ML20128J981
| ML20128J981 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 04/23/1985 |
| From: | NUCLEAR ENERGY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20128J920 | List: |
| References | |
| 80A2903, NUDOCS 8505310059 | |
| Download: ML20128J981 (222) | |
Text
mir NUCLEAR ENERGY SERVICES. INC. DOCUMENT NO. 80A2903 REifl 4' E = ' " ' * -~ EE# PAGE i __o OF' iv CONTROLLED .
$ DOCUMENT CONTROLLED COPY MAY l 31985 E I SHOREHAM NUCLEAR POWER STATION PullP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR LONG ISLAND LIGHTING COMPANY SHOREHAM NUCLEAR P0' DER PLAllT UNIT 1 ProjeCl AppilCatlOn Copy No Assigned To 5536 _ . .
APPROVALS --
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TITLE / DEPT. - SIGN ATURE - D ATE
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j REV NO PREPARED BY Program Engr. Project !QualityAssurance' --- J Deot. Manager Manacer $4anacer 0 i 1
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- OATE gg DESCRIPTION APPROVAL 1 Mar,17,1982 See CRA 2422 , Incoporate s Customer -
p Comments and corrects typn'a. -l_ .
2 2/25/83 All c;n n cRA #3179. Total revision incorocrat es 28 customer and NRC comment.
3 4/04/83 See CRA 3275 Incorporates Customer A, comments, redefines " passive" valves, removes stroke times for Air Operated valves, adds Document numbers to title paces for attachments 2 through 24 of Section III, revised test requirements for system "Keeo Fill" Valves (Ell-0022A,B:
Ell-0023: Ell-0028: E21-0018A,B: 41-0019),
p Revised test requirements for E21-AOV-
,'j 081A,B. added new relief recuest for valves T48-SOV-136A,B: T48-SOV-137A,B, renumbered Daces to reflect revised test requirements add a ceneral relief recuest to perform omn vibration velocity measurements, and enrrected 1gn n. e 4 12/13/84 See CRA 4876. Incorporated custcraer Q jggj ,
comments, redefined applicable Code and addenda, added pump vibration test criteria, delayed testing of FPCCU pumps, added twc relief requests for pump testing, corrected valve. table typing errors, revised valve stroke times, removed or revised valve
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. table remarks as necessary, corrected valve tes't requirements, added relief re-quest to Standby Liquid Control, removed FORM # NES 206 2/80
80A2903 may g DOCUMENT NO. Rev. 4 NUCLEAR ENERGY SERV CES, INC. PAGE iii OF IV g
'qj E DESCRIPTION
{E'O DATE APPROVAL 4 12 /13/84 testing f rom valves made passive by being continued electrically disconnected, corrected valve test stroke directions, removed cold shut-down justificaticn frcm RHR, added valve to relief request for HPCI and RCIC, re-vised relief request for HPCI and RCIC, l added relief request to Service Water, removed cold shutdown justification from RBCIEW, removed valves from Instrument and Service Air, added valves to Fuel Oil Transfer, removed relief request frcm Primary Containment Atmosphere Control.
(
4 4/19/85 Additional revision from customer review 9, M, of preliminary revision. Revised Intro-duction, Pump Relief Request for P-201A, B.C; P-202A,B,C revised to incorporate plant comments, corrected typing errors, corrected valve stroke directions and times, added ET-R to pages III-17-8 and III-17-9, added system T-47 to pages III-18-8 and III-18-9, revised Program Plan Period section, added Relief Request (RR-1) to pages 111-15-2 and III-15-3, added LT test to page III-10, added dwg.FM-29C to page III-13, added new tables and Relief
'"] Request (RR-2) to attachment III-1.
FT.RM # NES 206 2/80 ,
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! DOCUMENT.NO. 80A2903 REV 4
' PAGE .. OF iv iv N
TABLE OF CONTENTS s
Pace Section I - Overview ~ I-l Section II - Pump IST Program Plan II-l
'Section III - Valve IST Program Plan. III-l s
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Document No. 80A2903 Rev. 2 a
PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHOREHAM NUCLEAR POWER STATION UNIT 1 SECTION 1 OVERVIEW h.
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I-1 NUCLEAR ENERGY SERWCES WC.
A Document No. 80A29'CG Rzv. '4
- 1. Introduction This document presents the Program Plan for Inservice Testing (IST) programs for the :2horeham Nuclear Power Station, Unit 1,. 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 A Edition through the' Winter-1981 Addenda in accordance with'10CFR50.55a. Q4 b .
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- 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.
Pequests Pursuant to 10CFR50.55a(g)" and the November 1981 Draft Regulatory Guide
" Identification of Valves for Inclusion in Inservice Testing Programs."' These three documents provide the basis for selection of components, test requirements, relief requests and format.
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Document No. 80A2903 Rev. 4
- 3. IST Program Plan Period 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 the date of issuance of the operating licensa. ; 4 This 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.
v NUCLEAR ENERGY SEfMCES INc
Document No. 80A2903 Rev. 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, out whose functions fall outside the three crite.-ia
, 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 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 w ;, operation and full-stroke exercising at cold shutdown.
- :r m. th Since the Code accepts cold shutdown testing, this program does not request
- rc relief for those valves for which testing is delayed until cold shutdown. The
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Program does provide a justification for delay of testing until cold shutdown. These
- s justifications are prepared in a format similar to relief requests, and are included
_v. following the valve Test Tables.
. .a c :s Where it has been determined that testing is not practical during plant go: , or operation, or at cold shutdown, a specific relief request has been prepared. Each 2- ~.1: specific relief request provides justification for not performing the Code specified oru tests, and provides appropriate alternative testing.
I h In addition to specific relief requests, general relief requests which address
- 1. . c d, specific Code requirements found to be impractical for this site have been prepared.
y ,( Because of the general nature of those relief requests, and the number of components cat involved, they are presented in a separate section, and are not repeated in the 3ys individual systeam sections.
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NUCLEAR ENERGY SERVICES. INC/ "
Document No. 80A2903 ~ Rev. 2 i
5.' organization The Pump and Valve-InserM ce Testing 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 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 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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- p. 6. Definitions w'
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, but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after 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-shutdown. The 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> interval will not hold for planned cold shutdown.
Refueling: Testing delayed until, refueling will be performed during the normal scheduled refueling shutdown
-before returning to power operation.
/'5 Period: Category C safety and relief valves (IWV-3511) and k 'g Category 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 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 valve which is required to chance position to l} g 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.
O I-7 NUCLEAR ENERGY SERVICES. Dec.
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Document No. 80A2903- Rev. 2 4
[' .7. General Relief Requests
, J 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 ~
m number of components this section requests . general relief as presented below.
General Relief Request: G-1' Component: -Rapid actuating power operated. valves with stroke 4
times of 5. seconds or less.
t Category: A,B i- Code Requirements: IWV-3417' requires corrective action-if the measured 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 when the valves are
!- functioning normally. These valves are generally small_ air and solenoid operated valves which because
~ of their size and actuator types stroke very quickly.
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ooer tine wi terv en **1 tree er w 1 e indic te -
that they generally either operate inmediately or fail to operate--in'a reasonable length of-time.-
The intent of the referenced Code sections is"to
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track valve stroke time as a means of detecting valve degredation. This type of valve does not lend itself to this tracking technique. .
1 Alternate Testirm: 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- ,
i- considered as acceptable and no corrective action
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will be required. If the valve exceed five seconds 4
it will be: considered inoperable and appropriate.
corrective action will be taken.
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Docum:nt No 80A2903 Rev. 2 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 tl.at valve leakage is limited to an acceptable value. For containment isolation valves an acceptable total allowed leakage rate has been established in compliance with the requirements of 10CFR50 Appendix J. Performance of Appendix J, Type C Local Leak 7 ate testing fulfills the intent of Section XI Category A valve 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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s Dodum:nt No. 80A2903 Rdy. 2
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PN General. Relief Request: .G-3 1.L K ]:. -Excess flow check valves Component:
Category: AC Code Requirement: IW-3521 requires ' operability test of che' ck
. valves and IW-3522 describes. .the required
.. testing procedure.
Basis for Relief: ;The excess-flow checks are devices which are designed to activate and limit flow to a specified value. The test' requirements for check valves-in the Code are' intended for simple. check valve testing. Quarterly testing
'is not practical since these are instrument 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 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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'- , - Documsnt No. 80A2903. Rsv. 2 y
General' Relief Request: .G-4 3 Component:
Pressureiisolation 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
--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 affeet-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.
J^ Alternate Testing: The Technical Spe_cification defined surveillance-5 .
testing will be performed, but no comparison of test'results to previous-results will'be performed.
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7 . General-Relief Request: G Component: All safety-related pumps.
Test Requirements: Vibration amplitude measurement uc.ing displacement (IWP-4500) and allowable ranges of test quantities (Table IWP-3100-2).
Basis for Relief: A survey of plants with existing pump vibration test 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 vibraticn displace-ment. Specific values for alert and required action setpoints have been developed for all safety-related pumps and are provided below.
Alternate - Testing: Pump vibration testing will be performed for both preservice and inservice testing using vibraticn velocity measurements in lieu of displacement measurements. Limits are as. specified below.
a n e Points Un/sec.)
./ Pump I.D.
Alert Required Action-IC41*P-024A,B O.30- O.40 IEll*P-014A ,B ,C ,D O.33 0.40 IE21*P-Ol3A,B O.33 0.40 IE41*P-Ol6 (Main) 0.35 0.60
, (Booster) 0.35 0.53 -
IE51*P-015 0.20 0.30 IGll*P-270C O.20 0.30 IG41*P-023A,B O. 15 0.23 IM50*P-137A,B _O.20 0.30 IM50*P-138A,B O.20 0.30 IM50*P-139A,B O.20 0.30 IM50*P-140A,B O.20 0.30 IP41*P-OO3A,B,C,D O.30 0.40 IP42*P-OOSA,B,C O.20 0.30 IR43*P-2OlA,B,C O.20 0.30 IR43*P-202A,B,C O.20 0.30 I
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Document No. 80A2903 Rev. 2 e
- .v PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR' SHOREHAM NUCLEAR POWER STATION UNIT 1 SECTION II PUMP IST PROGRAM PLAN i
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Document No. 80A2903 Rev. 4 4
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- 1. Introduction This section presents the Program Plan for Inservice Testing of pumps for the Shoreham Nuclear Power Station, Unit 1 in compliance with the requirements of 4 .
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 in accordance with 10CFR50.55a.
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.DoCumtnt No. 80A2903 Rev. 2
- 2. Pump IST Program Plan Concept p .
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The. Pump Program Plan specifiesSection XI testing requirements for all ASME Class 1, 2,,and 3 pumps provided with an emergency power source and which are required for safety related system operation. .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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Docum:nt No. 80A2903 Rev. 2
- 3. Pump List 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 RHR FM-20B 15 2 HPCI FM-25B 12 1 RCIC FM-22B 11 1 CORE SPRAY FM-23A 15 2 SBLC FM-21A 14 2 SERVICE WATER FM-47A 12 4 RBCIEW FM-15A 13 3 RBSVS & CRAC CHILLED WATER FB-43A 11 2 s RBSVS & CRAC CHILLED WATER FB-43B 11 2 RBSVS & CRAC CONDENSING 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 NUCLEAR ENERGY $(RVICES, NC.
Document No. 80A2903 Rev. 4 0 4. Pump Table Nomenclature The~following abbreviations have been used in the pump test table.
N = Rotative Speed Pi = Inlet Pressure AP ' = Differential Pressure Across Pump 9f = Flow Rate V = Vibration Amplitude Tb = Bearing Temperature Q = Quarterly X = Measurement / Observation Per IWP L = Lubricant Level or Pressure R = Relief Request O
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Documznt No. 80A2903 Rev.4
.. 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 amplification, deviations and exceptions to the Code requirements and are further discussed below:
(1) Pump with constant speed drive, speed is not measured since test will 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 Reference Data sets and used as information during subsequent test analysis.
(3)' Bearing temperature measurement not required (IWP-4310) since bearings are l 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.
(7) Pump inlet pressure determined from head tank level.
b -(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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PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN l FOR 1
! SHOREHAM NUCLEAR POWER STATION i
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P-014C IM-20A P-8 2 O (1) X X X X ( 3) (6)
P-014D EN-20B E-8 2 O (1) X X X X ( 3) (6) 1001 P-016 EM-25B D-4 2 0 X X X X X R X FCIC P-015 IN-22B D-4 2 Q X X X X X R X 00RE SPRAY P-013A IN-23A B-8 2 O (1) X X X X (3) (6)
P-013B EM-23A 11- 8 2 Q (1) X X X X (3) (6)
STRJDDY LIQUID P-024A iM-21A 11- 5 2 O (1) X X X X (10) X P-024B EM-21A 11- 7 2 Q (1) X X X X (11) X NES s245
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PUMP UST MEASURED 5%RAMETERS REV SY3 TEM PUMP LD. DWG. NO. COORD. CLASS FR Q. N Pi AP Of V Tb L SEINICE Mu1R P-00 3A FN-47A G-7 3 O (1) (2) X X R (3) (6)
P-003B EN-47A 11- 7 3 0 (1) (2) X X R (3) (6)
P-00r EM-47A F-7 3 Q (1) (2) X X R ( 3) (6)
P-00 3D EM-47A J-7 3 0 (1) (2) X X R (3) (6)
RDCILM P-005A IN-15A E-2 3 Q (1) (7) X (5) X X (6)
P-005B FM-15A J-2 3 0 (1) (7) X (5) X X (6)
P-005C IN-15A 11- 2 3 0 (1) (7) X (5) X X (6)
E VS & CRtc P-137A FB-43A D-4 3 0 (1) X X X X X X Oil m .A m P-137B F11-4 3B D-4 3 0 (1) X X X X X X P-138A FB-43A D-6 3 Q (1) X X X X X X P-138B Ell-4 3I5 >6 3 0 (1) X X X X X X E VS & CRAC P-139A FB-43A D-3 3 Q (1) X X X X X X UNIE #N P-139B FB-d M D-3 (1) X X X X X X 3 Q P-140A FB-4 3A >5 3 Q (1) X X X X X X P-1408 FB-43B D-5 3 0 (1) X X X X X X IT*IU P-023A EN-19A E-7 3 Q R R R R R R R /2\
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- Document No. 80A2903 Rev. 2 i
Shoreham No,' 1
, Relief Request
- l. System: HPCI 1'1 Pump P-016 1
Class: 2
! Function: Emergency Core Cooling i
~
Test Requirments: Measure bearing temperature. ,
4 f Basis for Relief: The HPCI Pump is an integral unit itith the steam driven i turbine. Bearing temperature is a direct function of steam temperature. Therefore, measurement of bearing temperature would provide no meaningful information j about the bearing'.
!' Alternate Testing: - None.
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Document No 80A2903 R;v. 2 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 Relief: 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.
II-1-6 sucLE AR ENERGV SERWCES W(.
Document No. 80A2903 Rev. 2 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: Vibration measurements will be made on the lower (closest to pump) motor bearings.
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m II-1-7 wuctsan esency SEnytCES INC.
Documsnt No. 80A2903 R:v. 2 -
Shoreham No. 1 Relief Request i
System Suppression. Pool Leakage Return 1
Pump: P-270C Class: 3 Function: Return fluid to the' suppression pool resulting from pump seal leakage, instrument line leakage or valve packing failure.
Test Requirements: Measure pump inlet and differential pressures.
Basis for Relief: Pump is located above the sump pump fluid level and is.
i designed to be self primino (negative NPSH) pump capable of five foot of lift. There is no pressure tap installed to measure puL.p inlet 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. 80A2903 Rev. 2 4
Shoreham No. 1 Relief Request.
-System: Diesel Fuel Oil Transfer.
Pump: P-201A,B,C : P-202A,B,C Class: 3 4
Function: Transfer diesel fuel oil from the storage tank to the day tank.
Test Requirements: Measure pump inlet and differential pressures.
t Basis for Relieft- 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 j be used to evaluate pump performance.
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I Document No. 80A2903 Rev. 4 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: Per IWP-3500(b), when the measurement of bearing temperature is required, each pamp shall be run for a minimum of thirty (30) minutes until the bearing temperatures stabilize.
Basis for Relief: Diesel Fuel Oil Transfer pump running time is dictated by. interlock circuitry and administrative limits corresponding to allowable day tank levels.
The interlock circuits, which control automatic transfer o pump operation, limit the day tank levels from either;
-d- falling below + 27 inches or rising above + 38 inches (above tank bottom). The upper limit has a manual over-ride feature, however, operation of the pumps above the 38 inches limit is precluded by administrative controls g4 and local / remote alarms. The allowable limits correspond to 149 gallons day tank capacity. With an average transfer pump capacity of 12.3 gpm, the maximum allowable pump run time is an average of 12.1 minutes, far short of the required 30 minutes.
Alternate Testing: None. Bearing condition will be evaluated by analysis of vibration measurements (IWP-4500).
b-111-1-10 NUCLEAR ENERCY SERWCES WC.
r Docum"nt No. 80A2903 R v. 4 Shoreham No. 1 Relief Request System: Spent Fuel Pool Cooling Pump: P-023A,B Class: 3 Functicn : Remove decay heat from the Spent Fuel Storage Pool.
Test Requirement: Measure pump rotative speed, inlet pressure, differential pressure, flow rate, vibration, and lubricant level quarterly. Measure bearing tempera-ture yearly.
Basis for Relief: During the establishment of new qualified kilowatt load ratings for the TDI Emergency Diesel Generators, these pumps were eliminated f rom the load ratings of EDG-lOl & 102 respectively. The purpose for this change is to reduce the post-LOCA kilowatt loadings on the diesels in order to enhance their reliability.
The justification is that there will be no spent fuel storage pool heat load until the first refueling outage. Thus, these pumps will be maintained out of service until that time.
Alternate Testing: None. ASME XI testing of these pumps will not commence until the first refueling outage when there is spent fuel in the storage pool and the Colt Emergency Diesel Generators are placed into service.
t II-1-ll Nuctraa ens acy stavicES INC.
Document No. 80A2903 Rev. 2
- 1 i
O PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHOREHAM NUCLEAR POWER STATION UNIT 1 SECTION III VALVC IST PROGRAM PLAN o
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III-1 NUCLEAR ENERGY SERVICES. NGC.
Document No. 80A2903 R:v. 4
.O
- 1. Introduction This section presents the Program Plan for Inservice Testing of Valves for A the Shoreham Nuclear Power. Station, Unit _1, in compliance with the requirements of 10CFR50.55a. This Program Plan has been prepared to th*e requirements of the ASME l Q4 I ;
Boiler and Pressure Vessel Code,Section XI. Subsection IWV, 1980 Edition through the Winter 1981 Addenda in accordance with 10CFR50.55a.
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Docum:nt No. 30A2903 R v. 2
- 2. Concept 7
The Valve Test Program Plan was developed to verify the operability of safety 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 position 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 inclusion in the test program based on a review of all 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 normal operation. Those valves for which quarterly testing is determined to be inappropriate are analyzed further to determine if Code allowed cold shutdown testing is possible. If so, a justification for delay of test to cold shutdown is 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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III-3 wuCLEAR ENEAGY SERVICES. WC.
Docum:;nt No. 80A2903 Rev. 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 those which perform a system pressure relief function. Thermal relief valves, whose only function is to protect components or piping from thermal expansion are not considered to be safety related and are not addressed in the program. Where a relief valve performs both a system and a thermal relief function it has been included as testable. 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.
A 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 progrart.
Pressure and Flow Control Valves:
The reference Code excludes valves which perform pressure or flow control q functions. This program excludes them unless they also perform a system safety U
III-4 NUCLEAR ENERGY SERVICESL INC.
Docum:nt No. 80A2903 Rev. 4 related response function, such as, automatic closure on system initiation. The i7.
,) . 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. These valves may be included as passive valves, if appropriate.
Remote Power Operated Valves:
The program includes power operated valves activated by remote swit'ches 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 included in the program, only if they perform a safety related function. Valves which rx provide normal system operation control and whose position has no effect on safety
(_,)
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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 (4
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 valve's which are. required to cycle open and closed are tested to verify full opening with forward
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(/ flow and closure on loss of forward flow.
III-5 NUCLEAR ENERGY SERvM:ES.WC
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Documtnt No. 80A2903 Rev. 4 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 fbrward 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 exercisors will be tested as a simple check l g or by exercising using the manual exercising device. Check valve equipped with a power operator installed for the sole purpose of exercising the valve for operability will be tested as a simple check or by use of the power operator.
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 the operator. In addition to exercising, the operator will be timed and failed as (d'T appropriate.
Pump Discharge Check Valves:
. .As a minimum, pump discharge check valves will be forward flow exercised. In addition, reverse flow clos tre 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 .ancunt 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 ECC" system piping whose function is maintenance of system water inventory to preclude water hammer. Forward flow operability is verified by a system check of water inventory performed at least quarterly. . Reverse flow closure verification is performed only if failure of the valve to close could result in a significant reduction of ECCS system operation.
O III-6 wucLEAR ENERGY SERWCES.MC
Document No. 80A2903 Rev. 2 Check Valve Full / Partial Stroke:
In most cases full design flow through a check valve requires less than full mechanical valve movement. As used in this program, the term full stroke refers to the ability of the valve to pass design flow and not the full mechanical stroking.
Forward flow full stroke operability testing will be by any method tha' verifies the valve capable of passing design flow. Any test that verifies less then 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 Jocal 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 the 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 function between the Reactor Coolant System and a low pressure system are included in the Valve IST Program as Category A valves. These valves will be tested to the requirements specified in IWV-3420.
f- s Category A (Containment and Pressure Isolation Valve) Leak Testing:
Valves which perform both a containment isolat on 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 cold 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.
J
Document No. 80A2903 R;v. 2 Testable Check Valve E*> pass Pressure Equalization Valves:
s _ ,
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.
III-8 NUCLEAR ENERGY SERVICES INC.
Document No. 80A2903 Rev. 2
/~~N D 4. Valve Test Table Nomenclature The fellowing abbreviations have been used in the Valve Test Table.
Valve Type Actuator Type GT Gate BA Eall MO Motor GL Globe A Angle. SA Self C Check D Diaphragm AO Air SC Stop Check VR Vacuum Relief EM Electro-Mech.
R Relief M Manual E Explosive EYD Hydraulic B Butterfly E Explosive
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Normal-Position Frequency O Open Q Once per 92 days ID . Locked open C Testing performed during cold shutdown (but no sooner than.90 daysJ 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 valtes)' P - Tested during time period defined in:
- IW-3511 (safety and relief valves)
IW-3610 (explosive actuated valves)
.III-9 NUCLEAR' ENERGY SERvCES. MC.
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Document No. 30A2903 Rev. 4 l')
~V. Test Requirements ET Full exercise ST Stroke time PV Passive valve FS Fail safe 7
SR Relief valve XT Explosive valve 4
. VR Vacuum Relief Valve LP Leak test per Section XI (pressure isolation)
-IJ Isak test per Appendix'J, Type C (containment isolation)
IC Leak test per both Section XI and, Appendix J, Type C
'(both pressure and containment isolation)
LT Special leak test for ADS short term accumulator back leakage check valves (pressure decay method) i 4
Stroke Direction 4 .
O Open C' Closed I Check Valve Test Direction F Forward Flow R Reverse Flow 4
NOTE: Position indicators will be verified in accordance with IW-33OO.
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Document No. 80A2903 Rtv. 2 ff'j 5. Valve Test Table Format
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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. I 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 two.
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
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assumed idle.
The test requirements which apply to the valve. For
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. Test Req.
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 time (second'line). .If both directions are safety related, four lines are used. This column also includes direction and maximum stroke time for positive 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.
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III-11 wuctran smenov sanvcauc. j
Document No. 80A2903 Rev. 2
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' C.S. or Alt. Test- Cold shutdown or alternatie testing which is i$ Perf.. being performed in lieu of Code specified 1 quarterly testing. ,
- Remarks Amplifying remarks as appropriate.
Rev. No. This column records the latest document revision number for each valve. '
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Document No. 80A2903 Rev. 4 I 6. Index (l/
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-29C FM-32A 4
12 2 l4 B-31 Reactor Water Recirculation FM-26A 11 3 :
FM-26B 4 !
C-ll Control Rod Drive FM-27A 13 4 FM-27B 13 FM-27C 9
' .C-41 Standby Liquid Control FM-21A 14 5 C-51 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 FM-20B 15
.t - - E-21 Core Spray FM-23A 15 9 E-32 MSIV: Leakage Control FM-69A 5 10 E-41 HPCI FM-25A 13 11 I 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 Water Cleanup FM-24A 15 14 i
G-41 Fuel Pool Cooling & Cleanup FM-19A 12 15 M-50 RBSVS & CRAC FB-43A 11 16-FB-43B 11 P-41 Service Water 'FM-47A 12 17 P-42 RBCLCW FM-15A 13 18 FM-15C 10 FB-23B 14 4- 1P-50 Instrument & Service Air FM-38D 7 19 i FM-38E 4
Document No. 80A2903 Rev. 2 I
i 6 Index (cont.)
System No. System' Dwg. No. Rev. No. Attachment No. .)
R-43 Fuel Oil Transfer FM-44A 11 20
-R-43 LDiesel Generator Air Start' FM-44B 4 21 T-23 Drywell Floor Seal Pressure FM-SSA 7 22 Monitoring T-46 Reactor Building Normal FB-23A 12 23 Vent' T-48. Primary Containment Atmospheric FM-52A 10 24 Control FM-84A 2 e
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Document No. 80A2903 Rev. 2 i'
p'.
4 PLNP AND VALVE INSERVIG TESTING PROGRAM PIAN FOR SHOREHAM NUCEAR POWER PIANT UNIT NO. 1 i
SECTIN III t ATIAO NENT 1 O v-cTcSTTom- - -
FOR MAIN AND AUX. S'IEAM (B-21)
DWG. NO. EM-29A J
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CLASS SIZE DIRECT. CHECK JUSI OR AND (M) ACT11 NORM TEST REMARKS REV yALVE NO. %ALVE AND VALVE OR ALI NO.
DWG. CAT. AND TYPE POSIT. REO. m TEST pELIEF TEST CN TYPE (SEC.) DIRECI REO.NO. PERF.
MOV-031 1 A 3 MO O LT-Q C g F-7 GT ST-Q 18.8 IJ-R MOV-032 1 A 3 MO O LT-Q C 11- 7 cr ST-Q 8.6 IJ-R NN-081A 1 A 24 AO O LT-Q C CS-1 LT-C F-4 GL ST-Q 5 CS-1 SP-C FS-Q G-1 ES-C LJ-R ADV-081B 1 A 24 AO O LT-Q C G-1 LT-C P-4 GL SP-Q 5 CS-1 ST-C FS-Q CS-1 FS-C IJ-R ADV-081C 1 A 24 AO O LT-Q C CS-1 ET-C F-5 GL ST-Q 5 CS-1 ST-C FS-Q CS-1 FS-C IJ-R ADV-081D 1 A 24 AO O LT-Q C CS-1 LT-C F-6 GL ST-Q 5 CS-1 ST-C FS-Q CS-1 ES-C LJ-R ADV-082A 1 A 24 AO O LT-Q C CS-1 LT-C 11- 4 GL ST-Q 5 G-1 St{
FS-Q CS-1 PS-C LJ-R NFSs244
% /^N p w b V g NAIN MO NN. SIDH (B-21)' VALVE TEST TABLE gg FM-29A DOCUMENT NO. 80A2903 w4 p,gg III-1-3 op M44 l STROKE C.S. C.S.
CLASS M DIRECT CHECK JUSE OR yuVE NO. AND VALVE (M) ACT11 NORM TEST AND VALVE OR Att REMARKS REV DWG. CAL AND TYPE posit REQ. TIME TEST RELIEF TEST NO.
COOR. WPE DIRECT REO.NO.
(SEC.) PERF.
NN-0828 1 A 24 AO O LT-Q C CS-1
- ET-C 11- 4 CL ST-Q 5 G-1 ST-C FS-Q G-1 FS-C IJ-R NN-082C 1 A 24 AO O LT-Q C G-1 LT-C 11-5 CL ST-Q 5 G-1 ST-C ES-Q CS-1 FS-C IJ-R N N-082D 1 A 24 AO O ET-Q C CS-1 LT<
11- 6 CL ST-Q 5 CS-1 St-C FS-Q G-1 Es-C IJ-R RV-092A 1 BC 6 SA -
SR-P ME Valw C-3 R AD C ET-Q O RR-1 IT-R ST-Q RR-1 ES-Q RR-1 FS-R RV-0928 1 DC 6 SA -
SR-P ME Valw C-3 R AO C ET-Q O RR-1 ET-R St-Q RR-1 FS-Q RR-1 FS-R RV-092C 1 C 6 SA -
SR-P C-4 R AO RV-092D 1 C 6 SA -
SR-P C-4 R AO NES 3244
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- DOCUMENT NO. 80A2903 Ibv 4 pagg 111-1-4 og W4W STROKE C.S. C.S.
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DIRECT CHECK JUSI OR VALVE NO. AND VALVE (H) ACTL1 NORM TEST AND VALVE OR ALT. REMARKS REV N CAI AND TYPE POSII REO. TIME TEST RELIEF TEST NO.
(SEC.) DIRECT REO.NO. PERF.
SR-P ADS Valw C-4 R AO C ET-Q O RR-1 LT-R ST4 RR-1 FS-Q RR-1 FS-R W-092L 1 DC 6 SA -
SR-P ADS Valw C-4 R AO C LT-Q O RR-1 LT-R SP-Q DR-1 FS-Q I<R-1 IS-R RV-092F 1 C 6 SA -
SR-P C-5 R AO RV-092G 1 C 6 SA -
SR-P C-5 R AO RV-092K 1 BC 6 SA -
SR-P ADS Valw c-5 R AO C LT 4 O RR-1 ET-R ST-Q RR-1 FS4 RR-1 PS-R W-09211 1 DC 6 SA -
SR-P ADS Valw C-6 R AO C LT 4 O RR-1 ET-R ST4 RR-1 FS-Q I<R-1 ES-R RV-092J l DC 6 SA -
SR-P ADS Valm C-6 R AO C LT-Q O RR-1 LT-P.
STS RR-1 FS4 i<R-1 PS-R NE$ 5244 i
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N M DeRECT. CHECK JUSE OR AfdO MhWE (W) ACiu Nones TEST MALVE REMARKS REV wkt.VE900. AND OR Att CAI AND TYPE posit REQ- NO.
DWG. TMAE TEST N TEST
. COOR. WPE (SEC.) OtRECI REO.NO. .PERF.
KN-061 1 A 2 60 O ET-Q C 7.O g
i 11- 3 CL ST-Q U-R l
MN-062 1 A 2 M0 O LT-O ST-Q C
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11 - 4 CL W-R MN-063 1 11 - 5 A 2 cL MO O ET-0 ST-O C
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W-R HN-064 1 A 2 MO O LT-Q C g' 11- 6 GL ST-O 7.2 W-R IW-093A 2 A-7 C 24 C
SA -
FT-O ET-Q P
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IN-09 3A throts3h IN-09 3M.
IW-093D 2 A-7 C 24 C
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CLASS SIZE DIRECT. CHECK JUSI OR AND VALVE (ut) ACTil NORM TEST VALVE OR ALI REMARKS RW VALVE NO. AND NO.
DWG. CAI AND TYPE POSII REO. m TEST RELIEF TEST COOR. TYPE (SEC.) DIRECI REO.NO. PERF.
W-093L 2 C 24 SA -
LT 1 P - b a-7 C LM R IN-09E 2 C 24 SA -
LT-O F b A-7 C ET-Q R W-095A 3 C 6 SA - VR-P W-095A throtrJh IN-095L are vacetrn D-7 VR relief valves. 'Ibsted as vactazn mlief valves.
Rv-0958 3 C 6 SA -
VR-P D-7 VR IN-095C 3 C 6 SA -
VR-P D-7 VR IN-095D 3 C 6 SA -
VR-P D-7 VR IN-095E 3 C 6 SA -
VR-P D-7 VR l
l t
t o
' NFS 5744
'] (g ( %.,,
<J \,.J O' SYSTEM:
' #* 2II VALVE TEST TABLE DWG. NO. W-N DOCUMENT NO. 80A2903 Pev4 PAGE m 8 OF STROKE C S. C.S.
M IS SIM DIRECT. CHECK JUSI OR WEVE NO. AND VALVE (N) ACTu NORM TEST AND VALVE OR ALI REMARKS REV DWCL CAT. AND TYPE POSII REO. TIME TEST NO.
RELIEF TEST M DIRECT REO. NO.
(SEC.) PERF.
W-095F 3 C 6 SA -
VR-P C-7 VR RV-095G 3 C 6 SA -
VR-P C-7 VR RV-095H 3 C 6 SA -
VR-P C-7 VR RV-0957 3 C 6 SA -
VR-P C-7 VR 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 throtzJh RV096L are vauan D-7 VR relief valves. Tested as vaciun relief valms.
I l
r NES 5244
.4. u u-O O O e
gg HAIN & AUX. SIThe (B-21) VALVE TEST TABLE
__ ,_,W m 903 w 4 mg 111-1-9 M+U
_ EW , y l STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK JUSI OR wuyE NO. AND M (M) ACTu NORM TCST ANO VALVE OR ALI REMARKS REV.
DWG. CAI AND TYPE POSII REO. TWE lEST RELIEF TEST NO.
N N (SEC.) DIRECI REO NO. PERE W-096B 3 C 6 SA -
VR-P D-7 VR W-096C 3 C 6 SA -
VR-P D-7 VR RV-096D 3 C 6 SA -
VR-P D-7 VR W-096E 3 C -6 SA -
VR-P D-7 VR RV-0%F 3 C 6 SA -
VR-P C-7 VR WH)96G 3 C 6 SA -
VR-P C-7 VR RV-09611 3 C 6 SA -
VR-P C-7 VR NES 8244
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4 SYSTE3 Main and Aux. Steam 001) VAiVE TEST TABLE m-29C 80A2903 Rev. 4 111-1-12 111-1-15 DWG. NO. DOCUMENT NO. PAGE OF STROKE C.S. C.S.
. CLASS SIZE DeRECT CHECK JUSI OR AND WA!VE (W) ACTU NORM TEST REMARKS- REV VALVE NO. AND VALVE OR ALI DWG. CAI AND TIPE POSII REQ. TEST NO.
TIME REllEF TEST COOR. WPE (SEC.) DIRECT REQ. NO. PERF.
ET-Q R RR-2 ET-R Leak test by pressure decay method.
D-3 C LT-R Criteria as follows: P =o 90psig. Pg) 70psig at to minutes. P 2p 55psig at 30 mini.tes.
ET-Q R RR 2 ET-R Leak test by pressure decay method.
D-3 C LT-R Criteria as follows: Po = 90psig. PgA 70psig
, at 10 minutes. P 2t.55psig at 30 minutes.
ET-Q R RR-2 ET-R Leak test by pressure decay method.
D-3 C LT-R Criteria as follows: P =o 90pulg. Pg &70psig at 10 minutes. P 2h 55psig at 30 minutes.
ET-Q R RR-2 ET-R Leak test by pressure decay method.
D-3 C LT-R Criteria as follows: Po = 90psig. Pg &70psig 4 at to minutes. P 2a 55psig at 30 minutes.
ET-Q R RR-2 ET-R Leak test by pressure decay method.
D-3 C LT-R Criteria as follows: Po = 90psig. Pga 70psig at 10 minutes. P y h 55psig at 30 minutes.
ET-Q R RR-2 ET-R Leak test by pressure decay method.
D-3 C LT-R Criteria as follows: P =o 90psig. Pgh 70psig at 10 minutes. P a 55psig at 30 minutes.
ET-Q R RR-2 ET-R Leak test by pressure decay methoJ.
D-3 C LT-R Criteria as follows: Po = 90psig. Pl> 70psig at 10 minutes. P 2A 55psis at 30 minutes.
er9 ose
, DOCUMENT NO. 80A2903 Rev 4 PAGE III-1-13 OF 111-1-15 4 NUCLEAR ENERGY SERVICES, INC.
r3 U -
COLD SHLITDOWN TEST JUSTIFICATION CS - 1 System: Main and Aux. Steam Valve: AOV-081A,B,C,D : AOV-082A,B,C,D Category: A Chu: 1 Function: Main steam line isolation valves.
ASME Section XI Quarterly Test Requirements: Exercise and time.
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.
l Quarterty Part Stroke Testing: Partial stroke close exercise.
i l
V Cold Shutdown Testing: Full stroke exercise and time.
l l
FORM e NEs-24712/82
DOCUMENT NO. 80A2903 pnv 4__
m 11 NUCLEAR ENERGY SERVICES, INC. PAGE 111-1-14 OF_ III-1-15 l V
RELIEF REQUEST RR - 1 l
System: Main and Aux. Steam Valve: RV-092A,B,E,H,K,J,L Category: BC Class: 1 Function: ADS Val */es.
ASME Section XI Quarterly Test Requirements: Exercise and time.
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 of 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 exercis, testing of the ADS valves will be delayed to refueling interva's. . b Alternate Testing: Exercise at refueling intervals.
O FORM # NES-24612/82
DOCUMENT NO. 80A2903 Rev. 4 NUCLEAR ENERGY SERVICES, INC. PAGE III-1-15 op III-1-15 _
(
REUEF REQUEST RR - 2 System: Main and Aux. Steam Valve: 0004A,B,E,H,J K&L Category: AC Class: 2 Function: ADS valve short term accumulator back leakage check valves.
ASME Section XI Quarterly Test Verify reverse flow closure.
Requirements:
O Basis for Relief: These valves are located within the reactor building primary containment. Testing of these valves either quarterly or at 4 cold shutdowns is precluded due to an inerted primary contain-ment atmosphere.
Alternate Testing: These valves will be tested during refueling outages where a special leak rate test (pressure decay) will be performed to verify the leaktight integrity of the check valves.
l l
f
's t
FORM # NEs-24612/82
Document No. 80A2903 Rev. 4
,= (
PENP AND VALVE INSERVIG TESTING PROGRAM PIAN MR SHOREHAM NUCIEAR POWER PIANT LNIT NO. 1 SECI'ICN III
- . ATTACH?ENT 2
. o.
VALW TEST TARTFR AND FFT.TEP REQUESTS 4,
MR FECDLRTER (B-21) -
DWG. NO. EM-32A f
+
2-
.i 1
. O III-2-1 mnean awnov saavcas.sc
't d-- - y b y3r, %p.--y+ ~+M-- v - --+n.- t-try eay 4.- n*- -C---7Mi- F "-T
~
W F f 7 W 9 -*
/~N "N ', A U {b (D-21) VALVE TEST TABLE SYSTEM:
m go. IM- 32A DOCUMENT NO. 80A2903 lov 4 PAGE TTT-2-2 op TTT-2-4 STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK JUST. OR AND VALVE (in) ACT11 NORM TEST VALVE REMARKS REV M NO. AND OR ALT.
DWG. CAT. AND TYPE posit REO. TEST NO.
TIME RELIEF TEST COOR. TYPE (SEC.) DIRECI P.EG. NO. PERF.
NN- 035A 1 1C 20 SA -
LT-Q F Positive closure snotor geratect b D-4 SC FO O LT-Q C R CS-1 LT-C stqi cihxi.
ST-Q 120 CS-1 ST-C 70/-035B 1 IC 20 SA -
LT-Q F Positive closure motor geratal b D-5 SC FO O LT-Q C R CS-1 LT-C stop ckck.
ST-Q 120 CS-1 ST-C NN-036A 1 E 18 SA -
LT-Q F Testable eleck. Air g erator C-4 C LT-Q R CS-1 LT-C for te st only.
IJ-R N R-036D 1 E 18 SA -
LT-Q F Testable chtd. Air gerator C-5 C LT-Q R CS-1 LT-C for test only.
IJ-R 1103A 1 E 18 SA -
IM F C-4 C LT-Q R RR-1 LT-R IJ-R 1103B 1 E 16 SA -
LT-Q F C-5 C LT-Q R RR-1 LT-R IJ-R NFS WN4
1 DOCUMENT NO. 80A2903 Rev 4 l NUCLEAR ENERGY SERVICES, INC.
PAGE III-2-3 OF III-2-4 O,o '
l 1
i COLD SHUTDOWN TEST JUSTIFICATION CS - 1 System: Feedwater Valve: MOV-035A,B : AOV-036A,B Category: AC Class: 1 Function: Feedwater inlet valves, d ASME Section XI Quarterly Test o Requirements: Exercise ( AOV-03E A , B )
C 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.
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 partial stroke exercised.
Col-1 Shutdown Testing: Exercise (AOV-036A,B)
Exercise and time (MOV-035A,B)
FORM e NEs-24712/82
DOCUMENT NO. 80A2903 Rev 2 m
NUCLEAR ENERGY SERVICES, INC. PAGE III-2-4 .OF III-2-4 g
O' RELIEF REQUEST RR - 1 System: Feedwater Valve: 1103A,B Category: AC Class: 1 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).
ASME Section XI Quarterly Tnt Requirements: verify reverse flow closure.
Basis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C testing at refueling.
Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C testing at refueling.
O FORM # NES-24612/82
Document No. 80A2903 Rev. 3 f-J V
PLNP AND VALVE INSERVICE TESTING PROGRAM PLAN mR SHOREH7M NUCLEAR POWER PI. ANT UNIT NO. 1 SECTICN III I
ATTACHMENT 3 i VALVE TEST TABLES AND RRrJFP REQUESIS NR REACIOR NATER RECIBCUIATIO1 (B-31)
DWG. NO. FM-26 A,B' 4
9 d
1 III-3-1 NUCLEAR ENERGY SERVICES. INC.
. - - . - - ,. . . . . . _ . _ _ . . . . . . ..__.. -._,-.. _ ,. --. ,--.m. . _ _ _ - . _ _ _ _ _ _ . , , ~ , , , - . _ . , , .
y- s- s~
b U N.s SYSTEM. Rf'JCIOR WHER REEIFORATIO4 (B-21) VALVE TEST TABLE N NO. EM-26A DOCUMENT NO.
8 03 h2 PAGE III- 3-2 III-3-5 OF STROKE C.S. C.S.
DIRECT. CHECK JUSI OR WLVE NO. AND VALVE ilR) ACTL1 NORM TEST AND VALVE OR ALI REMARKS REV DWG. CAT. AND TYPE POSII REO. TIME TEST RELIEF TEST NO.
- (SEC.) DIRECI REQ.NO. PERF.
MW-031A 1 B 28 MO O LM C G-1 L'r-C E-7 GT ST-Q 33 CS-1 ST-C M N-032A 1 B 28 FD O LT-O C G- 1 LT-C 11- 6 CP ST-O 33 CS-1 ST-C 2A 2 Ac 3/4 SA -
L't-Q R RR-1 LT-R J-5 C LI-R s
NES s244
y fx LJ L] O SYSTEM:
Em M I tim (B-2D ME TEST TA61E FN-26B DOCUMENT NO. 80A2903 Fev 4 - PAGE III~ 3- 3 OF II T- 3-5 DWG. NO.
STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK JUST OR AND WLLVE (IM) ACTL1 NORM TEST REMAR%S REV M NO. AND VALVE OR ALI DWG. CAI AND TYPE POSIT. REO. TEST NO.
TIME RELEF TEST COOR. TYPE (SEC.) DIRECT. REO.NO. PERF.
NN-081 2 E-1 A 3/4 GL N) O LT-Q ST-Q C
h-FS-O Lal-R X N-082 2 t>- 1 A 3/4 GL AO O LT-Q ST-O C
5 h
PS-O I.]-R MOV-031B 1 B 28 FD 0 ET-O C G-1 In'-C P-7 GT ST-O 33 G-1 ST-C MOV-032B 1 .B 28 FD 0 LT-O C G-1 LT-C C-7 GP ST-Q 33 G-1 ST-C 0002B 2 Ac 3/4 SA -
LT-O R PR-1 LT-R B-5 C I.1-R NF S s244
DOCUMENT NO. 80A2903 Rev 2 e
PAGE III-3-4 OF III-3-5 NUCLEAR ENERGY SERVICES. INC.
\J COLD SHUTDOWN TEST JUSTirCATION CS - 1 System: Reactor Water Recirculation Valve: MOV-031A,B : MOV-032A,B Category: B Chu: 1 Function: Reactor recirculation pump isolation valves.
ASME Section XI Quarterly Test Requirements: Exercise and time.
Cold Shutdown Test Justification: These valves are in the reactor recirculation main flow path.
Partial or full stroke exercising during normal operation would reduce or stop flow in one loop of the reactor coolant system.
Disturbance of normal operating reactc,r recirculation flow could result in adverse plant operation, such as changes in reactivity, I power transients, and a possible reactor trip.
l l
l l
Quartetty Part Stroke Testing: NA
' O c
Shutdown Testing: Exercise and time.
c,- .
FORM e NES-24712/82
DOCUMENT NO. 80A2903 Rev 2 NUCLEAR ENERGY SERVICES, INC. PAGE III-3-5 OF III-3-5 o
RELIEF REQUEST ~
RR - 1 System: Reactor Water Recirculation Valve: 0002A,B Category: AC Class: 2 Function: Containment isolation simple check valve (reverse flow closure for conteinment isolation only).
- Quarterly Test l Requirements: verify reverse flow closure.
Basis for Relief: The only w thod available to verify reverse flow closure is by valve leak testing during Appendix J, Type C testing at refueling.
l l
Altemate Testing: Reverse flow closure will b.e verified during Appendix J, Type C testing at refueling.
i O
l G l
FORM e NEs-24612/82
Document No. 80A2903 Rev.' 3-g i
i t
PLNP AND VALVE INSERVICE TESTING PROGRAM PIAN NR SHOREHAM NUCLEAR POWER PL f T UNIT NO. l-i I
U l
SECTION III ATTACHMENT 4 f
i.
VALVE TEST TABIES AND PFT.TEF REQUESTS NR .
CCNTROL RCD DRIVE (C-ll) -
(
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O III-4-1 wettaa rwaov senvens.nc
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)
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SYSTEM: NRL RU DR4W (C-ll)
VALVE TEST TABLE E NO. IN-27C 80A2903 R'v 2 III~4~4 DOCUMENT NO. PAGE OF III-4-0 STROKE C.S. C. S.
CLASS SIZE DIRE CT, CHECK JUST OR VALVE NO. AND VALVE (tN) ACTtl NORM TEST AND VALVE OR ALI REMARKS REV DWG. CAT AND TYPE POSIT REO TIME TEST RELIEF NO.
m DPE (SEC) DIRECT REO NO.
TEST PERF.
NN-127 2 B 3/4 AD C ET-Q O RR-2 Tested by Tech. St ec. Control ful Scram B-2 Cr ST4 PR-2 Insertion Tine Testing. To te FS-O PR-2 gerformx1 on 10% of in!'s each 120 days arul 100% of IGJ's each refuelirn.
NN-126 2 B AO C
\ EX-O O RR-2 Tested ty Tech. Spec. Control Ibl Scram B-4 Cr ST-Q RR-2 Insertion Tine Testing. To te gerforn<t FS-Q RR-2 on 10% of ini's each 120 days armi 100%
of ini's each refueling.
101-114 2 C 3/4 SA -
IX-0 F PR-2 E-2 C Tested tv Tech. Sl ec. Control thi Scram Insertron Tine Testing. 1b te gerformi on 10% of Int's each 120 days and 1001 of Int's each refuelirvi.
IKX)-115 2 C SA -
L'F-O R RR-3 G-4 C llCU-138 2 C SA ET-Q R PJ4-4 'Ibsted by Tech. Spec. Control Rod Scram D-5 C Insertion Tine Testirq. To te gerformi on 10% of int's each 120 days arul 100%
of IGl's each refueling.
NES s244
80A2903 Rev 2 mr DOCUMENT NO.
m 11 = NUCLEAR ENERGY SERVICES, INC. PAGE III-4-5 oF III-4-8 REUEF REQUEST RR 1 System: Control Rod Drive Valve: 1028A,B Category: AC Class: 2 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).
ASME Section XI l Quarterly Test Requirements: Verify reverse flow closure.
A 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 Alternate Testing: Reverse flow closure vill be verified during Appendix J, Type C testing at refueling.
l O
FORM a NES 24612/82
my DOCUMENT NO. 80A2903 Rev 2 PAGE III-4-6 op III-4-8 NUCLEAR ENERGY SERVICES, INC.
V RELIEF REQUEST' 2 '
RR System: Control Rod Drive Vah. AOV-126 : AOV-127 : HCU-ll4 (To be done for all 137 HCU's)
Category: B (AOV-126 : AOV-127)
C (HCU-ll4)
Class: 2 Function: Reactor shutdown.
ASME Section XI Quarterly Test Requirements: Exercise, time and fail (AOV-126 : AOV-127).
fi
<J 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 rods 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
.Y FORM e NES-24412/$2
DOCUMENT NO. 80A2903 Fev 2 my 11
- NUCLEAR ENERGY SERVICES,INC. PAGE III-4-7 OF III-4-8 b,\
RELIEF REQUEST RR 3 System: Control Rod Drive Valve: HCU-115 (To be done for all 137 HCU's)
Category: c Class: 2 Function: Reactor Shutdown.
ASME Section XI Quarterly Test Requirements: Verify reverse flow closure.
F
(
, Basis for Relief: Verification of reverse flow closure requires securing the CRD pumps, depressurizing the header and monitoring the individual accumulator pressure and alarm to verify that the valves have closed on reverse flow. To do this requires entry into a high l
radiatjon work area and could also result in a plant scram.
l l
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Alternate Testin9- 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 j allow extend entry for testing. Testing will be by depressurizing the header and monitoring the individual accumulator 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.
l l
rs L) l l FORM e NEs-24612/82
my DOCUMENT NO. 80A2903 Rev 2 11 " NUCLEAR ENERGY SERVICES. INC. PAGE III-4-8 OF III-4-8
(
NJ HELIEF REQUEST' RR -- 4 System: Control Rod Drive Valve: HCU-138 (To be done for all 137 HCU's)
Category: C Class: 2 Function: Peactor shutdown.
ASME Section XI Quadedy T<ut Requirements: Verify reverse flow closure.
D.
U Basis for Rdied: 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.
AMenisde Testing: Verification of reverse flow closure 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.
FORM # NES-24612/82
. = - _ . - .
Document No. 80A2903 Rev. 3 f t
i i
k
+
PLEP AND VALVE INSERVIG 'IESTING PPOGRAM PIAN EUR SHOREHAM NUCIEAR POWER PIANT LNIT NO. 1 l-SECTICN III ATTACHMENT 5
.O VALVE TEST TABIES AND RELIEF REQUESTS
=
FOR STANDBY LIQUID CONIPOL (C-41)
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DOCUMENT NO. 80A2903 Rev 4 NUCLEAR ENERGY SERVICES, INC. PAGE III-5-4 OF III-5-6 REUEF REQUEST-hA 1 I
System: Standby Liquid Control i Wive: 0008 : 0010 Category: AC Chu: 1 Function: SBLC injection line check valves.
ASME Section XI Quarterly Test Requirements: Verify forward flow operability.
O V
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 squin valve and pumps demineralized water into the reactor vessel.
t FORM e NES-24612/82
DOCUMENT NO. 80A2903 Rev 4 my
" " " NUCLEAR ENERGY SERVICES, INC. PAGE III-5-5 oF III-5 6 lb i\
U REUEF REQUEST-RR - 2 System: standby Liquid Control Valve: 0008 : 0010 Category: AC Class: 2 Function: Containment isolation simple check valve (reverse flow closure for i 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.
Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C testing at refueling.
i l
O FORM # NES-24612/82
DOCUMENT NO. 80A2903 Rev. 4 m
" " " PAGE III-5-6 OF III-5-6 NUCLEAR ENERGY SERVICES, INC.
(_/
REUEF REQUEST' RR - 3 System: Standby Liquid control Valve: 0007A,B Category: C Class: 2 Function: Standby Liquid control System Pump Discharge Check Valves.
ASME Section XI Quarterly Test t'erify reverse flow closure. g Requirements:
Basis for Relief: To test these valves, one train of the SIC System must be taken eut of service, thereby defeating the redundancy of the SIC pumps and placing the plant in a Technical Specification Limited Condi-tion of Operation (LCO).
Alternate Testing: Reverse flow closure will be verified during refueling outages.
l O FORM # NEs 24612/82 l
Oucument Nc. 50A2903 Rev. 3 -
PLNP AND VALVE INSERVICE TESTING PROGRAM PIAN l
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!- SHOREHAM NUCIEAR'PGE.R PIANT UNIT NO. 1 SECTICH III ATTACHMENT 6 o
VALVE TEST TABIES AND PRT.TEF REQUESTS FOR NElfrRON MCNITORING (C-51)
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. PlbP AND VALVE INSERVICE TESTING PFOGRAM PIAN 4
FOR A SHOREHAM NUCLEAR POWER PIAVf i- UNIT NO. 1 f SECTICN III ATTAONENT 7
- i. VALVE TEST TABLES AND PET.TEP RDQUESTS FOR RADIATICN MCNI'IORIIC '(D-ll)
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PUMP AND VALVE INSERVICE TESTING PROGRAM PIAN.
FOR SHOREHAM NUCIEAR POWER PIANT UNIT NO. 1 1
O SECTICN III ATI%CENENT 8 VALVE TEST TABIES AND RELIEF REQUESTS FOR RESIDUAL HEAT RDOVAL (E-ll)
- DWG. NO. EM-20 A,B
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-20A DOCuuENT NO. 80A2903 Rev 4 PAGE 111-8-2 op III-8-2 3 '
DM M.
STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK JUST. OR NORM TEST REMARKS REV wuYE NO. AND VALVE (W) ACT11 AND VALVE OR ALT.
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TIME RELIEF TEST COOR. WPE (SEC.) DIRECT REO.NO. PERF.
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CLASS SIZE DIRECT CHECK JUST. OR AND MLVE (M1 ACTu NORM TEST AND VALVE REMARKS REV MLVE NO. OR ALT DWCL CAI AND TYPE POSIT REO TIME TEST RELIEF TEST U
COOR. TYPE (SEC) OtRECT REO.NO. PERF.
NN-055A 2 A 1 FO C W Wis valw is avlicated to tlw? Id!R A-6 CL IJ-R steam corxk nsing anb of q= ration.
lic sot as a nomil q= ratirw; nexk Ms tum d?leted at F2HS-l.
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Bc TOi as a nornal ga ratirvi armb Ns twn (blettd at f2KS-1.
RV-157A 2 fc 1 SA -
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nW-081A 1 A 2 FO C W Valve opens arki autonatically J-2 GL IC-R recloses onm pressure opulizes across tM testable etwrk valw.
MN-044A 2 A 4 FO C W Wis valw is ikdicataxi to tk MIR E-6 cr IJ-R steam cr2*bnsing rrnb of qoration.
The S01 as a nornal qm rat tr<j nob has Imn deletal at CAS-l.
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g RESIEUAL lEAT R2sA"AL (E-ll) WhtVE TEST TA81.E EM-20B 80A2903 T4 v 4 PAGE TIT-8-10 op III-8-21 m uo. DOCUMENT NO.
STROKE C.S. C.S.
N M DIRECT, CHECK M OR AND (M) ACTL1 NORM TEST ggo REMARKS REV MELVE NO. WELVE whLVE OR ALI CAI AND TYPE POSII REO. NO.
DWG. TIME TEST RN TEST M WPE (SEC.) DIRECI REO.NO. PERF.
MN-032D 2 B 20 FO C ET-O ST4 O g C-8 Cr 113.5 M N-042B 2 A 16 FO C L"r-Q C g D-6 CL STS 81.3 IJ-R M N-049 2 B 10 FO C W 'Ihis valve is dedicated t.o tk MIR E-5 CT steam contbnsiry armb of geraticn.
1k RN as a nornal qu?ratiry onb has Imen &leted at 90S-1.
PtW-043B 2 B 4 70 C W '!his valve is ckdicated to tJe HIR F-4 CT steam <xnkmirs en3e of qcratico.
'Ite SIN as a norval geratirq nub has taxn &letal at RIPS-1.
M W-044B 2 A 4 Ft1 C IV 'Ihis valve is <bdicated t.o the MIR G-4 Cr I.Y-R ste.un corubnsirq nob of geration.
'IN RM as a norTral geratirq nxub has taen deletcsi at SFPS-1.
FW-035B 2 8 16 PO O W ther disctrumetal. b II-4 Cr MX-033b 2 B 16 M) O IV Power dis (xnnected. d G-7 Cr ed 5 s244
,, (
~,Y Q) N_
g fesIDin IEAT MMAE (E-II) VALVE TEST TABLE g IM-20B N NT m 80A2903 Fev 4 PAGE III-8-11 op III-8-23 STROKE CS. C.S.
n att SIZE 00 RECT. CHECK JUSI OR AND WELVE (M) ACT11 NORM TEST REMARKS REV yhLVE HCL AND WALVE on ALI D WCL CAE AND TYPE POSII REa TasE TEST RELEF TEST NO.
COOfL ME (SEC.) DIRECT REa NO. PERF.
W-163 2 E 1 SA -
IJ-R %ernal relief valve. 4p. J, G-2 R Tyle C test only.
RV-164 2 E 1 SA -
IJ-R % ental relief valw. 4p. J, F-3 R 'IYle C test cnly.
MA/-0343 2 G-8 B 18 A
to O LT-O ST-O O
139.1 g
N3/-081B 1 E 24 SA -
LT-O F CS-2 17-C Testable etwdt valm (turt A-3 C LT-O R CS-2 LT-C strcAe).
If-R OG20B 2 C 16 SA -
LT 4 F F-7 C W-155 2 E 2 SA -
1.1-P %is valm is dedicated to tie MIR F-5 R steam condensirs pnb of geration.
'Itc Sm as a normul geratire nub has txen deleted at SrFS-1.
Rv-152B 2 E 4 SA -
IJ-R Wis valm is dedicatixt to flu 2 RIR I-5 R steam cxnbnsirq prxb of geration.
tJe Sm as a nontul gerating atxb has taen ableted at SrAs-1.
adSstee
,m n --
I
.,_,/ , ] L I g g. 54sIICAL 1223 EdMWAL (E-II) VALVE TEST TABLE EM-200 NEM M HOA2903 Inv 4 PAGE III-8-12 op III-8-23 STROKE CS. C.S.
n att SIZE DIRECT CHECK JUST OR gg AND M (M) ACT11 NORM TEST AND WLLVE OR ALL REMARKS REV DWCi CAI AND TYPE POSIT REO TWE TEST RELIEF TEST COOR. TYPE (SEC) DIRECT REQ. NO. PERF.
PtW-055D 2 A 1 PD C IV 'this vavle is (ktiicated to tim! MIR J-6 G. l.J-R ste:Jn ctruknsituJ nrxb of qu? ration.
%' SW as a norwil geratirvj nruht has lasn d:lettsl at SNPS-1.
PEN-0%ts 2 A 1 to C IV This valw is dslicated to t}m MIR J-5 Q. IJ-H steam corsknstru; namh> of geration.
mi Sm as a norws! q= ratiry; numkr has tatn d leted at SNPS-l.
lu-157B 2 pc 1 SA -
IJ-R mzri:sil r1: lief valw . Agg). J, I-6 R Tne C test only.
PtN-081B 1 A 2 to C IV Valve qm ns and autcratically A-3 c. Ir-I< recloses once pressure onnalizes across tie testable crack valve.
ftN-050 2 B 24 fu C IV Iwyr discveirm.ctttl to gerator.
C-4 cr 00358 2 C 3 SA -
17 4 F t'-7 C Cr-C H --
0014 2 C 3 SA -
CP-O l' E-8 C IT-Q R k edS C44
(~ y, (m N ..
y RESIIAJAI. IEAT MMNAL (E-ll) VAI,VE TEST M8LE IM-208 mg g 80A2903 kv 4 PAGE III-8-13 OF III-8-23 STROKE C.S. CS.
CLASS SIZE DIRECT. CHECK JUSI OR gg AND WELVE (W) JICTH NORed TEST REMARKS REV AND WhLVE OR ALI DW(i CE AND TYPE posit ftEn TMAE TEST REUEF TEST COOR. TYPE (SEC) DIRECT REO. NO. PERE MLN-057B 2 3 1 M0 C LT-Q O b J-4 CL ST-Q 14.7 RV-153d 2 C 1 SA -
SR-P I>-4 R 00228 2 C 4 SA -
LT-Q r Porvant flow gerability is wrified D-3 C LT-O R RR-2 by a systun check to wrify water inwntory.
0023 2 C 4 SA -
LT-Q F Forward flow gerability is wrified C-1 C LT-Q R RH-2 by a system cturk to wrify water inventory.
0037B 2 C 1 SA -
LT-Q F Porward flow gerability is verified D-2 C by a systan check to verify water inventory.
0028 2 C 4 SA -
LT-Q r RIH 3 A-4 C LT R RR-2 MLN-051 2 B 4 M0 C LT-Q O C-4 GT ST4 21.3 g DE Ss244
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DOCUMENT NO. 80A2903 pnv 3 5 W W NUCLEAR ENERGY SERVICES. INC.
n U
COLD SHUTDOWN TEST JUSTIFICATION CS - 1 System: RHR Wive: MOV-037A,B Category: A Class: 1 Function: LPCI injection valves.
ASME Section XI Quarterfy Test Requirements: Exercise and time.
O N._/
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 pres sure 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 Testing: NA Cold
' Shutdown Testing: Exercise and time.
rome e was-247 tves
DOCUMENT NO. 80A2903 nov 4 _.
m EE W NUCLEAR ENERGY SERVICES, INC.
PAGE III-8-17 OF III 23 i !
Q ,/
COLD SHUTDOWN TEST JUSTIFICATION CS - 2 System: RHR -
Valve: AOV-081A,B Category: AC Class: 1 Function: RHR injection valves.
ASME Section XI Quarterly Test Requirements: Verify forward flow operability and reverse flow closure.
O V
Cold Shutdown Test J'sstification: Valves are testable check valves with installed partial stroke open air operators. Partial stroke open testing during normal operation is precluded because stroking these valves would leave only one valve as a barrier between the high pressure reactor coolant system and the RHR system low pressure piping. 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-l system-LOCA. Testing operability by injecting water into the RCS l is not possible during normal operation because the PJtR pumps develop insufficient head to overccme RCS pressure.
I r
Quarterty Part Stroke Testing: NA (9 Cold V Shutdown Testing: Forwas.1 flow exercise during normal cool down utilizing two opere ing FJIR pumps per loop and verify reverse flow closure h
( using the valve position indicator lights.
Fonte e pas 24712/02
my DOCUMENT NO. 80A2903 Rev 3 PAGE III-8-18 op III-8-23 d NUCLEAR ENERGY SERVICES, INC.
O COLD SHUTDOWN TEST JUSTIFICATION CS - 3 System: ggg Valve: Mov-053 . Mov-054 Category: A Chu: 1 Function: Inboard and outboard containment isolation valves on RHR reactor vessel head spray line.
Quarterly Test Requirements: Exercise and time.
Cold Shutdown Test Jt.Mification: Valves are interlocked with reactor pressure at 135 psig and cannot be opened during normal plant operation.
i #
l l
l i
Quarterly Port Stroke Testing: uA O =hutdown S Testing: Exercise and time.
pons e us-247 tais
DOCUMENT NO. 80A2903 Fev 3__.
H E.h, NUCLEAR ENERGY SERVICES. INC. ~~ ~~
(q U
COLD SHUTDOWN TEST JUSTIFICATION CS - 4 System: RHR D: MOV-047 : MOV-048 Category: A Class: 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.
Cold Shutdown l
Test Justification: Valves are interlocked with reactor pressure at 135 psig and cannot be opened during normal plant operation.
l l Quarterly Part Stroke Testing: NA l Cold Shutdown Testing: Exercise and time.
Fone e us 2471vs2
Document No.:80A2903 Rev.~4 Page III-8-20 of III-8'-23 D
mm - . A O
O J_..._._...
DOCUMENT NO. 80A2903 Rev 3 NUCLEAR ENERGY SERVICES, INC. PAGE III-8-21 op III-8-23 d O
REUEF REQUEST RR - 1 Systom: RHR Valve: 3144 : 3145 : 0047 : 0048 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 clesure.
O Basis for Relief: The only method avai.*.able to verify reverse flow closure is by valve leak testing during Appendix J, Type C testing at refueling.
Alternete Testing: Reverse flow closure will be verified during Appendix J, Type C testing at refueling.
O l
FORet 8 NOB 24412/92
DOCUMENT NO. 80A2903 Rev 3 11 NUCLEAR ENERGY SERVICES, INC. PAGE III-8-22 OF III-8-23
\
'q)
RELIEF REQUEST RR - 2 s
System: RHR Valve: 0022A,B : 0023 : 0002A Category: C Class: 2 Function: Loop level injection line check valves to RHR system piping.
ASME Section XI Quarterly Test Requirements: Verify reverse flow closure.
("i
'u)
Basis for Relief: Loop level piping configuration precludes verification of reverse flow closure. To verify reverse flow closure 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.
l l 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 of individual valve reverse flow closure i verification. 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 l
be verified by a system check to verify system water inventory.
l l
f l
v i
FORM a NES-24412/82
DOCUMENT NO. 80A2903 Rev 3 NUCLEAR ENERGY SERVICES. INC. IMGE III-8-23 OF III-8-23 O
v RELIEF REQUEST-RR - 3 System: RHa Valve: 0028 Category: C Class: 2 Function: Loop level injection line check valve to RHR system piping.
ASME Section XI Quarterty Test Requirements: Verify forward flow operability.
n v
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 point 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 for manual exercising.
Altemate Testing: 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.
(o3 Fome e NEs-24412/82
Document No. 30A2903 Rev. 3 d-pO .
PUMP AND VALVE INSERVICE TESTING PROGPK4 PIAN FOR SHOREHAM NUCLEAR PCMER PIANT UNIT NO. 1 SECTICH III
. ATTAONENT 9 FOR CORE SPPAY (E-21)
DWG. NO. FM-23A l
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M E E TR TTC LLI TTC LL TPC LSI I
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D MI I RS C C C C C OO NP uE A A ) ) ) ) 0 TP t L t CY S S n f F F M AT E)D E 0 0 0P 0r 0L 0L r C C C ZNN S(A TY I l P 1 1 1 G 1 C 1 1 G 3 c
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l SYSTEM: N Tim $~21) VALVE TEST TABLE DWG. NO.
h2M DOCUMENT NO. 80A2901 14 v 4 PAGE IiT-9-3 OF T11-9-7 STROKE C.S. C.S.
CLASS S ZE DIRECT. CHECK JUST. ' OR AND VALVE (IR)' ACTil NORM TEST VALVE REMARKS REV VALVE NO. ANO OR ALT.
DWG. CAT. AND TYPE POSII REO. TEST NO.
TIME RELIEF TEST COOR. TYPE DIRECT. REO.NO. PERF.
(SEC.)
FKN-03415 2 I-6 A 3 CP 60 C L*P-O ST-Q C
18.6 g
IJ-R 0013A 2 C '12 SA -
L'F-O F A-5 C 0013B 2 C 12 SA -
E?r-O F J-S C Ft N- 031A 2 A 14 Fio O L'r-O C d C-7 Cr ' GP-Q vs.u IJ-R FKN-031B 2 A 14 FD O I!r-O C A G-7 Cr ST-Q a>a.9 ZE IJ-R FEN-081A 1 A 2 SD C f "> Valve qums arul autmatically E-3 CL AC-R recloses once pressure oiualizes across the testable dwk valve.
etN-081D 1 A 2 60 C IV Valw qm ns arul autuutically F-3 GL IC-R recloses once pret:sure opalizes acrons the testable duck valw.
NE S m244
,cy (y ,r"w,,
) N. '%Y SYSTEM:
SI' HAY -21) VALVE TEST TABLE DwG. NO.
DOCUMENT NO. 80A2903 lbv 3 PAGE III'9~4 OF III'9' STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK JUST OR VALVE NO. AND VALVE (M) ACTL1 NORM TEST AND VALVE OR alt REMARKS REV D WCL CAT AND TYPE POSlY REO. TIME TEST RELIEF TEST NO.
COOR. TYPE (SEC.) DIRECT REO.NO. PERF.
RV-093A 2 C lh
- SA -
SR-P B-3 R IW-0938 2 C l\ SA -
SR-P 11- 3 R 0018u 2 C 2 SA -
LT-Q F Femard flow qerability is wrifie.x) 11 - 2 C LT4 R 104- 2 by a systs clock to wrify dater inwntory.
Zh 00158 2 -C 1 SA --
LT-Q F Forwitti flcw qerability is wrifiul ll-2 C by a systan check to wrnfy water inwntory.
0018A 2 C 2 SA -
LT-O P Forwrd flow qerability is wrifiol C-2 C LT-Q R RR-2 by a systm cteck to Wrify water [g inw ntory.
0015A 2 C 1 SA -
LT-O F Ebrusrd flcu gerability is wrified C-2 C- by a systun check to wrify water inwntory, us e244
m DOCUMENT NO. 80A2903 Rev 3 PAGE III-9-5 OF III-9-7 f-.-
NUCLEAR ENERGY SERVICES. INC.
(_.)
COLD SHUTDOWN TEST JUSTIFICATION CS - 1 System: Core Spray l
l Valve: MOV-033A,B Category: A Class: 1 Function: Core spray injection line motor operated valves.
l ASME Section XI Ouarterly Test Requirements: Exercise and time, i 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 t
l Quarterly Part Stroke Testing: NA l
Shutdown Testing: Exercise and time.
FORM # NES-24712/82
l Document No. 80A2903 Rev 3 Pace III-9-6 of III-9-7 /h Relief Request
[ T RR - 1
\~/
System: Core Spray Valve: AOV- 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 p,ressure 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 I 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 down-stream manual valves and use a special test rig. Entry into the inerted drywell is pre ~cluded 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 first refueling.
Alternate Testing: The presently installed test. operators provide approximately 25%
open stroking. An investigation is being performed to determine 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 clsoure will be performed at the first refueling. Subsequent to the above modifications, forward flow operability and reverse flow closure will be verified during
("') cold shutdown.
'u d NUCLEAR ENERGY SERvtCES. NC.
)
DOCUMENT NO. 80A2903 Rev 3 H E . %e NUCLEAR ENERGY SERVICES. INC. PAGE III-9-7 OF TTT-9-7 b l t}
V REUEF REQUEST' RR - 2 System: Core Spray Vah: 0018A,B Category: C Class: 2 Function: Loop level injection line check valves to core spray system.
ASME Section XI Quarterly Test Requirements: verify reverse flow closure.
Basis for Relief: Loop level piping configuration precludes verification of reverse flow closure.
Alternate Testing: Design changes are presently under consideration to either trodify
[
the loop-level piping configuration or to modify the valves 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 l operability will be verified by a system check to verify system I
water inventory.
l l
FOmd # NEs-24612/82
. _ . - . . - , . - . - . . . .. .- - , ~ - . . ~ . . - . - - , - . . .
? Document No ' 30A2903 Rev. 3 -
4 i: '
l' i
4 s
1 PUMP AND VALVE INSERVIG TESTING PROGPAM PIAN WR
!~ SIlOREHAM NUCIEAR POWER PIANT 4
UNIT NO. 1 4
4 I
SECTICN III LO 4
^ * " " '
i.
. VALVE 'IEST TABIES AND PTT.TFF REQUESTS i
WR MSIV IIAKAGE CCNTROL (E-32) .
- OWG.~NO. EM-69A 4
i 2
i 4
4 4
.).
k '
i 1
1 t
- 01 i
1 III-10-1
.anun esennov saavces. sec.
- x. -.
SYSTEM mrv f rAKrCP mm(V. fi -m -
WALVE TEST TABLE FM-69A III- 2 III-l -6 DM NO. DOCUMENT NO. J0A2903 IOv 4 PAGE OF STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK JUST. OR M NO. AND WLLVE (W) ACTti NORM TEST VALVE REMARKS REV AND OR ALT.
DwG. CAI AND TYPE POSII REO- TIME TEST RELIEF TEST COOR. TYPE DIRECT REO.NO. PERF.
(SEC.)
FtW-021A 1 A l\ FU C Ur-Q C CS-1 Ur-C b D-4 CL ST-Q 7.5 CS-1 ST-C IJ-R etN-02111 ,,
1 u-4 A 15 CL FO C Ur-Q Sr-o C
7.I m-1 m-1 I?r-C Sr-C g
IJ-R FEN-021C 1 E-2 A l\
6.5 G- 1 CS-1 F.T-C SP-C g
IJ-R F1N-021D 1 A 1 FO C Ur-Q C CS-1 I"r-C E-3 CL SP-Q 7.0 CS-1 SP-C IJ-R FEN-022A 2 B l\ on C Ur-Q O D-4 CL SP-O 7.8 d
FEN-022B 2 8 l\ FU C Ur-Q O D-5 CL SP-Q 7u d etN-022C 2 B 1 FD C CP-O O E-2 CL SP-O 7.9 g
NE S #244
V(% -
O^s O MSIV 11 AKNE CENrin, (L:-32) VALVE TEST TABLE SYSTEM:
TM-69A DOCUMENT NO. 80A2903 Ihv 4 PAGE III-10-3 OF III-10-6 M NO.
STROKE C.S. C.S.
CLASS SIZE DIRECT, CHECK JUSI OR AND VALVE (H) ACTU NORM TEST REMARKS REV VALVE NO. AND VALVE OR ALI DWG. CAI AND TYPE POSII REO. TEST NO.
TIME RELIEF TEST COOR. TYPE (SEC.) DIRECT REO.NO. PERF.
nN-022D 2 B 15 FO C LT-O O A 73 LU E-3 GL ST-Q nN-023A 2 B 15 FO C LT-Q UO O d C-6 GL SP -Q MN-023B 2 D-6 B 1 GL FO C LT-O SP-Q O
7.9 d
MN-023C 2 B 15 M) C LT-O O b G-6 GL ST-Q 7.8 M N-023D 2 B 15 FO C LT-Q O F-6 CL ST-Q 8.0 MN-024 2 B 2 FO C LT-O O CS-2 LT-C C-4 GL SP-Q 7.6 CS-2 ST-C MN-025 2 C-5 B 2 n) C UT-Q O 7.0 d
GL CP-O NE S s244
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DOCUMENT NO.
80203 h2 PAGE III-10-5 OF III-10-6 NUCLEAR ENERGY SERVICES. INC.
COLD SHUTDOWN TEST JUSTIFICATION CS - 1 ,
System: MSIV Leakage control Valve: MOV-021A,B,C,D Category: A Chu: 1 Function: Upstream bleed line isolation valves.
ASME Section XI Quarterly Test Requirements: Exercise and time.
O, Cold Shutdown Test Justif' cation:
. Valves are interlocked to main steam line pressure and cannot be opened at pressures greater than 35 psig. The interlock precludes inadvertent steam discharge.
I i
l Quarterly Part Strom Testing: NA O Ca Shutdown Testing: Exercise anc' time.
FORM e NEs-24712/82
i i
J 80A2903 Rev 2 DOCUMENT NO.
11
- NUCLEAR ENERGY SERVICES, INC.
PAGE III-10-6 OF III-10-6
. [v)
COLD SHUTDOWN TEST JUSTIFICATION CS - 2 System: MSIV Leakage control Valve: Mov-024 : Mov-026 Category: B Class: 2 Function: Downstream bleed isolation valve (MOV-024)
Downstream depressurization branch line isolation valve (MOV-026)
ASME Section XI Quarterly Test Requirements: Exercise and time O
Cold Shutdown Test Justification: Valves are interlocked to main steam line pressure and cannot be opened at pressures greater than 35 psig. The interlock precludes inadvertent steam discharge.
Quarterly Part Stroke Testing: NA Cold Shutdown Testing: Exercise and time.
FORM # NEs-24712/82
V. ,
Document No. 80A2903 Rev. 3 PLNP AND VALVE INSERVICE TESTING PROGRAM PIAN EUR SHOREHAM NUCIEAR POWER PIANT UNIT NO. 1 SECTION III ATTACINENT 11 VALVE TEST TABIES AND RELIEF REQUESTS FOR HPCI (E-41)
DWG. NO. EM-25 A,B i
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CLASS SIZE DIRECT. CHECK JUST OR yALVE NO. AND VALVE (N) ACTti NORM TEST AND VALVE REMARKS REV OR Alt DWG. CAI AND TYPE POSIT REO. TEST O.
TIMei RELIEF TEST COOR. TYPE DIRECT REQ.NO. PERF.
(SEC.)
MN-031 2 B 16 :D O LT-Q C b F-8 CP ST-O 55.2 MN-036 2 A 4 70 C LT-Q O D-6 CL ST-Q 10 LJ-H MW-032 2 A 1(> FO C LT-Q C D-8 CP ST-O 67.0 IJ- R MLN-04 3 2 G-6 B 10 CP FO C LT-O ST-Q O
15.8 d
MN-0 35 1 B 14 FO C LT-Q G b E-5 CP ST-Q 20.4 M N-042 1 D-4 A 10 CP 70 C IT-Q ST-Q C
14.9 g
L1-R 0001 2 C 16 SA -
!?P-Q F F-8 C
- Ness 244
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III-II'3 111-11-12 g IH-25A NNT NO 80A2903 lev 4 PAGE OF STROKE C S. C.S.
CLASS SIZE DIRECT. CHECK JUSI OR AND WEVE ACTti NORM TEST og REMARKS REV yhtVE NO. (IN ) AND WALVE Att CAI AND TYPE POSII REO. NO.
DWG. M TEST REUEF TEST COOR. TYPE (SEC.) DIRECT REO.NO. PERF.
0002 2 C 16 SA -
LT-O P RR-3 Valve will le [ art strohx1 gen D-8 C <purterly usity; dirnin. water arut tostrearn arwi (kwtest taps.
0012 2 C 4 SA -
LT-O P E-6 C 0013 2 C 14 SA -
C.'-O P E-5 C 0021 2 AC 18 SA -
LT-O LT-O P
R RR-1 ET-R g
D-5 C IJ-R AC 18 SA LT-O P Verify forward flow qcrability 0022 2 -
D-5 C 17-0 R RH-1 LT-P quarterly during pzrp test. Verify IJ-R reverse flow closure at refueling during A[p. J, Ty[e C testiruj.
Mar-037 2 B C F0 C LT { C P-5 CL ST-O 55.6 g F0V-041 1 A 10 to O 17-0 C C-4 a. ST1 20.3 A I.1-R 4D 96 $ m244
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- S g !!IGi PM.SSult. 000LRTr IMJILTIQ4 (E-41) VALVE TEST TABLE g g, FM-25A DOCUMENT NO. 80A2903 IW 4 PAGE III-II~4 OF III-ll-12 STROKE C.S. C.S.
CLASS SIZE DmECT. CHECK JUSI OR M NO. AND WALVE (M) m NORM TEST AND WALVE OR alt REMARKS REV NO.
DWG. CAI AND TYPE POSII REG w TEST RELIEF TEST N TYPE (SEC.) DMECT REO.NO. PERF.
MOV-047 1 C-4 A 1 MO O LT-Q C 16.4 h
a ST-Q IJ-R MN-048 1 C-4 A 1 m O LT-Q SP-Q C
16.9 d
cL IJ-R NN-081 2 11- 7 B 1 cp AO O LT-Q SP-Q C
10.0 d
IS-Q NN-082 2 Il-7 B 1 N) O LT-Q ST-Q C
10.0 g
cr FS-Q nN-044 2 C-5 A 18 m O LT 4 ST-Q C
103.5 d
GT IJ-R MN-049 2 A 2 m O LT-Q C A C-5 CL ST-O 18.7 lh IJ-R 0023 2 C 2 SA -
LT-Q F Mt-4 Valm to 11- disass(sibled arul visually g D-5 C IT-Q R RR-4 inspucted durinJ refueliruj outajes.
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- g. lilGI PidSSUIC CUGRtr IrLIILTIQ4 (E-41) VALVE TEST TABLE gg EM-25A DOCUMENT NO. 80A2903 fint4 PAGE III-l1-5 op III-11-12 STROKE C.S. C.S.
CLASS SIZE DIRECT CHECK JUSI OR AND VALVE (M) ACTL1 NORM TEST VALVE REMARKS REV m NO. AND OR Alt DWG. CAI AND TYPE POSII REO- TEST NO.
TIME RELIEF TEST COOR. TYPE DIRECT. REO.NO. PERF.
(SEC.)
0024 2 C 2 SA -
LT-O F RR-4 Valm to le disassabled ark! visually b I)-5 C LT-Q R RR-4 insinstax! duri1x3 retuulirw) outajes.
NN-034 2 B 1; tu o LT-Q O 55.4 g
E-4 cr Sr-Q 0019 2 C 2 SA -
IT-O F Forward flaw qerability if wrified F-3 C 1.T-Q R RR-5 tsy a systm cluck to wrify water inwntory.
0018 2 C 2 SA -
IT-Q F Formrd flcw qerability i.. veri fiel F-3 C t.;y a systs check to wri fy water inwntory.
M W-038 2 B 10 tu C I?r-O C 43.4 g
11- 5 cr Ur-O M S s244
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- p. IIIGi PlasSUIC GXXRfr IPU0CTIOJ (E-41) \ALVE TEST TABLE peg no, iW2% DOCUMENT NO. 80A2903 Fev 4 PAGE III-ll-6 og ITT-ll-12 STROKE C.S. C.S.
NS8 E DIRECT. CHECK JUSI OR AND M (N) ACT11 NORM TEST REMARKS REV MALVE NO. AND VALVE OR ALI DWG. CAI AtJD TYPE posit REO. NO.
TMAE TEST RN TEST N M (SEC.) DeRECT REO.NO. PERF.
NN-039 2 D-5 8 2 GL FO C LT-Q ST-Q O
21.4 A
IKW-051 2 !! 10 LIYD C LT-Q !!rCI turbine throttle and stqi 11-2 Cr ST-Q RR-2 valm.
IKW-052 2 B 10 t h'D C IT-Q IIICI turbirms control valw.
G-2 Cr ST-Q ide2 IW-145 2 C 3/4 SA -
SleP C-7 R 0007 2 C 2 SA -
LT-Q F C-5 C 0011 2 C 2 SA -
LT-Q F D-7 C NN-083 2 13 1 AO C fT-Q C b F-7 Cr ST-Q lO 13D NE $ s244
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80A2903 Rev 4 DOCUMENT NO.
NUCLEAR ENERGY SERVICES. INC. PAGE III-ll-8 OF III-ll-12_
(q_)
REUEF REQUEST RR - 1 System: HPCI Valve: 0022 : 0021 Category: AC Class: 2 Function: Containment isolation simple check valves (reverse flow closure for containment isclation 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.
4 Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C tecting at refueling.
O ro . . . ..s ,...
DOCUMENT NO. 80A2903 Rev 3 NUCLEAR ENERGY SERVICES. INC. PAGE III-ll-9 OF III-ll- 12 /3\
O RELIEF REQUEST RR - 2 System: HPCI Valve: HCV-051 : HOV-052 Category: B Class: 2 Function: HPCI turbine throttle and stop and control valves.
ASME Section XI QuarterfyTest Requirements: Measure stroke time.
b v
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 position is steam line pressure and turbine speed dependent and thergfore will not repeatedly throttle to the same position. During turbine operation these valves move in response to control signals.
Alternate Testing: Proper operation of these valves will be verified during turbine test. No stroke time testing will be performed.
O FoMA 8 NEs-24412/92
DOCUMENT NO.
1
- NUCLEAR ENERGY SERVICES, INC. PMIE III-ll-10 op III-ll-12 d o
N.]
REUEF REQUEST '
RR 3 System: HPCI yaw. 0002 Category: C Chu: 2 Function: Suppression pool suction line to pump check valve.
ASME Section XI Quarterty Test Requirements. Full flow forward flow exercise.
o Basis for Relief: The 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 pool 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 l
after testing which would over burden the radwaste system. The valve can be partial stroke exercised by injecting demin. water l at the upstream test tap and verifying partial valve opening at the downstream test tap.
Altemate Testing: 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 modificetion is possible the valve will be modified during the first refueling and a full exercise test performed quarterly. During the interim the valve will be partial stroke exercised quarterly using demin, water.
b Fonte e MS-24412/82
OA2903 Rev 4 DOCUMENT NO.
HEL%m NUCLEAR ENERGY SERVICES, INC. PAGE III-ll-ll OF III-11-12 RELIEF REQUEST RR - 4 System: HPCI Valve: 0023 : 0024 Category: C 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 Quarterly Test Verify forward flow operability and reverse flow closure.
Requirements:
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 g
operability is by disassembly and visual inspection or valve inte rnals.
p s
l l
I l
i Alternate Teeting: Valves will be disassembled and visual inspection of valve internals will be performed during refueling.
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my DOCUMENT NO. 80A2903 Rev 3 NUCLEAR ENERGY SERVICES, INC. PAGE III-11-12 op III-11-12
,o REUEF REQUEST RR - 5 System: HFCI h: 0019 M*90fY: C Class: 2 Function: Mop level injection line check valve to HPCI system.
ASME Section XI Quarterly Test Requirements: Verify reverse flow closure.
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.
Alternate 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.
O
,o.. _
Document No. 80A2903 Rev. 3 LO PtNP AND VALVE INSERVICE TESTING PROGRAM PIAN FOR SHOREHAM NUCIEAR PNER PIANT UNIT NO. 1 SECTICN III ATF10NENT 12 10 -uErESrr=zS- - -
EUR BCIC (E-51)
, DWG. NO. EM-22 A,B l
l l-l I
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FO X"IOR ODif: ISOIATICN (XOIJfC (E-51) VALVE TEST TABLE IN-22A 8 W 903 Ihv 4 III~ ~ ~
gg DOCUMENT NO. PAGE OF STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK M. OR VALVE NO. AND VALVE (N) ACTu NORM TEST AND VALVE REMARKS REV OR ALT.
DWG. CAI AND TYPE POSII REQ. TIME TEST RELIEF TEST NO.
N WPE (SEC.) DIRECT- REO.NO. MRF.
nN-042 1 A 3 MD C LT-O C 17.9 g
D-3 Cr ST-Q IJ-R nN-031 2 G-8 B 6 Cf PO O IX-Q ST-O C
30.3 d
nN-032 2 A 6 FO C 1"P-Q C D-8 CP ST-9 u-R 29,7 d MN-036 2 A 2 FO C IX-Q O E-6 CL ST-Q IJ-R 6.3 h nN-037 2 B 4 to C LT-O C P-S GL ST-O 40.6 A nN-o3s 1 B 6 on C Ix-o o t>-4 Cr ST-o 16.0 A nN-04 3 2 B 3 on C 17-0 O G-6 Cr ST-Q l8.6 NFS#744
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- g. REACIOR CORE ISOLATION OXXJNG (E-SI) VALVE TEST TABLE FN-22A DOCUMENT NO. 80A2903 Ibv 4 PAGE III-12-3 op 111-12-11 N NO.
STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK JUST. OR AND VALVE (R) ACT11 NORM TEST REMARKS REV WuYE NO. AND VALVE OR ALI DWG. CAI AND TYPE POSII REO. 7.ME TEST RELIEF TEST NO.
N TYPE (SEC.) DIRECT. REO. NO. PERF.
0001 2 C 6 SA -
LT-Q F F-8 C 0002 2 C 6 SA -
!?P-Q F RR-3 Valve will be part stroked gen D-8 C 4turterly using cknin. water and tpstream arul ckwtstream test taps.
0012 2 C 4 SA -
LT-Q F Verify forward flw quarterly during [onp E-5 C LT-Q R RR-1 LT-R test. Verify reverse flw closure at tv- b IJ-R fteling during A[p. J, Type C testing.
LT-Q F Verify forward flw qcrability D-5 C LT-Q R RR-1 l'P-R ytarterly during psa) test. Verify IJ-R reverse flw closure at refueling during A[p. J, Type C testing.
0022 2 C 1g SA -
LT-Q F RR-4 VaIvo to tx2 disass staled and visually g D-5 C LM R RR-4 inspoted during refueling mtages.
0023 2 C Ig SA -
LT-Q F RR-4 Valve to to disassentiled armi visually D-5 C LT-Q R RR-4 inspected during refueling mtajes. d NE S a244
7 p (~
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r SYNTEM:
REJCIOR ODRE ISOIATIO4 COOLIto (E-51) VALVE TEST TABLE f
DwG. NO.
m-22A DOCtMENT NO. 80A2903 R>v 4 PAGE YYY-1?-4 op ri1-i9_ii STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECM JUSI OR AND VALVE (M) ACTti NORM TEST REMARKS REV VALVE NO. AND VALVE OR ALI DWG. CAI AND TYPE POS11 REO. NO.
UME TEST REMF TEST COOR. TYPE (SEC.) DIRECI REO.NO. PERF.
LT-Q P Verify forward flow operability IF-6 C LT 4 R RR-1 LT-R quarterly during prp test. Verify IJ-R reverse flow closure at refmlirq durirq Igy. J, lyle C testing.
0024 2 C 2 SA -
LT-Q F E-6 C
. NN-041 1 A 3 Fu O LT-Q C b C-3 GT ST-Q 18.8 IJ-R MOV-047 1 A 1 m O LT-Q C 16.6 g
C-3 GL ST-Q IJ-R MN-048 1 A 1 PD O LT-Q C D-3 CL ST-Q 15.6 -8 IJ-R MOV-034 2 B 4 m O LT-Q O E-5 GT ST-Q 22.8 FDV-045 2 A 8 to O LT-Q C C-5 Cr ST-Q IJ-R 49.2 g NFS s244
pm n 7- ,
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SYSTEM.
RLJCIOR QMC ISOIATIG4 000LItsi (E-51) VALVE TEST TABLE gg IN-22A DOCUMENT NO. 80A2903 lbv 4 PAGE 111-12-5 op I11-12-11 STROKE C.S. C.S.
. CLASS SIZE DIRECT. CHECK JUSI OR AND WALVE (R) ACTLL NORM TEST VALVE REMARKS RW MALVE NO. AND OR ALT.
DWG. CAT. AND TYPE POSII REQ. TEST NO.
TIME RELIEF TEST COOR. TYPE OtRECT. REO.NO. PERF.
(SEC.)
MOV-049 2 A l\ MO O f*P-Q C 17.7 g
C-5 GL DrK)
L1-R 2 C SA LM P tbrward fl w q erability is w rifits!
0015 1 E-4 C I!r-O H tr/ a systen ctmk t.o wrify water inwnt ory. Tbverse fl w closure is verifits! by absence of flw at relief valw IN-149 duriry gap test .
0016 2 C 1 SA -
IN'-Q F Porward flw q erability is verified C-4 C by a system ctock to wrify water inwntory.
17P-0 P Forward flw gerability is verified d
D-6 SC 50 O l'IN C R during turbine test. Irrverse closum SP-Q 13.1 is verified using gositive closure LJ-R rotor gerator.
NN-081 2 H I M O I?r-O C 10 g
11- 7 Cr ST-Q IS O NN-082 2 B 1 GT m O I'r-O C g Il-7 SP-O 10 FS-O
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NFS 5744
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SYSTEM:
14)CIOR COIE ISOIATIO4 CODIJNG (E-51) VALVE TEST TABLE DOCUMENT MO.
80A2903 Itzv 4 PAGE 111-12-6 OF III-12-Il DWG. NO. FN-22H STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK JUST OR AND Ware (in) ACTu NORM TEST REMARKS REV VALVE NO. AND . VALVE OR ALT.
DWG. CAI AND TYPE POSII REO. TIME TEST REUEF TEST COOR. TYPE DIRECT REO.NO. PERF.
(SEC.)
nN-038 2 D 2 FD C LT -O O A D-5 GL ST-0 19.6 FIN-044 2 B 3 FO O LT-Q ICIC turbine throttle and sttp valve.
G-3 CT ST-Q Rit-2 IKN-051 2 B 3 ffYD 0 ET-Q ICIC turbine goveming w.lve.
G-3 Gr Sr-Q Rit-2 0006 2 C 2 SA -
LT-O P F-6 C 0008 2 C 1 SA -
LT-Q P Forward flow operability,is verified B-5 C by a system check to verify water inventory.
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DOCUMENT NO. 80A2903 Rev 4 mur NUCLEAR ENERGY SERVICES. INC. PAGE III-12-8 OF III-12-ll o REUEF REQUEST RR - 1 System: RCIC
%. 0021 : 0025 : 0020 b Category: AC Class: 2 Function: Containment isolation simple check valves (reverse flow closure for containment isolation only).
k 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 I
i l Altemate Testing: Reverse flow closure will be verified during Appendix J, Type C testing at refueling.
I n
U Fome # NES-24412/82
80A2903 Rev 2
, DOCUMENT NO.
= " " NUCLEAR ENERGY SERVICES, INC. PAGE III-12-9 OF III-12-ll G
REUEF REQUEST
- RR - 2 System: RCIC Vah. MOV-044 : HOV-051 Category: B Cau: 2 Function: RCIC turbine throttle stop and governing valves.
ASME Section XI Quarterly Test Requirements: Measure stroke time.
nv Basis for Relief: The purpose of these valves is to regulate steam flow to the RCIC turbine. Operability is adequately demonstrated by proper turbine operation. Valve position is steam line pressure and turbine speed dependent and therefore will not repeatedly throttle to the sarae position. During turbine operation these valves move in response to control signals.
i Alternate Testing: Proper operation of these valves will be verified during turbine test. No stroke time testing will be performed.
l l
t l
O l FOMI 8 NES-24412/82 r
, DOCUMENT NO. 80A2903 Rev 2 NUCLEAR ENERGY SERVICES, INC. PAGE III-12-10 OF III-12-ll V
RELIO: REQUEST RR - 3 System: RCIC Valve: 0002 Category: C Class: 2 Function: Suppression pool suction line to pump check valve.
ASME Section XI Quarterly Test Requirements: Full flow forward flow exercise.
O
(_)
Bans for Relief: The 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 pool
~
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 fitshing of the system after testing which would over burden the radwaste system. The i 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.
l Alternete 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 performed quarterly. During the interim the valve i will be partial stroke exercised quarterly using demin, water.
l l
t O
FomM e NES-24412/82
DOCUMENT NO. 80A2903 Rev. 4 m
" " PAGE III-12-ll op III-12-11
= NUCLEAR ENERGY SERVICES, INC.
fS O
REUEF REQUEST RR - 4 System: FCIC Valve: 0022 : 0023 Category: C Class: 2 Function: Vacuum breakers (forward flm) to preclude drawing water into the turbine exhaust line and to prevent steam (reverse flw closure) flw to the suppression pool air space.
Ouarterty Test Verify forward flw grrability and reverse flw closure.
Requirements:
r O
Basis for Relief: The system design has no test provisicns to allw for quarterly testing in either directicn. The mly method available to verify l
operability is by disassembly and visual inspecticn of valve internals.
p i
l Alternate Testing: Valve will be disassembled and visual inspection of valve l
internals will be perfonted during refueling. b l
l O i
l FORM e NEs-24411/82 1
Document tio. 80A2903 Rev 3 d PUMP NO VALVE INSERVICE TESTING PROGPMI PIAN FOR SIIOREllM1 NUCU%R POER PIANT LNIT NO. 1 SECTION III ATTACIDID7r 13 VALVE TEST TN3IIS NO RELIEF REQUESTS FOR RAEW\STE EQUIPMOTP (G-ll)
- 30. NO. D1-46 A,8 f
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DOCUMENT NO. 80A2903 Fev 2 m
" " NUCLEAR ENERGY SERVICES, INC. PAGE III-13-3 OF III-13-4 REUEF REQUEST RR 1 System: Radwaste Valve: 2110C Category: AC Class: 2 Function: Containment isolation simplc check valve (reverse flow closure for containment isolation only).
ASME Section XI Quarterly Test Requirements: Verify reverse flow closure.
l 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 l testing at refueling.
l l
l O
FORM e Ms-24412/82
DOCUMENT NO. 80A2903 Rev 2 my
- " PAGE III-13-4 op III-13-4 NUCLEAR ENERGY SERVICES. INC.
l U
RELIEF REQUEST RR - 2 System: Radwaste y.g. 2110C Category: AC Class: 2 Function: Leakage return pump discharge line containment isolation valve.
ASME Section XI Quarterly Test Requirements: Verify forward flow operability.
O 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 pcor 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.
l Alternate Toding: Verify forward flow operability at refueling.
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rORM # NES-24412/02 4
Document No. 80A2903 R;v. 3 PUMP NJD VALVE INSERVICE TESTING PPJ0 GRAM PIAN FOR SHOREHAM NUCIIAR POWER PIAvr UNIT NO. 1 SECTIO 1 III ATTACHMENT 14 s
VALVE TEST TABIES NJD RELIEF REQUESTS FOR REACIOR WATER CLEN4LP (G-33)
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ar PAGE III-14-3 OF III-14-3 NUCLEAR ENERGY SERVICES, INC.
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RELIEF REQUEST RR - 1 System: Peactor Water Cleanup Valve: 0036A,B : 0050A,B Category: C Class: 1 Function: System isolation ASME Section XI Quarterly Test Fvauirements: Verify reverse flow closure.
O Basis for Relief: Valves are located in the main steam tunnel which is inaccessible during rormal 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.
Alternate Testing: Reverse flow closure will be verified at refueling when entry to the main steam tunnel is possible.
l l
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l FORM e NEs 24412/8.
Document No. SOA2903 Rev. 3 PLMP MiD VALVE INSERVICE TESTIIC PPOGPM PIR4 FOR SHORElW1 NUCLEAR POLCR PIRE UNIT NO. 1 SECTICN III ATr/ CIDER 15 VALVE TEST TABIES N1D RELIEF REQLU7FS FOR FUEL POOL COOLING NJD CLEl&'P (G-41)
DU. NO. D1-19A "x
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m DOCUMENT NO. 80A2903 Rev. 4 NUCLEAR ENERGY SERVICES. INC. PAGE III-15-4 OF 111-15-4
\j REUEF REQUEST' RR - 1 System: Spent Fuel Pool Cooling Valm: OfV-0003A,B
' ate, ory: C Class: 3 Function: Fuel Pool Cooling pump discharge check valve.
ASME Section XI /4\
Quarterty Test Full flow forward flow exercise.
Requirements:
b) v Basis for Relief: Relief Request 1, for the Spent fuel Cooling pumps C41-P023A and B, delays pump testing until the first refueling outage. Since the pump discharge check valve cannot be tested, unless the pump is run, and the pumps are to be maintained out of service until the first
. refueling outage, the check valves should not be tested until then.
Alternate Tooting: Begin full flow forwatd flow exercise testing at the first refuel outage.
(vD rom e us.24e tdes
Docum_nt No. 80A2903 Pc,v. 3 g
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CLASS SIZE DIRECT. CHECK JUSI OR AND MLVE (IM) ACTH NORM TEST VALVE REMARKS REV M Na AND OR ALT.
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0020 3 C-6 C 20 C
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m) F A-6 C 0010B 3 C 16 SA -
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CLASS SIZE DIRECT CHECK JUSI' OR AND W4LVE (M) ACT11 NORM TEST UnufE REMARKS REV M NO. AND OR ALI DWG. CAI AND TYPE POSII REQ. TEST NO.
TIME RELIEF TEST COOR. TYPE (SEC.) DIRECI REO.NO. PERF.
MG/-129A 3 B-3 B
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35.4 g
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EP-Q P Verify forward flw operability quarterly.
I-3 C UP-Q R RR-1 ET-R verify rumise flw closure at rufmling by A disassembly and vism1 inspection of valve intemals.
OO32B 3 C 10 SA -
P Verify forward flw qerability quarterly.
I-3 C R RR-1 ET-R verify ruwrse flw closure at refueling by A disassably and visual inspectial of valm internals.
OO33A 3 C 10 SA -
I?P-Q P Verify forwant flw gerability quarterly. g I-3 C ET-Q R RR-1 ET-R verify reverse flw closure at ref wling by cu disassepbly arul visual inspecticn of valve internals.
0033B 3 C 10 SA -
LT-Q P Verify forward flw qerability quarterly. 3 I-3 C R RR-1 ET-R verify rewrse flw closure at rufueling by til ET-Q disassenbly and visual insicctim of valm intemals.
0034A 3 C 8 SA -
T -Q E. P Verify forward f1w qerability quarterly.
J-3 C UP-Q R RR-1 ET-R verify reverse fim closure at refmling by d disassenbly arxl visual inspecticn of valve intemals.
NF S s?44
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SYSTEM- SiilNUl: WA'll:34 (P-411 VALVE TEST TABLE N NO. Wi-47A DOCUMENT NO. WV2903 IOV- 4 PAGE III-I7-9 OF III-I7-IO STROKE C.S. C.S.
CLASS SIZE DIRECT CHECK JUST OR AND VALVE (IM) ACT11 NORM TEST REMARKS REV VALVE NO. AND VALVE OR ALI DWG. CAT. AND TYPE POSIT REQ- TEST NO.
TIME RELIEF TEST N TYPE (SEC.) DIRECT REO.NO. PERF.
0034B 3 C 8 SA -
110 1 F Verify forward flw qerability quarterly.
K-3 C LT-O R l*-1 ET-R verify reverse flw closure at aufmliry by A disassenbly and visual insloctim of valve internals.
OD35A 3 C 8 SA -
LT -O F Verify forward flw q erability quarterly.
J-3 C LT 1 R ltR-1 ET-R verify reverse fim closure at refueling by A disassably and visual ins [cetim of valve intenuls.
0035B 3 C 8 SA -
LT-Q F Verify forward flw qerability quarterly.
K-3 C IT-Q R is-1 ET-R verify reverse flw closure at rufueling by A disassenbly and visual ins [(ctim of valve intemals.
NFS s244
m DOCUMENT NO. 80M903 Rev. 4_
" " " NUCLEAR ENERGY SERVICES, INC. PAGE III-17-lO OF III-17-lO N.
O REllEF REQUEST' RR - 1 System: Service Water Valve: OO32A,B : CO33A,B : OO34A,B : OO35A,B Category: C Class: 3 Function: b&tain water inventory in the riser to the RBSVS/CRAC Ccndensing Water Punps fcllowing loss of power.
ASME Section XI Quarterty Test Requirements: Verify reverse flcw closure, p
The cnly nethod available to verify reverse flow clmure is by dis-g Basis for Relief:
assenbly and visual inspecticn of valve internals. To perform such a procedure requires shutting down the associated Service Water train and draining the riser of water. This procedure would place the plant in a Technical Specification Limiting Ccmditicn for Operaticn (ICO) and/or would eliminate the redundancy of several safety-related systems if performed during nonnal operaticn or cold shutdown.
Alternate Testing: Reverse ficw closure will be verified by disassenbly and visual inspecticn of valve internals during refueling.
A
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FORM e NES 24612/82
. . . .. . _. -. .. . -- . = . - . .. .--
Document No. 80A2903 - Rev. 3 4
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l PLNP AND VALVE INSERVICE TESTING PROGRAM PIAN FOR SHOREHAM NUCLEAR POWER PLANT 2
LNIT NO. 1 r
i SECTICE III 3
ATTACHMENT 18 I
VALVE TEST TABIES AND PELTEP REQUESTS
. EUR ParTag (p-42)
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CLASS SIZE DIRECT. CHECK JUST OR AND WALVE (M) ACTu NORM TEST REMARKS REV m NO. AND WALVE OR ALT.
DwG. CAI AND PfPE posit REO. TEST NO.
DME REUEF TEST COOR. TYPE (SEC.) DIREC1 REO.NO. PERF.
FKN-032A 3 G-1 8 8 Cr FO O LT-Q ST4 C
09.9 d
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Cr ST-Q MN-034A 3 8 6 FD 0 13'-Q C A I-1 Cr STg 37.1 411 MN-0348 3 B 6 FO O LT-O C 11- 1 CP ST-Q 38.2 g FKN-042A 3 B 14 FO C LT-O o G-9 Cr ST-Q 78.5 b PIS N244
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SYSTEM. REtCIDR BIJU. CIfEFD IonP moiItn Wm'R (P-42) VALVE TEST TABLE l
g fM-15C DOCUMENT NO. 80A2903 Rev 4 PAGE III-18-6 op 111-18-16 STROKE C.S. C.S.
CLASS SIZE DIRECT CHECK JUSI OR AND M (M) ACTL1 NORM TEST REMARKS REV VALVE NO. AND VALVE OR ALI DWG. CAI AND TYPE POSII REO. NO.
M TEST RELIEF TEST COOR. TYPE (SEC.) D4 RECT REQ.NO. PERF.
FKW-035 2 E-6 A
21.1 CS-3 CS-3 LT-C Tr C g
IJ-R FIN-036 2 A-4 A
22.3 CS-3 G-3 1T-C ST-C g-IJ-R FKW-047 2 A 4 FO O LT-Q C CS-3 LT-C F-6 cr SP-O 21.9 CS-3 ST-c b IJ-R FtN-048 2 A 4 FO O LT-O C G-3 LT-C A J-4 cr ST-O 21.2 G- 3 ST-C Ln IJ-R NN-293 3 Ic 6 SA -
LT-O F Positiw closure stop dock valw.
A-4 SC AO O LT-O C R G-4 LT-C Air gerator usexl to test for 1 ST-O 10 CS-4 ST-C reverse closure.
NN-294 3 to 6 SA -
LT-O F Positive closure stop chmk valve.
K-4 SC AO O LT-O ST-O 10 C R CS-4 CS-4 ET-C ST<
Air operator used to test for rewrse closure.
d NFS5744
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$YSTEM: Mm b!Iri. Clam tire autIn le1T:R (P-42) VALVE TEST TABLE DWG. NO. FB-23B DOCUMENT NO. 80A2901 ry.v4 PAGE III-I8-9 OF III-IH-Ih STROKE CS CS M SS SIZE DIRECT. CHECK JUST. OR VALVE NO. AND VALVE (IN) ACTU NORM TEST AND VALVE OR ALI REMARKS REV DWG. CAT AND TYPE POSIT REO TIME TEST NO.
RELIEF TEST COOR. TYPE (SEC ) DRECT REO NO PERF 0037/c 2 A-5 AC 3 C
SA -
17-0 IJ-R R' FP-1 IT-R System T-47 b 0037AD 2 A-6 AC 3 C
SA -
IT-Q IJ-R R HP-1 IT-R System T-47 b 0037DA 2 L-2 AC 3 C
SA -
LT-Q IJ-R R FF-1 IT-R System T-47 b 0037m 2 L-4 AC 3 C
SA -
LT-o IJ-R a PR-1 tT-R System T-47 b 00371C 2 L-5 AC 3 C
SA -
LT-Q IJ-R R PR-1 LT-R System T-47 b 003700 2 tr6 AC 1 C
SA -
IT-Q IJ-R R FR-1 LT-R System T-47 b IN-291A 2 AC 1 SA -
IJ-R W-rm i relief valve. Ag g e. .I ,
A-1 R h p. e tent rally.
NE S 5244
V . _
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6 _
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E N. 2 T G s S S Y W d S D E
Docunent No. 80A2903 Rev. '4 Page III-18-ll' of III-18-16
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DOCUMENT NO. 80A2903 Rev 2 PAGE III-18-12 op III-18-16 NUCLEAR ENERGY SERVICES, INC.
O COLD SHUTDOWN TEST JUSTIFICATION CS - 2 System: RBCLCW Wlve: AOV-282 Category: BC Class: 3 Function: Return isolation check valve.
ASME Section XI Quarterly 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 averheat and cause a possible plant shutdown.
l
! Quarterly Part
! Stroke Testing: Valve is a full stoke only valve and cannot be partial stroke l exercised.
1o Shutdown Testing: Exercise, time and fail.
FORM e NEs-24712/82
80A2903 ,Rev 2 DOCUMENT NO.
PAGE III-18-13 OF III-18-16 NUCLEAR ENERGY SERVICES, INC.
7_
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COLD SHUTDOWN TEST JUSTIFICATION CS - 3 System: RBCLCW Velve: MOV-035 : MOV-036 : MOV-047 : MOV-048 Category: A Chu: 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.
Cold Shutdown Test Justification: To test these valves would require interruption of cooling water to the recire. 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.
I i
l l Quarterly Part l Stroke Testing: Valves are full stroke only valves and cannot be partial stroke l exercised.
, Cold l Shutdown Testing: Exercise and time.
FOMI # NEs-24712/82
DOCUMENT NO. AnA?9n1 pnsr >
PME III-18-14 op III-18-16 7s NUCLEAR ENERGY SERVICES. INC.
COLD SHlfrDOWN TEST J'JSTIFICATION CS - 4 System: RBCLCW Valve: AOV-293 : AOV-294 Category: BC Chu: 3 Function: Isolate non-essential cooling loads during a IDCA.
ASME Section XI Quarterly Test Requirements: Exercise and time.
(qJ 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 t
addition, failure of these valves to reopen could cause damage
( to equipment being cooled.
l
( Ouarterly Part l
Stroke Testing: Valves are full stroke only valves and cannot be partial stroke exercised.
l Shutdown Testing: Exercise and time.
l FONI e NEs-24712/83 1
DOCUMENT NO. 80A2903 pnv 2 e
III-18-15 op III-18-16 mW NUCLEAR ENERGY SERVICES, INC.
PAGE O
COLD SHUTDOWN TEST JUSTIFICATION CS 5 System: RacLcw Valve: MOV-147 : MOV-148 : MOV-231 : MOV-236 Category: A Chu: 2 Function: Drywell cooling water supply and return containment isolation valves.
ASME Section XI Quarterly 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.
l l
l l
l l
l l
Quarterly Part i Stroke Testing: Valves are full stroke only valves and cannot be partial stroke exercised.
I o C.
Shutdown Testing: Exercise and time.
i FOMA # NEs-24712/02
my DOCUMENT NO. 80A2903 Rev 2 PAGE III-18-16 op III-18-16 NUCLEAR ENERGY SERVICES. INC.
RELIEF REQUEST RR- 1 System: RBCLCW Valve: 0037 AA,AB,AC,AD,BA,BB,BC,BD 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.
)
V Basis for Relief: The only method available to verify reverse flow closure is by l
valve leak testing during Appendix J, Type C testing at refueling.
i l
Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C testing at refueling.
l l
O FORM 8 NEs-24412/82 m ~ ~ - . -
Document No. 80A2903 Rev. '3 .
P ',
PLNP. AND VALVE INSERVIG TESTING PROGRAM PIAN FOR SHORE 2IAM NUCLEAR POWER PIANT i UNIT NO. 1 SECTICN III ATTAC11 MENT 19 i VALVE TEST TABLES AND PET.TFP REQUESTS i
A FDR
' . -V INSTRLNENT AND SERVIG AIR (P-50)
DWG. NO. EM-38 D,E t
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O O O INSlHM2TP NU GI3NIC1' AIn (P-50) M TEST M Na NE NNT NO. 80A2903 Rt v 4 m TTT-19-? w r r r t o r, STROKE C.S. C.S.
DM CT. CHECK WSt OR WhLVE NO. AND M (M) ACTu NORM TEST AND M OR ALI REMARKS REV DWG. CAT. AND TYPE posit REO- NO.
M TEST RN TEST (SEC.) N ECT. REa NO. PERF.
NN-104 2 C-7 A 1 GL Fo C LT-Q SM C
10.7 A
U-R FtN-106 2 A 1 F0 C LT4 C A 11- 7 GL SP-Q 10.0 411 U-R MOV-103A 2 A 15 FO O LT-Q C C-5 CL ST-Q 7.6 b U-R MW-103B 2 A l\ FO O LT-O P G-5 CL SP-Q U-R 0.3 d 0695A 2 AC l\ SA -
LT-O R RR-1 LT-R P-5 C U-R 06958 2 AC l\ SA -
LT-Q R RR-1 LT-R D-5 C U-R 0698A 2 AC 1 SA -
LT-Q R RR-1 LT-R 11- 7 C U-R b pdMe?44
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80A2903 Rev 4 DOCUMENT NO. -
H E L %m NUCLEAR ENERGY SERVICES, INC. PAGE III-19-5 Op III-19 5 O
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RELIEF REQUEST RR 1 System: Instrument and Service Air Valve: 0695A,B : 0603 0690A : 0698B : IC51-0867 b Category: AC Class: 2 Function: Containment isolation simple check valve (reverse flow closure for containment isolation only).
ASME Section XI Quarterly Test Requirements: Verify reverse flow closure.
Basis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C testing at refueling.
l l
Alternate Testing:
l Reverse flow closure will be verified during Appendix J, MeC testing at refueling.
l l
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Document No. 30A2903 Rev. 3 d
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PLNP AND VALVE INSERVIG TESTING PROGPAM PIAN FOR SHOREHAM NUCIEAR POWER PIANT UNIT NO. 1 SECTICN III ATTAGMENT 20 VALVE TEST TABIES AND RET.TFF REQUESTS FOR ETEL OIL TRANSFER (R-43)
DWG. NO. FM-44A-l T
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CLASS SIZE DIRECT, CHECK
. JUST. OR VALVE Na AND VALVE (M) ACTu NORM TEST AND VALVE OR ALI REMARKS REV DWG. CAL AND TYPE POSII REQ- TIME TEST Na RELIEF TEST COOR. TYPE (SEC.) DIRECT REO. NO. PERF.
0200A 3 C 2 SA -
LT-Q F C-8 C 0201A 3 C 2 SA -
LT-Q F C-8 C 0200C 3 C 2 SA -
LT-Q F C-6 C 0201C 3 C 2 SA -
LT-Q F C-6 C 0200B 3 C 2 SA -
LT-Q F -
C-5 C 0201B 3 C 2 SA -
LT-Q F C-5 C i
IN-025A 3 C 3/4 SA -
SR-P C-8 R I
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VALVE TEST TABLE EM-44A g g, 80A2903 fev 2 PAGE III-2b3 op III-2&4 STROKE C.S. ' C.S.
CLASS SIZE DMECT. CHECK JUSI OR M NO. AND W.VE (N) ACTLL h0RM TEST ANO VALVE OR ALI REMARKS REV DWQ. CAI AND TYPE POSII RCO. TIME TEST REUEF NO.
TEST COOR. TYPE
'(SEC.) DIRECI REO. NO. PERF.
RV-025B 3 C 3/4 SA -
SR-P C-5 R RV-025C 3 C 3/4 SA -
SR-P C-6 R RV-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
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SR-P E-8 R RV-099B 3 C 3/4 SA -
SR-P E-5 R NES s244
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' Document No. 80A2903 Rev.~ 3
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PUMP AND VALVE INSERVICE 'IESTI?C PROGRAM PIAN FOR SHOREHAM NUCLEAR POWER PIANT
^
UNIT NO. 1 SECTION III ATTACHMENT 21 4
VALVE TEST TABIES AND RPT.TPF REQUESTS FOR DIESEL GENEPA'IOR AIR START (R-43)-
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EM-44B IlE vAtve 1ES11ABtE g DOCUMENT NO. 8 903 Aw 2 PAGE III-21-2 op 111-21-4 STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK JUSt OR VALVE NO. AND VALVE (IN) ACTU NORM TEST AND VALVE REV OR ALI REMARKS DWG. CAI AND TYPE POSII REQ TIME TEST NO RELIEF TEST N. TYPE (SEC 3 OtRECT REO.NO. PERE 0209A 3 C 4 SA -
LT-O R F-7 C 0208A 3 C 4 SA -
LT-(J R D-7 C 0209C 3 C 4 SA -
LT-Q R F-4 C 020tlC 3 C 4 SA -
LT-O R D-4 C 0209B 3 C 4 SA -
LT-O R F-2 C 0208B 3 C 4 SA -
LT-O R D-2 C SV-034A 3 C 1 SA -
SR-P C-6 R NESe244
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gg IM-448 m gg 8QA2903 Rev 2 III-21-3 i!t-2I-4 NE op STROKE CS. C.S.
CLASS SIZE peRECT. CHECK . JJSt OR MuVE Na AND WM.VE (N) ACTu NORM TEST AND VALVE OR Att REMARKS RW DwG. CAI AND TYPE POSet REE TME TEST RELIEF TEST O.
COOR. TYPE (seq DIRECT 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 l SV-03it 3 C 1 SA -
SR-P G-4 R NES a244 e
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CLASS SIZE DIRECT. CHECK Just og whDIE NO. AND M (N) ACTL1 NORM TEST AND VALVE OR ALI REMARKS REV DWG. CAI AND TYPE POSII REO. TIME TEST RELIEF TEST NO.
COOR. TYPE DIRECT REO. NO. PERF.
(SEC.)
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-037B 3 C 1 SA -
SR-P G-1 R NES 5244
Documtnt No. 80A2903 Rev. 3 b
Q PWP AND VALVE INSERVIG TESTING PROGRAM PIAN
'FOR SHOREHAM NUCIEAR POER PIANT UNIT NO. 1 SECI'IN III ATI%CINENT 22
- VALVE 'IEST TABIES AND FFT.TFT REQUESTS FOR DRYWEIL FICOR SEAL PRESSURE MCNI'IORING (T-23)
DWG. NO. EM-55A F
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G- l PUMP AND VALVE. INSERVICE TESTING PROGRAM PLAN FOR' SHOREHAM NUCLEAR POWER PIAVP UNIT NO. 1 SECTICN III ATTACHMENT 23 VALVE TEST TABLES AND RET.TEP REQUESTS' FOR REACIOR BIDG. NORMAL VENT. (T-46)
DWG. NO. FB-23A i
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u0A2903 kv 2 PAGE 111-23-2 OF I I 3 '# I~4 STROKE C.S. C.S.
CLASS SIZE DIRECT. CHECK JUST OR WM3fE g AND VM3fE (N) ACTu NORM TEST AND VALVE OR ALI REMAFiKS REV DWG. CAI AND TYPE POSII REQ. TIME TEST RELIEF TEST COOR. TYPE DIRECT REQ.NO PERF.
(SEC.)
Ny-038A 2 A 18 AO C W H-8 B W-R ADV-038B 2 A 18 AO C W 11- 8 B W-R ADV-038C 2 A 18 AO C W
F-8 B W-R ADV-039C 2 A 18 AO C W H-8 B U-R NES 5244
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Document No. 80A2903 Rev. 3 g t.(
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e PLNP AND VALVE INSERVICE TESTING PROGPAM PIAN FOR SHOREllAM NUCLEAR POWER PIANT UNIT NO. l-t SECTION III ATTACHMENT 24 VALVE TEST TABLES AND P ETFP REQUESTS
. 7
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CLASS M DIRECT CHECK JUSI OR WLVE NO. AND WLVE (94) ACTu NORM TEST AND WLVE og att REMARKS REV DWG. CAI AND TYPE PoslI REa TueE TEST REUEF TEST Na COOR. TYPE (SEC) DIRECT HEO. NO. PERF.
SO/-126A 2 A 3/4 EM C ET 4 C F-3 Cr ST4 5 FS4 W-R Sov-1268 2 A 3/4 IN C ET-O C F-3 cr ST-O 5 IS-O W-R SO/-127A 2 A 3/4 EN C ET-O C C-7 Cr ST4 5 IS-O W-R StN-127B 2 A 3/4 EN C ET. -O C C-7 Cr ST-O 5 FS-O W-R SOV-128A 2 A 3/4 EM C ET-O C E-3 Gr ST-O 5 IS-O W-R SO/-1288 2 A 3/4. EN C ET-O C E-3 Cr ST-O 5 FS-Q U-R SCN-129A 2 A 3/4 Dt C ET-O C H-7 CF ST-O 5 FM U-R us s244
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STROKE CS. C.S.
N E DeRECT. CHECK JUSI OR AND M (R) M NORed TEST REIAARKS REV WELVE NO. ANO VELVE OR ALI DWG. CAI AND TYPE POSII REO- TEST NO.
TueE N TEST N M (SEC) DIRECI REO.NO. PERF.
SOV-129B 2 A 3/4 IN C LM C H-7 cr ST-O 5 PS-O W-R 50/- 130 2 A 3/4 IN C LT-O C b I-5 GT ST-O 5 IS-O U-R SOV-131 2 A 3/4 EN C LM C C-5 cr ST-O 5 FS-O U-R MOV-031A 2 A 6 to C ET-O C 29.1 g
F-5 or Sw U-R MN-031B 2 A 6 MD C L'r-O C E-5 Cr ST-O 23.1 M-R MN-032A 2 A 6 M) C L'r-O C F-6 cr ST-O 27.5 g W-R MM-032B 2 A 6 K) C LT-O C E-6 GT St-Q 27.9 g U-R I
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gg. PRIMARY CGTTAI!M2R KIMEPtERIC OL2frHfL (T-48) WALVE TEST TA8LE g g, EN-52A mg g 80A2903 Rev 4 III-24-4 III-24-12 PAGE OF STROKE C.S. C.S.
N M DIRECT. CHECK JUSI OR WMVE NO. AND WALVE (N) ACTti NORM TEST AND WALVE ALI REMARKS REV OR DWG. CAT. AND TYPE POSII REO. m TEST RELEF TEST NO.
m WPE (SEC) DIRECI REO.NO. PERF.
NN-033A 2 A 6 70 C LT-O C b F-6 GT ST-Q 29.0 IJ-R MN-033D 2 A 6 70 C LT 4 C E-6 GT ST-O 28.7 IJ-R MN-034A 2 A 6 to C LT-O C G-8 Cr ST-O 29.3 IJ-R MN-034B 2 E-8 A 6 GT 70 C LT-O ST-Q C
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gg EM-52A & IM-84A DOCUMENT NO. 80A2903 kw4 PAGE III-24-6 op III-24-12 ,
STROKE C.S. C.S.
CLASS SIZE DeRECT. CliECK JUSI OR g yo, AND WLVE (K) ACT11 NORM TEST MLVE REMARKS REV AND OR ALI DWG. CAI AND TYPE POSII REO- TM TEST REUEF TEST COOR. TYPE DIRECT REO.NO. PERF.
(SEC.)
LT-O R RR-1 LT-R 11- 5 C IJ-R O
LT-O R RR-1 LT-R C-5 C IJ-R NN-004A 2 A 4 to C 1T-0 C Systan 'l-24. LAaj. IN-84A.
D-8 CL gr-o ES4) 5 d IJ-R NN-004B 2 A 4 AO C LT-O C Systesn T-24. Dwg. FN-84A.
D-8 CL Sr-O FS-Q 5 b IJ-R M W-043A 2 C-5 B 4 Gr 70 C IT-Q ST-O O
28.8 g
MN-043D 2 D-5 B 4 Gr en C LT-O ST-O O
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MN-041 2 B 4 70 C t.T-O O 26.3 b
D-2 Gr ST-Q g l
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CLASS SIZE DIRECT CHECK JUSI OR gg AND VALVE (M) ACTit NORM TEST AND VALVE REMARKS REV OR ALT DWG. CAI AND TYPE POSII REO- w TEST RELIEF TEST COOft TYPE (SEC.) DIRECI REO.NO. PERF.
FEN-042 2 B 4 70 C LT-Q O b C-3 cr ST-Q 27.1 0004A 2 C 6 SA -
LT 4 F RR-2 Test with hydrcxien nmbirer H-5 C gerability test, every 6 nonths.
0004u 2 C 6 SA -
LT-Q F RR-2 Test with hydrojen reorbiner B-5 C gerability test, ewry 6 gronths.
etN-044A 2 B 4 to C LT-Q O b G-7 cr ST-Q 25.3 FN-044B 2 B 4 to C LT-Q O D-7 cr ST-Q 27.4 d FIN-016A 2 B 3/4 FO C LT-Q O RR-3 tocated on NJ. Il600.026.87-lE.
I-4 GL Sr-Q 35.1 RR-3 H2 recxrbiner water spray valve. A Tested with hydrotten rearbiner in gerability test, every 6 ureths.
K N-0168 2 B 3/4 on C LT-Q O RR-3 locatal on Dup. Il600.026.87-lE.
B-4 CL ST-Q 35.5 RR- 3 11 recrmbirer water spray valw.
2 3 Tested with hydrcxjen recxrbiner 411 qerability test, every 6 proths.
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DOCUMENT NO. 80A2903 Fev 3 NUCLEAR ENERGY SERVICES, INC. PAGE III-24-9 OF III-24-12 h RELIEF REQUEST RR 1 System: Primary Containment Atmospheric Control Valve: 0016A,B Category: AC Class: 2 Function: Containment isolation simple check valve (reverse flow closure for containnent 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, 7ype C testing at refueling.
Altemate Testing: Reverse flow clsoure will be verified during Appendix J, Type C testing at refueling.
FoMM a Ms-24612/82
DOCUMENT NO, 80A2903 Fev 3 NUCLEAR ENERGY SERVICES, INC. PAGE TTT-24-10 __OF TTT 12_d (JD RELIEF REQUEST RR - 2 System: Primary Containment Atmospheric Control Valve: 0004A,B Category: C Class: 2 Function: !!ydrogen recombiner outlet check valves.
ASME Section XI Quarterly Test Requirements: Exercise v
Basis for Relief: The only way to verify full flow opening is during the hydrogen recombiner functional test which is performed by Technical Specification Surveillance Requirements 4.6.6.1 which test the hydrogen recombiners for operability at least once every six months.
I l
l Alternate Testing: Verify operability during hydrogen recombiner functional testing at least once every six months.
1 O
1 G FORM e NEs-let 12/82
DOCUMENT NO. 80A2903 pcv 3 ar NUCLEAR ENERGY SERVICES. INC. PAGE III-24-11 of III-24-12 d n
\J RELIEF REQUEST RR - 3 System: Primary containment Atmospheric Control Valve: MCf/-016 A , B Category: B Class: 2 Function: Hydrogen recombiner water spray valves.
- Quarterly Test Requirements: Exercise and time.
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O Basis for Relief: These valves are slaved to the hydrogen reconbiner controls 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 valves 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.
Alternate Testing: Exercise and time during hydrogen recombiner functional testing at least once every six months.
FORM e NES-24412/82
Doctment No. RM2903 aev 4 -
Page III-24-12 of III-24-12
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