Text

Rev 3 to Pump & Valve Inservice Testing Program Plan
	ML20073K145
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	04/04/1983
From:	Holland N, Koehl A; NUCLEAR ENERGY SERVICES, INC.
To:	;
Shared Package
ML20073K134	List: ML20073K133; ML20073K145;
References
	80A2903, NUDOCS 8304190544
	Download: ML20073K145 (200)
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DOCUMENT NO, 80A2903 REV. 2 mr NUCLEAR ENERGY SERVICES, INC. PAGE i 0F 4ii q

O PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR LONG ISLAND LIGHTING COMPANY SHOREHAM NUCLEAR POWER PLANT ym UNW1 r i

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i Date Project Applicatiori Prepared By Albert A. Koehl 12/21/81 5536 APPROVALS DATE TITLE / DEPT. SIGN AT U R E

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, No) DATE ^[ DESCRIPTION APPROVAL 1 Mar,17,1982 See CRA 2422 , Incoporate s Customer -

Comments and corrncts typn'n. l

-p 2 2/25/83 All son CRA #3179. Total ravision incorreratas NI customer and NRC comment.

3 4/04/83 See CFA . Incorporates Customer A, b comments, redefines " passive" valves, removes stroke times for Air Operated valves, adds Document numbers to title pages for attachments 2 through 24 of Section III, revised test requirements for system " Keep Fill" Valves (Ell-0022A,B:

Ell-0023: Ell-0028: E21-0018A,Bt 41-0019),

Revised test requirements for E21-AOV-

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v' 081A.B. added new relief recuest for valves T48-SOV-136A.B: T48-SOV-137A,B, renumbered oaces to ref' lect revised test recuirements add a ceneral relief recuest to perform pmm vibration velocity measurements, and enrroevoA rypn*n.

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DOCUMENT NO. 80A2903 REV 2 -

PAGE iii OF iii TABLE OF CONTENTS ~

Page Section I - Overview y_y Section II - Pump IST Program Plan II_1 Section III - Valve IST Program Plan III_1 O

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Document No. 80A2903 Rev. 2 N_./

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SIIOREHAM NUCLEAR POWER STATION UNIT 1

( ,) SECTION 1 OVERVIEW fg

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Docum:nt No. 80A2903 Rtv. 2

1. Introduction This document presents the Program Plan for Inservice Testing (IST) programs at Unit 1 of the Shoreham Nuclear Power Station in compliance with the requirements of 10CFR50.55a. These Program Plans have been prepared to the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Subsections IWP and IWV, 1980 Edition through the Winter 1981 Addenda. Acccrding to 10CFR50.55a, the Code edition and addenda applicable to Pump and Valve IST Programs will be these in effect twelve months prior to issuance of an operating license. Accordingly, these Program Plans will be revised, as necessary, to meet the requirements of new Code editions and addenda as applicable.

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l Docum:nt No. 30A2903 R:.v. 2 j

2. Basis In addition to the reference Code edition and addenda, these Program Plans have been prepared in compliance with NRC guidance contained in " Guidance for Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests Pursuant to 10CFR50.55a(g)" and the November 1981 Draft Regulatory Guide

" Identification of Valves for Inclusion in Inservice Testing Programs." These three documents provide the basis for selection of components, test requirements, g relief requests and format. *

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Docum:nt No. 80A2903 Rev. 2 l' ,

'x_ / 3. IST Program Plan 2eriod 10CFR50. 55a (g) specifies that the Section XI Pump and Valve Inservice Testing Program shall be initiated at the start of commercial operation of the facility.

Further, the Program Plan must conform to the requirements of the Code edition and addenda in effect no more than twelve months prior to commercial operation. This plan will be reviewed, as necessary, to assure conformance.

The plan will then be in effect for the first 120 month period. It will be updated for each subsequent 120 month period to conform to the edition of the Code and addenda in effect no more than twelve months prior to the start of that period.

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Document No. 80A2903 R;v. 2

4. General Program Plan Concept The Program Plan specifiesSection XI testing requirements for components providing, either by action or position, a safety related function. By definition, a safety related function is one that is used in, a) Mitigating the consequences of an accident b) Shutdown of the reactor to the cold shutdown condition c) Maintaining the reactor in a safe shutdown condition Plant technical specifications, special manufacturer's tests, system operating conditions, etc., may dictate additional components which should be included in the overall plant testing program, but whose functions fall outside the three criteria above, and are therefore not addressed by this Program Plan.

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

a) Be impractical due to system or component design b) Render a safety related system inoperable c) Cause a reactor scram or turbine trip d) Require significant deviations from normal plant operations e) Require entry into inaccessible plant areas

_ f) Increase the possibility of an intersystem LOCA

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Each component excluded from quarterly testing has been analyzed to determine when appropriate testing may be performed. If operation of a valve is not practical during plant operation, the Code allows part-stroke exercising during normal plant operation and full-stroke exercising at cold shutdown.

Since the Code accepts cold shutdown testing, this program does not request relief for those valves for which testing is delayed until cold shutdown. The Program does provide a justification for 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.

Where it has been determined that testing is not practical during plant operation, or at cold shutdown, a specific relief request has been prepared. Each specific relief request provides justification for not performing the Code specified tests, and provides appropriate alternative testing.

In addition to specific relief requests, general relief requests which address specific Code requirements found to be impractical for this site have been prepared.

Because of the general nature of those relief requests, and the number of components involved, they are presented in a separate section, and are not repeated in the individual systems sections.

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Document No. 80A2903 - Rev. 2 3

V' 5. Organization The Pump and Valve' Inservice Testir.g Program Plan is organized into three independent sections, each of which can' be removed from the Procram Plan for review.

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 impractical for this site.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 7 summarizes the basis 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, a f_ justification for . delay of test to cold shutdown, or a relief request -is provided, following the appropriate Pump or Valve Test Tables.

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Document No. 80A2903 Rev. 2

'/~N 6. Definitions d'

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

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

Cold Shutdown: Testing delayed until cold shutdown will commence as soon as the plant cold shutdown condition is achieved, buc no later than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after shutdown.

Testing will continue until all tests are complete, or the plant is ready tb return to power. Completion of all testing is not a prerequisite to return to power, and any testing not completed at one cold shutdown will be performed during subsequent cold shutdowns before the refueling outage. No cold shutdown testing will be performed on components tested less than 90 days. prior to achieving cold

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shutdown. The 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months interval will not hold for planned cold shutdown.

Refueling: Testing delayed until refueling will be performed during the normal scheduled refueling shutdown before ret,urning to power operation.

Period: Category C safety and relief valves (IWV-3511) and J( ) ' LCategory D explosive actuated valves (IWV-3610) are tested to the time periods defined in the appropriate Code sections.

Pressure Isolation: Any valve which acts as an isolation boundary

.. between the high pressure reactor coolant system

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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, type C Local Leak Rate test program.

Active: Any valves which is required to chance position to accomplish its safety related function.

Passive: Any valve which is not required to change position to accomplish its safety related function but whose position is important to safety related system

' operation.

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Document No. 80A2903 Rev. 2 O- 7. General Relief Requests This section requests relief from specific sections of Section XI found to be impractical for this site. Since they are general in nature and pertain to a number of components this section requests general relief as presented below.

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

Category: A,B ;

Code Requirements: IWV-3417 requires corrective action if the mear ed -

stroke time for a valve which normally strokes in .

ten seconds or less varies by fifty percent from the ,

last measured stroke time. IWV-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 wnen the valves are functioning normally. These valves are generally small air and solenoid operated valves which because

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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 degredation. This type of valve does not lend itself to this tracking technique.

Alternate Testing: A maximum stroke time of five seconds will be specified for each rapid actuating valve. If the valve strokes in five seconds or less it will be considered as acceptable and no corrective action 1

will be required. If the valve exceed five seconds j it will be considered inoperable and appropriate i corrective action will be taken.

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Document No. 80A2903 Rev. 2 4

General Relief Request: G-2

Component: Containment Isolation Valves Code Requirements: For Section XI category A valves IWV-3426 requires the establishment of individual valve permissible

leakage rates. Each time leak-rate tests are

, performed the test results are to be compared with the previous. test results and the permissible leakage rates. IWV-3427 establishes test result rejection criteria.and specifies corrective actions to be taken.

Category: A,AC Basis for Relief: IWV-2200(a) defines category A valves as " valves for which seat leakage is limited to a specified maximum amount in the closed position of fulfillment of their function. " The intent of the Code requirement is to verify that valve leakage is limited to an acceptable value. For containment i

isolation valves an acceptable total allowed leakage rate has been established in compliance with the requirements of 10CFR50 Appendix J. Performance i .

of Appendix J, Type C Local Leak Rate testing O fulfills the intent of Section XI Category A. valve V seat leak testing for containment isolation valves. ,

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

individual valve seat leak testing.

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Document No. 80A2903 Rev. 2 G-3 General Relief Request:

Component: Excess flow check valves Category: AC

Code Requirement: IW-3521 requires operability test of check valves and IW-3522 describes the required

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testing procedure.

Basis for Relief: The excess, flow checks are devices which are designed.to activate and--limit flow to a ,

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specified value. The test requirements for a

check valves in the Code are intended for simple check valve testinif. Quarterly testing i

is not practical since these are instrument 4 line valves which are-in use during plant operation and cold shutdown.

Alternate Testing: Plant Technical Specifications Table 3.6.3-1 lists all excess flow checks which require l testing. Technical Specification

-Section 4.6.3.4 specifies testing to verify operability and acceptance criteria for measuring the flow limiting capability.

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General Relief Request: G-4 Component: Pressure isolation valves Code Requirements: For Section XI Category A Valves, IWV-3426 requires comparison of measured leakage rates with previous measured leakage rates.

Category: A,AC i

Basis for Relief: Technical Specification section 3.4.3.2 defines the limiting conditions for operation and section 4.4.3.2.2 defines the surveillance requirements for pressure isolation valves. The limiting condition is specified as a maximum leakage rate of 1 gal / min at normal operating pressure. The surveillance requirements specifies leak rate testing once every 18 months and when repair or maintenance is performed that could affect the leakage rate. The intent of the Code requirement to' compare leakage rates is to perform trend analysis which could be used to predict failure. Because of the long time

{ interval between tests the comparison of data will not provide any useful information.

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Alternate Testing: The Technical Specification defined surveillance testing will be performed, but no comparison of test results to previous results will be performed.

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Document No. 80A2903 Rev 3 4

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V General Relief Request: G-5 Component: All safety-related pumps.

Test Requirements:

Vibration amplitude measurement using displacement (IWP-4500) and allowable ranges of test quantities

. (Table IWP-3100-2). .

Basis for Relief: A survey of plants with c.~.isting pump vibration test t

programs has been conducted in conjunction with a review of pump vibration testing literature. The consensus of opinion from both sources is that a significant improvement in the predictive capability of vibration testing can be achieved by measuring

vibration velocity in place of vibration displace-ment. However, the literature review failed to provide a definitive reference standard for analysis of test results. A standard will be developed and submitt.ed to the NRC for review and approval prior to commerical operation.

Alternate Testing: Pump vibration testing will be performed for,both preservice and inservice testing using vibration velocity measurements in lieu of displacement (g) m measurements.

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Document No. 30A2903 Rev. 2

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PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHOREHAM NUCLEAR POWER STATION UNIT 1 SECTION II PUMP IST PROGRAM PLAN

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Document No. 80A2903 Rev. 2

1. Introduction This section presents the Program Plan for Inservice Testing of pumps at Unit 1 of the Shoreham Nuclear Power 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 IWP, 1980 Edition through the Winter 1981 Addenda. According to 10CFR50.55a, the Cc>de edition and addenda applicable to pump IST programs will be those in effect twelve months prior to issuance of an operating license. Accordingly, this Program Plan will be revised, as necessary, to meet the requirements of new Code editions and addenda as applicable.

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j Document No. 30A2903 Rev. 2 d

.)( 2. Pump IST Program Plan Concept 7

The Pump Program Plan specifiesSection XI testing requirements for..all ASME l, . Class 1, 2, and 3 pumps provided with an emergency power source and which are

required _for safety related system operation. Section'XI test requirements found to-be impractical for this site are addressed in relief requests. Each relief request provides justification for not performing the Section XI.specified test, and provides ,

appropriate alternate testing.

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Document No. 80A2903 Rev. 2 f"%

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Pumps required for safety related system operation for this site are as follows:

System Dwg. No. Rev. No. No. of Pumps RHR FM-20A 15 2 RIIR FM-20B 15 2 IIPCI FM-2 W 12 1 RCIC FF-22B 11 1 CORE SPRAY FM-23A 15 2 SBLC FM-21A 14 2 SERVICE WATER FM-47A 12 4 RBCLCW FM-15A 13 3 RBSVS & CRAC

--s CHILLED WATER FB-43A 11 2 RBSVS & CRAC CIIILLED WATER FB-43B 11 2 RBSVS & CRAC cot 1DENSING WATER FB-43A 11 2 RBSVS & CRAC CONDENSING WATER FB-43B 11 2 FPCCU FM-19A 12 2 DIESEL FUEL OIL TRANSFER FM-44A 11 6 SUPPRESSION POOL LEAKAGE RETURN FM-46B 9 1 II-4 NUCLE AR ENERGY SERVICES IPeC.

Document No. 80A2903 Rev. 2

4. Pump Table Nomenclature The following abbreviations have been used in the pump test table.

N = Rotative Speed Pi = Inlet Pressure AP = Dif ferential Pressure Across Pump Of = Flow Rate V = Vibration Amplitude Tb = Bearing Temperature Q = Quarterly X = Measurement / Observation Per IWP L =

Lubricant Level of Pressure R = Relief Request

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Document No. 30A2903 Rev. 2

5. Pump Table Notes In the pump table, the test parameters to be measured or observed and the test frequency are identified. Footnotes 1 through 10 refer to anplification, deviations and exceptions to the Code requirements and are further ciscussed below:

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

(2) Inlet pressure to be calculated from the inlet liquid level. The liquid level will be measured while establishing and verifying Feference Data sets and used as information during subsequent test analysis.

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

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

(5) Clamp on ultrasonic flow meter to be used. Report No. ARL 35-82/C324 verifies the tolerance and accuracy to be within Section XI requirements.

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

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(7) Pump inlet pressure determined from head tank level.

(8) Pump inlet pressure determined from spent fuel pool level.

(9) Flow rate will be measured by measuring day tank level vs time during pump test.

(10) Lubricant temperature measured (IWP-4310) by installed thermocouple in the pump crankcase in lieu of measuring bearing temperature.

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Document No. 30A2903 Rev. 2 7m, N_,]

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHOREHAM NUCLEAR POWER STATION UNIT 1

,N SECTION II E I s ,/

ATTACIDIENT 1 PUMP TEST TABLE AND PILIEF REQUESTS FOR PU:!PS f

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. x-DOCUMENT NO. 60A2903 WV 2 11EN PUMP TEST TABLE PAGE II-l-2 OF II-I-9 PUMP LIST MEASURED PARAMETERS REV SYSTEM PUMP l.D. DWG. NO. COORD. CLASS N P6 i. P Og V L Tb

, P-014A RI-20A F-7 2 O (1) X X X X ( 3) (6)

P-014B ITt-200 E-7 2 O (1) X . X X ( 3) (6)

P-014C HF20A F-8 2 O (1) X X X X ( 3) (6)

P-0140 ET1-20B E-8 2 Q (1) X X X X ( 3) (6) linCI P-016 ET1-25B D-4 2 0 X X X X X R X fCIC P-015 IT1-22D D-4 2 Q X X X X X R X L14C SPRAY P-013A FN-23A B-8 2 O (1) X X X X ( 3) (6)

P-013B Ell-23A 11 - 8 2 O (1) X X X X (3) (6)

I l STNUlY llOUID P-024A fM-21A 11- 5 2 O (1) X X X X (10) X P-024B E11-21A 11- 7 2 O (1) X X X X (10) X i

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DOCUMENT NO. 80A2903 lbv 2 PUMP TEST TABLE op TT-1-9 PAGE TT-1-3 PUMP UST MEASURED PARAMETERS REV SYSTEM PUMP LD. DWG. NO. COORD CLASS FR O. N Pt aP Qg V Tb L SERVICE WNITR P-003A EN-47A G-7 3 0 (1) (2) X X R (3) (6)

P-003B EM-47A 11- 7 3 0 (1) (2) x X R ( 3) (6)

P-00 M EM-47A F-7 3 Q (1) (2) X X R ( 3) (6)

P-003D EM-47A J-7 3 Q (1) (2) X X R (3) (6)

Id1CILW P-005A EM-15A E-2 3 Q (1) (7) X (5) X X (6)

P-005B EW 15A J-2 3 0 (1) (7) X (5) X X (6)

P-005C EM-15A 11- 2 3 Q (1) (7) X (5) X X (6)

I43SVS & CI'JC P-137A FB-43A D-4 3 Q (1) X X X X X X P-137B FD-43B D-4 3 Q (1) X X X X X X P-138A FB-43A D-6 3 0 (1) X X X X X X P-138B m-43B D-6 3 Q (1) X X X X X X F4L'VS & CRAC P-139A FB-43A D-3 3 0 (1) X X X X X X

P-139B EB-41n D-3 3 Q (1) X X X X X X P-140A FB-43A D-5 3 0 (1) X X X X X X P-140B FB-43B D-5 3 0 (1) X X X X X X ERI'U P-023A EM-19A E-7 3 0 (1) (8) X X X X X P-023B EM-19A E-8 3 0 (1) (8) X X X X X ses s245

x C,/h U("'t V DOCUMENTNO. 80A2903 M2 DES PUMP TEST TABLE II~I-4 II'l~9 PAGE OF PUMP LIST MEASURED PARAMETERS REV SYSTEM PUMP l.D. DWG. NO. COORD. CLASS F . N P6 i.P Og V Tb L SUPPIESSILH WXL P-270C FN-46B C-7 3 ID JG E ICIUlt4 0 (1) R X X X X X DIESEL FUE:L OIL P-201A EN-44A B-5 3 O (1) R X (9i X X (f)

P-2018 FN-44A a-8 3 0 (1) P X (9* X X (f)

P-201C IN-44A D-6 3 0 (1) R X (9) X X (h)

P-202A EN-44A C-8 3 O (1) P X (9i X X (6)

P-202B f>F44A C-5 3 0 (1) R X (9) X X (6)

P-202C FN-44A C-6 3 0 (1) R X (9) X X (0)

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Document No. 80A2903 Rev. 2 n'

Shoreham No. 1 Relief Pequest System: HPCI Pump: P-Ol6 Class: 2 Function: Emergency Core Cooling Test Requirments: Measure bearing temperature.

Basis for Relief: The HPCI Pump is an integral unit with the steam driven turbine. Bearing temperature is a direct function of steam temperature. Therefore, measurement of bearing temperature would provide no meaningful information about the bearing.

Alternate Testing: None.

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Document No. 30A2903 Rev. 2

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..r Shoreham No. 1 Relief Request System: RCIC Pump: P-015 Class: 2 Function: Provide adequate core cooling during reactor shutdown and isolation should the feedwater system not be available to provide the required make-up water.

Test Requirements: Measure bearing temperature.

Basis for 'lelief: The RCIC pump is an integral unit with the steam driven turbine. Bearing temperature is a direct function of steam temperature. Therefore, measurement of bearing temperature would provide no meaningful information about the bearing.

Alternate Testing: None. .

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Document No. 80A2903 Rev. 2 v

Shoreham No. 1 Relief Request System: Service Water Pump: P003A,B,C,D Class: 3 Function:

Provide cooling water to safety related equipment.

Test Requirements:

IWP-4500 specifies measuring vibration at the pump bearing housing or its structural support unless it is separated from the driver by any resiliant mounting.

Basis for Relief: The service water pumps are submerged under water and are inaccessible to perform vibration measure-ments. The motor drivers are shaft connected to the pumps and are accessible.

Alternate Testing:

i Vibration measurements will be made on the lower (closest to pump) motor bearings.

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Document No. 80A2903 Rev. 2 Shoreham No. 1 Relief Request System: Suppression Pool Leakage Return Pump: P-270C Class: 3 Function: Return fluid to the suppression pool resultisig from pump seal leakage, instrument line leakage or valve packing failure.

Test Requirements: Measure pump inlet and differential pressures.

Basis for helief: Pump is located above the sump pump fluid level and is designed to be self primina (neaative NPSH) pump capable of five foot of lift. There is no pressure tap installed to measure pui..p Anlet pressure or differential pressure.

Alternate Testing: Pump outlet pressure and flow are measured per code and will be used to evaluate pump performance.

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Document No. 30A2903 Rev. 2 l'

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Shoreham No. 1 Relief Request System: Diesel Fuel Oil Transfer Pump: P-201A,B,C P-202A,B,C Class: 3 Function: Transfer diesel fuel oil from the storage tank to the day tank.

Test Requirements: Measure pump inlet and differential pressures.

i Basis for Relief: Pump is located above the storage tank fluid level and is designed to be a self priming negative NPSH pump.

There is no pressure tap installed to measure pump inlet or differential pressure.

Alternative Testing: Pump outlet pressure is measured per Code and flow rate determined by measuring day tank level vs time during pump test. Outlet pressure and flow rate will be used to evaluate pump performance.

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Document No. 80A2903 Rev. 2 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHOREHAM NUCLEAR POWER STATION UNIT 1 SECTION III VALVE IST PROGPA'1 PLAN 7_

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Document No. 30A2903 Rev. 2

1. Introduction This section presents the Program Plan for Inservice Testing of Valves at Unit 1 of the Shoreham Nuclear Power 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, 1980 Edition through the Winter 1981 Addenda. According to 10CFR50.55a, the Code edition and addenda applicable to valve IST programs will be those in effect twelve months prior to issuance of an operating license. Accordingly, this Program Plan will be revised, as necessary, to meet the requirements of new Code editions and addenda as applicable.

i III-2 NUCLEAR ENE AGY SERVICES INC

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Document No. ' 30A2903 Rev. 2

2. Concept The Valve Test Program Plan was developed to verify the operability of safety i

related systems. Two of the elements assuring system operability are valve operability and position of self actuated and power operated valves. The program addresses those self actuated and power operated valves whose operability and/or

, positicn are essential to safety related system operation.Section XI valve testing is performed to verify. valve operability. The correct positioning of passive valves is verified by either direct observations or by other appropriate indicators, such .

as, indicator lights. This program. specifies either Section XI.or alternate testing,-

as appropriate, for those valves which perform a safety related function.

valves are selected for incluslon in the test program based on a review of all 4 plant systems. This review identifies those systems performing safety related functions. Each safety related system is then analyzed to determine which valves are essential to the safety related operation of the system. These valves are

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

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i NUCLEAR ENERGY SERVICES INC.

Docum:nt No 80A2903 R v. 3

3. Code Interpretation A number of items in Subsection IWV of the Code are subject to interpretation.

The interpretations of a number of general items encountered in preparing the Valve Test Program Plan are provided below.

Relief Valves:

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

Passive Valves:

The reference Code excludes valves used only for operating convenience and/or maintenance from testing. Also, the Code defines passive valves but specifies no operability test requirements. This program defines as passive any power operated valve which does not have to change position, but whose position has a direct bearing on safety related system operation.

b System Test Valves:

Valves included in a system to align the system for testing are included for Section XI testing if their position is critical to safety related system operation. The system analysis postulates that the system is in a test mode when the initiation signal occurs. All valves, including those used only for testing, which must respond to the initiation signal, are included in the test program.

Pressure and Flow Control Valves:

,_ The reference Code excludes valves which perform pressure or flow control

(

1 functions. This program excludes them unless they also perform a system safety III-4 NUCLEAR ENERGY SERWCES WC.

Document No. 80A2903 Rev. 2 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 functions.

Automatic Power Operated Valves:

Power operated valves which receive an automatic signal on system initiation are included in the program. Thase valves may be included as passive valves, if appropriate.

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, terminate safety related system operation, or provide containment isolation capability during the long term post-LOCA operating mode. Typical of such valves are suppression pool suction valves which remain open during the accident but provide system isolation during the long term post-LOCA cooling mode.

Normal vs Safety Related System Operation:

Valves in systems which have both normal and safety related operating modes are

, s included in the program, only if they perform a safety related function. Valves which

! provide normal system operation control and whose position has no efrect on safety ,

related operation are excluded from the program.

Dual Function Valves :

Valves which provide more than one function are tested for their safety related function only. Valves with multiple safety related functions are tested for each function. Examples are the automatic depressurization valves, which open and close in response to either an automatic or remote manual signal, and also act as relief valves. Both are safety related functions, and testing for both functions is included in the program. A manual stop check valve will also be a dual function valve if system operation is dependant on both check valve operability and manual operator position. When this condition exists the valve is treated as both an active testable check valve and a passive valve.

Simple Check Valves:

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

III-5 MJCLE AR ENF AGY SE AvlCES INC

Document No. 80A2903 Rev. 2 i

'~'

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 will be tested a simple check or by exercising using the manual exercising device. Check valve equippea with a power operator installed for the sole purpose of exercising the valve for operability will be tested as a simple check or by use of the power operator.

Power Operated Stop Check Valves:

Power operated stop check valve testing 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 i the operator. In addition to exercising, the operator will be timed and failed as appropriate.

Pump Discharge Check Valves:

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

System Piping Keep Fill Check Valves:

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

o III-6 NUCLEAR ENERGY $FRVICES INC

Document No. 80A2903 Rev. 2 i

~r Check Valve Full / Partial Stroke:

In most cases full design flow through a check valve requires less than full mechanical valve movement. As used in this program, the term full stroce refers to the ability of the valve to pass design flow and not the full mechan.eal stroking.

Forward flow full stroke operability testing will be by any method that verifies the valve capable of passing design flow. Any test that verifies less hen full design flow capability is considered as a partial stroke test.

Category A (Containment Isolation Valve) Leak Testing:

All valves ,specified for Appendix J, Type C local leak rate testing are included in the Valve IST Program as Category A valves. A Relief Request (See G-2) has been included to perform tne Appendix J, Type C testing in lieu of testing specified In IWV-3420.

Category A (Pressure Isolation Valve) Leak Testing:

All valvas which perform a pressure isolation functivu between the Re&ctor 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.

w [

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

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

Category A (Pressure Isolation) Valve Operability Testing:

When the pressure boundary consists of a testable check valve and a normally closed power operated valve, operability testing of both will be delayed until 2010 shutdown. Delay of the power operated valve is addressed in Section B.6 of the proposed Regulatory Guide " Identification of Valves for Inclusion in Inservice Testing Program" dated November 1981. Exercising the testable check valve during plant operation is also delayed, based on the lack of provisions for measuring leakage across the check valve. If the check were to be exercised and failed to fully reclose, then any subsequent inadvertent operation of the power operated valve could result in an inter-system-LOCA situation.

Other valve configurations which constitute a pressure boundary will be analyzed on a case-by-case basis to determine if exercising would result in a potential for an inter-system-LOCA. Where such a potential would result, operability testing will be delayed.

III-7 NUCLEAR ENERGV $ERVICES INC

Document No. 80A2903 Rev. 2 Testable Check Valve Eypass Pressure Equalization Valves:

Small power operated valves whose function is to equalize pressure across a testable check valve are not operability tested, but are included in the program as passive valves. The control of these valves is slaved to the check valve test operator. When the check valve is tested the bypass valve opens to equalize pressure and automatically recloses and remains closed at all other times. Its only safety related function is to provide containment isolation, which is assured by performing a position verification.

Locked Valves:

This program plan classifies as locked valves only those which are physically restrained from movement (i.e., chain and padlock), or sealed (i .e. , wire and seal) in position. Keylocked valves are not considered to be physically locked.

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III-8 NUCLEAR ENE AGY SEAvtCES INC.

Docum:nt No. 80A2903 R;v. 2 m

4. Valve Te st Table Nomenclature The following abbreviations have been used in the Valve Test Table.

Valve Type Actuator Type GT Gate BA Dall MO Motor GL Globe A Angle SA self C Check D Diaphragm AO Air EC Stop Check VR Vacuun Felief EM Electro-Mech.

R Relief M Manual E Explosive HYD Hydraulic B Butterfly E Explosive ij Normal Position Frequency 0 Open Q Once per 92 days LO Locked open C Testing performed during cold shutdown (but no sooner than 90 days)

Note: Testing may be performed during C Closed plant operating modes between normal operation and Tech. Spec.

defined cold shutdown conditions .

- Normal position depends on R Once per refueling system conditions (check and relief valves) P Tested during time period defined in:

IWV-3511 (safety and relief valves)

IWV-3610 (explosive actuated valves) n,./

III-9 NUCLE AR ENE AGV SE AvlCES INC

Document No. 80A2903 Rev. 2 x _-/

Test Requirements ET Full exercise ST Stroke time PV Passive valve FS Fail safe SR Relief valve XT Explosive valve VR Vacuum Pelief Valve LP Leak test per Section XI (pressure isolation)

LJ Leak test per Appendix J, Type C (containment isolation)

If Leak test per both Section XI and Appendix J, Type C (both pressure and containment isolation)

'N Stroke Direction v

)

0 Open C Closed Check Valve Test Direction F Forward Flow R Reverse Flow

,r-C a.-l III-10 NUCLEAR ENE AGv SE AvlCES INC

Docum:nt No. 80A2903 R;v. 2 I )

5. Valve Test Table Format Valve No. Unique number assigned to each valve.

Class and Drawing Coor. The ASME valve class and drawing reference location.

This is a two line entry with the class on the first line and drawing coordinate on the second line.

Valve Cat. Valve category as defined subsection IWV-2200.

Size (in.) and Type A two line entry with the first being the valve size in inches and the second the valve type.

Actu. Type The type of operator used to change valve position.

For dual function valves this will be a two line entry. For example, a locked open stop check valve is entered as self-actuating on line one and manual on line t'<o.

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

For multiple loop systems where valve position will depend on which loop (s) is in service, on loop is assumed in operation and the remaining loops are assumed idle.

/ 3

\- Test Req. The test requirements which apply to the valve. For dual function valves multiple line entries of applicable tests which correspond to actuator type.

For example, a locked open stop check valve is entered as exercise test on line one and as passive on line two.

Stroke Direct, and This is a multiple line entry for safety related Time (sec.) stroke direction (first line) and maximum stroke l

time (second line). If both directions are safety related, four lines are used. This column also includes direction and maximum stroke time for posiuive closure power operated stop check valves.

Check Valve Test Direct. Direction of check valve operability verification.

May be a two line entry if valve operability is safety related in both directions.

C.S. Just. or Relief Reference number of the cold shutdown justification Req. No. or relief request which are located following the valve test tables for each system.

v III-11 Nucada ENEaov sEawcEs INc

Docum;nt No. 80A2903 Rev. 2 l

/ C.S. or Alt. Test Cold shutdown or alternate testing which is .

Perf. being performed in lieu of Code specified quarterly testing.

Remarks Amplifying remarks as appropriate.

Rev. No. This column records the latest document revision number for each valve.

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a' III-12 NuctEAa ENEacv stavicts ac

Document No. 80A2903 Rcv. 2 d 6. Index System No. System Dwg. No. Rev. No. Attachment No.

B-21 Main & Aux. Steam FM-29A 11 1

. FM-40B 8 B-21 Feedwater FM-32A 12 2 B-31 Reactor Water Recirculation FM-26A 11 3 FM-26B 4 C-ll Control Rod Drive FM-27A 13 4 FM-27B 13 . w FM-27C 9 C-41 Standby Liquid Control FM-21A 14 5 C-Sl Neutron Monitoring FM-62A 6 6 FM-62B 6 D-ll Radiation Monitoring FM-76A 7 7 E-ll Residual Heat Removal FM-20A 15 8

,m FM-20B 15 E-21 Core Spray FM-23A 15 9 E-32 MSIV Leakage Control FM-69A 5 10 E-41 !!PCI FM-25A 13 11 FM-25B 12 E-51 RCIC FM-22A 13 12 FM-22B 11 G-ll Radwaste Equipment FM-46A 10 13 FM-46B 9 G-33 Reactor Watec Cleanup FM-24A 15 14 G-41 Fuel Pool Cooling & Cleanup FM-19A 12 15 M-50 RBSVS & CRAC FB-43A 11 16 FB-43B 11 P-41 3ervice Water FM-47A 12 17 P-42 RBCLCW FM-15A 13 18 FM-15C 10 s

FB-23B 14 j P-50 Instrument & Service Air FM-38D 7 19 FM-3Et 4

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Document No. 80A2903 Rev. 2 I

x_.,.

6 Index (cont.)

System No. System Dwg. No. Rev. No. Attachment No.

R-43 Fuel Oil Transfer FM-44A 11 20 R-43 Diesel Generator Air Start FM-44B 4 21 T-23 Drywell Floor Scal Pressure FM-55A 7 22 Monitoring i

T-46 Reactor Building Normal FS-23A 12 23 Vent T-48 Primary Containment Atmospheric FM-52A 10 24 Control FM-84A 2

'%,I i !

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Document No. 80A2903 Rev. 2 i

n, /

PUMP AND VALVE INSERVICE TESTING PROGPN1 PIAN FDR SHOREHAM NUCLEAR POWER PI1RT UNIT NO. 1 SECTIO 1 III l

ATIAONI27f 1 v VALVI' TEST TADLES NJD FELIEF PEOCESTS FOR WsIN NJD AUX. STEN 4 (B-21)

DWG. NO. FM-29A i

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SYSTEM: MAIN ND AUX. SWW1 (t5-21)

VALVE TEST TAELE DWG. NO. p 29A 80A2903 Rev 2 DOCUMENT HO. PAGE III-I-2 OF III-I-I L CLASS STROKE C.S. C.S.

SIZE AND DIRECT CHECK JUSI OR VALVE NO. VALVE (IN.) ACTti NORM TEST AND VALVE DWG. CAT. AND TYPE POS11 OR ALI REMARKS REV REQ. TIME TEST CN N RELIEF TEST NO.

(SEC.) DeRECT REO. NO. PERF.

etN-031 1 A 3 to O LT-O C F-7 Cr ST-Q 18 LJ-R ttN-032 1 A 3 FU O LT-Q C 11 - 7 GT ST-Q 18 IJ-R NN-081A 1 A 24 AO O LT-Q C CS-1 LT-C F-4 CL ST-Q 5 CS-1 ST-C FS-Q CS-1 IS-C IJ-R NN-081D 1 A 24 AO O LT-Q C G-l' LT-C F-4 CL ST-Q 5 G-1 ST-C IS-Q G-1 IS-C IJ-R N N-081C 1 A 24 AO O LT-Q C CS-1 LT-C

?-5 CL ST-Q 5 CS-1 ST-C FS-Q CS-1 IS-C IJ-R h W-081D 1 A 24 AO O C LT-Q G-1 Ur-C F-6 CL S F-Q 5 ES-1 ST-C FS-Q CS-1 ES-C IJ-R NN-08. A 1 A 24 AO O LT-Q C CS-1 LT-C 11-4 CL 5 CS-1 ST-Q ST-C FS-Q CS-l ES-C IJ-R NE S d244

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VALVE TEST TABLE N NO. IN-29A DOCUMENT NO. 80A2903 Rev 2 III~I'3 III~I-I3 PAGE OF CLASS STROKE CS. C.S.

SIZE AND DEECT. CHECK JUSI OR VALVE NO. bA1VE (IM) ACTU NORM TEST REV AND VALVE OR ALI REMARKS DWCL CAI AND TYPE POSII REQ. TEST TIME REUEF TEST COOR. TYPE (SEC) DIRECI REO.NO. PERF.

ADV-082D 1 A 24 AO O ET-Q C G-1 ET-C H-4 GL ST-Q 5 CS-1 ST-C FS-Q CS-1 FS-C IJ-R ADV-082C 1 A 24 AO O EM C G-1 ET-C 11- 5 CL ST-Q 5 G-1 ST-C FS-Q CS-1 FS-C IJ-R NN-082D 1 A 24 AO O LT-Q C G-1 ET-C 11- 6 GL ST-Q 5 CS-1 ST-C Fs-Q G-1 FS-C

!J-R RV-092A 1 BC 6 SA -

SR-P ADS Valm C-3 R AO C ET-Q O RR-1 FT-R ST-Q RR-1 FS-Q RR-1 FS-R RV-092B 1 BC 6 SA SR-P ADS Valw C-3 R AD C LM O RR-1 ET-R ST-Q RR-1 FS-Q RR-1 FS-R IN-092C 1 C 6 SA -

SR-P C-4 R AO IN-092D 1 C 6 SA -

SR-P C4 R AO NES e244

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1 (v':I SWTEM: MAIN No NTX, S1F#4 (B-21)

VMVE TEST TABLE DwG. NO. m-29A DOCUMENT NO. 80A2903 Rev 2 PAGE III~I'4 III~I-I3 OF STROKE C.S. C.S.

CLASS StZE DIRECT CHECK JUSI OR VALVE NO. AND VALVE (IR) ACTu NORM TEST VALVE REV ANO OR ALT. REMARKS DWG. CAI AND TYPE POSTI RE(1 TIME TEST NO.

REUEF TEST N WPE (SEC.) DIRECI REO.NO. PERF.

W-092E 1 DC 6 SA -

SR-P AES Valw C-4 R AO C ET-Q O RR-1 ET-R SM RR-1 E'S4 RR-1 IS-R W-092L 1 BC 6 SA -

SR-P ADS Valw C-4 R AO C ET-Q O RR-1 ET-R ST4 RR-1 l'S4 RR-1 ES-R W-092P 1 C 6 SA -

SR-P C-5 R AO W-092G 1 C 6 SA -

SR-P C-5 R AO RV-092K 1 DC 6 SA -

SR-P ADS Valve C-5 R AO C EM O RR-1 ET-R ST-Q RR-1 FS-Q RR-1 ES-R RV-09211 1 DC 6 SA -

SR-P ADS Valve C-6 R AD C ET-Q O RR-1 ET-R ST-Q RR-1 ES-Q NR-1 FS-R RV-092J l DC 6 SA -

SR-P ADS Valve C-6 R AO C ET-Q O RR-1 EPP.

ST-Q RR-1 IS-Q HR-1 ES-R NES B244

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g g. MAIN & AUX. S1EAM (B-21) VAINE TEST TABLE DWG. NO. % 29A III-I'S III~I~I3 DOCUMENT NO. JOA2903 h 2 PAGE OF STROKE C S. C.S.

CLASS SIZE DIRECT. CHECK JUSI OR yLIVE NO. AND VALVE (IPL) ACT11 NORM TEST VALVE REV AND OR ALI REMARKS DWG. CAI AND TYPE POSII REQ. TIME TEST "-

RELIEF TEST COOR. TYPE (SECL) DIREC1 REQ.NO. PERE FEN-061 1 A 2 PO O EP-Q C 11 - 3 CL ST-O 10 IJ-R BEN-062 1 A 2 70 0 ET-Q C 11- 4 GL ST-O 10 IJ-R M N-063 1 A 2 MO O ET-O C 11- 5 GL ST-Q 10 IJ-R MN-064 1 A 2 MO O ET-Q C 11 - 6 GL STS 10 IJ-R W-093A 2 C 24 SA -

El'-Q F 1bstable check valve. Use air A-7 C test operator to test for valves RV-093A throujh W-0911.

RV-093B 2 C 24 SA -

ET-O F A-7 C "

W-093C 2 C 24 SA -

ET-Q F A-7 C NES B244

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SYSTEM: MAIN & NfX. S'WM4 (B-21) VALVE TEST TABLE Dwa NO. H1-29A DOCUMENT NO. 80A2903 fev 2 III-1-6 III'I-I3 PAGE OF STROKE C.S. C.S.

CLASS SIZE DIRECT, CHELL ANO JUSI OR VALVE NO. VALVE (M) ACTu NORM TEST AND VALVE OR ALI REMARKS REV DWG. CAI AND TYPE POSII REQ. TIME TEST Na RELIEF TEST N WPE (SEC.) DIRECI REa NO. PERE W-09 3D 2 C 24 SA -

EM P A-7 C W-093E 2 C 24 SA -

EM P A-7 C W-093P 2 C 24 SA -

L'.'M) F A-7 C W-093G 2 C 24 SA -

EIM) P A-7 C W-09311 2 C 24 SA -

L'IM) F A-7 C W-093J 2 C 24 SA -

L'IM) F A-7 C W-093K 2 C 24 SA -

E'IM) F A-7 C NES N244

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M TEST TAM EM-29A 80A2903 Ibv 2 N NO. DOCUMENT NO. PAGE III-I-7 OF III-1-13 STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUSI OR MLVE NO. AND VALVE (M) ACTta NORM TEST REV AND VALVE OR ALI REMARKS DWG. CAI AND TYPE POSII REQ. TWE TEST "

RELIEF TEST COOR. TYPE (SEC.) DIRECI REO.NO. PEPS.

W-093L 2 C 24 SA -

LT-Q P A-7 C W-0934 2 C 24 SA -

W F A-7 C RV-095A 3 C 6 SA -

VR-P RV-095A through W-095L are vacctsn D-7 VR relief valves. Tested as vactuu relief valves.

W-095B 3 C 6 SA -

VR-P D-7 VR W-095C 3 C 6 SA -

VR-P D-7 VR W-095D 3 C 6 SA -

VR-P D-7 VR W-095E 3 C 6 SA -

VR-P D-7 VR NES 5244

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VALVE TEST TABLE DWG. NG. W-MA DOCUMENTNO. 80A2903 Rev 2 PAGE III-1-8 op III-1-13 STROKE C.S. C.S.

CLASS SIZE AND DIRECT. CHECK M OR m NO. VALVE (M) ACTil NORM TEST AND VALVE OR ALT. REMARKS REV DWG. CAI AND TYPE POSII REQ. TIME TEST RELIEF TEST m TYPE (SEC) DIRECT REO. NO. PERF.

W-095F 3 C 6 SA -

VR-P C-7 VR RV-095G 3 C 6 SA -

VR-P C-7 VR RV-09511 3 C 6 SA -

VR-P C-7 VR RV-0951 3 C 6 SA -

VR-P j C-7 VR i

RV-095K 3 C 6 SA -

VR-P C-7 VR RV-095L 3 C 6 SA -

VR-P C-7 VR RV-096A 3 C 6 SA -

VR-P RV-096A through RV096L are vacutsu D-7 VR relief valves. 1bsted as vactun relief valves.

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VALVE TEST 1ABLE gg fM-29A 80A2903 lbv 2 ggg NT NO. PAGE III-1-10 op IIT-1-13 STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUSI OR VALVE NO. AND VALVE (M) ACTt1 NORM TEST AND VALVE REV CAI AND OR ALI REMARKS DWG. TYPE POSII REQ. TIME TEST RELIEF TEST COOR. TYPE (SEC.) DIRECI REO. NO. PERE RV-09&J 3 C 6 SA -

VR-P C-7 VR RV-096K 3 C 6 SA -

VR-P C-7 VE RV-096L 3 C 6 SA -

VR-P C-7 VR 50V-083 1 B 2 to C W A-4 GL M3/-084 1 B 2 60 C W A-4 GL M0/-034 2 B 3 to C W I-7 GL FEN-068A 2 D 2 MD O LM C 11- 3 GL ST-Q 7 I

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, DOCUMENT NO. 80A2903 Pnv 2 PAGE III-1-12 OF III-1-13 NUCLEAR ENERGY SERVICES. INC.

%J COLD SHUTDOWN TEST JUSTlRCATION CS - 1 System: Main and Aux. Steam l

Valve: AOV-081A,B,C,D : AOV-082A,B,C,D Category: A Class: 1 Function: Main steam line isolation valves.

ASME Section XI Quarterly Test l

Requirements: Exercise and time.

A Cold Shutdown Test Justification: Full stroke exercising results in loss of steam flow from one main steam line to the turbine. 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 degrada-tion. The valves are designed for partial stroke exercisina 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.

Quarterly Part Stroke Testing: Partial stroke close exercise.

) Cold V Shutdown Testing: Full stroke exercise and time.

FORM e NES-24712/82

m DOCUMENT NO. 80A2903 Pnv 7

" " " NUCLEAR ENERGY SERVICES, INC. PAGE III-1-13 OF III-1-13

[ 'N O

RELIEF REQUEST' RR - 1 System: Main and Aux. Steam Valve: RV-092A,B,E,H,K,J,L Category: BC Class: 1 Function: ADS Valves.

ASME Section XI Quarterly Test Requirements: Exercise and time.

O V

Basis for Relief: If the valves were to fail to reclose after testing the plant would be placed in a LOCA condition. Stroke time is a function or reactor pressure and, therefore, shall not be measured during exercise testing. 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) reccomends that the number of ADS valve openings be reduced as much as possible.

Based on this study and the potential for causing a possible LOCA condition exercise testing of the ADS valves will be delayed to refueling.

Alternate Testing: Exercise at refueling.

v FORM # NES-24812/82

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

Documsnt No. 80A2903 Res. 3 g cO

'l 2

i 1

1 t

PLNP AND VALVE INSERVICE TESTING PROGRAM PIAN ,

EDR SHOREHAM NUCLEAR POWER PIANT (NIT NO.1

, SECTICN III i ATTAHCMENT 2 l VALVE TEST TARTF4 AND FRT.TEP RBQUESTS IVR I'223RTER (B-21)

DWG. NO. EM-32A i

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O III-2-1 wuct aan e=ency senwcas.sec.

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SYSTEM: F12 dan:R (B-21) VW TEST TAM DWG. NO. N 32A DOCUMENT Na 80A2903 k?v 2 PAGE TTT-2-2 op ii1-2-4 STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUSI OR VALVE NO. AND VALVE UM) ACTil NORM TEST AND VALVE OR ALI REMARKS REV DWG. CAI AND TYPE POS31 REQ

TIME TEST RELIEF TEST E-N M (GEC.) DIRECT REO. NO. PERF.

N N- 035A 1 IC 20 SA -

LT-Q P Positive closure motor gerated D-4 50 FO C LT-Q C R CS-1 LT-C stcp check.

ST-Q 139 CS-] ST-C MN-0358 1 IC 20 SA -

LT-Q P Positive closure motor geratal D-5 SC FO O LT-Q C R G-1 LT-C stop cherk.

ST-Q 139 CS-1 ST-C ADV-03bA 1 E 18 SA -

LT-Q P Testable check. Air gerator C-4 C LT-Q R CS-1 EI-C for test only.

LT-R ADV-036B 1 E 18 SA -

LT-Q P lbstable check. Air gerator C-5 C LT-Q R CS-1 ET-C for test only.

IJ-R 1103A 1 E 18 SA -

LT-Q P C-4 C LM R RR-1 LT-R IJ-R 1103B 1 E 18 SA -

LT-Q P C-5 C ET-Q R RR-1 LT-R IJ-R NES s244

DOCUMENT NO. 80A2903 Fev 2 any

" " " NUCLEAR ENERGY SERVICES, INC.

PAGE III-2-3 OF III-2-4

( '1 V

COLD SHUTDOWN TEST JUSTIFICATION CS - 1 System: Feedwater Valve: MOV-035A,B : AOV-036A,B Category: AC Class: 1 Function: Feedwater isolation valves.

ASME Section XI Quarterly Test l Requirements: Exercise (AOV-036A,B) l Exercise and time (MOV-035A,B)

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

I i

l Quarterly Part Stroke Testing: MOV-035A,B are designed for partial stroke exercising during normal operation. AOV-036A,B are full stroke only and cannot be pertial stroke exercised.

Cold O' Shutdown Testing: Exercise (AOV-036A,B)

Exercise and time (MOV-035A,B)

FORM # NES-24712/82

mur DOCUMENT NO. 80A2903 Fev 2 NUCLEAR ENERGY SERVICES. INC. PAGE III-2-4 OF III-2-4 O REUEF REQUEST' RR - i System: Feedwater Valve: 1103A,B l

Category: AC Class: 1 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).

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

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

l l

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

i FORM e NES-24612'P2

Docum:nt No. 80A2903 Rsv. 3 g

^

O l

, PLEP AND VALVE INSERVIG TESTING PROGRAM PIAN i

l IOR SHOREHAM NUCIEAR POWER PIANT UNIT NO. 1 i

i i SECTIN III f ATDONENT 3 0 - - = - --

EOR REACIOR WATER RECIBCUIATIW (B-31)

DWG. NO. EM-26 A,B i

l i

i o III-3-1 NUCLEAA ENERGY SERVICES 38C.

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

v tJ v SYSTER RF/CIUR WNIER R1rIICRATIO4 (B-21) yALVE TEST TABLE FW2M mm m 80A2903 Rev 2 III-F2 III-b PAGE OF STROKE C.S. C.S.

CLASS SIZE 04 RECT. CHECK JUSI OR WEVE NO. AND VALVE (M) ACT11 NORM TEST REV CAI AND VALVE ca ALI HEMARKS DWG. AND TYPE posit REa TIME TEST REUEF TFJST -

COOR. WPE (SEC.) DIRECI REa NO. PERF.

MN-031A 1 B 28 m O ET-Q C CS-1 ET-C E-7 CF ST-Q 33 CS-1 ST-C M N-032A 1 B 28 PO O ET-Q C CS-1 ET{

11- 6 CF SP-Q 33 CS-L ST<

0002A 2 Ac 3/4 SA -

ET-Q R RR-1 ET-R J-5 C IJ-R l

NES 8244

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kJ V v g g. REACIOR WNIER FRCIIOXATIQJ (B-21)

WLVE TEST RBLE E NO. FM-26B DOCUMENT NO. 80A2903 Rev 3 g III-3-3 op III-3-5 SMOKE CS. C.S.

CLASS SIZE DIRECT. CECK JLISI OR MtVE NO. AND WLVE (M) ACT11 NORM TEST MLVE REV DWG. CAI AND OR ' ALI REMARKS ANO TYPE POSII REQ. TIM TFST RELIEF TEST '

COOR. TYPE (SEC) DIREC1 REQ.NO. PERF.

uw-081 2 A E-t 3/4 m.

AD 0 ' LT-O m

C Stroke tine not available. Will tm

- ~ & tem.

b FS-Q LJ-R AN-082 2 A 3/4 AO D-1 ct O LT-Q ST-Q C

Stroke time not available. Will, te . b aw e detennined.

FS-Q I.7-R MLV-031B 1 B 28 M) O ET-Q C G-1 El-C F-7 GT ST-Q 33 G-1 ST-C K V-032D 1 B 28 K) O ET-Q C G-1 LT-C C-7 GT SB-Q 33 G-1 ST-C 0002B 2 AC 3/4 SA -

EM R RR-1 LT-R B-5 C LI-R kiS e244 6

m DOCUMENT NO. 80A2903 Rev 2 PAGE III-3-4 OF III-3-5 NUCLEAR ENERGY SERVICES. INC.

O COLD SHUTDOWN TEST JUSTIFICATION CS - 1 System: Reactor Water Recirculation Valve: MOV-031A,B : MOV-032A,B l

Category

AC Class: 2 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).

ASME Section XI i Quartetty Test Requirements: verify reverse flow closure.

p U

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

i Alternat4 Teing: Reverse flow closure vill be verified during Appendix J, Type C testing at refueling.

O 9

FOms s NES-24612/82

mur DOCUMENT NO. 80A2903 Rev 2 PAGE III-4-6 op III-4-8 NUCLEAR ENERGY SERVICES, INC.

)

j '

RELIEF REQUEST' RR 2 System: Control Rod Drive

! g. AOV-126 : AOV-127 : HCU-ll4 (To be done for all 137 HCU's)

Catwf: B (AOV-126 : AOV-127)

C (HCU-ll4)

Class: 2 Function: Reactor shutdown.

ASME Section XI Quarterty Test Requirements: Exercise, time and fail (AOV-126 : AOV-127).

p Verify forward flow operability (HCU-ll4).

Basis for Relief: Individual valve testing is not possible without causing a control rod scram with a resulting change in core reactivity. Quarterly testing of these valves would violate plant Technical Specifi-cations which govern the methods and frequency of reactivity changes. The Technical Specification Control Rod Scram Insertion Time testing meets the intent of Section XI testing requirements.

Alternate Testing: Tech. Spec. Control Rod Scram Insertion Time testing serves to verify proper operation of each of these valves. To be performed on 10% of the HCU's each 120 days; on each individual control rod after any maintenance or modification to that rod or system is performed which would affect the scram insertion time for this rod; for all rods prior to thermal power exceeding 40% of rated thermal power following core alterations or after a reactor shutdown that is greater than 120 days.

/O k

Foned e MS-24412/82

m f'OCUMENT NO. 80A2903 Rev 2 NUCLEAR ENERGY SERVICES, INC. RAGE III-4-7 OF_III-4-8 RELIEF REQUEST' RR 3 System: Control Rod Drive Valve: HCU-ll5 (To be done for all 137 HCU's)

Category: C Class: 2 Function: Reactor Shutdown.

ASME Section XI Quarterly Test Requirernents: verify reverse flow closure.

G Basis for Relief: Verification of reverse flow closure requires securing the CRD pumps, depressurizing the header and monitoring the individual e ccumulater pressure and alarm to verify that the valves have closed on reverse flow. To do this requires entry into a high radiation work area and could also result in a plant scram.

Alternate Testing: verification of reverse flow closure will be performed at refueling when the header can be depressurized without a possible plant scram and when area radiation is sufficiently reduced to allow extend entry for testing. Testing will be by depressurizing the header and monitoring the individual accumulater pressure and alarm to verify that the valves have closed on reverse flow. This test if required by plant Tech. Spec. Surveillance requirement 4.1.3.5.

O v

FORM # NES-24612/82

l my DOCUMENT NO. 80A2903 Rev 2 NUCLEAR ENERGY SERVICES, INC. PAGE III-4-8 OF III-4-8 O

O RELIEF REQUEST' RR - 4 System: Control Rod Drive Velve: HCU-138 (To be done,for all 137 HCU's) t Category: C Class: 2 Function: Reactor shutdown.

ASME Section XI Quarterly Test

Requirements: Verify reverse flow closure.

l A i 4

G Basis for Relief: Individual valve testing is not possible without causing a control rod scram with a resulting change in core reactivity. Quarterly testing of these valves would violate plant Technical Specifi-cations which govern the methods and frequency of reactivity changes. The Technical Specification Control Rod Scram Insertion Time Testing meets the intent of Section XI testing requirements.

Alternate Testing: Verification of reverse flow clcsure will be performed in conjunction with the Control Rod Scram Insertion Time Testing by observing the control rod cooling line pressure and flow indications. In addition the cooling water header relief valve will be monitored during the test. This test method is currently being analyzed to determine if it meets the intention of Section XI. If it does not, an alternate test method will be developed and implemented by the first plant refueling outage.

(q i

FOMA 8 NES-24612/82

Docum:nt No. 80A2903 Rev. 3 g g

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l l

PLNP AND VALVE INSERVICE 'IESTIE P10 GRAM PIAN EUR SHOREHAM NUCLEAR POWER PIANT UNIT NO. 1 SECTIOT III ATTACHMEITT 5

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FOR STANDBY LIQUID OCN1TOL (C-41)

DWG. NO. IM-21A l

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NUCLEAR ENEDGY SERVICESINC.

gg. STAtKEY LIQUID 0211T01 (C-41)

VALVE TEST TABLE m Ew2M Nm 80A2903 Rev 2 PAGE III-5-2 op 111-5-5 STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUSI OR M NO. AND WALVE (K) ACTu NORM TEST AND WALVE OR ALI REMARKS SEV DWG. CAI AND TYPE POSIL REQ- TEST NO.

"M N TNAE RN TEST (SEC.) DMECI REQ. NO. PERF.

EV-010A 1 D 1 E C XT-P D-5 E EV-010B 1 D 1 E C XT-P D-7 'E RV-021A 2 C 1 SA -

SR-P F-5 R RV-0218 2 C 1 SA -

SR-P F-7 R 0008 1 AC 1 SA -

ET-Q P RR-1 ET-R A-6 C ET-Q R RR-2 ET-R IJ-R 0010 1 AC lh SA -

ET-Q P RR-1 ET-R B-6 C ET-Q R Ra-2 ET-R IJ-R 0007A 2 C lh SA -

EM P F-5 C NES 8244

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my DOCUMENT NO. 80A2903 Rev 2 NUCLEAR ENERGY SERVICES, INC. PAGE III-C-4 OF III-5-5 l REUEF REQUEST' RR - 1 System: Standby Liquid control f

h* 0008 : 0010 Category: AC Class: 1 Functica: SBLC injection line check valves.

ASME Section XI Quarterly Test I Requirements: Verify forward flow operability.

)

Basis for Relief: To verify forward flow operability during normal operation would require firing a squib valve and injecting water into the reactor vessel using the SBLC 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.

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

O FORM e NES-24612/82

DOCUMENT NO. 80A2903 Rev 2 1 NUCLEAR ENERGY SERVICES, INC. PAGE III-5-5 op III-5-5 s

RELIEF REQUEST' RR - 2 System: Standby Liquid Control Velve: 0008 : 0010 Category: AC l Class: 2 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).

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

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

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

O V

mu . ,as.u. ,ma

Document No. 80A2903 Rev. 3 sO C/

PUMP AND VALVE INSERVIG TESTING PROGRAM PIAN EUR SHOREHAM hTCIEAR PGER PIANT UNIT NO. 1 SECTICN III A'ITACHMEN~1' 6 i

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l VALVE TEST TARTF9 AND FFTJRP REQUESTS FOR NEUIRCN ENI'IORING (C-51)

DWG. NO. EM-62 A,B i

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Docum:nt No. 80A2903 Rev. 3 A

D v

PLEP AND VALVE INSERVICE TESTING PROGRAM PIAN FOR SHOREHAM NUCLEAR POWER PI1NP UNIT NO. 1 SECTICN III ATI'ACHMENT 7 O)

(

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VALVE TEST TABIES AND FMM mwuns FOR RADIATICN MCNI'IOPlNG (D-ll)

DWG. NO. EM-76A f

v III-7-1 NUCLEAR ENERGY SERVCEilNC,

A g_ RADIATIOJ KNIMC, (D-ll)

WWE TEST TABLE FM-76A DWG. 980. DOCUMENT NO. 80A2903 Fev 2 PAGE III-7-2 op TII-7-2 STROKE C.S. C.S.

CLASS SE JUSt DIRECT. CHECK OR M NO. AND WYE (10 4 ) ACTu NORM TEST AND WLLVE OR At1 REMARKS REV DWG. CAI AND TYPE POSIT REQ. TIME TEST RELIEF TEST '

COOR. TYPE (SEC.) DIRECT REO.NO. PERF.

MDV-032A 2 A 1 70 0 ET-Q C B-6 GL SM 18 IJ-R MN-032B 2 A 1 FD O ET-Q C l B-6 GL ST-Q 18 IJ-R l

M3/-033A 2 A 1 to O ET-Q C B-8 GL Sr-Q 18 IJ-R MDV-033B 2 A 1 FO O ET-Q C B-8 CL ST-Q 18 IJ-R l

l t

l NES s244

Document No. 80A2903 Rev. 3 A

O

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T L

PLNP AND VALVE INSERVICE TESTING PROGRAM PIAN FOR i SHOREHAM NUCIEAR POWER PLWT UNIT NO. 1 l

l O SECTICN III ATDCHMENT 8 VALVE TEST TARTFS AT RFT.TEP REQUESTS 1

g RESIDUAL HEAT REMOVAL (2-11)

DWG. NO. FM-20 A,B t

N

O I

III-8-1 mnsAn ammar senwess.ed

rh U,a U Ur ggg. RESIWAL HEAT REMWAL (E-11)

M TEST M W 20A gg DOCUMENT E 80A2903 kv 3 PAGE III-8-2 op III-8-2 3 h STROKE C.S. C.S.

CLASS SIZE DIRECT, CHECK JUSI OR VALVE NO. AND WLVE (IK) ACTt1 NORM TEST AND VAU/E og REMARMS REV Att DWG. CAI AND TYPE POSII REQ. m TEST NO.

RELIE# TEST COOR. TYPE (SEC.) DIRECI REO.NO. PERF.

M N-041A 2 A 6 to C ET-Q C I-6 GL S'P-Q 44 IJ-R MW-038A 2 A 10 PO C ET-Q C G-2 A SIM) 10 IJ-R M W-039A 2 A 10 to C ET-Q O I-2 GP ST-Q 51 IJ-R MOV-037A 1 A 24 PO C ET-Q O G-1 DF-C I-3 GF ST-Q 24 G-1 ST-C IC-R MN-045A 2 A 4 to O ET-Q C E-7 GF ST-Q 24 IJ-R MN-036A 2 B 24 PO O ET-Q O G-3 A ST-Q 53 M W-040A 2 A 16 PO C ET-Q C G-5 GP ST-Q 90 IJ-R NES 8244 e

fM ('

. Y/ N.

gyggy. RESI[UAL lEAT IOt0 VAL (E-ll) y4LVE TEST MBLE g FN-20A N ENT M EJA2903 lbv 3 PAGE III-8-3 op III-8-2 3 b STROKE C.S. C.S.

CLASS EIZE DIRECT CHECK JUS 1 OR V4tVE NO. AND VALVE (M) ACTti NORM TEST AND VALVE OR Att REMARKS REV DWG. CAI AND TYPE posit REQ. TIME TEST REUEF U TEST N TYPE (SEC.) DIRECT REO.NO. PERF.

MOV-031A 2 A 20 m O ET-Q C I-7 cr SM 120 IJ-R M N-031C 2 A 23 m O ET-Q C I-8 GT ST-Q 120 LJ-R MOV-032A 2 5 20 m C ET-Q O Il-) Cr ST C 120 MOV-032C 2 5 20 M0 C EM O 11- 8 Gr ST-Q 120 MOV-042A 2 A 16 m C ET-Q C G-6 GL ST9 90 IJ-R KN-043A 2 B 4 m C IV 1his valve is dedicated to the NIR D-4 GT stean -thing snode of operstion.

The SO4 as a nonnal operaticm unie MOV-033A 2 p 16 m has been dele's.x2 at W s-1.

O E'IM) C D-7 Gr ST-Q 85

~

NEh 5244 6

B O[N O g g. RESIDUAL lEAT IU10 VAL (E-ll)

MLVE TEST R8LE gg ni-20A DOCUMENT NO. 80A2903 lbv 3 III~0'd III-O23 PAGE OF STROKE CS. C.S.

OfASS SIZE AND MLVE DIRECI CHECK m Oa WuYE NO. (M) ACTu NORef TEST AND MLVE- OR ALI REMARKS REV DWG. CAT. AND TYPE POSII REO. TIME TEST RN TEST NO.

N TYPE (SEC) DIRECI REQ.NO. PERF.

MOV-034A 2 D 18 MO O ET-Q C D-8 A ST-Q ' 144 MOV-035A 2 B 16 MO O EP-O C B-4 Gr ST-Q 85 AOV-0817- 1 AC 24 SA -

ET-Q P ci-2 ET-C Testable check valve (part J-3 C ET-Q R G-2 LT-C stroke).

IC-R 0020A 2 C 16 SA -

ET-Q P D-7 C 0020C 2 C 16 SA -

ET4 P D-8 C IW-153A 2 C 1 SA -

SR-P f1-3 R RV-152A 2 AC 4 SA LT-R B-5 R

'Ihis valve is dedicated to th! MR steam condensing mode of operation.

'Ihe SO4 as a nomal cperating mode tus been &leted at StPS-1.

NES 5244 i

N

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v) gg. RESIDUAL !! EAT RENOVAL (E-11) wuvE TEST RBLE N NO. FM-20A DOCUMENT NO. 80A2903 Rev 3 PAGE III-8-5 op III-8-23 b STROKE C.S. C.S.

CLASS SIZE DIRECT CHECK JUSE OR wuYE NO. AND M (IN) ACTu NORM TEST AND WuVE OR ALI REMARKS REV DWG. CAI AND TYPE POSII REQL WF TEST NO.

r.ELFF TEST COOR. TYPE (SEC) DIRECT REO. NO. PERF.

MOV-055A 2 A 1 MO C W Titis valve is dedicated to the Rim A-6 GL IJ-R steam omdensing mode of operation.

1he SO4 as a normal operating mode has been deleted at SNPS-1.

HN-056A 2 A 1 m C PV titis valve is dedicated to the Mm A-5 CL IJ-R steam condensing mode of operation.

The SO4 as a normal operating node has bem deleted at SNPS-1.

RV-157A 2 pc 1 SA B-6 IJ-R 1hernal relief valve. App. J, Type C R test only.

MOV-081A 1 A 2 K) C PV Valve opens and autanatically J-2 GL If-R recloses once pressure equalizes across the testable check valve.

MN-044A 2 A 4 M) C PV E-6 Utis valve is dedicated to the Mm GT IJ-R steam emdensing mode of operation.

The SO4 as a normal egerating mode has been deleted at SNPS-1.

MN-057A 2 B 1 M) C ET-O O A-4 cL SM 17 00035A 2 C 3 SA -

ET-Q P E-7 C NES 3244 i

o N

(N L

Q

g. RESIOUAL IIEAT REMNAL (E-ll)

VMVE TEST M g g, EN-20A DOCUM M NO. 80A2903 Itry 3 PEE III-8-6 y III-8-23 d

STROKE C.S. C.S.

N SIZE DIRECT. CHECK JUSI OR VuVE NO. AND M (IK) ACTtt NORM TEST- AND VALVE REV DWG. CAI AND OR ALI REMARKS TYPE POSII REO. TIME TEST RELIEF NO.

TEST N M (FECs) DIRECI REQ.NO. PERE 0035C 2 C 3 SA -

M P E-8 C 0037A 2 C 1 SA -

ET 4 P G-2 C Ftuvard ficw cperabil*ty is verified by a systern check to verify water inventory.

3145 2 Ac 1 SA -

W R RR-1 ET-R I-5 C LT-R 314e 2 Ac 1 SA -

ET-Q R RR-1 ET-R I-5 C IJ-R 0022A 2 C 4 SA -

ET S F 11- 3 C Forward ficw operability is verified ET-Q R RR-2 by a systan check to verify water inventory.

MS s244 I

O O O

g. _ EIDUAL IFAT IDOVAL (E-ll) M TEST M g FM-20A 80A2903 Ibv 3 N ENT m PAGE III-8-7 OF III-E'23 STROKE C.S. C.S.

N SIZE DIRECT. CHECK JUSI OR WEVE NO. AND WhLVE (IK) ACTu NORM TEST VALVE og AND AI.I REMARKS . REV DWG. CAI AND TYPE POSII REQ. 1EST NO.

TIME REUEF TEST COOR. M 4

(SEC.) DIRECI REQ. NO. PERE ADV-061A 2 B 3/4 AO C 'ET-Q C A-6 GT ST-Q Stroke time not availat-le. Will be k added when determined.

FS-Q ADV-062A 2 8 3/4 A3 C E'IM) C A-6 GT ST-Q Stroke time not available. Will be d added when determined.

FS-Q

]

SOV-168 2 A 3/4 D4 C ET-Q C H-6 Cf SIM) 5 ES-Q IJ-R 0047 2 AC 3/4 SA -

LT-Q R RR-1 ET-R H-6 C IJ-R SOV-166A 2 B 3/4 D4 C UIM) C D-6 GL SP-Q 5 FS-Q SOV-It6B 2 B 3/4 Di C EIM) C D-6 GL WIM) 5 FS-Q NES #244 6

d v V EM-20B gg DOCUMENT NO. 80A2903 Bev 3 _

g III-8-8 op III-8-23 h SMOKE C3. C.S.

, CtJutS SEE DMECT. CHECK JUSI OR VALVE NO. ANO M4tVE SK) ACTtt NORM TEST CAI AND AND WELVE on Att REMARKS REV N

DWG.

N TYPE posit REQ. m TEST REUEF TEST NO.

(SFC.) DIRECI REQ. NO. PERF.

M W-041B 2 A 6 m C ET-Q C D-6 GL SM 44 M-R MOV-040B 2 A 16 MO C ET-Q C D-4 Cr ST-Q 90 IJ-R MW-038B 2 A 10 M0 C ET-Q C C-2 A ST-Q 10 IJ-R MOV-0398 , 2 A 10 MD C ET-Q O

.Pc2 Cr ST-Q 51 IJ-R M N-037D 1 A 24 PO C EM O G-1 EM B-3 GT ST-Q 24 G-1 Fr-C IC-R MN-036B 2 B 24 PO O ET-Q O D-3 -A ST-Q 53 Mov-045D 2 A 4 m O NP-Q C F-7 Cr SM 24 IJ-R NES M44 I

O O O g IESIMRL IEAT REMNAL (E-ll)

MEWE TEST M

m. MW 80A2903 Rev 3 N ENT M FAGE III-8-9 op III-8-2 3 d STROKE C.S. C5.

. CLASS M DIRECT. CHECK JUST. OR WVENO. ANO WWE (IK) ACTti NORM TEST MuvE M AND Cet ALT. REMARKS DWG. CAI AND TYPE posit REQ. TEST COOR.

DME REUEF TEST NO.

TYPE (SEC) DIRECI REQ.NOL PERF.

W -053 1 A 4 *10 C ET-Q C G-3 ET-C B-2 CL SIM 22 G-3 SP C 14-R M N-054 1 A 4 m C Ely C G-3 ET C A-2 Cr ST-Q 22 G-3 ST-C IO-R MN-047 1 A 20 m C ETC C G-4 ET-C A-4 GT ST-Q 35 G-4 SF-C

!&R M N-048 1 A 20 HO C C ET-Q G-4 ETC A-4 GT ST C 35 G-4 ST-C I&R MM-031B 2 A 20 m O EBC C B-7 m ST-C 120 IJ-R M N-031D 2 A 20 m O ET-Q C B-8 Cr SFO 120 IJ-R MN-032B 2 B 20 M0 C O ET-Q C-7 Cr ST-Q 120 PES f?44 6

s e

"N N,

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g, R03100AL IEAT IUt0 VAL (E-II) -

g TEST M mm FM-20n DOCUseEpiT E 80A2903 Rev 3 RAGE TIT-8-10 op ITT-8-23 h SDE Ci C.S.

Ct. ASS SIZE DIRECT CHECK JUSI Ca WMVE NO. AND M 000) ACTL1 NORM TEST AND M REV CAI OR AI.t REleARxS DWG. AND TYPE POSII REQ. TIteE TEST RELIEF TEST U N N (SEC-) DIRECI REO. NO. PERF.

MN-032D 2 B 20 to C E'M) O C-8 GT SM) 120 M -Cl2B 2 A 16 to C EM) C D-6 GL .SM) 90 IJ-R M -049 2 B 10 HD C W 1his valve is dedicate 1 to the R m E-5 cr steam condensing mode of operatim.

The SCM as a nonral gerating rode has been deleted at SNPS-1.

M -043B 2 B 4 60 C W 1his valve is dedicated to the R m F-4 Gr steata cmdensing made of operation.

1he Set as a normal eterating rode M -044D has bem deleted at SNPS-1.

2 A 4 70 C W 1his valve is dedicated to the Rm G-4 cr IJ-R Bteam corwknsing mode of geratim.

The set as a normal operating mode

!- has been deleted at SNPS-1.

W -035B 2 B 16 to O ETK) C H-4 Cr SM) 85 M -033B 2 B 16 HD 0 Er-Q C l G-7 Gr SM) 85 f(S s244 4

Og 1 /

Y % Y N,_

g g. RESIWAL IIEAT RE2-tWAL (E-ll) guyE TEST MSLE m-208 g NNT NO. 80A2903 lbv 3 FRGE III-8-ll OF III-8-23 d S.OKE C4. C.S.

CLASS SEE DIRECT. CHECK JUSI OR MuyE NO. AND WMVE (IK) ACT11 HORM TEST AND UM.VE OR ALI HEMARKS M DWG. CAT. AND TYPE POSII REQL w TEST N TEST NO.

COOR. TYPE (SEC) DIRECI REO.NO. PERF.

W-163 2 AC 1 SA -

IJ-R 1hermal relief valve. App. J, G-2 R Tfpe C test only.

W-164 2 AC 1 SA -

IJ-R 1hernal relief valve. Arp. J, F-3 R Type C test (mly.

M N-034B 2 B 18 60 0 ET-Q C C-8 A SIM) 144 ADV-081B 1 AC 24 SA -

E1M) F CS-2 EP-C 1bstable deck valve (part A-3 C E7-Q R CS-2 ET-C stroke),

lor 0020B 2 C 16 SA -

E'IM) F F-7 C W-155 2 AC 2 SA -

IJ-R F-5 R 1his valve is dedicated to the MR steam condensing mode of operaticn.

1he SCM as a normal operatiruj mode W-152B 2 has boen daleted at SNPS-1.

AC 4 SA -

I-5 R IJ-It this valve is dedicated to the Rm stean condensing mode of operation. ,

the Sot as a normal gerating mode has been deleted at SteS-1.

n NES 8244 6

I (N. /~N CN

\

b; (b) {d

g. iEIIXJAL IFAT IDD/AL (E-ll)

M TEST N m-20B mg 80A2903 Dev 3 g III-8-12 og III-8-2 3 d

! CLASS SEE

=0. C u DIRECT CHECK JUSE OR WuVE NO. AND WuYE (Ik) ACTu NORM TEST AND WEVE M OR Ag.7, REMARKS DWG. CAT AND TYPE POSIE REQ- TRAE TEST No.

REUEF TEST COOR. TYPE

.- (SEC.) DIRECE REO.NOL PERF.

HOV-055B 2 A 1 m C W Siis vavle is dedicated to the H m J-4 GL IJ-R stem andensing node of cperation.

h SCI as a nonnal cperating node has been deleted at SNPS-1.

E V-056B 2 A 1 m C W 1his valve is dedicated to the RR J-5 GL IJ-R steam crrukmsing noie of cperaticn.

W SCM as a normal operating unb has hvn deleted at SNPS-1.

RV-157B 2 Jc 1 SA IJ-R I-6 R Thernal relief valve. Aop. J, Type C test culy.

NOV-081B 1 A 2 m C W Valve (pens and autentically A-3 GL IOR recloses once pressure equalizes across the testable check valve.

MN-050 2 B 24 m C W Power dibun.M to operator.

C-4 Cr OG35B 2 E-7 C

C 3 SA -

W F 0035D 2 E-B C

C 3 SA -

W F NES s244 6

7% CN

(

\ CN)

\/ (k-)

mg lesitEAL lEAT MMNAL (E-ll) MuyqiTEST1A8LE Mi-200 g mm 80A2903 mv 3 gg III-8-13 op III-8-23 d CLASS SUE S==E a a DMECT. CHECK JUST. OR MuYE NO. AND WLLVE (N) ACTLL NORM TEST AND WALVE OR ALI REMARKS M DWG. CAL AND TYPE POSf1 REE TudE TEST REUEF TEST COOIL TVPE (SEC.) DMECI REO. NO. PERF.

Mov-057B 2 2 1 m C EIM) O

.J-4 GL S'IM) 17 RV-153B 2 C 1 SA -

SR-P D-4 R 00228 2 C 4 SA Forward flw qerability is wrified b ET-Q F D-3 C EF-Q R RR-2 by a systen duxk to verify uter inventory.

0023 2 C 4 SA -

EIM) F Fbrard flow qerability is verified d C-1 C EIM) R RR-2 by a systen check to verify water inventory.

0037B 2 C 1 SA F D-2 C ET-Q fbrward flow operability is verified by a systen duck to verify water inw mtory.

0028 2 C 4 FA -

EIM) F RR-3 A-4 C EIM) R RR-2 d

KN-051 2 B 4 m C EIM) O C-4 cr S'IM) 24 NES s244 6

O) %)

'%J

)

gg. RESIUJAL IEAT REMNAL (E-ll) yMVE TEST M g IM-20D 8072903 Rev 3 III-8-14 III'0-23 M ENT E g OF E

STROKE C.S. C.S.

CLASS SIZE DIRECT. CilECK Just OR WuYE NO. AND M (IR) ACTLL NORM TEST AND WM.VE OR ALI REMARKS M DWG. CAI AND TYPE POSII REO. m TEST REUEF TEST NO.

COOR. TYPE (SEC.) DIRECI REQ.NO. PERF.

M W-052 2 B 4 to C ET-Q O C-4 GL ST-Q 16 ADV-061B 2 J-6 B 3/4 Cr AO C ET-Q ST-Q C Stroke tine not available. Will be added den detemined.

d PS-Q A0V-062B 2 J-6 B 3/4 GP AO C EP-Q St-Q C Stxtme time not available. Will be added den determined.

d WQ RV-154 2 C 1 SA -

SR-P C-5 R 0030 1 C 4 SA -

EF-Q F CS-S EF-C A-2 C SOV-169 2 A 3/4 EM C EF-Q C B-6 GT SIM) S FS-Q IJ-R 0048 2 Ac 3/4 SA -

EP-Q R RR-1 EF-R b-6 C IJ-R NES s244 8

d O

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2 8

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- N 7 7 N E 6 6 O

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- D. 2 8

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,. l

DOCUMENT NO. 80A2903 nnv 3 PAGE III-8-16 OF III-8-23 d NUCLEAR ENERGY SERVICES. INC.

COLD SHUTDOWN TESTJUSTIFICATION SY.

Syste n: RHR Wive: MOV-037A,B Category: A Class: 1 Function: LPCI injection valves.

ASME Section XI Quarterly Test Requirements: Exercise and time.

Cold Shutdown Test Justification: Exercising these valves during normal operation increases the possibility of a inter-system-LOCA accident.

If either of these valves is opened during normal operation a single downstream check valve becomes the sole pressure boundary between the reactor coolant system and the low pressure RHR system. A failure of the check valve while cycling the upstream motor operated valves could result in over pressurization of the RHR low pressure piping.

Quarterly Port Stroke Testks: NA l l Cold Shutdown Testing

Exercise and time.

1 l

l l PORM # NES-24712/82

l DOCUMENT NO. 80A2903 nnu t l m

- NUCLEAR ENERGY SERVICES, INC.

PAGE III-8-17 OF III 23 d~

COLD SHUTDOWN TEST JUSTIFICATION CS - 2 System: RHR Wlve: AOV-081A,B Category: AC Class: 1 Function: RHR injection valves.

ASME Section XI l Quarterly Test l Requirements: Verify forward flow operability and reverse flow closure.

_ Sh-n Test Justification: valves are testable check valves with installed partial stroke open air operators. Partial stroke ope $ testing during normal operation i's precluded because stroking these valves would leave only one valve as a barrier between the high pressure reactor coolant system and the RiiR system low pressure pi eing.

l In addition, there are no provisions to measure leakage across the check valves during normal operation and full leak tight closure after exercising cannot be verified. Inadvertent operation of the upstream motor operated valves could result in an inter-system-LOCA. Testing operability by injecting water into the RCS is not possible during normal operation because th,e RHR pumps develop insufficient head to overcome RCS pressure; d Quarterly Port Stroke Testing: NA l Cold Shutdown Testing: Forward flow exerciso during normal cool down and verify reverse flow clonure using the valve position indicator lights.

FORM e NES-24112/82

" DOCUMENT NO. 80A2903 Rev 3 PAGE III-8-18 OF__III-8-23 d NUCLEAR ENERGY SERVICES. INC.

]

COLD SHUTDOWN TESTJUSTlFICATION CS - 3 System: RHR Wlve: MOV-053 : MOV-054 Category: A Class: 1 Function: Inboard and outboard containment isolation valves on RHR reactor vessel head spray line.

ASME Section XI Quarterly Test Requirements: Exercise and time.

Cold Shutdown Test Justification: Valves are interlocked with reactor pressure at 135 psig and cannot be opened during normal plant operation.

Quarterly Port Stroke Testing: NA 9 Shutdown Testing: Exercise and time.

I FORM e NES 24712/82

4 DOCUMENT NO. 80A2903 Pov 3 m

- 11 NUCLEAR ENERGY SERVICES, INC.

I-'

COLD SHUTDOWN TEST JUSTIFICATION CS - 4 System: RHR h: MOV-047 : MOV-048 Category: A Cimas: 1 Function: Inboard and outboard containment isolation valves on RHR suction line from the reactor vessel.

ASME Section XI Quarterly Test Requirements: Exercise and time.

G Cold Shutdown Test Justification: valves are interlocked with reactor pressure at 135 psig and cannot be opened during normal plant operation.

Quarterly Part j

Stroke Testing: NA l l ' Co6d l Sheldown Testing: Exercise and time.

l FORM e NES-24712/87

DOCUMENT NO. 80A2903 Rev 3

~

NUCLEAR ENERGY SERVICES, INC.

C COLD SHUTDOWN TESTJUSTIFICATION CS - 5 System: RHR Wive: 0030 Category: C Class: 1 Function:

ASME Section XI i Quarterly Test Requirmwnts: Verify forward flow operability.

Cold Shutdown Test Justification: valve is inside the drywell (maintained inerted) and is downstream of valves MOV-053 an~d MOV-054 which.are interlocked to prevent opening at reactor coolant system pressure above 135 psig. The only way to verify forward flow operability is by injecting water through the head spray line at cold shutdown when reactor coolant

( system pressure is less than 135 psig.

l l

l Queriarty Part l

Stroke Testing: NA G Shutdown Testing: rorward flow exercise.

l Fones e NES-24712/02

DOCUMENT NO. 80A2903 .Rev 3 E

~ ~

=

NUCLEAR ENERGY SERVICES. INC.

T<

RELMh REQUEST

RR - 1

~

System: RHR Valve: 3144 : 3145 : 0047 : 0048 Categem AC Clase: 2 Function: Containment isolation simple check valve (reverse flow closure ,

for coatsinment isolation only).

ASME Section XI Quarterly %et Requirement : Verify reverse flow closure.

O Boeie for ReHof.

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

l 8

t .

l l

Alternete Test'ng: Reverse flow closure will be verified during Appendix J, Type C testing at refueling.

l l

l

~

I romt # NES-2441FS2

I

,, m DOCUMENT NO. 80A2903 Rev 3

= NUCLEAR ENERGY SERVICES, INC. PAGE III-8-22 OF III-8-23 REUEF REQUEST' RR - 2 System: RHR l

I WlV3: 0022A,B : 0023 : 0002A Categog': C l

Class: 2 Function: Loop level injection line check valves to RHR system piping.

( ASME Section XI l ouarte.sv Test l Requirements: verify reverse flow closure.

1 l I Basis for Relief: Loop level piping configuration precludes verification of reverse flow closure. To verify reverse flow cleuure would require securing the. loop level pump and draining the loop level piping, operating the.RHR system and monitoring an upstream vent line for leakage. This method would require opening vent valves during system operation at operating pressure, which presents a potential for injury to plant personnel.

i l

Alternete Testing: Design changes are presently under consideration to either mMify the loop level piping configuration or to modify the valves to provide a means of individual valve reverse . flow closure verificatior.. An appropriate modification (s) will be selected and completed during the first refueling outage. During the interim forward flow operability of valves 0022A,B and 0023 will be verified by a system check to verify system water inventory.

l I

- . s.u. = =

DOCUMENT NO. 80A2903 Rev 3 m

NUCLEAR ENERGY SERVICES, INC. PAGE III-8-23 OF III-8-23 REUEF REQUEST' RR - 3 System: RHR Wlve: 0028 Category: C Class: 2 Function: Icop level injection line check valve to RHR system piping.

ASME Section XI Quarterty TM Requirements: Verify forward flow operability.

l l Basis for Relief: This check valve is a branch line from the loop level pump to the 20 inch RHR pump suction line. The RHR piping that this branch line connects to is normally isolated from the RHR system by normally closed valves, and has no installed high p6 int vent connection. Therefore, it is not possible to verify forward flow operability by performing a system check to verify system water

! inventory. The valve is a simple. check valve without., provisions l for manual exercising.

AltWe W: Design changes are presently under consideration to either modify the piping configuration or to modify the valve to provide a means to. verify forward flow operability. An appropriate modifications (s) will be selected and completed during the first refueling outage. -

l i

i FoFM S NES 24412/82

Docum:nt No. 80A2903 Rev. 3 d

.s C .

PLNP AND VALVE INSERVIG TESTIE PROGP#1 PIAN EUR SHOREHAM NUCIEAR POhCR PIANT UNIT NO. 1 SECTICN III ATDONENT 9 O

( VAWE TEST TAmm AND Fim R3gms FOR CORE SPRAY (E-21)

DWG. NO. EM-23A i

m NUCLEAR EPEE AGY SERvtCES. INC.

\,

S E.. = c seaAv <E-213 QM m nST _

__ ,_ e-3 -> ,_ m-m

___ . m. T b Smo cS. cS.

CLASS 882E DIRECT. CHECK JUSE OR WuVE NO. AND M (IK) ACTti .J TEST AND WOE REV DWG. CAI AND OR ALI REMARKS C00st TYPE TYPE posit REQ. m TEST N TEST "

(SEc) DIRECI REQ. NO. PERF.

NN-081A 1 E-3 1C 10 C

SA -

UFO ETM)

F R

RR-1 RR-1 ET-R FN1 b

IE-R MN-081B 1 F-3 to 10 C

SA -

ET-Q ET-O F

R RR-1 RR-1 EBR L'F R b

IC-R M N-033A 1 A 10 m C EIM) O G-1 EFC b D-3 GT SIM) 20 G-1 SF-C IC-R MOV-033B 1 A 10 m C ET-Q O G-1 EF-C b F-3 Cr ST-O 20 G-1 ST-C IC-R MOV-035A 2 A 10 HD C L'IM) C C-4 GL SFO 67 IJ-R MOV-0358 2 A 10 Ho C EFO C G-4 CL ST-O 67 LJ-R MOV-034A 2 A 3 MD C ET-Q C B-6 GT ST-O 17 IJ-R NES s?44 i

N l */ \ kj l

l l

l l SYSTEM CORE SPRAY (E-21) WuME TEST 1n8LE gg FM-23A g,0CUMENTm 80A2903 Rev 3 PAGE TTT-9-3 ry TTT-9-7 d CLASS SIZE SamE es. es.

AND WuME DIRECT. CHECK Just on WuYE M SK) ACYu NORM TEST AND WuME OR ALI PtEMAAAS REV DWG. CAI AND TTT POSTE REQ. TEST REUEF TEST NO.

N N TRIE . DIRECI REO. PERF.

(SEC.) NO.

McN-034B 2 A 3 m C EIM) C I-6 Gr S'IM) 17 L3-R 0013A 2 C 12 SA -

EIM) F A-5 C 0013B 2 C 12 SA -

EF-Q F J-5 C MN-031A 2 A 14 m O EIM) C C-7 cr SIM) 77 IJ-R M3/-031B 2 J. 14 M) O EIM) C G-7 cr SIM) 17 IJ-R H3/-081A 1 A 2 M) C W E-3 Valve opens and autmatically CL 1C-R recloses once pressure equalizes across the testable check valve.

K N-081B 1 A 2 M) C W F-3 Valve quics and autcmatically GL 1C-R recloses once pressure equalizes acroos the testable check valve.

NES 5244 i

,-~ ~

(.J V V SYSTERA: _ CORE SPRAY (E-21) ykLVE TEST M g, IN-23A eg 80A2903 kv 3 III-9-4 pg y III-9-7 S1MOKE C.S. 0.8.

CLASS SEE DIRECT. CHECK JUSI OR ykLVE NO. AND MLVE M) ACTtl NORM TEST AND WLVE E OR ALI REMARKS

, DWG. CAI AND TYPf POSII REQL TueE TEST RELjEF NO.

TEST COOR. TYPE (SEC.) DM RECL 440. PERF.

W-093A 2 C 1 SA -

SR-P B-3 R

W-093B 2 C 1 SA -

SR-P H-3 R 0018B 2 C 2 SA -

LT-Q P Ebnant flow ope- tility is verified H-2 C ETM) R RR-2 by a systan chec'. to verify 6Jater in - tory.

d 0015B 2 C 1 SA P E'IM) Fonard flw operability is verified H-2 C by a systen check to verify uter inventory.

0018A 2 C 2 SA F 13M) Ibrward flw operability is verified C-2 C EIM) R RR-2 by a systen dieck to verify uter inventory.

b 0015A 2 C 1 SA -

EIM) F Ibnerd flow operability is verified C-2 C by a systen dieck to verify mter inventory.

wa s244 e

903 h my DOCUMENT NO.

PAGE III-9-5 op III_9 7 NUCLEAR ENERGY SERVICES, INC.

i l

COLD SHUTDOWN TEST JUSTIFICATION CS - 1 System: Core Spray Wlve: MOV-033A,B Category: A Class: 1 Function: Core spray injection line motor operated valves.

ASME Section XI Quarterfy Test Requirements: Exercise and time.

Cold Shutdown Test Justification: Valves are interlocked with reactor coolant system pressure which precludes valves operation at RCS pressures greater than 500 psig.

In addition,. if the motor operated valve were to be opened the downstream check valve becomes the single boundary between the RCS and the low pressure core spray piping. This situation is a matter of concern since failure of the check valve as a pressure boundary could result in an inter-system-LOCA if the motor operated valve is exercised during normal plant operation.

l l

Quarterly Port ,

Streke Teeting: NA l I Cold Shutdown Testing: Exercise and tire.

a.

FORM e NEs-24712/02

Document ho. 80A2903 Rev 3 Page III-9-6 of III-9-7 Relief Request l' ') RR - 1 s_'

Systems Core Spray Valve ADV- 081A,B Category: AC Class: 1 Function . Core spray system injection check valves.

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

Basis for Relief: These are pressure isolation valves.between the RCS and the low pressure core spray system piping. Plant Technical Specification 4.4.3.2.2 has been revised to require demonstration of valve operability by leak testing each time the valves have been disturbed, until the first refueling outage. During the first refueling outage the low pressure permissive interlocks on the up-stream motor operated valves (MOV-033A,B) will be modified to preclude overpressurization of upstream piping which could occur coincident with a failure of the check valves. After modifica-(~~ tions are complete the leak test requirement will be deleted.

( ) There are no provisions in the present design for measuring leakage across the valves after they have been exercised. They are located in long runs of vertical piping such that once they are opened and reclosed it is not possible to determine if a solid column of water exists above and below the valves. Without a solid column of water it is not possible to measure leakage using RCS pressure during startup. In order to verify reverse flow closure and leak tight integrity it is necessary to enter the drywell, close the dovn-stream manual valves and use a special test rig. Entry into the inerted drywell is precluded during normal operation and cold shutdown. Since verification of leak tight closure is required each time the valves are exercised, verification of forward flow operability and reverse flow closure will be delayed until the i first refueling.

Alternate Testing: The presently installed test operators provide approximately 25%

open stroking. An investigation is being performed to determine l if this is adequate to verify full flow opening. In addition, possible modifications to the operators to provide full stroke opening is being investigated. If the operators need to be modified to perform full stroke exercising, the modifications will be performed during the first refueling. Verification of forward flow operability and reverse flow c1soure will be performed at the first refueling. Subsequent to the above modifications, forward

~

flow operability and reverse flow closure will be verified ddring

["

cold shutdown.

Vl wetsam twenov senvers me.

m DOCUMENT NO. 80A2903 Rev 3 NUCl. EAR ENERGY SERVICES. INC. PAGE III-9-7 OF TTT-9-7

~

/

RELIEF REQUEST' RR - 2 System: Core Spray h: 0018A,B M *90fY: C Clase: 2 Function: Ioop level injection line check valves to core spray system.

ASME Section XI Quarterfyinst W: Verify reverse flow closure.

O Beeis for Relief: Loop level piping configuration precludes verification of reverse flow closure.

Altemate Testing: Design changes are presently under consideration to either modify the loop level piping configuration or to modify the valves to provide a means cf. valve reverse flow closure verification. An appropriate modification (s) will be selected and completed during the first refueling outage. Durir.g the interim forward flow operability will be verified by a system check to verify system water inventory.

\

renueuns. m w s:

Docum:nt No. 80A2903 R:v. 3 d

rm

(\s)

PUMP AND VALVE INSERVIG TEfING PROGRAM PIAN FOR

! S1KEEHAM NUCLEAR TOWER PIANT

, UNIT NO. 1 i

SECTI N III ATT10iMENT 10 l

l [V T VALVE 1EST DATE AND FM REQUESTS EUR MSIV IEAKAGE CCNTROL (E-32) l DWG. NO. EM-69A i

l l

)

III-10-1 mneaarwaovsenvers.ac. -

/'"% 7'N ;

[N (U )

(G') '%l 4

SYSTEM:- mrv rnyr.P rnmrv tr- m MLVE TEST TABLE Dwa NO. EN-69A DOCUMENT NO. 903 h2 III~I 2 PAGE OF _ III~

STROKE C.S. C.S.

CLASS M peRECT. CHECK JUSI OR WIME NO. AND MLVE (ut) ACTL1 NORM TEST VALVE REV AND OR Aly RLuktKS DwG. CAI AND TYPE POS41 REa w TEST No.

REUEF TEST COOR. M (SECL) DIRECI REQ.NO. PF.RF.

M -021A 1 A 1 m C EP-Q C G-1 ET-C D-4 GL SM 8 G-1 ST-C IJ-R M -021B 1 A 1 50 C EP-Q C CS-1 ET-C D-4 GL SP-Q 8 CS-1 ST-C IJ-k M -021C 1 A 1 60 C EF-Q C CS-1 EP-C E-2 GL ST4 8 CS-1 ST:C IJ-R W -021D 1 A 1 70 C EF-Q C CS-1 EF C l E-3 GL SM 8 CS-1 SP-C IJ-R j M -022A 2 B 1 PO C ET4 O l D-4 GL ST-C 7 M -022B 2 B lh 70 C EF-Q O D-5 GL ST-Q 7 M -022C 2 B 1 PO C Er4 O E-2 GL SM 7 MS s244

I O

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SIZE DIRECT. CHECK AND MLVE JUSI OR WLVE NO. C4) ACT11 NORM TEST AND MLVE OR ALI. REMARKS REV DWG. CAI AND TYPE POSII REQ. m TEST U REUEF TEST N M (SEC,) DIRECT REO. NO. tERF.

KN-022D 2 B 1 MD C E"P-Q O E-3 % SP-Q 7 M W-023A 2 B lh m C ET-Q O E-6 E ST-Q 7 MOV-023B 2 B lh m C ET-Q O D-6 CL SP-Q 7 MOV-023C 2 B lh m C EM O G-6 G ST-Q 7 MN423D 2 B ?. MO C E'P-Q O F-6 GL ST-Q 7 PtN-024 2 B 2 m C ET-Q O CS-2 ET-c C-4 GL SP-Q 7 CS-2 SP-C MOV-025 2 B 2 M0 C EM O C-5 a st-Q 6 uts e2*1

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DOCUMENT NO. __ 8 03 . mv 2 NUCLEAR ENERGY SERVICES, INC.

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COLD SHUTDOWN TEST JUSTIFICATION CS - 1 System: MSIV Leakage Control Velve: MOV-021A,B,C,D Categosy: A Class: 1 Function: Upstream bleed line isolation valves.

ASME Section XI Quarterty Test Requirements: Exercise and time.

Cold Shutdown Test Justification: Valves are interlocked to main steam line pressure and cannot be opened at precsures greater than 35 psig. The interlock precludes inadvertent steam discharge.

Quarterly Port Stroke Testing: NA v ca Shutdown Testing: Exercise and time.

FOMG # NES-24712/82

m m --

DOCUMENT NO. , ,

m

NUCLEAR ENERGY SERVICES, INC. -

COLD SHUTDOWN TEST JUSTIFICATION CS - 2 ,

p m

System: MSIV Leakage coarrol . 1.

/,

Velve: Mov-024 Mov-026 ,- , - . ,

Category: B '

Class: 2 Function: Downstroam bleed isolatiore valve (MOV-024)

Downstream deprer,surization branch lige isolation valve (Mov-026)

ASME 3ection XI - <-- ,

Quarterly Test Requirements: Exercise and time

_ S,u,_ 2 Test Justification: valves are interlocked to main steam line pressure and cannot be opened at pressures greater than 35 psig..Thi interlock ,... c precludes inadvertent steam discharge._

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s Quarterly Part - -

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s Stroke Testing: NA '

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O Cold Shutdown Testing: Exercise and time. -

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Docum:nt No., 80A2903 R2v. 3 A

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%d PLNP AND VALVE I F E ICE TESTING PROGRAM PIAN EOR SIORE2W4 NUCEAR POWER PIANT UNIT NO. 1 O s SECTICN III

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l ATIEHMENT 11

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VALVE TEST TARTFS AND RET.TEF REQUESTS EVR HPCI (E-41)

DWG. NO. EM-25 A,B b

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g g. IIIGI PRESSURE QXXMFr ItUUCTIO3 (E-41) g ggy m fM-25A 80A2903 Inw 3 em g III-ll-2 y III-ll-12 d S.O. Ci cS.

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N WST N N (SEC.) DIRECT REO.NO. PERF.

KN-031 2 B 16 m O EF-Q C F-8 CF SP-Q 85 MN-036 2 A 4 m C kT. -Q O D-6 CL SM 10 i

LJ-R MOV-032 2 A 16 m C EF-O C D-6 CT SBC 90 L7-R MW-043 2 B 10 m C EP O O G-6 Cr .W 17 I

H N-035 1 B 14 m C EF-Q O E-5 Cr ST-Q 20 HOV-042 1 A 10 m C EF-O C D-4 Cr CBC 18 LJ-R 0001 2 C 16 SA -

EP-Q F F-8 C NEs e244 6

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gg. !!IGi PRESSURE Q)OUWF IRTE.

T IQJ (E-411 M TEST M FM-25A gg NO. 80A2903 Rev 3 g III-ll-3 y III-11-12 d CLASS M STRO#E C1 C1 DIRECT. CHECK JUST. OR MLVE NO, AND MLVE (IK) ACT11 N001M TEST MLVE AND OR A4.I REMARILS REV DWG. CAI AND TYPE POSfI REO TuaE TEST NO.

M REUEF TEST M

(SEC.) DIRECI REO. NO. PERF.

0002 2 C 16 SA InM) F D-8 RR-3 Valve will be part strdked open C qturterly using danin. water and qmtream and dowatest tape.

0012 2 C 4 SA -

L'IM) F E-6 C 0013 2 C 14 SA -

ET-Q F E-5 C 0021 2 C 18 SA -

IT-Q F D-5 C 0022 2 AC 18 SA -

ET O F Verify forward ficw gerability D-5 C I ET-Q R RR-1 ET-R quarterly during pulp test. Verify LT-R reVETSe flow Closure at refueling during W. J, Type C testing.

MW-037 2 B 10 m C IMM) O F-5 GL s'IM) 66 MN-041 1 A 10 to O W C C-4 GL S'IM) 17 IJ-R l

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CLASS SIZE DIRECT, CHECK Just OR ifuVE NOL AND iguyE SK) ACiu NORM TEST AND imLVE OR AI.I, REMARKS M DWG. CAI AND TYPE POSII RE(1 TEST NO.

TMAE REUEs' TEST COOR. M DIRECT REO. NO.

(SEC.) PERF.

MOV-047 1 A 1 PO O ETM) C 1 C-4 cL ST-Q 18 IJ-R 70/-048 1 A 1 PO O ET-Q C C-4 cL SP-Q 18 LT-R n -081 2 B 1 AO O EM C 11 - 7 Cr SD"Q Stroke time not available. Will be added h determined.

d 50 i

Jnt-082 2 B 1 JC 0 EM C u-> C,- ss Stroke time not available. Will be

~ ~ . tem. d FS-Q MOV-044 2 A 13 90 0 ETM) C C-5 Cr ST-Q 109 LT-R 70/-049 2 A 2 PO O EP-Q C C-5 cn SP-O 22 L7-R 0023 2 C 2 SA. -

EF-Q P RR-4 ET-R D-5 C EM R PR-4 EP-R

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STROKE CA CA M DIRECT CHECK JUSE OR wu.VE NO. AND MLVE M) M NORM TEST AND WLWE Og ALI ItEMARKS REV DWG. CAI AND TYPE POSII REO- M TEST NO.

M TEST N N (SEC) DIRECI REO. NO. PERF.

PDf-039 2 B 2 10 C ' ET-Q O D-5 GL S1M) 22 IKN-051 2 B 10 !!YD C E1M) HPCI turth throttle ard st@

H-2 CF ST-4) RR-2 valve.

IKN-052 2 B 10 ilYD C Ef-Q IECI turbine cxmtrol valve.

G-2 CF ST-Q RR-2 RV-145 2 C 3/4 SA -

SR-P C-7 R I

0007 2 C 2 SA -

ET-Q F C-5 C i

0011 2 C 2 SA -

ET-Q F D-7 C ADV-083 2 F-7 B

GT 1 AO C ET-Q ST-Q C Strtie time rxtevallable. Will be N h dete m ned.

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DOCUMENT NO, 80A2903 Rev 3 -

m 11 NUCLEAR ENERGY SERVICES. INC. E ~ ~ ~ ~

{ ,

REUEF REQUEST' RR - 1

~

System: HPCI l

h: 0022 l

Mogory* AC Class: 2 l

l Functica: Containment isolation simple check valve (reverse flow closure for containment isolation only).

, ASME Section XI

(

Ouarterhr Test Requirements: Verify reverse flow closure.

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

9 l

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

, l I

- . = =

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

DOCUMENT NO. 80A2903 .Rev .3 m

-" NUCLEAR ENERGY SERVICES, INC. PAGE III-ll-9 0F III-ll-12 /3\

9 REUEF REQUEST RR - 2

~

System: HPCI Wive: HOV-051 : HOV-052 Categosy: B Class: 2 Ft:nction: HPCI turbine throttle and stop and control valves.

ASME Section XI Questerly Test Requirements: . Measure strcke time.

l I Basis for Relief: The purpose of these valves is to regulate steam flow to the HPCI turbine. Operability is adequately demonstrated by proper turbine operation. , Valve p~osition is steam line pressure and turbine speed dependent and the19 fore will not repeatedly throttle to the same position. During turbine operation these valves move in response to etntrol signals.

4 Altemate Testing: Proper operation of these valves will be verified during turbine test. No stroke time testing will be performed.

l I FORM # NES-24412/82

1 8 A2903 Rev 3 DOCUMENT NO.

NUCLEAR ENERGY SERVICES. INC. .

PAGE III-ll-10 0F III-ll-12 d ReueFneoueur RR 3

~

System: HPCI

m. 0002 M C Class: 2

unction: Suppression pool suction line to pump check valve.

ASMe Section XI Quarterly Test Requirements: Full flow forward flow exercise.

e Beeis for Relief: The only possible full flow test would require pumping suppression pool water to eithe,r the a) feedwater system or b) condensate storage tank. .The first is precluded by the poor quality of pool water and possible thermal shock induced pipe cracking probinms

'and the second by condensate tank water quality problems that would result from introducing pool water into the storage tank.

Either method would also require extensive flushing of the system after testing which would over burden the radwaste system. The valve can be partial stroke exercised by injecting de. min. water at the upstream test tap and verifying partial valve opening at the downstream test tap.

AltometeTesting: A design change is presently under investigation to modify the valve by adding mechanical exercising feature that would provide full stroke test capability. If valve modification is possible the valve will be modified during the first refueling and a full exercise test performed quarterly. During th,e interim the~vhlve will be partial stroke exercised quarterly using demin. water.

l

' M FORM J NES 24412/22

my DOCUMENT NO. 80A2903 Rev 3 l

NUCLEAR ENE9GY SERVICES, INC. PAGE III-ll-ll OF III-ll-12 /A rs REUEF REQUEST RR - 4

~

System: HPCI Valve: 0023 : 0024 Category: C Claeo: 2 1

Function: Vacuum breakers (forwierd flow) to preclude drawing water into the turbine exhaust line and to prevent steam (reverse flow closure) flow to the suppression pool air space.

ASME Section XI Querterly Test Requirements: Verify forward flow operability and reverse flow closure.

O Basis for Relief: The system design has no test provisions to allow for quarterly

- ' testing in either direction. The only method available to verify

' operability, is by using a test similar to the Appendix J, T.ype C test. This. test will be devised to verify.both forward flow

opening and reverse flow closure and will be performed at refueling.

Alternate Testing: A special test procedure similar to the Appendix J, Type C test procedure will be used to verify forward flow operability and reverse' flow closure at refueling /

0 l

FORM # NES-24412/8 I

I DOCUMENT NO. 80A2903 Rev 3 NUCLEAR ENERGY SERVICES, INC. E

~

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A I

V RELEF REQLEST*

RR - 5 System: HPCI M' 0019 C " x-+ i C Class: 2 Function: Loop level injection line check valve to HPCI system.

ASME Section XI Quarterly'lhet Requiremente: Verify reverse flow closure.

l i

O Basis for Relief: Loop level piping configuration precludes verification of reverse flow closure. To review reverse flow closure would require securing the, loop level pump and draining the loop level piping, operating the. HPCI system and monitoring an upstream vent line for leakage. This method would require opening vent valves during

! system operation at operating pressure, which presents a potential for injury to plant personnel.

i l

Me* Testing: Design changes.are presently under consideration to either modify the loop level piping configuration or to modify the valve to provide a means of valve reverse flow closure verification. An appropriate modification (s) will be selected and completed during the first refueling outage. During the interim forward flow operability will be verified by a system check to verify system water inventory.

l 8

PORM e NEs-24412A2

Docum:nt No. 80A2903 Rsv. 3 A

o)

(

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i PWP AND VALVE INSERVICE 'I"rSfING PROGRAM PIAN MR SHOREHAM NUCEAR POWER PIANT UNIT NO. 1 SECTI N III ATTACHMENT 12 rh Id VALVE TEST TARTE AND FFTJFP REQUESTS MR RCIC (E-51)

DWG. NO. EM-22 A,B O

III-12-1 wuctan curaov stavers me

G O N U

f O J SYSTEM: 10C11M CORE ISGATim mite (E-51)

WLVE TEST TABLE m-22A DOCUMENT NO. PAGE I ~ ' ' '

OF CLASS STHOKE C.S. C.S.

SIZE MLVE NO. ANO WM DIRECT. CHECK JUSI OR (W) ACTu NORM TEST AND VACJE DWG. CAI AND TYPE POSII REO.

OR Alt REMARKS RW COOR. lYPE Tm TEST RELIEF TEST '

(SEC.) DIRECI REQ. NO. PERF.

, HDV-042 1 A 3 tu C C ET-Q D-3 CP ST-Q 18 IJ-R M W-031 2 B 6 50 0 ET 4 C G-8 GF ST-Q 37 HDV-032 2 A 6 to C ET-Q C D-8 CP ST-Q 36 IJ-R HDU-036 2 A 2 HD C ET-Q O E-6 GL 5 ST-Q IJ-R HDV-037 2 B 4 H0 C ET-Q O F-5 GL ST-Q 35 MW-035 1 B 4 70 C ET-Q O D-4 4

GT ST4 25 HDV-04 3 2 B 3 PO C ET 1 O G-6 Cr ST4 16 NEa s244

(' r j (V 'O V SYSTEM: N40R CORE ISOIATIW COOLItC (E-51)

VALVE TEST YABLE gg EN-22A DOCUMENT NO. 80A2903 Rev 2 PAGE III-12-3 op 111-12-11 STROKE C.S. C.S.

CLASS SIZE ceRECT, CHECK AND JUS 1 OR MLVE NO. VALVE (M) ACTtt NORM TEST AND W LVE OR Att REMARKS R DWG. CAI AND TYPE POSII REO- TEST TIME REUEF TEST '

COOR. TYPE 1 (SEC.) DIRECI REO.NO. PERF.

0001 2 C 6 SA -

LT-Q P P-8 C 0002 2 C 6 SA ET4 P RR-3 Valw will be part stroked gen D-8 C quarterly using danin. water and t4x;tream and downstream test taps.

0012 2 C 4 SA -

LT-O P E-5 C 0020 2 C 8 SA -

EN) P E-5 C 0021 2 A0 8 SA D-5 LT-Q P Verify forward flow operab".ity C LT-Q R RRal ET-R quarterly during prrp test. Verify IJ-R reverse flow closure at refueling during App. J, Type C testing.

0022 2 C Ig SA -

LT-Q P RR-4 LT-R D-5 C LT-Q R RR-4 LT-R t

0023 2 C gg SA -

LT 4 P RR-4 LT-R D-5 C LT 4 R RP.-4 LPR M S m244

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i SYSTEM: R5:lCIDR (DRE ISOIATION COX,DU (E-SI)

VALVE TEST TABLE DWG. NO. 22A DO*UMENT NO. BOA 2903 Rev 2 PAGE Y i T - D-4 OF TTT- M-11 STROKE C.S. C.S.

CLASS SIZE DEECT, CHECK AND VALVE JUST. OR VALVE NO. (IN.) ACTLA NORM TEST AND VALVE DWG. AND OR ALT. REMARKS REV CAT. TYPE POSII REO. TIME TEST M-COOR. RELIEF TEST TYPE (SEC.) DIRECT REO.NO. PERF.

0025 2 AC 2 T4 -

Lt1 P Verify forward flw gerability D-6 C LT-Q R RR-1 LT-R quarterly during purp test. Verify U-R reverse flw closure at refueling during App. J, lype C testing.

0024 2 C 2 SA -

LT-Q F E-6 C MOV-041 1 A 3 FD O i:T-Q C C-3 GT ST-O 18 Ld-R POV-047 1 A 1 SD O LT-O C C-3 GL ST-Q 18 U-R FEN-048 1 A 1 to O ET-O C D-3 CL ST-Q 18 U-R FtN-034 2 B 4 FD O LT-O O E-5 GT ST-Q 20 FKN-045 2 A 8 FD 0 ET-O C C-5 Cr '

ST-Q 48

U-R edSm244

i

.- S

~s n gg REACIOR OF3 ISOIATICN mntDG (E-51) M TEST M i

m yo, IN-22A DOCUMENT m 80A2903 hav 3 RAGE JI-12-5 op III-12-Il i

STROKE C.S. C.S.

CLASS SIZE tMRECT. CHECK JUSE OR 1ELVE NO. AND 1EL.VE (W) ACTL1 NORM TEST AND MM.VE E OR AA.I REMARKS DWG. CAI AND TYPE posit REO. TiteE TEST NO.

REUEF TEST COOR. TYPE (SEC.) DIRECE REO. NCL PERF.

Maf-049 2 A 1 m O EN C C-5 GL ST-Q 16 IJ-R 0015 2 C 1 SA -

ET4 F Forward flw cperability la verifia!

E-4 C EM R by a syntan check to verify water inventory. Reverse ficw closure is verified by 2senm of f1w at relief valve RV-149 durirq pwp test.

, 0016 2 C 1 SA -

EP-Q F Porward flw cperability is verified E-4 C by a systen deck to verify water inventory.

60/-046 2 AC 2 SA -

ET-Q F Forward flw cperability is verified D-6 SC MG O ET-Q C R during turbine test. Deverse closure S1M) 36 is verified using pooltive closure IJ-R potor operator.

ACV-Oel 2 B 1 AO O FP-Q C H-7 GP W Stroke time is not available. Will be k adied We detennined.

FS4 Aav-082 2 a 1 AO O Er4 C H-7 GT STS Stroke time not available. Will be added when determined.

d ES-Q d

NES 8244 i

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\ \/")u \v) g RDCIOR CORE ISOIATICH mnrE (E-51) M TEST M DWQ. NO. m-22B DOCUMENT NO. 80A2903 lbv 2 g III-12-6 y III-12-11 STROKE C S. C.S.

CLASS M DIRECT. CHECK Just on AND MALVE (Ift) ACTu NORM WALVE NO.

DWG. CAI AND TYPE POSII TEST AND M OR m REMARKS REV REO. TIME TEST RELIEF TEST E N WPE DIRECI REQ.NO.

(SEC.) PERF.

HOV-038 2 B 2 m C EP-Q O D-5 CL SIM) 13 1G'-044 2 8 3 to O ET. -Q ICIC turbine throttle and stcp valw.

G-3 GP ST-Q RR-2 Il0V-051 2 B 3 HYD O EP-Q ICIC turbine governing valw.

4 G-3 Cf S'P-Q RR-2 0006- 2 C 2 SA -

EIM) F F-6 C 0008 2 C 1 SA -

EP-Q F Fonard flow or.erability is verified B-5 C by a systen chdc to verify wter inventory.

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av DOCUMENT NO. 80A2903 Rev 2 NUCLEAR ENERGY SERVICES, INC. PAGE III-12-8 op III-12_11 m

O '

REUEF REQUEST RR - 1 System: RCIC l

l ysive: 0021 : 0025 i

Category: AC Class: 2 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).

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

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

Mornate TMnG" Reverse flow closure will be verified during Appendix J, Type C testing at refue*ing.

l lO FORM s NES-24412/82

DOCUMENT NO.

80A2903 Rev 2 NUCLEAR ENERGY SERVICES, INC. PinGE III-12-9 OF III-12-ll l

b REUEF REQUEST RR - 2 System. RCIC t

i m: MOV-044 : HOV-051 Category: B Class: 2 Function: RCIC turbine throttle stop and governing valves.

ASME Section XI Quarterty Test Requirements: Measure stroke time.

Basis for Relief: The purposa of these valves is to regulate steam flow to the RCIC turbine. Operability is adequately demcnstrated by proper tu wine operation. Valve position is stean line pressure and turbine speed dependent and therefore will not repeatedly throttle to the same position. During turbine operation these valves move in respont.o to control signals.

Alternate Testing: Proper operation of these valves will be verified during turbine test. No stroke time testing will be performed.

FORM 9 NES-24412/82

DOCUMENT NO. 80A2903 Fev 2 m

= " NUCLEAR ENERGY SERVICES, INC. PAGE III-12-10 op III-12-11 _

)

%J RELIEE REQUEST RR - 3 System: RCIC

m. 0002 Categmy: C Class: 2 Function: Suppression pool suction line to pump check valve.

ASME Section XI Quarterly Test Requirements: Full flow forward flow exercise.

o Basis for Relief: Th'e only possible full flow test would require pumping suppression pool water to either the a) feedwater system or b) condensate storage tank. The first is precluded by the poor quality of poo' water and possible thermal shock induced pipe cracking problems and the second by condensate tank water quality problems that would result from introducing pool water into the storage tank.

Either method would also require extensive flushing of the system after testing which would over burden the radwaste system. The valve can be partial stroke exercised by injecting demin. water at the upstream test tap and verifying partial valve opening at the downstream test tap.

Alternate Testing: A design change is presently under investigation to modify the valve by adding a mechnical exercising feature that would provide full stroke test capability. If valve modification is possible the valve will be modified during the first refueling and a full exercise test perforned quarterly. During the interim the valve will be partial stroke exercised quarterly using demin. water.

f d

FORM e NES-24612/82

DOCUMENT NO. 80A2903 Rev 2 m

NUCLEAR ENERGY SERVICES, INC. PAGE I11-12-11 OF III-12-ll V

RELtEF REQUEST RR 4 System: RCIC i

y,3,.. 0022 : 0023 M *90fY: C i

Class: 2 Function: Vacuum breakers (forward flow) to preclude drawing water into the turbine exhaust line and to prevent steam (reverse flow closure) flow to the suppression pool air space.

! ASME Section XI l Quarterly Test l Requirements: verify forward flow operability and reverse flow closure.

Basis for Relief: The system design has no test provisions to allow for quarterly testing in either direction. The only method available to verify operability is by using a test similar to the Appendix J, Type C test. This test will .be devised to verify both forward flow opening and reverse flow closure and will be performed at refueling.

l Mernete W: A special test procedure similar to the Appendix J, Type C test procedure will be used to verify forward flow operability and reverse flow closure at refueling.

I l w l

i FORM # NES-24412/82

Document I?o. 80A2903 Rev 3 d (s3 s

i l

1 l

PLNP AND VALVE INSERVICE 'IESTING PPOGRAM PIM mR SHOREHAM NUCLEAR POWER PIANT UNIT 10.1 1

l p) t g/

SECTICN III ATIACHMENT 13 VALVE TEST TABIES AND FRrm REQUESTS EDR RADWASTE EQUIPMENT (G-ll)

DWG. NO. EM-46 A,B l

i t

1

\v\

III-13-1 NUCLEAR ENERGY SERVICES INC,

( f f

%/ % )

2 SYSTEM: rat 106TE (G-ll)

WLVE TEST TABLE DM NO. 46A,B DOCUMENT NO. 80A2903 lbv 2 NE III-13-2 op 111-13-4 STROKE C.S. C.S.

CLASS SIZE AND WLVE DIRECT. CHECK A*JT. OR VALVE NO. (IN) AChL NORM TEST AND MLVE DWG. CAI AND TYPE OR ALT. REMARKS REV POSIT. REO. TEST TIME RELIEF TEST COOR. TYPE (SEC.) DIRECT HEO. NO. PERF.

etW-248 2 A 3 to O LT-Q C h 46A A-5 GT STM) 18 IJ-R MN-249 2 A 3 70 0 ET-Q C FM-46A A-5 Cr ST-Q 18 IJ-R KN-246 2 A 4 70 O LT-Q C J-5 GT ST-Q 18 IJ-R MW-247 2 A 4 FD 0 ET-Q C J-5 CT ST-Q 18 IJ-R IEN-639C 2 A 3 to C LT-Q C D--6 GT ST-Q 20 IJ-R 2210C 2 Ac 3 SA P ET-Q RR-2 LT-R D-6 C LT-Q H RR-1 ET-R LI-R h1S m244

my +

DOCUMENT NO. 80A2903 Rev 2 NUCLEAR ENERGY SERVICES, INC, PAGg III-13-3 OF III-13-4 Osv REUEF REQUEST RR - 1 l

System: Radwaste Valm: 2110C Category: AC Class: 2 Function: Containmenc isolation simple check valve (reverse flow closur . for containment i. solation only).

ASME Section XI Quarterty Tsd l

Requirements: Verify reverse flow closure.

1O t

Basis for Relief:

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

l l

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

T l roms e us.m was

my DOCUMENT NO. 80A2903 Rev 2 NUCLEAR ENERGY SERVICES, INC. PAGE III-13-4 op III-13-4 g

V REUEF REQUEST RR - 2 System: Radwaste

%: 2110C Category: AC Class: 2 Function: Leakage return pump discharge line containment isolation valve.

ASME Section XI Quarterly Test Requirements- verify forward flow operability.

Basis for Relief: To verify forward flow operability would require pumping water from the floor drain sump into the suppression pool. Typically water pumped from the sump is of relative poor quality. Injection of this poor quality water into the suppression pool would result in water quality control problems. This would be a plant operating problem during normal operation and cold shutdown when the suppression pool water is maintained relatively clean. It would have much less impact on operations at refueling when pool water quality tends to drop.

Alternate Testing: Verify forward flow operability at refueling.

FORM S NES-24612/82

Documrnt No. 80A2903 R;v. 3 g

fi v

PGP AND VALVE INSERVIG TESTING PROGRAM PIRI EOR SHOREHAM NUCLEAR POWER PIANT UNIT NO. 1 SECTICN III ATTACHMENT 14 O

O VALVE TEST TABIES AND FFT.TTP REQUESTS FOR REACIOR NATER CEANUP (G-33)

DWG. NO. M4-24A l

l l

l fh u/

l III.-14-1 NUCLEAR ENERGY SERVICES. INC.

( j)

Q f

( x 0

DM NO. EM-24A DOCUMENT NO. 80A2903 Rev 2 PAGE 111-14-2 op III-14-1 STROKE C.S. C.S.

CLASS SLIE AND DIRECT. CHECK JUST. OR VALVE NO. VALVE (H) ACTti NORM TEST AND VALVE og ALI REMARKS REV DWO. CAI AND TYPE 'POSII REQ.

COOR. TYPE TIME TEST RELIEF TEST "-

(SEC.) DIRECT. REO. NO. PERF.

WN-033 1 A 6 FO O LT-Q C F-6 cr ST-Q 36 L1-R KN-034 1 A 6 FD 0 LT-O C F-6 GT ST-O 36 L1-R 0050A 1 C 6 SA -

ET-Q R RR-1 LT-R A-1 C 0050B 1 C 6 SA -

LT-Q R RR-1 LT-R A-2 C 0036A 1 C 6 SA -

LT-Q RR-1 R ET-R B-1 C 0036B 1 C 6 SA -

LT-Q R RR-1 LT-R B-2 C Ness 2e4

l I

2 m DOCUMENT NO.

NUCLEAR ENERGY SERVICES. INC. PAGE III-14-3 of III-14-3 REUEF REQUEST RR - 1 System: Reactor Water Cleanup y,g. 0036A,B : 0050A,B Category: C Class: 1 Function: system isolation ASME Section XI Quarterty Test Requirements: verify reverse flow closure.

Basis for Relief: valves are located in the main steam tunnel which is inaccessible during normal plant operation or cold shutdown. In addition, interruption of normal RWCU letdown flow during, normal operation or cold shutdown could cause serious reactor water chemistry problems.

l l

l Alternate Testing: Reverse flow closure will be verified at refueling when entry to the main steam tunnel is possible.

l FORM # NES-24612/82

Docum:nt No. 80A2903 R:v. 3

,o t i

\%

PLMP AND VALVE INSERVICE TESTING PROGRAM PIAN EDR SHOREEW1 NUCLEAR POWER PIANT INIT NO. 1 SECTIm III ATI%CHMENT 15 (Gv/ VALVE TEST BRTF9 AND FFITEP iq2,3;tsis FOR E'UEL POOL COOLING AND CLEANUP (G-41)

DWG. NO. EM-19A n

v -

III-15-1 nuctua rnenov stavers ac.

e----- - - - - - - - - - - . , - - - - - , , - - - - - - - ,

\& 'mj '%Y ITJE1 ICOL 000LDC & CIERAP (C-41)

VM TEST TAM EM-19A gg NT M. 80A2903 lbv 2 PAGE III-IS-2 op III-IS-3 STROKE CS. C.S.

CLASS SEE AND DIRECT. CHECK JUSI OR wu.VE NO. W4LVE (IK) ACTt1 NORM TEST AND WLLVE OR ALI REMARKS REV DWG. CAI AND TYPE POSII REO. TIME TEST NO.

REUEF TEST N WPE (SEC.) DIRECI REO. NO. PERF.

MOV-034A 2 A 10 m C ET-Q C C-6 GP SM 60 IJ-R m V-034B 2 A 10 m C ET-Q C C-6 Gr ST-Q 60 IJ-R MUV-033A 2 A 6 m C ET-Q C A-6 GP ST-Q 36 IJ-R MOV-033B 2 A 6 m C EM C A-7 GT SM 36 IJ-R MOV-032A 2 B 6 m C ET-Q O

! 11- 5 D SM 38 l MOV-032D 2 B 6 M0 C ET-Q O II-6 D ST-Q 38 0003A 3 C 6 3A -

ET-Q F F-7 C NES e244

O O O V m REL POOL C00LIPC & CEANUP (G-41) mtVE TEST TABLE gg m-13A g 80A2903 Ibv 2 III-I 3 II' ~

f%GE OF STROKE CS, C.S.

CLASS SEE MLVE NO. AND MLVE (M) ACTu NORM TEST DIRECT. CHECK m OR AND m!VE OR ALT REPAARKS REV DWG. CAT. AND TYPE POSII REQ. TME TEST U REUEF TEST COOR. TVN (SECL) DIRECT REQ.NO. PERF.

0003D 3 C 6 SA -

ET-O F F-8 C H N-031 3 B 2 60 C PV J-5 D s e

I l

, NES 8244

Docum:nt No. 80A2903 Rev. 3 g

[QJ '

PUMP AND VALVE INSERVICE TESTING PPOGRAM PIAN EDR SHOREHAM NUCLEAR POWER PIANT UNIT NO. 1 SECTICN III ATIACHMENT 16

(

N.)

VALVE TEST TARTFR AND FRT.TEP REQUESTS FOR RBSVS AND CRAC (M-50)

DWG. NO. EM-43 A,B l

I l

(~^)

w l

l NUCLEAR ENERGY SERVICES. INC,

O O O m PibVi & CRAC (M-50) WuvE TEST ROLE DW(1. NO. FB-43A DOCUMENT NO. 80A2903 Bev 2 PAGE TTT-16-2 op TTT-16-7 STROKE C.S. C.S.

CLASS M DmECT. CHECK JuSt On VALVE NO. AND MALVE (N) ACTti NORM TEST AND VALVE OR ALI REMARKS REV DWG. CAI AND TYPE POSII REQ. TEST NO.

N M TM4E RRE TEST (SEC.) DIRECT REQ.NO. PERF.

0179A 3 C. 6 SA -

ET-Q F C-2 C 0140A 3 C 6 SA -

ET-Q F C-5 C 0178A 3 C 6 SA -

ET-Q F C-2 C

, Ol39A 3 C 6 SA -

ET-Q F C-5 C 0007A 3 C 6 SA -

ET-Q F E-3 C 0008A 3 C 6 SA -

ET -Q F E-5 C ADV-062A 3 B 6 AO O ET-Q E-3 cr Stroke tinu not available. Will ST-Q be added h determined.

FS-Q NES e244

V .

Eo k h

[V 7 6

RN b

e b e

b e

1

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I i i i I W W W _

e e e F l l l O b b b

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ld ie ld ld an ie ie vi an an S amr vi vi 4 K ann ann R te te E

L 3 A ot ot te ot 8 - M n ne ne 6

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mn e d d T I ie mn ie mn ie S I th th th E

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e w e w o ki kd M r mh o rb M

I m kW S

t tA Sa t&

Sa T F,

. RI SR L

S. O A C EE TP O

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e K I R CVSETC E EL ER 3

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KCDEC OE N ME a O72 O72 C72 C72 C C RR TI ATS (

O SD N

T )))

N T .

SQ Q) )Q M- QQ Q) QQQ QQQ MMH rI M M E - - - - - - - - - -

M E E I I f I T FT PI TTS rPS U TR b'SF ES ES ES ES ESF ESF C

O D MI I RS C/ C OO O C C / O O NP O O i

t E TP O 0 O O CY AT A M m m m A A E) r 0 0 0 0 r r Z

6C 1 B 1 B 1 B 1B 2C 2C S (M I

A NDM E

VI LA B B B B B B B MC S .

_ SDG 3 3

) 5 4 4 4 4 0

5 ANWN LA C D 3 -

E 3 -

A 3 -

A M

(

C A

R C

A S 3 O. A A A A A A A V 4 N 3 4 3 2 1 9 8

- S -

E 6 3 3 3 3 6 6 B B M 0 0 0 0 0 0 0 b

P F I - - - - - -

A V N N W N N N N-N M M M M N N

[ :

M g 4 4

2 E 8 T 3 S S E

Y N S

O O O SYSTEM: N'#W VALVE TEST TABLE N NO. m-4 3A DOCUMENT NO. 80A2903 lbv 2 PAGE III-16-4 II- 6-7 OF STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUSI OR WuYE NO. AND M (K) M NORM TEST ANO VALVE REV On Att REMARKS DWG. CAI AND TYPE posit REQ. TEST NO.

TIME REUEF TEST COOR. M (SEC.) DIRECI REO. NO. PERF.

0019A 3 C 6 SA -

E'IM) F E-4 C 0020A 3 C 6 SA -

E*r-O F E-6 C AOV-039A 3 B 2 AD C E'F-O Stroke tinn not available. Will be E-2 cr SF-O added then determined.

FS-Q ADV-040A 3 B 2 AD C 'Tr-O Stroke tinn not available. Will be G-5 cr S1M) added then determined.

FS-O RV-091A 3 C 1h SA -

SR-P F-7 R ms s244

V R"

E '

7 6 e 1 b

- l I

I l I i b

p e o l b

a .

ld ie S

an vi K amr R

E 5 A te L M ot B 6 E

ne A 1 R d T - e n

T I S

E T

E I

I ih t

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A A t V P S '~

S. R T. SR T F.

OOAL EE TP FO S RIE N.

CmO LREQRE 2

v e K I R C ETC E V. S E

_ 3 hue C U TI R F F F F F P 0

D 9

2 A F T. ).

0 KCDE C 8 OE RR NM I E TI SD ATS (

O N

T N T .

SQ Q Q- Q Q- Q- Q OOQ E - - -

M E E T T T T T T TTS U TR L E E E E E ESF C

O D MI RSI OO - - - - - - O NP i E t

TP A A A A A A O CY S S S S S S A AT E)D E ZMN P 6C 6C 6C 6C 6C 6C 6 T G S(AW I

E VIA C L C C C C C B nC U

S .

)

0 SDG 5 5 2 2 3 5 2 5

M ANWN LA C D 3 -

C 3 -

C 3

C-3 -

D 3 -

E N

8 3 .

4 O B

- N 2 N m E V

L 8

0 B

9 B

9 8

8 B

7 8

8 6

0 E 4 3 7 7 0 0 D 1 l 1 1 0 0 N

. 0 O 0 0 0 0 A M

O 4 4

2 E N. e T G S S

Y W E N

S D

^ ,F\

r h

( b mg RBSVS & CRAC (M-50)

WuVE TEST 1ASLE gg FB-43B mg 80A2903 Rev 3 III-16-6 g OF III-16-7 STROKE C.S. C.S.

CLASS M DIRECT. CHECK JUST. OR Wu.VE NO. AND WEVE OK) ACTH NORM TEST WuvE E ANO OR ALI REMARKS DWG. CAI AND TYPE posit REO. TuaE TEST NO, REUEF TEST COOR. TYPE (SEC.) DIRECI REO. NO. PERF.

ADV-063B 3 B 6 AO O T-Q E-S Stroke time not available. Will be GP SP4 uMvi den determined.

FS-Q i MOL/-034B 3 B 10 MO c EIQ O A-3 B SP4 72 MOV-033B 3 B 10 m C EP4 O A-4 B ST-Q 72 M W-032B 3 B 10 MO O ET-Q C

, A-4 B S'oC .72 i

K M-031B 3 B 10 MO O ET-Q C A-4 B ST4 72 ADV-069B 3 B 2 AO O ET-Q C A-3 or SM Stroke time not available. Will be b

% determined.

FS-Q ADV-068B 3 B 2 AO O EP-Q C A-4 GT ST-Q Stroke time not available. Will be d added Wum determined.

FSS NES e244

]

r r* ! .

k SYSTEM: RDSVS & Catc (M-50) WLVE TEST TABLE gg fB-43B g 80A2903 Rev 2 III-16-7 ITI-16-7 PAGE op STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUSI OR i

MLVE NO. ANO ELVE (IK) ACTti NORM TEST W LVE REV

Jio OR ALI REMARKS i

DWG. CAI AND TYPE POSII REQ. TIME TEST "

REUEF TEST N M (SEC.) DIRECI REO.NO. PERF.

0019D 3 C 6 SA -

ET-O P E-4 C 00200 3 C 6 SA -

ET-O F E-6 C ADV-039B 3 B 2 AD C LM F-2 Stroke time not available. Will be Cr ST-O added h determined.

FS-Q 1

ADV-040B 3 B 2 AO C G-5 EP O Stroke tine not available. Will be Cr ST O added h determined.

FS C RV-091B 3 C lh SA -

SR-P F-7 R KS a244

Docum:nt No. 80A2903 Fev. 3 g e'

(s_ ,/

s PUMP AND VALVE INSERVIG 'IESTING PROGRAM PIAN EUR SHOREHAM NUCIEAR POWER PIANT UNIT NO. 1 SECTIW III ATIACHMENT 17 1

{

VALVE TEST TABLES AND RU M REQUESTS FOR SERVIG NATER (P-41)

IXG. NO. FM-47A O

III-17-1 _

uctua rwncv stavers ac.

L

m ,, -~\

SYSTEM SERVIG WNIER (P-41)

VALVE TEST TABLE gg EN-47A 80A2903 Rev 2 III~II-2 III~I7-9 DOCUMENT NO. PAGE OF i

STROKE C.S. C.S.

CLASS SEE DMECT. CHECK JUSI OR MLVE NO. AND M (E) ACTti NORM TEST AND M REV

OR ALI REMARKS DWG. CAI AND TYPE POSII REQ. TIME TEST "*

RELIEF TEST N WPE (SEC.) DMECI REO. NO. PERF.

NN-031A 3 B 15 60 O/C ET-Q C G-6 B ST-O 72 MOV-031B 3 B 15 FO O/C ET-O C I-6 B SM) 72 MN-031C 3 B 15 60 O/C ET-Q C F-6 B ST-O 72 MN-031D 3 B 15 70 O/C ET-Q C J-6 B ST-Q 72 tKW-032A 3 B 24 to O ET-O C 11- 5 B SM) 72 MN-032B 3 B 24 PO O ET-Q C H-5 B ST-Q 72 M N-035A 3 B 24 70 IC PV J-5 B NES s244

[ ,f l N N \_j l

l l

l SYSTEM: SERVIG MHR (P-41)

VALVE TEST TABLE EM-47A 8 903 h2 DM M. DOCUMENT NO. PAGE III-17~3 OF III"I7*9 STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUST. OR VALVE NO. AND VALVE (M) ACTti NORM TEST REMARKg REV AND VALVE OR ALT.

DWG. CAT. AND TYPE posit REO. TIME TEST REUEF TEST COOR. TYPE (SEC.) DIRECI REO.NO. PERF.

H N-035B 3 8 24 FD IC PV J-5 B KN-033A 3 B 20 to C LT-Q O E-5 B ST-Q 72 -

HlN-033u 3 B 20 FU C LT-Q O D-6 B ST-Q 72 MOV-033C 3 B 20 to C LT-Q O D-5 B ST-Q 72 MOV-0330 3 B 20 FD C LT-Q O C-6 B ST-Q 72 M N-039A 3 B 1 FD O LT-Q C D-6 D ST-Q 72 MW-039B 3 B 1 FD O LT-Q C D-6 D ST-Q 72

PdSa244 a

m sm ry

\ ,

g. SERVICE WPSER (P-41) yhtVE TEST TABLE m m. m-m mm 80A2903 Dev 2 III~I7~4 III'I7-9 PAGE OF STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUST. OR MALVE NO. AND VALVE (IIt) ACT11 NORM TEST AND WALVE OR Att REMARKS REV DWG. CAI AND TYPE posit REO. TEST "-

TIME REUEF TEST COOR. TYPE (SEC.) DIRECI REQ. NO. PERF.

M N-034A 3 B 20 70 C ET-Q O D-7 B SM 72 M W-034B 3 B 20 to C ET-Q O B-7 B M 72 MOV-037A 3 B 16 20 O/C ET-Q O B-5 B SM 72 M N-037B 3 B 16 MO O/C EM O B-4 B ST-Q 72 ADV-016A 3 B 6 AD C ET-Q H-1 GT Stroke tinu not available. Uill le SF-Q added W n determintxi.

FS4 NN-016B 3 8 6 AO C ET-Q F-1 cr ST-Q Stroke tian not available. Will be added h n determined.

FS-Q ADV-016C 3 B 6 AO C EM G-1 GT ST-Q Stroke time not available. Will le added h determined.

FS-Q NES N244

/ f V

V U SYSTEM. SERVIG HNIER (P-41)

WMWE TEST TABLE EN-47A g NNT M 8Ch2903 142v 2 g III-17-5 op III-17-9 STROKE C.S. C.S.

CLASS SEE ymLVE NO. AND ELVE (N) ACTti NORM TEST DIRECT, CHECK m OR AND WMVE OR ALI REMARKS REV DWG. CAI AND TYPE POSII REO. TWE TEST RELIEF TEST -

N TYPE DIRECI REQ. NO.

(SEC.) PERF.

K N-036A 3 B 10 to O ET-Q O J-3 Cr ST-Q 72 MN-036B 3 B 10 70 0 EM O K-3 Gr ST-Q 72 j M N-036C 3 B 10 70 0 ET-Q O E-3 cr ST-Q 72 0002A 3 C 18 SA -

ET-Q F G-6 C EM 3 1

0002B 3 C 18 SA -

FF-Q F 11- 6 C ET-Q R i 0002C 3 C 18 SA -

ET-Q F F-6 C EM R 0002D 3 C 18 SA -

EM P J-6 C EM R I

MS s244

\ b b\

v V U SYSTEM: SERVICE WGER (P-41)

VALVE TEST TABLE g g, IN-47A III-17-6 DOCUMENT *eO. 80A2903 Rev 2 PAGE op III-17-9 STROKE C.S. C.S.

CLASS SIZE DIRECI CHECK M OR UMVE NO. AND MLVE (IP&) ACT11 NORM TEST AND WLVE REV DWG. CAI AND OR ALI REMARKS TYPE POSII REQ. TIME TEST RELIEF "

COOR. TEST TYPE (SEC.) DIRECE REa NO. PERF.

VIC-041 C4 3 C 20 C

SA M

W F flanually testable deck valve. LLie ET-Q R full stake test operator to verify operability.

0008A 3 C 20 SA -

ET-Q F A-7 C 0008B 3 C 20 SA -

ET-Q F A-7 C 0010A 3 C 16 SA -

ET-Q F A-6 C 0010D 3 C 16 SA -

ET-Q F A-6 C 6V/0013A 3 C 6 SA -

ET-Q F G-3 C EIM) R 6V/00130 3 C 6 SA -

ET-Q F E-3 C EM R 9

l NES R244

1

V

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RU 7

I I

F O

S K

R E 7 A L - M B 7 E A I R

T -

T I S I E I T

E E V

L G W M I

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S.

C ORISR t

A TP Ef

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CUO J EL Q R RE 2

ve K I R C E

ETC V. SE 3

hue CWTIR FR FR FR FR 0 O

- ' '- 9

, 2 E T.

A KC ) .

0 8 OE D C C 42 C 2 4

C 4 RR A 2 O

TI SD Nm(E S N

T N T .

SO Q QQ QQ Q Q- QQ Q E

M E E TM - -

TT TT TT TT

- - Q%

Tl U

C TR EE EE EE EE ES ES TE E

O D Mt i RS OO NP

- - - - C C O 1 E RP A A A A 0 0 O CY S S S S 6 6 M AT E)D T 6C 6C 6C 6C 6B 6B 1 ZMNM I

S(A G E

VI LA C C C C B B B WC

)

1 4 S .

P

- SDG .RO 3 3

( ANwO LA D C 3-F 3 -

H 3 -

3 F

3 -

3 3 -

4 3 -

4 R C G E E E E

I N

W G

I A

7 V

R 4

E N O. C A B C A B S F N 3 1

4 1

4 2 2 3 1 4 4 4 2 0 0 0 0 0 0 0 b 0 0 0 0 -

\

s L W /

V 6

/

V 6

/

V 6

/

V 6

N M

N H

W-M M

g 4 4

E 2 s

T S

Y S

g S E

N

pJ V,- - U,,

ggg. SERVIG WATER (P-41)

VALVE TEST L8LE mm FM-47A DOCUMENT NO. 80A2903 Dev 2 PAGE III-17-8 op TIT-17-9 STROKE C.S. CS.

CLASS SIZE AND DIRECT. CHECK JuSt OR VMVE NO. VALVE (IN) ACH1 NORM TEST ANO VALVE REMARKS hEV DWG. CAI AND OR ALI TYPE POSII REQ. TIME TEST REUEF TEST COOR. WPE (SEC) DIRECI REO. NO. PERF.

M N-129A 3 B 10 M) OS LT-Q C B-3 B ST-Q 36 MN-1298 3 B 10 m c/C ET-Q C A-2 B ST-Q 36 0032A 3 C 10 SA -

ET4 F I-3 C 0032B 3 C 10 SA -

ET-Q F I-3 C 0033A 3 C 10 SA -

L'P-Q F I-3 C 0033B 3 C 10 SA -

ET-Q F I-3 C 0034A 3 C 10 SA -

ET-Q F J-3 C ET-Q R NES s244

l

\) \) L/

l l

I l

l gg, SERVIG WIER (P-41) g nggg gg EM-47A 8 03 Av 2 III~I7-9 DOCUMENT NO. PAGE OF III~II-9 STROKE C.S. C.S.

M SIZE DIRECT. CHECK JUSI OR WuYE NO. AND M OK) ACTl1 NORM TEST AND WMVE REV OR ALI REMARKS DWG. CAT. AND TYPE POSII REO. ME TEST NO.

RN TEST N N (SEC.) DIRECT REO. NO. PERF.

0034B 3 C 10 SA -

D4 F K-3 C EIM) R 0035A 3 C 10 M -

W F J-3 C EP-Q R 0035B 3 C lo SA -

ET-Q F K-3 ,C ET-Q R NES W244

Docum;nt No. 80A2903 R;v. 3 A

1

/"xl (V

PINP AND VALVE INSERVICE TESTIN3 PROGRAM PIAN EDR SHOREHAM NUCLEAR POWER PIANT INIT NO. 1 SECTICN III ATD4HENT 18

/^%

(j VALVE TEST TARTPR AND PETM i<F.umb'm FOR RBCIG (P-42)

DWG. NOi FM-15 A,C : FB-23B t

I 1

III-18-1 NUCLEAR ENERGY SERVICES. INC.

(^

x V U

.l

g. Id>CIOR BIIG. (1Mn 100P C0QIlPC WNIER (P-42) EtyE TEST TABLE g EN-15A DOCUMENT NO. 80A2903 Rev 2 PAGE III-18-2 OF III-18-16 STROKE C.S. CS.

CLASS SIZE DIRECT. CHECK JUST. OR MtVE NO. AND M ufE (IK) ACTu NORM TEST ELVE REV AND OR ALI REMARKS DWG. CAI AND TYPE POSII REO- TM4E TEST

RELIEF TEST COOR. WPE (SEC.) DIRECI REQ.NO. PERF.

MOV-032A 3 B 8 m O ET-Q C G-1 Cr ST-Q 60 MOV-032B 3 B 8 MO O ET-Q C H-1 Cr ST-Q 60 MOV-033A 3 B 6 MO O ET-Q C CS-1 ET-C E-1 Cr ST-Q 40 CS-1 ST-C M -033B 3 B 6 MO O ET-Q C CS-1 ET-C E-1 GP ST-Q 40 CS-1 ST-C M-034A 3 B 6 m O ET-Q C CS-1 ET-C I-l Cr ST-Q 40 CS-1 ST-C M-034B 3 B 6 m O ET-Q C CS-1 EF-C 11- 1 Cr ST-Q 40 CS-1 SM M -042A 3 D 14 m C EF-Q C G-9 cr SM 80 NES s244

.* 2 O

'm.

gg. HE:ACIOR BIOG. NMn IIXP 000LDG WNIER (P-42) WLVE TEST TABLE IN-15A 80A2903 Fev 2 III-18-3 N ENT M PAGE op III-18-16 4

STROKE C S. C.S.

CLASS SEE

! wayE NO. AND WLVE Opt) ACTLL NORM TEST OMECT. CHECK m OR AND MLVE OR ALI REMARKS REV CAI 4

DWG. AND TYFE POSII REQ. TMAE TEST "

RELIEF TEST N WPE (SEC.) DIRECI REO. NO. PERF.

MOV-042B 3 B 14 MO C 12-Q C G-9 m SM 80 2OV-043A 3 B 8 70 0 EF-Q C E-7 Cr SM 52 MOV-0433 3 B 8 m O ET-Q C E-7 GT ST-Q $2 M -044A 3 3 8 to O EM C G-7 Cr SF-Q 52 M -0443 3 B 8 PO O ET-Q C G-7 m SM 52 M -031A 3 .B 8 m O Er-Q C G-6 GT SM 60 M-031B 3 B 8 MO O ET-Q C G-6 Gr SP-Q 60 NES s244

C U V

g. RDCIOR DIIE. CIDE 2D IIXP CX)DI.Itn WMER (P-42) VALVE TEST TABLE IM-15A mg 80A2903 Ibv 2 III~IO*4 III-18-16 RAGE OF STROKE CS. C.S.

CLASS SIZE .pgRECt CHECK JUST. OR V41VE NO. AND VALVE (BL) ACTLL NORM TEST VALVE RE W REV AND OR ALI DWG. CAI AND TYPE POSII REQ. TMAE TEST RELIEF NO.

TEST COOR. TYPE (SEC4 DIRECI REO.NO. PERF.

W W-041A 3 B 14 m O EP-Q C G-9 Gr SIM) 80 Maf-04IB 3 B 14 m O LT-Q C G-9 Gr SIM) 80 0005A 3 C 8 SA -

L7-Q F F-2 C ET-Q R 0005B 3 C 8 SA -

EIM) F J-2 C ENM) R 0005C 3 C 8 SA -

ET-Q F 11- 2 C ET-Q R 0036A 3 C 12 SA -

EIM) F D-6 C 0036D 2 C 12 SA -

ET-Q F -

J-6 C NES 5244

,- s SYSTEM: EDCIUR BIDG. CIIEED 12P GILItJG HNIER (P-42)

MLVE TEST TA8LE DWG. NO. FM-15A DOCUMENTi40. 80A2903 Rev 2 PAGE III-18-5 op ITT-18-16 STROKE C.S. C.S.

CLASS StZE AND DIRECT CHECK JUST OR mtVE NO. VALVE (M) ACTL1 NORM TEST AND VALVE OR REV DWG. CAI AND ALT. REMARKS TYPE POstI REO- TIME TEST NO.

COOR. RELIEF TEST TYPE (SEC.) DIRECI REO, NO. PERF.

NN-292 3 BC 8 SA -

LT-Q P G-8 SC N) O Positive closure stop check valve.

L7-Q C R CS-2 LT-C Air operator used to test for ST-Q cr.-; ST-c reverse closures. Stroke tire not availat:le. ' fill te aMx' W n determined.

IKS m244

(mV) fs

( >)

(r

'v-SYSTEM: M'7CIOR BIRL CIMED IOOP GOLUD WA1TR (P-42)

VALVE TEST YABLE Th-15C DM M DOCUMENT NO. 80A2903 rev 2 PAGE III-18-6 og 111-18-16 STROKE C.S. C.S.

CLASS SIZE AND DIRECT CHECK JUSI OR VALVE NO.

DWG.

VALVE CAI (IM)

AND ACTu NORM TEST AND W OR ALI RF. MARKS REV TYPE POST 1 REO- TEST TIME RELEF TEST COOR. TYPE (SEC.) DmECT REO.NO. PERF.

PKN-035 2 A 4 FD O Cr-Q C CS-3 Cr-C E-6 cr ST-Q 24 CS-3 St-C IJ-R HOV-036 2 A 4 FD O CP-Q C CS-3 cr-C A-4 Gr ST-Q CS-3 24 ST-C IJ-R PEN-047 2 A 4 FO O EP-Q C G-3 Cr-C F-6 Cr ST-Q 24 G-3 ST-C IJ-R FIN-048 2 A 4 FD 0 EF-Q C G-3 EF-C J-4 Cr ST-Q 24 CS-3 ST-C IJ-R NN-293 3 BC 6 SA -

CP-Q F Ibsitive closure stop check valve.

A-4 SC AO O EF-Q C R G-4 EP-C Air operator used to test for SP-Q CS-4 ST-C reverse closure. Stroke time not available. Will be added when determined.

NN-294 3 BC 6 SA -

Er-Q F rositive closure stop check valve.

K-4 SC AO O EF-Q C R G-4 EP-C Air operator used to test for Ur-Q CS-4 ST-C reverse closure. Stroke time not available. Will be adiad when determined.

M S m244

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.t N. 55 55 1 1 S.SRNQ C JUO R RE GCS SS R

R 2 CC F R v I M KE C TC EL VS E HA E R R R 3

0 C V TID 9

2 E T.

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KC OE E

8 C

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C 18 C 8 8 4 C 24 8

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f E

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n EE TR WSUT TT-ESU PT-ESU PT ESU FT ESU PI EL T

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D MI I AS OO NP O O C O 0 - -

t E t

TP O )

D D D A A CY M K i F F S S AT E)D EP r T ZNN S(AW I

3 C 3 T G 3 F G 4 G 4 T G 3C 3C E

V LA T.

AC A A A A A C C V A A S .

SDG 3 5 6 1 1 2 4 ANWM LA C D 2 Ie 2 Ie 2 Ie 2 -

B 2 -

K 2 -

A 2 -

A B

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M f .

O N 8 9 0 7 8 E 3 3 4 4 4 A B V 2 2 2 1 1 A A d L A

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p ., f^%

s' SYSTEM: WJCIOR BIT., CINED IDnP WOLY?C M1ER (P-42)

VALVE TEST TABLE DWG. NO. FB-23B DOCUMENT NO. 80A2903 Rev 2 PAGE TTY-18-9 or TTT-18-16 STROKE C.S. C.S.

CLASS SIZE AND DIRECT. CHECK JUSI OR VALVE NO. VALVE (IN.) ACTU. NORM TEST DWG.

AND VALVE OR Alt REMARKS REV CAT. AND TYPE POSIT. REQ TEST TIME RELIEF TEST COOR.

TYPE (SEC.) DIRECT. REO.NO. PERF.

0037AC 2 AC 3 SA -

ET-O R RR-1 CT-R A-5 C W-R 0037AD 2 AC 3 SA -

LT-Q R RR-1 LT-R A-6 C W-R 003711A 2 AC 3 SA -

LT-O R RR-1 LT-R le2 C W-R Ge37til 2 AC 3 SA -

LT-O R RR-1 LT-R Ir4 C W- R 0037tC 2 AC 3 SA -

LT-Q R RR-1 LT-R Ir5 C W-R 0037BD 2 AC 3 SA -

LT-O R PR-1 LT-R Ie6 C W-R IW-291A 2 AC 1 SA -

U-R 1hermini relief valve. A[p. J, A-1 R Typ, C t. cst only.

NE $ u?44

N [^N)

-) v

) \

Nd S EM- REACIUR BII11. CIIEED II)OP C00t.ING HNIER (P-42)

VALVE TEST TABLE DWG. NO. D DOCUMENT NO. 80A2903 Rev 2 PAGE III-18-10 op 111-18-16 STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUST. OR VALVE NO. AND VALVE (H) ACT11 NORM TEST AND VALVE OR ALT REMARKS REV DWG. CAT. AND TYPE POSIT REO. TIME TEST RELIEF TEST NO.

COOR. 1YPE (SEC.) DIRECT. REO.NO. PERF.

RV-2918 2 AC 1 SA -

IJ-R K-1 R

'Ihertnal relief valve. Asp. J, T/pe C test only.

I

(

Pi Se?44

Ally DOCUMENT NO. ROA2901 nov 9 E

E O M III-M-M NUCLEAR ENERGY SERVICES, INC.

a COLD SHUTDOWN TESTJUSTIFICATION CS - 1 System: RBCIrw Valve: MOV-033A,B : MOV-034A,B Category: B Chu: 3 Function: Isolate non-essential cooling loads during a LOCA.

ASME Section XI Quarterly Tost Requirements: Exercise and time.

bi V

Cold Shutdown Test Justification: To test these valves would require interruption of cooling water flow to the RWCU non-regenerative heat exchangers and pumps, CRD pumps and one half of the drywell ccolers. Both halves of the drywell coolers are required during normal operation. Inter-ruption of flow to either half of the drywell coolers could cause a reactor trip due to high drywell temperature or pressure.

In addition, failure of these valves to reopen could cause damage to equipment being cooled.

i I

t Quarterly Part Stroke Testing: Valves are full stroke only valves and cannot be partial stroke exercised.

Cold v Shutdown Testing: Exercise and time.

FORM # NES-24712/82

, DOCUMENT NO. 80A2903 Rev 2 W W NUCLEAR ENERGY SERVICES, INC.

COLD SHUTDOWN TEST JUSTIFICATION CS - 2 Systan: RBCLCW W!ve: AOV-282 Cetegory: BC Chu: 3 Function: Return isolation check valve.

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

Cold Shutdown Test Justification: Exercising valve would interrupt flow to the recirculation pump M-G set oil coolers, this could cause oil to overheat and c.ause a possible plant shutdown.

l l

l

! Quarterly Part l Stroke Testing: Valve is a full stoke only valve and cannot be partial stroke exercised.

l M

Shutdown Testing: Exercise, time and fail.

FORM # NES-24F 12/82 l

DOCUMENT NO. 80A2903 .Rev 2 PAGE III-18--13 OF III-18-16

/\

NUCLEAR ENERGY SERVICES. INC. ,

COLD SHUTDOWN TESTJUSTIFICATION CS - 3 System: RBCLCW Wlve: MOV-035 : MOV-036 : MOV-047 : MOV-048 Category: A Class: 2 Function: Inlet and outlet isolation valves to recire. pump seal coolers, motor bearing cooler and motor winding cooler.

ASME Section XI Quarterly Test Requirements: Exercise and time.

J Cold Shutdown Test Justification: To test these valves would require interruption of cooling water to the recirc. pump seal coolers, motor bearing cooler or motor winding cooler. Loss of cooling water for more-than 10 minutes could damage the recirculation pumps. Loss of cooling requires the plant to be shutdown.

Quarterly Part Stroke Testing: valves are full stroke only valves and cannot be partial stroke exercised.

J Cold

'd Shutdown Testing: Exercise and time.

FORM e NES 24712/82

I DOCUMENT NO. RoA?on, w u 9 PAGE 111-18-14 OF III-18-16 NUCLEAR ENERGY SERVICES, INC.

t v

COLD SHUTDOWN TEST JUSTIFICATION CS - 4 System: RBCLCW Valve: AOV-293 : AOV-294 Category: BC Class: 3 Function: Isolate non-essential cooling loads during a IOCA.

ASME Section XI Quarterly Test Requirements: Exercise and time.

Cold Shutdown Test Justification: To test these valves would require interruption of cooling water flow to the RWCU non-regenerative heat exchangers and pumps, CRD pumps and one half of the drywell coolers. Both halves of the drywell coolers are required during normal operation. Inter-ruption of flow to either half of the drywell coolers could cause a reactor trip due to high drywell temperature or pressure. In addition, failure of these valves to reopen could cause damage to equipment being cooled.

i l

Quarterly Part i Stroke Testing: valves are full stroke only valves and cannot be partial stroke

! exercised.

Cold Shutdown Testing: Exercise and time.

l FORM # NES-24712/82 l

(

my DOCUMENT NO. 80A2903 Rev 2 PAGE III-18-15 op III-18-16

NUCLEAR ENERGY SERVICES, INC.

D (V

COLD SHUTDOWN TEST JUSTIFICAllON CS 5 System: RECIrw Wive: MOV-147 : MOV-148 : MOV-231 : MOV-236 Category: A Class: 2 Function: Drywell cooling water supply and return containment isolation valves.

A3ME Section XI Quarterty Test Requirements: Exercise and time.

U Cold Shutdown Test Justification: To test these valves would require interruption of cooling water to one half of the drywell cooling system. Both halves of the drywell cooling system are required during normal operation.

Interruption of flow to either half of the drywell coolers could cause a reactor trip due to high drywell temperature or pressure.

(

i Quarterly Part Stroke Testing: Valves are full stroke only valves and cannot be partial stroke exercised.

Ccid Shutdown Testing: Exercise and time.

FORM s NES-24712/82

)

l

my DOCUMENT NO. 80A2903 Rev 2 NUCLEAR ENERGY SERVICES, INC. PAGE III-18-16 op III-18-16 I

Ns' REUEF REQUEST RR - 1 System: RBCLCW ww. 0037 AA,AB,AC,AD,BA,BB,BC,BD Category: AC Chu: 2 Function: Centainment isolation simple check valve (reverse flow closure for containment isolation only).

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

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

Attemate Testing: Reverse flow closure will be "erified during Appendix J, Type C testing at refueling.

t i

O FORM # NES-24812/82

Documtnt No. 80A2903 Ray. 3 g

O PLNP AND VALVE INSERVIG TESTING PROGRAM PIAN FOR SHOREHAM NUCEAR POER PIANT ENIT NO.,1

('

y SECTICN III ATDCHMENT 19 VALVE TEST TABIES AND RFT.TW RBRUESTS INSTRLNENT AND SERVIG AIR (P-50)

DW3. NO. EM-38 D,E e

O n-~

3__- --

O) (3 (~'!

% L-INSTIU tNP AND SERVICE AIR (P-50)

M TEST TAM M NO. EM-38E DOCUMENT NO. 00A2903 Rev 2 PAGE TTT-19-2 op v r t _ i n s,_

STROKE C.S. C.S.

CLASS SIZE AND DIRECT. CHECK JUSI OR VALVE NO. VALVE (H) ACTil NORM TEST AND WALVE OR ALI REMARKg REV DWG. CAT. AND TYPE posit REO- NO.

TEaE TEST RELIEF TEST COOR. TYPE (SEC) DIRECT REQ. NO.' PERF.

POV-104 2 A 1 to C EIM) C C-7 GL SIM) 18 IJ-R MOV-106 2 A 1 60 C EIM) C 11- 7 GL SIM) 18 IJ-R KN-103A 2 A 1 60 0 EIM) C C-5 GL ST-Q 26 IJ-R FDV-103B 2 A 1 to O EIM) C G-5 GL S'IM) 26 IJ-R 0695A 2 Ac lh SA -

EIM) R RR-1 EF-R P-5 C IJ-R 0695B 2 Ac 1 SA -

UIM) R RR-1 EP-R D-5 C IJ-R 0811 2 AC 1 SA -

EIM) R RR-1 EP-R H-7 C IJ-R NES e244

{'s

() Nj -

SYSTEM: Ir m e E I , '20 )

VALVE TEST TABLE DWG. NO. 38E & 38D DOCUMENT NO. 80A2903 Rev 2 PACE III~I9-3 OF III~I9-5 STRCXE C.S. C.S.

CLASS SIZE DIRECT, CHECK JUST. OR VALVE NO. AND VALVE (lN) ACTU. NORM TEST DWG. CAI AND VALVE OR ALI REMARKS REV AND TYPE POSII REO. TIME TEST RELIEF TEST M*

COOR. TYPE (SEC.) DIRECT. REO.NO. PERF.

0821 2 AC 1 SA -

ET-Q R RR-1 LT-R C-7 C IJ-R 0603 2 AC l\ SA -

LT-Q R RR-1 LT-R located on Dwg. No. FM-38D.

E-6 C IJ-R 0601 2 A lb M If PV E-6 GT located on Dwg. No. IN-38D.

IJ-R FEN-105A 2 B 1 FO O LT-Q C F-5 GL SP-Q 14 FtN-105B 2 B 1 FD O LT-Q C E-5 GL ST-Q 14 FtN-ll3A 2 B 1 FO O LT-Q C C-5 CL ST-Q 13 FtN-ll 3B 2 B 1 FD 0 LT-Q C 11- 5 CL ST-Q 13 NE S m244

N

] -

~N

\ V k_/

SWEM. INSIMM2tr NA> SCINIC AIR (P-50) valve TEST TABLE DWG. NO. IN-38E DOCUMENT NO. 80A2903 Fiev 2 PAGE III~I9-4 OF III'I9'b STROKE C.6. C.S.

CLASS SIZE AND DIRECT. CHECK JUST OR VRVE NO. VALVE (IN.) ACTti NORM TEST AND VALVE DwG. CAI AND OR ALT. REMARKS RW TYPE POSII REQ. TIME TEST COOR. TYPE RELIEF TEST '

(SEC.) DIRECT REO. NO. PERF.

0702B 2 C 1h SA -

LT4 R D-5 C 0702A 2 C lh SA -

LT-Q R si-5 C HN-Il4A 2 B lh FD C LT-Q O C-4 CL STS I3 MN-Il4B C B 1 FD C LT-O O

!!-4 CL STT ]3 SOV-028 2 A 3/4 EN O LT-Q c Systen C-51.

F-3 B ST-Q 5 FS4 IJ-R 0867 2 C 3/4 SA -

LT-Q R RR-1 LT-R Systern C-51.

D-3 C' IJ-R rds n244

03 h2 ;

, DOCUMENT NO.

DAGE III-19-5 OF III-19-5 NUCLEAR ENERGY SERVICES, INC. )

[

V) REUEF REQUEST RR 1 System: Instrument and Service Air Wh: 0695A,B : 0603 : 0811 : 0821 : IC51-0867 Category: AC Class: 2 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).

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

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

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

FORM e NES-24612/82

Document No. 80A2903 Rsv. 3 d

.-O am PtNP AND VALVE INSERVICE 'IESTING PROGRAM PIAN MR SHOREHAM NUCIEAR POWER PIANT LEIT NO. 1 SECTICN III ATTACINENT 20 EOR O MJEL OIL TRANSFER (R-43)

DM3. NO. EM-44A O

III 1 wuctean awency senwces me.

m s, p.

(a) (a)

SYSTEM: OE MM (F43) WLVE TEST 1ABLE DWG. NO.

I"-44A DOCUMENT NO. 80A2903 Prw 2 PAGE TTT-20-2 or TTT-20-4 STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUSI OR MLVE NO. AND VALVE (K) ACTti NORM TEST Ano VALVE OR ALT. REMARKS REV .

DWG. CAI AND TYPE POSII REQ TEST NO.

TIME REUEF TEST COOR. WPE (SEC.) DIRECI REO. NO. PERF.

0200A 3 C 2 SA -

EUM) F C-8 C 0201A 3 C 2 SA -

EIM) F C-8 C 0200C 3 C 2 SA -

EIM) F C-6 C 0201C 3 C 2 SA -

EIM) F C-6 C 0200D 3 C 2 SA -

EIM) F C-5 C 0201B 3 C 2 SA -

EIM) F C-5 C IN-025A 3 C 3/4 SA -

SR-P C-8 R NES s244

i 4 V V V g g. IUEL OIL TIWNER (R-43) yMME TEST TABLE IM~44A 80A2903 Rev 2 Dm m NENT NO. PAGE III-20-3 y 111-20-4 STROKE C.S. C.S.

CLASS SIZE VALVE NO. AND VM.YE (IK) ACTu NORM TEST DIRECT. CHECK m OR AND VALVE OR ALI REMARKS REV DWQ. CAI AND TYPE POSII REQ. TEST NO.

COOR.

TM4E RN TEST TYPE (SEC.) DIRECI REO.NO. PEAR RV-025B 3 C 3/4 SA -

SR-P C-5 R W-025C 3 C 3/4 SA -

SR-P C-6 R W-026A 3 C 3/4 SA -

SR-P C-8 R RV-026B 3 C 3/4 SA -

SR-P C-5 R RV-026C 3 C 3/4 SA -

SR-P C-6 R RV-099A 3 C 3/4 SA -

SR-P

, E-8 R RV-099B 3 C 3/4 SA -

SR-P E-5 R l

NES 8244

\

V .

> EO RN rN

( 4 0

2 1

1 1

p o

S K

R E 4 A

- M K 0 E A

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.n S.OmSR C EE TP O

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2 S.moNE C

R v K I e C TC f

E SE 3 HMTI ER 0

C D 9

m\ 2 A E T. )

KC e[C 0

8 OE D C E R4NA T

SD NmS(

O N

T P

N E Sa T

E E R TR S M M T.

RS I

OO -

NP 1 E 1

A

- TP CY S AT E)D 4

/R ZKNM I

S (IA 3 T.

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)

3 4

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SDG.R O 7 ANW LA DO 3 -

E C C m

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O A 4

4 .

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- N C E 9 9

V l 0 A

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V W-I O 4 M N 4 E 2 8

T S S

Y M E N

S D

Docum:nt No. 80A2903 Rcy. 3 i

6 PGP AND VALVE INSERVICE 'IESTDG PROGRAM PIAN FOR SHOREHAM NUCLEAP PONER PIANT UNIT NO. 1 SECPION III ATTACHENT 21 VALVE TEST TABIES AND FRr.TRR REQUESTS o -

DTFRRr GENERAIOR AIR STARP (R-43)

DWG. NO. EM-44B J

.+

O III-21-1 uucteam n=acy senvces.nc

p r\ p v V V SYSTEM: DIESIL CE25:PA10R AIR START (R-43)

VALVE TEST TABLE EM-44B DWG. NO. N ENT M 80A2903 Rev 2 III-21-2 111-21-4 PAGE op STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUSI OR VALVE NO. AND VALVE (M) ACTu NORM TEST ANO VALVE On Att REMARKS REV DWG. CAI AND TYPE POSIT. REO. TEST TIME RELIEF TEST '

COOR. TYPE (SEC.) DIRECT REO.NO. PERF.

0209A 3 C 4 SA -

ET-Q R F-7 C 0208A 3 C 4 SA -

LT-Q R D-7 C 0209C 3 C 4 SA -

LT-Q R F-4 C 020 tlc 3 C ( SA -

LT-Q R D-4 C 02098 3 C 4 SA -

LT-Q R F-2 C 0208B 3 C 4 SA -

LT-Q R D-2 C '

SV-034A 3 C 1 SA -

SR-P C-6 R NE $ 444

s s

s C U ggg. DIESEL GE2ERNIOR AIR STARF (R-43)

M TEST TAM N NO. IN-440 DOCUMENT NO. 80A2903 Rev 2 PAGE III-21-3 op III-21-4 STROKE C.S. C.S.

CLASS SIZE DIRECT. CHECK JUST. OR VALVE NO. AND VALVE (IK) ACTti NORM TEST WLVE REV AND OR ALI REMAAKS DWG. CAI AND TYPE POSII REO. TEST NO.

COOR TMAE RN TEST TYPE (SEC.) DIRECI REO. NO. PERF.

SV-035A 3 C 1 SA -

SR-P E-6 R SV-036A 3 C 1 SA -

SR-P E-6 R SV-037A 3 C 1 SA -

SR-P G-6 R SV-034C 3 C 1 SA -

SR-P C-4 R SV-035C 3 C 1 SA -

SR-P E-4 R SV-036C 3 C 1 SA -

SR-P E-4 R SV-037C 3 C 1 SA -

SIFP G-4 R NES 5244 e

O O (O3

~

(J 1 g DIESEL G2 ERA 10R AIR STAIC (R-43) VAtVE TEST TABLE gg EM-44B NENT NO. 80A2903 lbv 2 RAGE III-21-4 op 111-21-4 STROKE CS. C.S.

CLASS SIZE DIRECT. CHECK M OR VALVE NO. AND VALVE (N) ACTl1 NORM TEST AND VAtyE OR ALI REMARKS REV DWG. CAI AND TYPE POSII REO. TIME TEST RELIEF TEST COOR. TYPF-(SEC) DIRECI REO.NO. PERE SV-034B 3 C 1 SA -

SR-P C-1 R SV-035B 3 C 1 SA -

SR-P E-1 R SV-036B 3 C 1 SA -

SR-P E-1 R SV-0378 3 C 1 SA -

SR-P G-1 R

Documtnt No. 80A2903 Rsv. 3 -

b

-O PLNP AND VALVE INSERVICE TESTING PROGRAM PIRT FOR

' SHORE 2]AM NUCTAR POWER PIANT UNIT NO. 1 '

SECTIOT III ATTACHMENT 22 O ,

VALVE 'IEST TABLES AND IELTEP REQUESTS FOR DRYWELL FIDOR SEAL PRESSURE MCNITOREG (T-23)

DG. NO. EM-55A O

III-22-1 wuctaan awmov senwcas.mc.

O t v V g DRWELL FIDOR SEAL PRESSUEE MITI1TRItG (T-23) M TEST TAM gg IM-55A 80A2903 Ibv 2 III-22-2 III-22-2 DOCUMENT NO. PAGE OF STROKE C.S. C.S.

CLASS SEE DIRECT. CHECK WST. OR VALVE NO. AND VALVE (NL) ACTl1 NORM TEST AND M REMARKS REV OR ALT.

DWG. CAI AND TYPE POSII REQ. TIME TEST U REUEF TEST M WPE (SEC.) DIRECT REQ.NO. PERF.

MOLf-031A 2 A 70 0 ET-Q C C-2 GL ST-Q 10 IJ-R M N-031B 2 A 70 0 ET-Q C C-6 GL ST-Q 10 IJ-R RV-021A 2 C 3/4 SA -

SR-P F-3 R RV-021B 2 C 3/4 SA -

SR-P F-6 R NES s244

Docum:nt No. 80A2903 Ray. 3 g

(r G) .

PtNP AND VALVE. INSERVICE 'IESTING PIOGRAM PIM FOR SHOREHAM NtXIEAR PWER PIANT UNIT NO. 1 SECTI N III ATIAONENr 23 FOR REACIOR BIDG. NORMAL VENT. (T-46)

DC. NO. FB-23A s

b I

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s v) r g g. REJCIOR BIIG. NOINAL VENP (T-46) W1VE TEST M8LE g FB-23A NNT NO. 80A2003 Ihrv gg III-23-3 op III-23-4 ,

STROKE C.S. CS.

CLASS M 04 RECT CHECK JUST. OR WMVE NO. AND WLVE (M) ACT11 NORM TEST W.1FE REV AND OR ALI REMARKS DWG. CAI AND TYPE POSII REO. m TEST NO.

REUEF TEST COOR. TYPE (SEC.) DIRECI REQ.NO. PERF.

M -039D 2 A IS AD C W 11 - 8 B IJ-R ADV-078A 2 G-8 A 6 CP AO C ET-Q ST-Q C Stroke time not available. Will be aAhi when determined.

d FS4 IJ-R ADV-078B 2 F-8 A 6 GT AO C ET-Q ST-Q C. Stroke time not available. Will be aAhi whdn available.

d FS-Q IJ-R ADV-079A 2 F-8 A 6 GP AD C ET-Q ST4 C Stroke time not available. Will be adhi when determined.

d FS-Q IJ-R ADV-079B 2 A 6 AO C ET-Q C Stroke tiFE not available. Will be F-8 GT ST-Q aA hi whei, determined.

M IJ-R ADV-035A -

Ie4 B 72 B

AO O ET-Q ST-Q C Stroke time tiot available. Will be added when determined.

d FS-Q ADV-035B -

Ie4 B 72 B

AO O UIM)

ST4 C Stroke time not available. Will be eAhi when determinal.

d FS-Q NES 5244 i

O O O ggg. FOCIOR BIDG. NOINAL VENr. (T-46) M TEST M g FB-23A 03 h3 III-23~4 DOCUMENT NO. RnGE OF III-23-4 STPOKE C.S. C.S.

C1m M DIRECT. CHECK JUST. OR VALVE NO. AND M (M) ACT11 NORM TEST AND WLVE REV OR A11 REMARKS DWG. CAT. AND TYPE POSE REO. TIME 1EST "'

RELIEF TEST COOR. TYPE (SEC.) D*ECE REO.NO. PERF.

NN-037A 72 B-5 B

B AD O EM)

SM)

C Stroke tirre not available. Will be Mba when determined.

d FS-Q N N-037B B 72 AO ET4 B-5 B O

STS C Stroke tine not available, will be adied when determined.

d FS-O l

1 NES 8244 6

Document No. 80A2903 Rev. 3 g O

~

PGe AND VALVE INSERVICE TESTING PROGRAM PUR EVR SHOREHAM NUCLEAR PCSER PIANT UNIT NO. 1 SB0rICN III ATDCHMENT 24 ,

i N .E E N l FOR PRIMARY CCNDGINENT A'DOSPHERIC CCNTROL (T-48)

I DWG. No. EM-5'2A : EM-84A I

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e PRIMAI& CEtttADMNr AMOSPtERIC CCNTIOL (T-48) WLVE TEST TA8LE m-52A gNWG. NO. DOCUMENTNO. 80A2903 nev 1 PAGE TTT-74-2 op 7TT-74-19 b STROKE C.S. C.S.

N SIZE DIRECT CHECK JuSt OR MLVE NO. AND M (W) ACTu NORM TEST AND MIVE REV DWG. CAI AND OR ALI REMARKS COOR. TYPE TYPE posit REO. m TEST RE'1 TEST - NO.

(SEC.) DIRECI REO.NO. PERF.

SOV-126A 2 A 3/4 Di C E'IM) C F-3 Cr ST-Q 5 FS-C U-R SOV-126B 2 A '3/4 Di C ET-O C F-3 Cr ST4 5 FS-C U-R SOV-127A 2 A 3/4 D4 C ET-O C C-7 Gr ST-O 5 M-O U-R S01-127B 2 A 3/4 Dt C ET-O C C-7 GT 57 0 5 FS-O U-R

.i SOV-128A 2 A 3/4 Di C ET-O C E-3 Gr ST-O 5 EU-Q U-R SOV-128B 2 A 3/4 Di C ET-O C E-3 Cr ST-O 5 FS1 U-R SOV-129A 2 A 3/4 Di C ET-O C 11 - 7 Gr ST-O 5 W

U-R NES e244 i

d V .

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EM-52A nas 80a2903 Rev 3

-EE.T-E d

gg em g III-24-4 OF III-24-12 mOE Cx C N SIZE D E CT. CMFCK JugI OR wuyE NO. AND WdWE SK) ACTu NORM TEAT A84u M CfE OR ALI REMARKS REV DWG. CAI AND TYPE PO8it Rett TIME TF.ST RE W TEST NO.

COOR. M (SEC.} DIRECI BEO. NO. PERF.

Mw-033A 2 A 6 M0 C ET4 C F-6 Gr ST{ 36 IJ-R MOV-033B 2 A 6 M) C D.W C E-6 GP ST@ 36 IJ-R MOV-034A 2 A 6 M0 C E'D-O C G-8 GT ST-O 36 IJ-R MOV-034B 2 A 6 MD C ETM) C E-8 Gr SM 35 IJ-R i

MOV-035A 2 A 6 MD C El% C G-5 GT ST@ 24 IJ R MOV-0358 2 A 6 M) C Er-Q C F-5 GT ST-O 24 IJ-R I

MOV-0371. 2 A 6 M0 C EF-O C G-6 Gr Sr-O 36 IJ-R NES 5244 i

C D g, PRIMARY C[WPADMNF ADOSPtERIC CCNIl0L (T-48) M TEST M gg EN-52A NNT E 80A2903 Rev 3 m III-24-5 op III 12 d STROME C.S. C.S.

. CLASS SIZE DIRECT. CHECK JUSI OR WuYE NO. AND WLVE (IK) ACTu NORM TEST WLWE e REV AND OR ALI DWG. CAI, AND TYPE POSII REO. TMAE TEST RELEF TEST NO.

' N M CIRECT REQ. WO.

(SEC.) PERF.

ftN-037B 2 A 6 M0 C ET-Q C E-6 Gr SM 36 IJ-R ww-038A 2 A 6 m C EM C G-6 Gr ST-Q 24 IJ-R M N-038B 2 A 6 20 C EP-Q C D-6 Gr ST-c 24 IJ-R M N-040A 2 A 6 MO C EIM,) C l . G-8 CF SM 36 IJ-R M N-040B 2 A 6 to C EF-Q C D-8 Gr STS 36 IJ-R NN-001A 2 A 4 AO C ET-Q C Systan T-24.

F-4 GF SM FS4 Stzuke time not available. Will be a&kd when determined.

d IJ-R NN-001D 2 A 4 AD C EP-Q C Systan T-24.

F-4 CF ST-Q PS4 Stroke time not available. Will be d

IJ-R NES s244 i

( L d g IN-52A & FM-84A e yo, 8CA2903 fiev .3 m III-24-6 op III-24-12_ d SIRO (E C.S. C.S.

CLASS SIZE DIRECT. CHECK JUSI OR MMME prg. AND WME (M) ACTl1 NORM TEST AND ELVE OR ALI REMARKS M DwQ. CAI AND TYPE POSII REQ- TIME TEST REUEF TEST NO.

COM TYPE (SEC.) DIRECI REO. NO. PERF.

0016A 2 Ac 3/4 SA -

$7-Q R RR-1 ET-R H-5 C IJ-R 0016D 2 Ac 3/4 SA -

ET-Q R RR-1 ET-R C-5 C IJ-R ADV-004A 2 A- 4 AO C' ET-Q C Systan T-24. Dwg. EM-84A.

o-8 GL ST-Q Fs-Q stroke time not available. will be added h detennined.

d LJ-R ADV-0048 2 A 4 AO C ET-Q C Systan T-24. Dwg. IN-84A.

D-8 GL ST-Q Fso stroke tinu not available, will be added m ee mined.

d IJ-R 60V-04 3A 2 B 4 PO C ET4 O G-5 Cr ST-Q 24 PO/-043B 2 B 4 MO C EP-Q O D-5 GT ST-Q 24 70/-041 2 B 4 PO C EIM.) O D-2 Cr ST-Q 24 NES s244 6

O O O l

gg. PRIMARY 00frADMNr A1NOSPIERIC (INIHL (548) WuME TEST TABLE H4-52A gg DOCUMEf(T m 60A290i rev 3 g III-24-7 OF III 12 d STRCXE C.S. C.S.

r1aan SIZE DIRECT CHECK JUSE OR wgVE NO. AND M (IK) ACTL1 NORM TEST AND WuME DWG. CAI On ALI REMARKS AND TYPE posit REO. TWE TFET REUEF TEST '

COOIL TYPE (SEC.) DIPECT r.CO. NO PERF.

M N-042 2 B 4 m C ET-Q O C-3 or ST-Q 24 0004A 2 C 6 SA FFQ ?

PR-2 Test with hydrogen recxmbiner H-5 C operability test, every 6 months.

0004B 2 C 6 SA EFQ P PR-2 Test with hydrogen recxmbiner B-5 C cperability test, every 6 nonths.

KN-044A 2 B 4 70 C CIM) O G-7 CP SBC 24 i

MN-044B 2 B 4 m C EFQ O N CP SBC 24 MW-016A 2 B 1 PC C EFQ 1-4 O R9-3 located on DWg. Il600.026.87-lE.

CL SM 30 PR-1 !!2 reambiner water spray valve.

Tested with hydrogen reembiner gerability test, every 6 months.

Mov-016B 2 B 1 MD C EP-Q O RR-3 Iocated on Dwg. Il600.026.87-1E.

B-4 GL SFO 30 RR 3 II, reambiner water spray valve.

T5sted with hydrogen reembiner operability test, every 6 months.

NES eM4 4

O O O S _ _ _ _ _ _ _ _ .> H P_ E - - -E gg EM 52A mg 80A2903 Rev 3 PAGE III-24-8 op III 12 h CLASS smoke C1 C.S.

SIZE DIRECT, CHECK AND JUSL OR WuVE NO. MLVE OK) ACTth NORM TEST MLVE AND OR AlI REMARKS REV DWG. CAI AND TYPE, POSII REG-COOR.

M TEST RELFJ TEST NO.

TYPE (SEC.) DCIECL MQ. NO. PERF.

SOV-136A 2 G-4 B Di C W C RR-4 k

GL ST-O 5 RR-4 PS-O PR-4 SOV-136B 2 B Dt O EIM) C D-4 cL ST-o 5 PR-4 RR-4 h

FS-O RR-4 SOV-137A 2 H-4 B Di C W C RR-4 h

CL S1M) 5 r&4 FS-Q RR-4 SOV-137B 2 B Di C C D-4 GL ET-O ST-Q 5 RR-4 p3-4 d FS-O RR-4 l

NES 8244 i

DOCUMENT NO. 80A2903 Rev 3 NUCLEAR ENERGY SERVICES, INC. PAGE III-24-9 OF III-24-12 ._d I

REUEF REQUEST' RR 1 System: Primary Containment Atmospheric Control h: 0016A,B Category: AC Class: 2 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).

AEME Section XI Quarterly Test Requirunects: verify reverse flow closure.

l I Basis for Heilef: The only method available to verify reverse flow closure is by valve leak testing during Appendix J, "ype C testing at refueling.

Alternate Testing: Reverse flow c1soure will be verified during Appendix J, Type C testing at refueling.

l I FORM # NES-24612/32

DOCUMENT NO. 80A2903 Rev 3 NUCLEAR ENERGY SERVICES, INC. PAGE TTT-24-10 __OF TTT--24-19d O REUEF REQUEST' RR - 2 System:

~

Primary Containment Atmospheric Control yaw. 0004A,B Category: C Class: 2 Function: Hydrogen recombiner cutlet check valves.

ASME Section XI QuarterlyTest Requiwneins: Exercise e Basis for Relief: The only way to verify full flow opening is during the hydrogen l recordainer functional test which is performed by Technical Specification Surveillance Requirements 4.6.6.1 which test the I hydrogen re' combiners for operability at least once every six '

months.

l Alternate Testing: verify operability during hydrogen recombiner functional testing at least once every six months.

l l l l

. es.u. im2

e DOCUMENT NO. 80A2903 Rev 3 NUCLEAR ENERGY SERVICES. INC. PAGE III-24-11 OF III-24-12 d O RELIEF REQUEST' RR - 3 System: Primary Containment Atmospheric Control Wive: MOV-016A,B Category: B Class: 2 Function: Hydrogen recombiner water spray valves.

i ASME Section XI Quarterly Test Requirements: Exercise and time.

l ,

Basis for Relief: These valves are slaved to the hydrogen recembiner ccntrols and open automatically on initiation of the hydrogen recombiner. They do not have separate test provisions and cannot be operated independent'of recombiner initiation. These val'ves can only be tested during the hydrogen recombiner functional test which is performed by Technical Specification Surveillance Requirement-4.6.6.1 which is performed at least once every six months.

I l

Alternate Testing: Exercise and time during hydrogen recombiner functional testing at least once every six months.

l l l l

l FORM e NES-24611/82

F F ,

I g,

DOCUMENT NO. 8W903 .Rev 3 my NUCLEAR ENERGY SERVICES, INC. PMIE III-24-12 OF III-24-12 O REUEF REQUEST' RR -

System: Prialary Containment Atmospheric Control h: SOV-136A,B : SOV-137A,B Category: B Class: 2 Function: H;/02 analyrer isolation valves.

ASi4E Section XI Quarterly Test Dequiremat&: Exerci se, timo ar.d fail.

G Basis for Relief: Valve design preclude verification of valve position. Valve position indication for these valves is by indicator lights which only indicate whether or not the solenoids are energized. The valve design does not provide any direct means to observe valve position. These valves are isolation valves in the lines to the H 2 /02 analyzers and cannot be position verified by other methods, such as, system flow or pressure.

Alternate Testing: Design changes are presently under consideration to modify the valves to provide a means of valve position indication. An appropriate modification (s) will be selected and completed at the first refueling outage. This modification will be such that ,

valve exercising, timing and fail safe testing will be possible. l In the interim valve exercising will be perofmred quarterly using the present indicators.

l l l

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_ _ _

ML20073K145

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