool. CL. Ill H-4 PGV ST-Q Inlet Blocking FS-Q Valve 210.1-0.2 3 3 APA DE FE-Q Cool CL. 812 H-4 PGV ST-Q Inlet Blocking FS-Q Valve 210.1-56 3 2.5 MOA DE FS-Q (MO-l)Chill F-4 TWV PI-R WTR RTN FCV I I I-28-2 January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.29 ATTACHMENT 29 VALVE TEST TASLES AND RELIEF REQUESTS FOR CONTROL ROOM HVAC OWG. NO. C-18047-C Pages III-29-1 through III-29-2 I I I-29-1 January 1989

SYSTEM C.R. HVAC NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18047-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.

210-39 3 12 APA 0 FE-Q C.R. Normal C-4 BFV ST-Q C Vent. Fan Suet. FS-Q C PI-R 210-08 3 B 14 0 FE-Q C.R. Normal C-4 BFV ST-Q C Vent. Fan Suet. FS-Q C P I-R I I I 2 January 1989

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR NINE MILE POINT NUCLEAR POWER STATION UNIT 1 SECTION III 5.30 ATTACHMENT 30 VALVE TEST TABLES AND RELIEF REQUESTS FOR INSTRUMENT AIR DWG. NO. C-18011-C SH.1 C-18011-C SH.2 C-18030-C SH.3 Pages III-30-1 through III-30-5

.I I I-30-1 January 1989

0 SYSTEM INSTRUMENT AIR NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18011-C SH.l C.S C.S CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK JUST. OR VALVE NUMBER AND (CAT.) ( IN. ) TYPE POSIT. REO. DIRECT. VALVE OR ALT. REMARKS DWG. AND TEST RELIEF TEST COOR. TYPE DIRECT. RE/. NO. PERF.

94-19 N 2 ADA FS-g 0 NOTE 1 Service Air J-6 GLV Receiver B.V.

PCV II I-30-2 January 1989

1 SYSTEM INSTRUMENT AIR NINE MILE POINT UNIT 1 VALVE TEST TABLE DHG. NO. C-18011-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.

94-47 N C .75 SEA C RT-P NOTE 1 Intercooler ¹4 C-4 REV R.V.

94-45 N .75 SEA C RT-P NOTE 1 Intercooler ¹3 C-2 REV R.V.94-05C N .75 SEA C RT-P NOTE 1 Aftercooler ¹3 E-2 REV R.V.94-06C .75 SEA C RT-P NOTE 1 Aftercooler ¹4 REV R.V.

94-51 N 3 SEA DE FE-Q NOTE 1 I.A. Receiver ¹ll H-2 CHV Outlet Ck. Vlv.

114-15 N .3 SEA DE FE-Q NOTE 1 B.A. System H-2 CHV Ck. Vlv.

94-91 4 APA C FE-Q NOTE 1 C.S. Air TPV ST-Q Receiver B.V FS-Q PI-R III-30-3 January 1989

SYSTEM INSTRUMENT AIR NINE MILE POINT UNIT 1 VALVE TEST TABLE DWG. NO. C-18030-C SH.3 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.

IA-219 N 1 SEA DE FE-Q NOTE 1 D.F.P. Air H-2 CHV Receiver 811 Inlet Ck. Vlv.

100-921 N .75 SEA C RT-P NOTE 1 D.F.P. Air I-2 REV Receiver Ill R.V.

IA-218 N 1 SEA DE FE-Q NOTE 1 D.F.P. Air K-2 CHV Receiver 812 Inlet Ck. Vlv.

100-922 N .75 SEA C RT-P NOTE 1 D.F.P. Air J-2 REV Receiver 812 R.V.

111-30-4 January 1989

0 NOTES FOR ATTACHMENT 30 SYSTEM: INSTRUMENT AIR NO. NOTE The Instrument Air System is Non-ASME Code classed per REG.

Guide 1.26. This system performs a safety-related function and the appropriate valves are in the IST Program and are tested in accordance with the Code.

III-30-5 January 1989

0 NIAGARA MOHANK PONER CORPORATION NINE MILE POINT UNIT 1 ATTACHMENT B RESPONSES TO NRC COMMENTS 6515G

NINE MILE POINT NUCLEAR STATION UNIT 1 PUMP AND VALVE INSERVICE TESTING PROGRAM REVISED RESPONSES

l. VALVE TESTING PROGRAM General Questions and Comments Revised Responses Check valves with manual operators are either full-stroke exercised with flow, disassembled and inspected, or have their torque measured in accordance with IWV-3522(b). Where torque measurement testing is impractical, NMPl will provide a request for relief providing the basis to demonstrate that this testing cannot be performed (e.g., MS-RR-2).

General Relief Request VG-2 has been revi sed stating "indi vidual val ve leakage rates wi 11 be obtained by test or analysis and the requirements of IWV-3426 and IWV-3427(a) will be applied using a separate procedure".

This position complies with the USNRC Draft IST Generic Letter Supplement 1, Item 12.

No change from the original response.

General Re 1 i ef Request VG-1 has been revi sed to identify rapid-acting power operated valves as those which stroke in less than either 2 or 4 seconds.. If stroke times exceed these limits, then the valves will be considered inoperable and corrective action initiated in accordance with IWV-3417(b). This position does not comply with the staff position or US NRC Draft IST Generic Letter Supplement 1, Item 7, however, see attached "Analysis of Valve Stroke Times at Nine Mi le Point Unit 1" for supporting information.

The basis of full-stroke times for all valves in the NMPl IST Program Plan is attached (see Procedure SEI-705). The basis for these values comply with the USNRC Draft IST Generic Letter Supplement 1, Item 6.

Full flow testing of check va 1 ves is ver ifi ed either by passing the maximum required accident condition flow through the valve or by disassembly and inspection of the valve. Relief Requests are provided for those check valves where disk position at a lower flow rate are fully open (i.e., CS-RR-2, CTS-RR-2). Except where specific relief is requested, this position complies with the USNRC Draft IST Generic Letter Supplement 1, Items 2 and 3.

Relief requests and cold shutdown justification bases have been revised in response to spec i fi c quest i ons.

Core Spray System Test line valves 40-05 and 40-06 have been added to the original response. Thi s position compli es with the USNRC Draft IST Generic Letter Supplement 1, Item 5.

Individual excess flow check valves are included in the IST Program Plan through General Relief Request VG-3 which was revi sed to pr ovi de a more detailed technical justification for not testing quarterly or during cold shutdowns.

10. No change from the original response. This position complies with the USNRC Draft IST Generic Letter Supplement 1, Item 4.

Safety related components in the Emergency Diesel Gener ator air start, cooling water and fuel oil transfer systems have been included in the IST Program Plan and are tested in accordance with the Code except where specific relief has been requested. This po'sition complies with the US NRC Draft IST Generic Letter Supplement 1, Item l.

12. No change from the original response, see Relief Request CS-RR-1. This position complies with USNRC Draft IST Generic Letter Supplement 1, Item

13. No change from the original response. The discussion on Page III-6, "Valve Fail Safe Testing" was revised to include more details concerning this testing. This position complies with USNRC Draft IST generic Letter SUpplement 1, Item 1.

14. Active valves with remote position indicators are tested in the IST Program Plan.

B. Main Steam S stem Main Steam System Relief Request, MS-RR-1 has been revised to expand the discussion on stroke time relief to demonstrate that it is impractical to obtain accurate stroke time measurement of these valves.

2. Main Steam System Relief Request, MS-RR-2, has been expanded to explain why it is not possible to enter the drywell during normal operation or cold shutdowns to exercise the ADS Vacuum relief line check valves. These valves will be exercised at refueling. This relief request also explains why the torque or force required to actuate the valves is not measured.

3. No change from the original response.

C. Feedwater System-No change from the original response.

2. No change from the original response.

D. Reactor Recirc S stem No change from the original response.

Control Rod Drive S stem Additional technical discussion has been provided in Relief Request, CRD-RR-1, to explain how the Technical Specification Control Rod Scram Insertion Time Testing meets the intent of Section XI testing requirements.

2. Relief Request CRD-RR-1 has been expanded to provide additional justification for testing eight of the 129 control rod drive valve sets (108, 126, 127 and 138) during cold shutdown.

3. Notes 2, 3, 4 and 5 in the CRD Section of the IST Plan together with Relief Request CRD-RR-1 provide the bases to demonstrate why the technical specification control rod scram insertion testing meets the intent of Section XI testing requirements. The reqUest for relief and the specification of the alternate test frequency are in accordance with the USNRC Draft Generic Letter Supplement 1, Item 8.

Reverse flow closure of control rod drive valves 138 is verified during the Technical Specification control rod scram insertion testing. See response to Item 3 above. Note 4 provides additional information on reverse flow testing of these valves.

5. These valves (301-3A and -3B) are not safety-related and are not included in the IST Program. The CRD pump and associated valves do not perform a safety-related function.

6. Valves 301-112 and 301-113 will be ASME XI leakage tested.

7. No change from the original response.

8. Additional discussion has been provided in relief request CRD-RR-2 to demonstrate the impracticality of stroke time testing valves 44.2-15 and 44.2-18 during power operation.

g. No change from the original response.

Hi h Pressure Coolant Injection (Feedwater/HPCI)

No change from the original response.

lA. Reverse flow closure of valves 31-01 and 31-02 will be performed during cold shutdowns as discussed in FW/HPCI-CS-2.

2. The valves listed in guestion 2 are not safety-related. These valves have been deleted from the IST Plan.

3. No change from the original response.

G. Reactor Core Spray S stem No change from the orig',nal response.

1A. Valve 53-08 is the Condensate Storage to CRD pump suction. This valve is not safety-related and is not included in the IST Program. All valves listed in guestion 1 are included in the IST Plan.

2. Valves 40-01, -09, -10 and -ll are not leakage rate tested to verify a pressure boundary isolation function. Cold Shutdown Test Justification CS-CS-1 has been deleted.

0

3. Valves 40-03 and 40-13 are exercised with approximately 2200 gpm during quarterly testing as opposed to design accident flow of 3400 gpm. Relief

' 4.

Request CS-RR-2 discusses the near full-stroke exercise of these valves.

These val,ves are not currently required to be Appendix J, Type C, leakage rate tested. These valves are tested as Pressure Isolation valves.

5. Core Spray Relief Request CS-RR-1 addresses testing for valves 40-20, -21,

-22 and -23. The valves will be verified to shut in series quarterly and individually at refueling and certain cold shutdowns.

6. Valves 81-07, -08, -27, and -28 are exercised with approximately 2200 gpm during quarterly testing as opposed to design accident flow of 3400 gpm.

Relief Request CS-RR-2 discusses the near full-stroke exercise of these valves.

7. No change from the original response.

8. No change from the original response.

9. When the system is shutdown these valves open to break vacuum and allow these pipes to drain to the torus. The valves (CRS-10, CS-C-3) are included in the plan for disassembly and inspection every refueling outage.

H. Emer ency Cooli n System Justification for cold shutdown testing of valves 39-05 and -06 has been addressed in Cold Shutdown Justification EC-CS-l. Opening these valves during power operation would cause a cold water reactivity transient and could result in a plant shutdown.

2. Valves 60-17 and 60-18 are control valves. The fail-safe feature of the actuator is tested in accordance with IWV-3415. Also, see Generic Valve Relief Request VG-5.

3. Valves 05-01, -02, -03 and -04 (05-01R, 02R, 03R and 04R in IST Program Plan) are included in the IST,Program and will be tested quarterly. The referenced cold shutdown justification was deleted.

4. No change from the original response.

5. Valves 05-05, -07, -ll and -12 are included in the IST Plan and are tested quar ter 1y.

Valves 39-03, -04, -05 and -06 are currently under a schedular exemption from leakage testing (1988). They will be leakage tested during the next refueling outage (1991). See Emergency Cooling IST Plan Section for other Section XI Test Requirements.

I. Reactor Shutdown Coolin S stem Valves 38-01, -02, -12 and -13 will be leakage rate tested in accordance with Appendix J, 10CFRSO. These valves are currently under a schedular exemption for the 1988 outage.

2. No change from the original response.

Containment S ray S stem Valves 80-01, -02, -21 and -22 are now included in the IST Program and tested in accordance with the Code.

2. Valves 80-05, -06, -25 and -26 are full exercised quarterly at the maximum flow-rate of the test line, about 2900 gpm as opposed to design accident flow of 3000 gpm. Relief Request CTS-RR-2 discusses the near full-stroke exercising of these valves.

3. The containment spray check valves 80-17, -18, -19, -37, -38,. -39, -65,

-66, -67 and -68 will be air tested to verify forward flow operability until a plant modification is implemented to facilitate full stroke exercising. See CTS-RR-l.

4. No. These valves are in the IST Program but are not required to be leakage tested. They fail open on loss of electrical power but fail as is on loss of air. See Note 1 in the Containment Spray IST Plan section.

5. Valve CS-C-4 has been retired. Valve 80-43 is a manual valve and is not in the IST program.

6. No change from the original response or from the additional comment.

Valves 93-49 and -50 have been retired from service and replaced by valves 93-60, -62, -72 and -73. Valves 93-60 and -62 are Category AC and 93-72 and -73 are Category A valves. These valves have been incorporated into the IST Program.

8. Valves 93-60 and -62 are exercised quarterly in both forward and reverse directions. These have been recategorized as Category AC. No relief is requested. See A.l response for general approach on check valve diassembly and inspection.

9. No change from the original response.

K. Reactor Cleanup S stem

l. No change from the original response.

lA. Valves 63.2-01 and -02 are forward and reverse flow tested. No relief is requested.

L. Inert Gas Pur e and Fill System No change from the original response.

2. No change from the original response.

1. No change from the original response.

2. Those valves having fail-safe actuators will be fail-safe tested to their safety function. Those valves which have remote position indication will have this feature verified in accordance with the Code.

3. Valves 201.7-08 and 201.7-09 are now Category A valves in the IST Program and are Appendix J, Type C tested.

4. No change from the original response.

N. Traversin In Core Probe S stem

1. No change from the original response.

2. No change from the original response.

3. No change from the original response.

S 1 S

1. No change from the original response.

2. Valves 201.8-02 and 201.9-49 are control valves. The fail-safe feature of the actuator is tested in accordance with IWV-3415. See Generic Valve Relief Request YG-5.

P. Reactor Buildin HVAC

1. No change from the original response.

Q. CR-HVAC

1. P@ID was provided. Valves in the CR-HVAC System are included in the IST Program. Dampers in the system are not included in the IST Program.

R. Reactor Liquid Poison

1. Reverse flow closure will be verified at refueling intervals until the next outage (1991) when modification will be performed to add the necessary test connections to permit quar terly testing. See Relief Request LP-RR-3.

2. Valves 42.1-02 and 42.1-03 are tested in the forward direction during refueling as detai led in Relief Request LP-RR-1. Reverse flow closure will be verif i ed at refueling during Appendix 0, Type C, testing per Relief Request LP-RR-2.

S. S ent Fuel Stora e Pool Filterin and Cool in S stem

1. No change from the original response.

lA. No change from the original response.

2. Valve 54-16 is a passive valve and is not included in IST Program Plan.

Valves 54-17 and -18 are included in the IST Program Plan.

1. No change from the original response.

2. Valves 110-127 and -128 are included in the IST Program and are Appendix J, Type C tested. See the Reactor Recirculation IST Program Plan Section.

U. Reactor Bui ldin Closed Loo Coolin S stem

1. No change from the original response.

2. Valves70-212 and -222 are included in the IST Program and are fail-safe tested. ~ They are also exercised and have their full-stroke times measured.. ~

3. Valve 70-257 and 70-MU-7 are disassembled and inspected every refueling.

These are check valves whose safety function is to isolate the RBCLCW System from the CLC makeup tank.

4. Valves 70-92, -93, -94 and -95 wi 11 be exercised and are leakage rate tested. Valves 70-93 and 70-95 wil'1 be tested for reverse flow in accordance with RBCLCW-RR-3. See response to guestion L.3.

V. Condensate Transfer S stem

1. No change from the original response.

1A. The safety-related function of this system is to provide makeup to the emergency cooling system and the fuel pool cooling system. The safety-related active valves associated with this system are included in the IST Program.

2. No change from the original response.

W. Torus Vacuum Relief

l. Valves 68-01, -02, -03 and -04 perform a safety-related function in the closed and open direction. These valves are equipped with remote position indication for verification of position.

2. Valves 63.1-01 and -02 are passive valves and are not included in the IST Program.

X. Emer enc Service Water S stem

1. No change from the original response.

lA. No change from the original response.

1B. Valves 72-11 and 72-12 do not provide a safety function in the closed direction. These valves wi 11 be disassembled for inspection in lieu of forward flow exercising per Relief Request ESW-RR-l.

1C. CS-1 as stated in Revision 0 has been presented as a Relief Request in Revision 1 (See ESW-RR-2).

Y. Emer enc Diesel Generator Start Air and Coolin Water

1. The EDG air start relay valves, (Relay Valve -102 and -103), the pinion drive solenoid valves, (DGA-SOV-1 and -2) are not included in the IST Program. These valves are skid mounted and the valves are inter locked with diesel operation.

Z. Waste Disposal

1. No change from the original response.

2. No change from the original response.

AA. Instrument Air S stem

l. No change from the original response.

NOTE: All active safety-related valves are included in the IST Program.

BB. Emer enc Diesel Generator Fuel Oil Handlin S stem

1. Safety-related active valves in this system are included in the IST Program, or relief is requested.

.

CC. Breathin Air to Dr well S stem No change from the or i g i na1 response.

2. Valves 114-BAl and BA2 have been renumbered 114-BA-102 and -103. They are Category A valves and are leakage tested in the Appendix J Type C Test Program.

DD. Chilled Water S stem All active safety-related valves in the chilled water system have been included in the IST Program.

2. PUMP TESTING PROGRAM General Pump Relief Request PG-1 has been revised to address vibration allowable ranges for pumps. Where code specified allowable ranges cannot be met for other parameters, specific pump relief requests wi 11 be provided, on a case by case basis.

2. Pump Relief Request PR-6 was revised to address vibration measurement points for the pumps listed in PR-6. Since these pumps are vertical centrifugal submerged pumps and the pump bearings are not accessible, the vibration measurements wi 11 be taken on the pump motors.

PR-1 was revised to provide tempor ary test instrumentation in order 'to measure individual flow rates for the Emergency Diesel Generator Cooling Water Pumps.

4, A plant modification is being performed to add pressure instrumentation in order to determine independent pump differential pressure for the Core Spray and the Core Spray Topping Pumps. General Pump Relief Request PG-2 was generated to calculate pump inlet pressure. Relief Request PR-2 was revised to delete the combined differential pressure request.

5. PR-1 was revised to provide temporary test instrumentation in order to measure individual flow rates on the Condensate Transfer Pumps. The PAID was provided that shows these pumps.

6. A plant modification is being performed to add pressure instrumentation on the discharge of the Emergency Diesel Generator Fuel Oil Transfer Pumps in order to determine pump di fferenti al pressure. General Pump Relief Request PG-2 was generated to calculate pump inlet pressure and the old pump Rel i ef Request PR-4 for the Emergency Di ese1 Generator Fuel Oi 1 Transfer Pumps was deleted.

7. Pump Relief Request PR-8 now addresses the use of 'the Emergency Diesel Generator Fuel Oil Day Tank level in order to calcul ate the Emergency Diesel Generator fuel oil transfer pumps flow rate for determining pump oper abi 1 i ty.

No change from the original response.

No change from the original response.

10. No change from the original response.

11. Pump Rel i ef Request PR-4 was revi sed for not measuring pump inl et pressure.

12. Pump Relief Request PR-5 was revised to provide tempo ary test instrumentation in order to measure Emergency Service Water Pump flow rates.

13. Pump Relief Request PR-3 now addresses testing to permit individual Reactor Bui lding Closed Loop Cooling Water pump flow rate measurements during cold shutdowns since these pumps are required, by system constraints to be run in pairs during normal plant operation.

14. Pump Test Table Note Number 3 was revised to reference General Pump Relief Request PG-2. This permits calculation of pump inlet pressure for the pumps that specifically utilize pump test table Note 3.