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APPENDIX A INSERVICE TESTING PROGRAM PLAN Vermont Yankee Nuclear Power Station Commercial Service Date: November 29,1972 l                                                  Revision 19
_l                                                October,1998 Prepared By:                                              Reviewed By:
k            b!.        ~                                    -
Y.
Plant IST Coordinator C/M 0            V
                              ~
Approved By:
DW ystem Eng
                        ~
g Man u l /s r W1./)), O N $dV?                                                            M Pirnt Operations Review /0[67          F                  Plant Manag h
v        ,    1.
                    ,    -      IM, @ _                                            .
l Director      erations Vermont Yankee Nuclear Power Corporation Governor Hunt Road Vernon, Vermont 05354 9811300149 981120              r7                                      Appendix A ADOCK O gDR                          1f                                        PP 7013 Rev. 3 Page 1 of 6
 
APPENDIX A (Continu2d)
Vermont Yankee Nuclear Power Station                                    inservice Testina Proaram Revision Summary R: vision          Affected Number              Pages                                        Summary 13                  All            Third Ten-Year interval Update.                                  ;
1 14    5-14, 5-15                  Revise valve listing for Diesel Generator Starting Air System to reflect changes made under PDCR 92-18, DCN 1. Minor revisions.                                                    _
15    Cover,1-1,1-2, 2-5, 3-1,    Revise to reflect Tech Spec Amendment No.138, EDCR 3-2, 4-1 to 4-5, 4-10,      92-404, EDCR 93-404, PDCR 92-016, PDCR 92-018, 4-12,4-14,4-17,4-19,        CARS 93-70 and 94-06, PRO 94-18, items identified during          l 4-21 to 4-23, 4-25, 4-29,    revisions to implementing procedures, current status of 5-1, 5-3 to 5-11, 5-13 to    each Relief Request per USNRC SEPs [ References (s) and 5-20, 5-22 to 5-30, 5-32    (u)], and minor revisions.
to 5-34, 5-36 to 5-71, 5-74 to 5-84, 5-87, 5-88, 5-91 to 5-94, 5-98 to 5-98b, 5-100, 5-102, 5-105,5-107,5-113, 5-115, 5-117, 5-119, 5-122 to 5-124, 5-126 16    Cover,4-3, 4-7 to 4-10,      Revise to reflect changes made due to the responses to the 4-30, 4-31, 5-5, 5-7 to      USNRC Safety Evaluation Report issued on September 3, 5-11, 5-17, 5-19, 5-20,      1994, Alternate Cooling Water System additions, items 5-27, 5-34, 5-36, 5-38 to    identified during the implementation of the program, current 5-41, 5-43, 5-52, 5-53,      status of each relief request and correction of typographical 5-56 to 5-59, 5-60, 5-68,    errors.
5-77, 5-83 to 5-84, 5-89 to 5-90, 5-104 to 5-112, 5-107,5-113, 5-114, 5-118,5-119,5-122, 5-125 17    Cover, 5 9, 5-129 & 5-130    Revise to allow the use of the sampling disassembly technique for V70-43A and V70-43B in accordance with the guidance specified in USNRC Generic Letter 89-04, Staff Position 2.
i Appendix A PP 7013 Rev. 3 Page 2 of 6
 
_ . _ .  .__m      _ _ _ . ._        ._, _ _ ._ . _ _ _ . _ _ _ . _ . . _ . _ . _ . _ _                                        _ _._ __.___. _
APPENDIX A (Continu d)                                                            j l
Vermont Yankee Nuclear Power Station                                                                  Inservice Testina Proaram
                                                                                                                                                      )
R; vision            Affected Number                Pages                                                                  Summary          ,
18                  All                                    General program revision committed to in LER 95-17 and BMO 95-07. Implemented changes due to IST program                        .
scope changes and IST program bases document upgrade.
implemented changes due to Appendix J Program upgrade.
implemented changes due to EDCR 93-405, PDCR 94-021, PDCR 94-022, EDCR 95-409, EDCR 96-410, EDCR 96-412, EDCR 96-416, PDCR 94-007 and Minor Mod.
96-34, 96-52. Revised program format as suggested by NUREG 1482.
              -18A  Cover, ii, iii, 3-3, 4-15,                            Revised to implement NRC SER on RR-P03, Rev.1, 4-16, 4-20 to 4-23, 5-13,                              RR P05, Rev.1, and RR-P06, Rev.1 to update the 5-39,5-40,5-42,5-43,                                  improved instrument accuracy currently in use compared to 5-48,5-55,5-56, 5-62,-                                those accuracies considered by the NRC previously in .
5-90, 5-128,5-129,                                    granting the original revisions of the subject relief requests.
5-148, 5-149, 5-163 t                                Revised to implement NRC SER on RR-V13, Rev. O, 5-172                                                RR-V14, Rev. O, and RR-V15, Rev. O, extending the Stroke Close testing frequency of check valves associated with keep fill / flushing lines in the RHR, Core Spray, HPCI and              i RCIC Systems.
Withdrew RR-V12 and issued ROJ-V32 to justify refueling outage full stroke testing of V70-43A and V70-43B on a                  i sampling basis.                                                        I issued Revision 2 to ROJ-V14 based on a change to the methods to be used to verify full stroke open of Service Water Pump discharge check valves V70-1 A,1B,1C, and 1 D.
Removed HCU Rupture Disks 3-3-132 (Typical of 89) from the program scope based on a review of the applicable                  ;
criteria of 10 CFR 50.55a and a 10 CFR 50.59 review                    I L                                                                            associated with this revision. (Page 5-48) l ii Appendix A PP 7013 Rev. 3 Page 3 of 6
 
APPENDIX A (Centinutd)
Vermont Yankee Nuclear Power Station                                      Inservice Testina Proaram l
l  Revision          Affected
(  Number                Pages                                        Summary 188    Cover, iii, iv, 2-3, 2-4, 4-6,  Revised Section 4, Table 4-1, Pump Listing, to include 4-7, 5-5 to 5-8, 5-12 to        component specific differential pressure and vibration 5-19, 5-21 to 5-24, 5-31        requirements for P-7-1 A through P-7-1D.
to 5 38, 5-42 to 5-46, 5-48 to 5-50, 5-54 t            Revised to eliminate set-point testing of the 10 Sorvice 5-58, 5 61 to 5-65, 5-68,      Water Vacuum Breakers and to add a sampling c'isassembly and inspection (CD) program.
5-73,5-76,5-86,5-88, 5-89, 5-93, 5-127, 5-142,      Added Instrument Air / Service Air, Containment Air and      j 5-143, 5-145,5-146,            Nitrogen System Relief Valves SR-72-3A/B, SR-72-5, &
5-148,5-153,5-154.              SR-16-19-77 to reflect their new safety class status per BMO 96-03.
Added Appendix J, Option B and variable frequency references to qualified components to reflect Technical Specification Amendment No.152.
Added CRD Cooler SW/RCW valves V70-30A/B &
I V70-31 A/B to address BMO 97-61.
Revised Program to reflect additions and deletions to        j components in the DGSA System per EDCR 97-401.              l i
Added position indication testing for FCV-2-39/40 to reflect EDCR 97-406.
Revised Program to reflect SDV vent & drain valve            l replacement per EDCR 97-410.                                :
Revised Program to reflect TIP Purge Modifications per EDCR 97-416.
Deleted Leak Testing (LT) of RHR V10-57/66.                  !
Revised Program to account for HPCl/RCIC Vacuum Breaker Modifications which added and deleted components per ll                                          EDCR 98-402. Issued ROJ-V33.
Deleted replacement requirements for Torus Rupture Disk S16-19-1 from Program based on its Beyond Design Basis active function.
iii Appendix A PP 7013 Rev. 3
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l
 
APPENDIX A (Continuc;d)
Vermont Yankee Nuclear Power Station                                  Inservice Testina Proaram Revision            Affected Number                Pages                                    Summary l    19    Cover, iii, iv, v, 5-21,    Revised Summary on page iii to reflect editorial notation of l            5-26,5-39,5-40,5-45,        ROJ-V33 as part of previous entry accounting for j            5-64,5-92,5-99,5-156.      HPCl/RCIC Vacuum Breaker Modifications.
'l                                        Revised to show correct normal and safety stroke direction l                                        for outboard MSIV Instrument Air System Isolation Valves l_                                      V72-28D and V72-28E.
l                                        Revised to .specify an additional quarterly test (Manual l                                        Stroke Open) for Diesel Oil Day Tank Level Control Valves l                                        LCV-108-2A/2B.
l                                        Revised to delete quarterly stroke close test for Diesel Fuel l                                        Oil Transfer Pump Discharge Check valves V78-28A and l                                        V78-288 based on the change in closed safety position l                                        basis caused by actions taken in response to ER 97-1577 l                                        and associated BMO 97-51.
j                                        Revised to reflect a new test frequency, method of l                                        inspection, and justification for performing component l                                        disassembly on a sampling basis for Core Spray check j                                        valves V14-13A/B in lieu of the previous cold shutdown l                                        mechanical exercising test. Issued ROJ-V34 and deleted j                                        CSJ-V05.
l                                        Revised to specify an additional quarterly test (Stroke Time l                                        Open) for Core Spray Tect Line Isolation Valves V14-26A l                                        and V14-268 based on a new active safety function
~j                                        established by EDCR 97-420.
'l                                        Deleted Note 2 of the Valve Notes section to reflect the l                                        transfer of responsibility from the IST Program to the PM j                                        Program when conducting a fatigue inspection of
-l                                        RCIC/HPCI check valves V13-50 and V23-65.
iv Appendix A PP 7013 Rev. 3 Page 5 of 6
 
APPENDIX A (Continued)
L  TYormont Yankee Nuclear Power Station                                                                  Jriservice Testina Proaram l  ' Tchle of Contents                                                                                                                      j t
l 1.0 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 1 Page 1                      i i
          - 1.1. Purp ose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Secti on 1 Page 1                  l l          1.2 Discussion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 1 Page 1 2.0 Program Plan Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 2 Page 1                              l 2.1 Test Deferral Justifications . . . . . . . . . . . . . . . . . . . . . . . . . Section 2 Page 1                              l 2.2 Relief Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 2 Page 2
                                                                                                                                            ]
2.3 Flow Diagrams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 2 Page 2 Table 2-1: List of inservice Testing Flow Diagrams . . . . . . . . . . . . Section 2 Page 3                                      I 3.0 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S e c ti o n 3 Pa g e 1 i
    - 4.0 Pump Inservice Testing Program Plan . . . . . . . . . . . . . . . . . . . . . . Section 4 Page 1 4.1 S c o pe . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S e cti on 4 Pa g e 1 4.2 ' Pump Program Listing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 4 Page 1                          l I          ~ Table 4-1: Pum p listing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 4 Page 4                        1 I          - 4.3 Pump N otes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 4 Page 8                        i i
i            4.4 Pump Relief Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 4 Page 9 l                                                                                                                                            >
5.0 Valve inservice Testing Program Plan . . . . . . . . . . . . . . . . . . . . . . Section 5 Page 1 5.1 Sc ope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S e ctio n 5 Pa g e 1
: 5.2 Valve Program Listing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 5 Page 2 Table 5-1: Valve Listing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 5 Page 8 l
5.3 Valve N otes . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . Section 5 Page 92 l  j:        5.4 Valve. Cold Shutdown Justifications . . . . . . . . . . . . . . . . . . . Section 5 Page 95 j;      - 5.5 Valve Refueling Outage Justifications . . . . . . . . . . . . . . . . . . Section 5 Page 114 j;        5.6 Valve Relief Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 5 Page 157 s
l-v Appendix A PP 7013 Rev. 3 Page 6 of 6 i
i r
 
Verm:nt Yenkee Nucle:r Pswer Ststi::n                                                        Inservico Tcsting Pr: gram 1.0 Introduction
[
1.1 l Purpose The Third-Interval Vermont Yankee Inservice Testing (IST) Program. establishes testing requirements to assess. the operational readiness of certain Safety Class 1, 2, and 3
.                      pumps and valves which are required to:
a)      ' Shut down the reactor to the cold shutdown condition, b) : Maintain the reactor in the cold shutdown condition, or i
c)        Mitigate the consequences of an accident.
The Third-Interval IST Program is applicable for the. interval from September 1,1993 through and including August 31,2003 [ References (q) and (r)].                                                            R 1
                        'Ihe Third-Interval IST Program is part of the Vennont Yankee Component Testing                                            j Program.
              .1.2    Discussion The Third-Interval Vermont Yankee IST Program was developed in accordance with the requirements of the 1989 Edition of Section XI, Division 1, of the ASME Boiler and Pressure -Vessel, Code, " Rules for-Inservice Inspection of Nuclear Power Plant Components," and 10 CFR 50.55a [ Reference (b)]. The Third-Interval IST Program                                            l provides compliance with Vermont Yankee Technical Specifications 4.6.E.
1 In accordance with Articles IWP-1000 and IWV-1000 and Table IWA-1600-1 of the
: 1989 Edition of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code and 10 CFR 50.55a(bX2Xviii), the pump and valve testing requirements were based on                    .
the ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM-1987, " Operation and Maintenance of Nuclear Power Plants". The additional requirements described in 10 CFR 50.55a(bX2 Xvii) and the recommendations described in Generic Letter 89-04 and its supplements were also included as applicable. Request for use of the ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM-1987, with the additional requirements, was submitted by Vermont Yankee and approved by the USNRC [ References (e) and (f)].
All references to the ." Code" made within this IST Program Plan will refer to the
                        'ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM-1987 unless otherwise
: specified.
The IST Program Plan identifies the scope of components (pumps and valves) included in the Third-Interval IST Program, the testing requirements for those components, and justifications or relief requests to support the scope and testing requirements.
Revision 19                                                                                              Section 1 Page 1 of 2
                                                                                                  -gp    , - - - *        .r-r  i
 
LVcrmnt Yczkee Nctl ,cr Pcwer Stati:n                                Ins:rvice Testing Progrcm                            j 1.2 Discussion (cont.) .
The IST. Program Plan provides conformance with Article.IWA-2420 of the 1989                                  )
Edition of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code and 10                        !
CFR 50.55a(a)(3), (f)(5) and (f)(6).                                                                          J
                  'Ihe USNRC Safety Evaluations for the 'Ibird-Interval Vermont Yankee IST Program are                          !
                  . provided in References Section.
l l
i l
Revision 19                                                                    Section 1 Page2 of 2
 
Vcrm::nt Yenkee Nucle:r P.:,wer St ti:n                            Ins:rvics Tcsting Program 2.0  Program Plan Description The IST Program Plan is comprised of two independent subprogram plans - the Pump Inservice Testing Program Plan and the Valve Inservice Testing Program Plan.
Key features common to both Program Plans are: the Pump and Valve Listings that define the scope of the Third-Interval IST Program, Cold Shutdown and Refueling Outage Justifications, Relief Requests, and applicable Notes.
Administrative and implementing procedures, reference values, test results, and other records required to define and execute the Third-Interval IST Program are retained at Vermont Yankee.
2.1  Test DeferralJustifications In accordance with Paragraphs 4.2.1.2 and 4.3.2.2 of Part 10 of the Code, certain valves are full stroke exercised during Cold Shutdown conditions when the valve cannot be exercised during Normal Operation. When the valve cannot be exercised during Cold Shutdown conditions, then the valve is full stroke exercised during Refueling Outages.
The technical justification for exercising a valve during Cold Shutdowns or Refueling      :
Outages, rather than during Normal Operations, is provided in a Cold Shutdown or
  .              Refueling Outage Justification.
Valves tested during Cold Shutdowns or Refueling Outages shall be scheduled and tested in accordance with Paragraphs 4.2.1.2 and 4.3.2.2 of Part 10 of the Code.
Cold Shutdown and Refueling Outage Justifications are numbered in a "XXJ-VNN, Revision Z" format, where:
XXJ: CSJ for Cold Shutdown Justifications, ROJ for Refueling Outage Justifications.
V: for Valves.
NN: A unique sequential number, (e.g. CSJ-V03, Rev 0, would be the third Cold Shutdown Justification for Valves).                        ,
Z: Revision Status.
Revision 19 Section 2 Page 1 of 4
 
Vermet Yenk:e Nucle:r Pcwer Stati n                                                                  Inservica Testing Pr:gr:m 2.2  ReliefRequests Specific requests for relief are included in accordance with 10 CFR 50.55a(a)(3), (f)(5) and (f)(6). Where conformance with the requirements of the Code have baen determined to be impracticable, alternate testing is proposed that would provide an acceptable level of quality and safety. Where conformance with the requirements of the Code would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, alternate testing is proposed that would provide useful information to assess the operational readiness of the component tested.
The Relief Requests define the component (s) and test (s) involved, the basis for relief, the proposed attemate testing, and the status of the USNRC evaluation to the Relief Request.
If testing requirements are determined to be impracticable during the course of the interval, additional or modified Relief Requests will be submitted in accordance with 10 CFR 50.55a(f)(4)(iv).
Relief Requests are numbered in a "RR-YNN, Revision Z" format, where:
RR:    for Relief Request.
Y:    P for Pumps, V for Valves.
NN:    A unique sequential number, (e.g. RR-V09, Rev 0, would be the ninth ReliefRequest for Valves).
Z:    Revision Status.
2.3  Flow Diagrams k
Table 2-1 provides a listing of those Flow Diagrams which depict the components, subsystems, and systems contained within the Third-Interval IST Program. Drawing number G-191155 explains the symbols and designations provided on the Flow Diagrams.
The Safety Classifications depicted on the Flow Diagrams are subject to the limitations stated in the Vermont Yankee Safety Classification Manual.
              "For Information Only" copies of the Flow Diagrams shall be provided with each USNRC Submittal. The copies shall be current as of the date of the IST Program Plan submittal. Controlled copies of the Flow Diagrams are maintained at Vermont Yankee to ensure that all system additions and modifications are addressed in the Third-Interval IST Program.
Revision 19                                                                                                Section 2 Page 2 of 4
 
l Vcrmrat Ycckee Nuslear Power St:tica                      I:s:rvica Tcsting Prcgram Table 2-1                                        ;
LIST OF INSERVICE TESTING FLOW DIAGRAMS (sorted by flow diagram number)
Flow Diagram                  System                                                      l Number                    Name                                                        I G-191155        Piping and Instrument Symbols G-191159 Sh 1_  Service Water System i
G-191159 Sh 2  Service Water System                                                    j G-191159 Sh 3  RCW Cooling Water System G-191159 Sh 5  Recirculation Pump Cooling Water l
G-191160 Sh 3  Instrument Air System                                                    '
G-191160 Sh 4  Instrument Air System G-191160 Sh 7  Diesel Generator Starting Air System G-191160 Sh 8  Instrument Air System                                                    l l
G-191162 Sh 2  Miscellaneous Systems-Fuel Oil G-191165        Sampling System G-191167      Nuclear Boiler
    ' G-191168      Core Spray System G-191169 Sh 1  High Pressure Coolant Injection System I      G-191169 Sh 2  High Pressure Coolant Injection System i                                                                                              !
G-191170      Control Rod Drive Hydraulic System G-191171        Standby Liquid Control System G-191172        Residual Heat Removal System r                                                                                              i Revision 19                                                        Section 2 Page3 of 4    )
 
l Vcrmrt Ycnkee Nucle:r P:wcr St:ti:n                          Inservic] Testing Progrcm Table 2-1                                            :
r
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LIST OF INSERVICE TESTING FLOW DIAGRAMS                                      :
(sorted by flow diagram number) 1 Flow Diagram                    System Number                        Name G-191173 Sh 1    Fuel Pool Cooling & Cleanup System G-191173 Sh 2    FuelPool Cooling & Cleanup System G-191174 Sh 1    Reactor Core Isolation Cooling System G-191174 Sh 2    Reactor Core Isolation Cooling System G-191175 Sh 1    Primary Containment & Atmosphere Control G-191175 Sh 2    Primary Containment & Atmosphere Control G-191177 Sh 1      Rdwaste Systems G-191178 Sh 1      Reactor Water Clean Up System G-191237 Sh 2      HVAC - Turbine, Service & Control Room Building                            l l
G-191238          HVAC - Reactor Building G-191267 Sh 1      Nuclear Boiler Vessel 1nstrumentation                                      i G-191267 Sh 2      Nuclear Boiler Vessel Instrumentation VY-E-75-002        Containment Atmosphere Dilution System 5920-271          Neutron Monitoring System
                                                                                                          \
Revision 19                                                            Section 2 Page 4 of 4
 
l Vcrment Ycrkes Nucl:Cr Paw:r St tien                              Ins:rvice Testing Pr: gram 3.0  References a)    License No. DPR-28 (Docket No. 50-271).
b)    United States Code of Federal Regulations, Title 10 Chapter 1, Part 50, Section 50.55a (57FR34666, dated August 6,1992).                                                            I c)    ASME Boiler and Pressure Vessel Code, Section XI, Division 1, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1989 Edition.
d)    ASME/ ANSI Standard OMa-1988 Addenda to ASME/ ANSI OM-1987, " Operation and Maintenance ofNuclear Power Plants".
e)    Letter, Mr. P.M. Sears, USNRC, to Mr. L.A. Tremblay, VYNPC, " Vermont Yankee                  l Nuclear Power Station, Approval of the Use of ASME/ ANSI Standard OMa-1988 With Clarification," NVY 92-161, dated September 2,1992.                                          ;
f)    Letter, Mr. J.P. Pelletier, VYNPC, to Document Control Desk, USNRC, " Vermont Yankee Nuclear Power Corporation Inservice Testing Program Update," BVY 92-98, dated August 13,1992.
l g)    Leder, Mr. J.G. Partlow, USNRC, to All Holders of Light Water Reactor Operating Licenses and Construction Permits, " Supplement to Minutes of the Public Meetings on Generic Letter 89-04", dated September 26,1991.
h)    Letter, Mr. J.G. Partlow, USNRC, to All Holders of Light Water Reactor Operating Licenses and Construction Permits, " Minutes of the Public Meetings on Generic Letter 89-04", NVY 89-239, dated October 25,1989.
i)    Letter, Mr. W.P. Murphy, VYNPC, to Document Control Desk, USNRC, " Response to USNRC Generic Letter 89-04: Guidance on Developing acceptable Inservice Testing Programs", BVY 89-90, dated October 3,1989.
j)    Letter, Mr. S.A. Varga, USNRC, to All Holders of L*;;ht Water Reactor Operating Licenses and Construction Permits, " Guidance on Developing Acceptable Inservice Testing Programs (Generic Letter 89-04)", NVY 89-75, dated April 3,1989.
k)    Letter, Mr. W.P. Murphy, VYNPC, to Dr. Thomas E. Murley, USNRC, " Response to USNRC Generic Letter 87.06: Periodic Verification of Leak-Tight Integrity of Pressure Isolation Valves", FVY 87-64, dated June 11,1987.
l Letter, Mr. R.W. Reid, USNRC, to Mr. R.H. Groce, YAEC, "NRC Staff Guidance for f
1)
Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests Pursuant to 10 CFR 50.55a(g)," dated January 10,1978.
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                                                                  \ .
y Vermet Ycakee Nucle:r Pcwer Statinn                                Ins:;rvice Testing Program -
3.0 _ References (cont.) .
m)      Letter, Mr. R.W. Reid, USNRC, to Mr. R.H. 'Groce, YAEC, "NRC Staff Guidance for Complying' with Certain Provisions of 10 CFR 50.55a(g), ' Inservice Inspection
                        . Requirements'," dated November 17,1976.
n)-    Vermont Yankee Final Safety Analysis Report.
o) . Vermont Yankee Technical Specifications.
p)    . Vermont Yankee Component Testing Program Plan.
q)      Letter, Mr. J.P. Pelletier, VYNPC, to Document Control Desk, USNRC, " Submittal of Vermont Yankee Nuclear Power Corporation Third-Interval Inservice Testing Program Plan and Safety Evaluation Responses," BVY 92-133, dated November 30,1992.
r)      . Letter, Mr. D.H. Dorman, USNRC, to Mr. J.P. Pelletier, VYNPC, " Relief from the
                      . ASME Section XI Requirement to Update (On a' 120-Month Interval) the Inservice Inspection and Testing Programs at Vermont Yankee (TAC No, M85067)," NVY 93-031, dated April 6,1993, s)      Letter, Mr. I).H. Dorman, USNRC, to Mr. D.A. Reid, VYNPC, " Safety Evaluation of the Inservice Testing Program Relief Requests for Pumps 'and Valves, Vermont Yankie Nuclear Power Station (TAC No. M85067)," NVY 93-151, dated September 3,1993.
,              t) . Letter, Mr. D.A. Reid, VYNPC, to Document Control Desk, USNRC, " Proposed Change No.168 to the Vermont Yankee Technical Specifications - Auxiliary Electric Power System Technical Specifications and Associated Revision to the Vermont Yankee Inservice Testing Program," BVY 93-30, dated August 4,1993.
u)      Letter, Mr. W.R. Butler, USNRC, to Mr. D.A. Reid, VYNPC, " Issuance of Amendment No.138 to Facility Operating License No. DPR-28, Vermont Yankee Nuclear Power Station (TAC No. M87171)," NVY 94-45, dated March 22,1994.                            ;
i v)      Letter, Mr. D.H. Dorman, USNRC to Mr. D.A. Reid, " Safety Evaluation of the Inservice l Test Program Relief Requests for Pumps and Valves, Vermont Yankee Nuclear Power      j Station (TAC No. M85067)".                                                            l w)~ Letter, Mr. P.F. McKee, USNRC to Mr. D.A. Reid, " Safety Evaluation of Relief              l Requests and Action Item Responses for the Third Interval Pump and Valve Inservice    l Testing Program - Vermont Yankee Nuclear Power Station, (TAC No. M91450)," NVY        j 95-88, dated June 12,1995.                                                            ;
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  - . _ - .-                .-      ..    .            -      .  . . - . .  . - . - .        .      ..-    ..- _~
              . Vcrment Ycnkee Nucimr Pswer Statica                            Inservice Testing Prcgrcm 3.0 References (cont.)
x)    Letter, Mr. P.F. McKee, USNRC to Mr. D.A. Reid, " Safety Evaluation of Relief Request RR-V12 for the Third Interval Pump and Valve Inservice Testing Program - Vermont Yankee Nuclear Power Station (TAC No. M92018)," NVY 95-100, dated July 27,1995.
y)    USNRC NUREG 1482, dated April 1995, " Guidelines for Inservice Testing at Nuclear            l Power Plants".
z)    USNRC NUREG/CR-6396,- dated February 19%, " Examples, Clarifications, and Guidance on Preparing Requests for Relief from Pump and Valve Inservice Testing Requirements".
aa) Letter, Mr. K. N. Jabbour, USNRC to Mr. D. A. Reid, " Safety Evaluation of Relief Requests for the Third Interval Pump and Valve Inservice Testing Program - Vermont Yankee Nuclear Power Station (TAC No. M97544)," NVY 98-03, dated January 15, 1998.
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Vcrmert Yorkee N:cle*r Pswer Stati:n                                    Irs:rvice Tcsting Pr:grcm 4.0 ' Pump Inservice Testing Program 4.1 . Scope The Third-Interval Pump Inservice Testing (IST) Program establishes testing requirements to assess the operational readiness of those Safety Class 1, 2, and 3 centrifugal and positive displacement pumps, provided with a Safety Class Electrical -
power source,which are required to:
a)    Shut down the reactor to the cold shutdown condition,                                  l b)    Maintain the reactor in the cold shutdown condition, or c)    Mitigate the consequences of an accident.                                              j Excluded from the above are:
a)    Drivers, except where the pump and driver form an integral unit and the pump bearings are in the driver; b)    Pumps that are provided with a Safety Class Electrical power source solely for system' design or operating convenience.
4.2 Pump Program Listing Table 4-1, " Pump Listing" lists all pumps included in the Third-Intenal Pump IST Program.
This Table identifies all pumps subject to inservice testing, the inservice test parameters, l testing frequency, tad any applicable relief requests and/or remarks. The column            l headings in Table 4-1 are listed and explained below:                                        l Pump Number
              - The unique number that identifies the pump. The pump number corresponds to the Maintenance Planning and Control (MPAC) Database utilized at Vermpnt Yankee. Table 4-1 is sorted by Pump Number.
Nomenclature              The common name for the pump.
Drawing The Flow Diagram which depicts the pump. If the pump appears on multiple Flow Diagrams, then the primary Flow Diagram identifier is listed.
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1 Vcrm=t Yenkee N cirr Pcwer Stati:n                                          Ins:rvice Tcsting Pr: gram 4.2    Pump Program Listing (cont.)
Dwg Coor The coordinate location (e.g., D-05) on the Flow Diagram where the pump appears.
Safety Class The safety classification of the pump, as determined in accordance with administrative
              . procedure AP 0014, " Safety Class Determination Instructions," and the Vermont Yankee Safety Classification Manual.
I Pump Type
              ' The pump type:
CENT                  for Centrifugal pumps.
VERT                  for Verticalline shaft pumps.                                          !
PD-RECIP              for Positive Displacement Reciprocating pumps.                          I PD-ROT                for Positive Displacement Rotary pumps.                                l Test Type
* I The Inservice Test Parameters to be determined and recorded during testing performed in                ;
accordance with Paragraph 5 of Part 6 of the Code. The abbreviations correspond to                      i those provided in Table 2 of Part 6 of the Code:                                                        !
l N      for Speed,(if variable speed).                                                        j dP      for differential Pressure, (for centrifugal and vertical line shaft pumps).          ;
P      for discharge Pressure, (for positive displacement pumps).                            1 l                        Q      for Flow Rate.                                                                        1 Vv . for Vibration, velocity, peak.                                                    -
Test Freq The test frequency associated with each test type.
t OC for Once Per Operating Cycle l                        Q for Quarterly                                              '
i l                        RO for Reactor Refueling Outage 4
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Vcrm :t Yc:kee Nrcle:r Pcw r Statim-                                    Inservics Tcsting Pregrsm              ,
l 4.2    Pump Program Listing (cont.) -
ReliefRequest I
                      - The Relief Request number associated with the subject pump and test type or test frequency,where applicable.
Remarks Clarifying comments or other remarks related to the subject pump and test type or test            j frequency, where applicable.
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f Revision 19                                                                    Section 4 Page3 of 31
 
Vermont Ycckee N: clear Power Statio:2                                                                                                                                                      Inservice Testing Program i
Table 4-1 Punip Listing Dwg Sa W                                            . Pump        Test Test  Relief                                Remarks Pump Number                        Nomenclature                              Drawing Coor Class                                              Type        Type  Freq Request                                                                        [
P-10-1 A                        RHR(LPCI) Pump            G-191172                                            Ir05                                        2        CENT  Fixed  dP    Q          n/a
-                                                                                                                                                                                    Q    Q          n/a Vv    Q          n/a RHR(LPCI) Pump            G-191172                                            L-12                                        2        CENT  Fixed  dP    Q          n/a P-10-1B                                                                                                                                                                                                                                                                    ,
                                                                                                                                                                  .                  Q    Q          n/a Vv    Q        .n/a P-10-1C                          RilR(LPCI) Pump          G-191172                                              J-05                                      2        CENT  Fixed  dP    Q          n/a-Q    Q          n/a Vv    Q          n/a RHR(LPCI) Pump            G-191172                                              J-12                                    2        CENT  Fixed  dP    Q          n/a P-10-1D Q    Q          n/a VV    Q          n/a Standby FuelPool          G-191173 Sh 2                                      G-12                                        3        CENT  Fixed  dP    Q          n/a P-19-2A Cooling Pump                                                                                                                                      Q    Q          n/a VV    Q          n/a Standby FuelPool          G-191173 Sh 2                                          I-12                                    3        CENT  Fixed  dP    Q          n/a P-19-2B Cooling Pump                                                                                                                                      Q    Q          n/a Vv    Q          n/a P-213-1 A                      RCIC Gland Seal          G-191174 Sh 2                                        K-13                                      3      PD-RECIP Fixed SKID    Q          n/a Condensate Pump                                                                                                                                                                                                                            '
HPCI(High Pressure)      G-191169 Sh 2                                        G-10                                      2        CENT  Vari  dP    Q  RR-P02 P-44-IA RR-P03 Pump N    Q          n/a Q    Q  RR-P02 Vv    Q  RR-PO4 Revision 19                                                                                                                                                                                                                Section 4  Page 4 of 31
 
Vcrmont Ycckee N: clear Power Statica                                                                                                                                                                      Inservice Testing Program Table 4-1 Pump Listing-8'                                                                                                                  M                Remarks -
Pump Nunber                Nomenclature                  Drawing                                                            Speed P-44-1B                  HPCI(Booster) Pump G-191169 Sh 2                    G-11    2                              CENT. Vari dP                                      Q                            RR-P02
.                                                                                                                                                                                                            RR-P03 N                                      Q                              n/a Q-                                      Q-                          RR-P02 Vv-                                      Q P-45-1A                  SLC Pump          G-191171                          H-OF    [                . PD-RECIP          Fixed  P                                      Q                              n/a                            .
Q                                      Q                              n/a Vv                                      Q                              n/a P-45-1B                  SLC Pump          G-191171                          Md      2                  PD-RECIP          Fixed  P                                      Q                              n/a Q                                      Q                              n/a Vv                                      Q                              n/a P-46-1A                  CS Pump            G-191168                          J-li    2                            ' CENT  Fixed dP                                      Q.                            RR-POS Q                                      Q                              n/a Vv                                      Q                              n/a P-46-1B                  CS Pump            G-191168                          J-14    2                              CENT  Fixed dP                                      Q                            RR-P05 Q                                      Q                              n/a Vv                                      Q                              n/a P-47-1 A                  RCIC Pump          G-191174 Sh 2                    F-08    2                              CENT  Vari dP                                      Q                            RR-P06 .
N                                      Q                              n/a                            ,
Q                                      Q                              n/a VV                                      Q                              n/a P-59-IA                  RBCCW Pump        G-191159 Sh 3                    A-07    3                              CENT  Fixed dP                                      Q                            RR-P08 l
Q                                      Q                              Wa VV                                      Q                              n/a P-59-1B                  RBCCW Pump        G-191159 Sh 3                    B-07    3                              CENT  Fixed dP                                      Q                            RR-P08 Q~                                      Q                              n/a Vv                                      Q                              n/a a
Revision 19                                                                                                                                                                                                      Section 4  Page 5 of 31.
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                          Inservice Testirg Program Table 4-1 Pump Listing                                                                                                                          .
Pump Number                Nomenclature                                Drawing Dwg ISafe                        Pump        Speed Test Tat    W                      Remarks Coor: Class                      Type                                                Type Freq  Request P-7-1A        isB Service Water Pump                          G-191159 Sh I                C-02    3                        VERT          Fixed                                  dP  RO    RR-P01    Note 1
        -                                                                                                                                                                                    dP    Q      n/a Q    RO    RR-Pol Vv  RO    RR-P01
                                                                                                                              .                                                            Vv    Q      n/a P-7-1B        18B Service Water Pump                          G-191159 Sh 1              B-02    3                        VERT          Fixed                                  dP  RO    RR-Pol    Note I dP    Q      n/a Q    RO    RR-Pol Vv  RO    RR-Pol Vv    Q      n/a P-7-IC        18B Service Water Pump                          G-191159 Sh 1              K-02    3                        VERT          Fixed                                  dP  RO    RR-P01    Note I dP    Q      n/a Q  RO    P?.-P01 Vv  RO    R "'- J Vv    Q      n/a P-7-ID        18B Service Water Pump                          G-191159 Sh 1              J-02    3                        VERT          Fixed                                  dP  RO    RR-P01    Note I dP    Q      n/a Q    RO    RR-Pol Vv  RO - RR-P01 Vv    Q      n/a P-8-1A            RIIR Service Water Pump G-191159 Sh 1                                  K-11    3                        VERT          Fixed                                  dP    Q      n/a Q    Q      n/a Vv    Q      n/a P-8-1B            RilR Service Water Pump G-191159 Sh i                                  A-11. 3                        VERT          Fixed                                  dP    Q      n/a Q    Q      n/a Vv    Q      n/a P-8-1C            RHR Service Water Pump G-191159 Sh 1                                    K-11    3                        VERT        Fixed                                    dP    Q      n/a Q    Q      n/a Vv    Q      n/a Revision 19                                                                                                                                                                                          Section 4        Page 6 of 31
 
Vcrmont Yankee Nuclear Power Station                                                                                                                          Inservice Testing Program Table 4-1 Pump Listing Nomenclature              Drawing                            Dwg Sa W        Pump                                      Speed TM  Test  W                Remarks Pump Number                                                                                                                                              Freq Coor Class        Type                                            Type      Request P-8-1D            RHR Service Water Pump G-191159 Sh 1                            B-11  3        VERT                                      Fixed  dP    Q    n/a Q    Q    n/a VV    Q    n/a P-87-1A          HPCIGland Seal        G-191169 Sh 2                            K-17  3      PD-RECIP                                    Fixed S!'ID  Q    n/a Condensate Pump                                                              -
P-92-1A          DFOTPump              G-191162 Sh 2                            E-05  3        PD-ROT                                    Fixed    P    Q    n/a Q    Q  RR-P09 Q    OC  RR-P09 Vv    Q    n/a P-92-1B          DFOT Pump              G-191162 Sh 2                            D-05  3        PD-ROT                                    Fixed    P    Q    n/a Q    Q  RR-P09 Q    OC  RR-P09 Vv    Q    n/a P-92-2A          Diesel Generator DG G-191162 Sh 2                            F-11  3        PD-ROT                                      Vari SKID    Q  -n/a I A Engine Driven Fuel OilPump P-92-2B          Diesel Generator DG G-191162 Sh 2                            D-11    3      PD-ROT                                      Vari SKID    Q    n/a IB Engine Driven Fuel Oil Pump SP-1              Control Room HVAC      G-191237 Sh 2                            E-4    3        CENT                                      Fixed  dP    Q    n/a Chilled Water Pump                                                                                                                Q    Q    n/a Vv    Q    n/a Revision 19                                                                                                                                                            Section 4        Page 7 of 31
 
Vcrmm:t Yenkee Nuclemr Power Stztien                                            Inservice Testing Pregram 4.3  Pump Notes
: 1. In~ accordance with the June 12,1995 Safety Evaluation Report (Reference w) the following commitments were made relating to inservice testing of the Vermont Yankee Service Water Pumps (P7-1 A through P7-ID):
Quarterly Testing (As-found for each pump)
: 1.        Differential Pressure Measurement (for information only)
: 2.        Full Spectrum Vibration Signatures (for information only)
: 3.        Overall Vibration Measurements (compared to code limits)
Once Per Operating Cycle
: 1.        One of the four service water pumps will be disassembled, inspected and refurbished as necessary. Additionally, in no case shall a service water pump exceed a period of 4 cycles of operation without being disassembled, inspected and refurbished as necessary.
                                      - Refuel'ing Outage l
: 1.        Full code specified IST testing will be performed at a flow rate greater than      !
or equal to design flow.                                                            I
: 2.        A head curve will be generated to provide information so that the performance of the pump can be compared to the degree possible with the as-found quarterly data and previous refueling outage head cutve data.
The approval of relief request RR-P01 is not subject to the performance of shutoff head testing or motor amperage monitoring as originally proposed in RR P01.
                                                                                                                                      )
Revision 19                                                                            Section 4 Page 8 of 31
                                                                                                  +
 
Verm:nt Ycnkee Nuclear Pcwer St:tisn                                  Inservice Testing Program RELIEF REOUEST Number: RR-P01, Revision 1 (Sheet 1 of 4)
SYSTEM: Service Water l
l  COMPONENTS:
i l    Pump Number            Safety Class            Drawing Number              Dwg. Coord.
P7-1A                          3                    G-191159 Sh 1                C-02 P7-1B                          3                    G-191159 Sh 1                B-02 P7-lC                          3                    G-191159 Sh 1                K-02 P7-ID                          3                    G-191159 Sh 1                J-02 l
These pumps are the station Service Water pumps. They have the safety function to provide cooling water to systems and equipment required to operate under accident conditions and to          i
,  provide an inexhaustible supply of water for standby coolant system operation.
EXAM OR TEST CATEGORY:                                                                                1 I
Flow Rate (Q).          .                                                                            l CODE REOUIREMENT: Part 6 Para. 5.1    " Frequency ofInservice Tests" "An inservice test shall be run on each pump, nominally every 3 months, except as        I provided in paras. 5.3, 5.4, and 5.5."                                                  l REOUEST FOR RELIEF:                                                                                  l Reliefis requested on the basis that compliance with the Code requirements is impracticable and that the proposed alternatives would provide an acceptable level of quality and safety.
During normal operations, neither differential pressure nor flow rate can be fixed or directly measured. Pump vibration levels may also vary due to the inability to establish a repeatable reference condition.
I I
i i
Revision 19                                                                  Section 4 Page 9 of 31
 
                                                                    -        - _ . - - - ~ -    --3    +      . a... ... -
l l
Vermant Ycnkse Nuclerr Power Station                                  Inservice Testing Prsgram RELIEF REOUEST Number: RR-P01, Revision 1 (Sheet 2 of 4) a REOUEST FOR RELIEF (cont.h The four Service Water pumps are vertical, two-stage, centrifugal-type pumps which are submerged in and take suction from the Connecticut River. They supply all the station Service Water System requirements. The station Service Water System is a dual header system using two parallel headers each containing two pumps. The two parallel headers supply both the turbine
,  and reactor auxiliary equipment, including the Residual Heat Removal Service Water System. A header interconnection is provided downstream of the pumps. Normally, the valves in the interconnecting line are open, permitting any of the pumps to supply the cooling water to both headers and to balance system operation. In addition, a cross-tie is provided to the non-nuclear safety station Fire Protection System. The 12-inch cross tie valve is normally closed, with a 1-inch cross-tie and a restricting orifice providing pressurization of the Fire Protection System header.
The Service Water System contains both automatic temperature and flow control valves used to independently regulate the cooling provided to the various turbine and reactor auxiliary                                I
;  equipment. Due to seasonal variations in Connecticut River water temperature and level and constantly changing heat loads, the system resistance and flow rate vary. The nu.nber of station Service Water pumps in operation is also varied dependent on system requireme.its. Due to these                          J
; variations and the need to maintain proper cooling, it is considered impracticable to establish repeatable reference values during quarterly inservice testing.
i As a result, it is impractica'cle to directly measure pump flow rate on a quarterly and cold 4  shutdown frequency. SmTicient stvight sections of piping are required to properly measure flow rate, through the use of either perma lently or temporarily installed instrumentation, such as non-intrusive flow measurement devices.
The only sufficient straight sections of piping in each of the two parallel headers exist between the intake structure and the entrance to the reactor building. Use of this piping is considered
; impracticable because:
a)    These sections of the two parallel headers are buried piping.                              .
b)    As discussed above, each parallel header is common to two pumps and is cross-connected to the other header. Thus, in order to measure flow rate for one pump, the parallel pump in the same header would have to be secured and the valves in the header interconnecting line closed. This would result in single pump operation for the portion of the station Service Water System supplied by the pump being tested.
Revision 19                                                                              Section 4 Page 10 of 31
 
Vcrm:nt Ycakee Nuclear Pcwer Statisn                                Inservice Testing Pr: gram RELIEF REOUEST Number: RR-P01, Revision 1 (Sheet 3 of 4)
REOUEST FOR RELIEF (cont.h c)    All four station Service Water pumps are required to be operating during power operations and cold shutdowns during approximately 7 months of the year to meet cooling load requirements.
Based on the above, significant redesign and modification of the station Service Water System
;        would be required to obtain direct measurement of pump flow. Such redesign and modification would be costly and burdensome to Vermont Yankee.
A review of the historical test data for these pumps indicates that theses pumps are highly reliable and have not been susceptible to frequent failures. Plant operating experience has shown that the performance of the Service Water pumps degrades slowly over an extended period due to
:        normal system wear.
l        ALTERNATE METHOD:
;        On a quarterly basis, during plant operation and cold shutdowns an as-found test will be performed by measuring pump differential pressure and motor vibration and the data will be j        compared to the degree possible with test data taken during the refueling outage head curve data.
During each refueling outage, pump flow, differential pressure and vibration will be measured at a reference condition which will meet or exceed the required design conditions for the pump. A temporary flow test loop installed on the plant fire protection system will be utilized to directly measure pump flow. 'Ihis will provide a mechanism to assess the hydraulic condition of the pump and to detect pump degradation against the code required limits. An additional reference condition will be established with the pump at a dead head condition where pump vibration and differential pressure can be measured for comparison in the event that maintenance is required to be performed between refueling outages.
Additionally, a head curve will be generated each refueling outage to provide information so that the performance of the pump can be compared to the degree possible with the as-found quarterly test data and previous refueling outage head curve data. Overall peak and full spectrum vibration measurements will be also be taken at each of the points used to generate the head curve to provide additional operational information.
Revision 19                                                                  Section 4 Page 11 of 31
 
l                                                                                                                      l u
i Vermant Yenkee Nucl:or Pcwer Statias                                Inservics Testing Pr gram 1                                                                                                                      i RELIEF REOUEST
: i.                                                                                                                      i Number: RR-P01, Revision 1 (Sheet 4 of 4)'
ALTERNATE METHOD (cont.h                                                                                        l A review of the operating history of these pumps has shown that they are highly reliable and l      have not been susceptible to frequent failures. In order to provide additional assurance of proper l      pump operation and mechanical condition, an enhanced maintenance / monitoring program for i      these pumps will be established which will include the following:
i
: 1. Service water pump motor amperage will be monitored on a once per shift frequency L          'during periods when the pumps are in operation.
!    ' 2. Full spectrum vibration signatures of the accessible motor bearing points will be obtained l            and analyzed on a quarterly basis.
l      3. At least one service water pump will be partially disassembled, inspected and refurbished l            as required every operating cycle. Additionally, in no case shall a service water pump i            exceed a period of 4 cycles of operation without being partially disassembled, inspected l          . and refurbished as required.
USNRC EVALUATION STATUS:                                                                                        i L      Provisional relief was g' ranted in the September 1993 SER [ Reference (s)) for Relief Request                  l
      - RR-P01, Revision 0. Approval of Revision 1 of Relief Request RR-P01, was granted in the June l
L      1995 SER [ Reference (w)]. Granting RR-P01 Rev.1 was not subject to monitoring pump motor l      amperage each shift or refueling outage shutoff head testing as specified in the relief request. '              I l
l L                                                                                                  .
i
!                                                                                                                      i l
)
i Revision 19                                                                Section 4 Page 12 of 31
 
Vcrm:nt Ycnkee Nucl=r P:wer Statian                                    Inservica Tcsting Pr: gram l
RELIEF REOUEST                                                  4 l
Number: RR-P02, Revision 0 (Sheet 1 of 2)                                  ;
SYSTEM: High Pressure Coolant Injection i
COMPONENTS:                                                                                                l l
Pump Number                Safety Class        Drawing Number                  Dwg. Coord.
P44-1A                              2              G-191169 Sh 2                      G-11 P44-1B                              2                0-191169 Sh 2                    G-10                I P44-1A and P44-1B are the High Pressure Coolant Injection (HPCI) main (high pressure) and                  l booster (low pressure) pumps, respectively. They have the safety functions to operate in series to        l
;    provide 1) adequate core cooling and reactor vessel depressurization following a small break              j loss of coolant accident, and 2) reactor pressure control during reactor shutdown and isolation.
!    EXAM OR TEST CATEGORY:
l Differential Pressure (dP).
i    Flow Rate (Q).              .
CODE REOUIREMENT: Part 6 Para. 4.6.2.2 " Differential Pressure" l                      "When determining differential pressure across a pump, a differential pressure gauge or transmitter that provides direct measurement of pressure difference or l                      the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe, may be used."
l.
Para. 4.6.5      " Flow Rate Measurement" "When measuring flow rate, use a rate or quantity meter installed in the pump test circuit. If a meter does not indicate the flow rate directly, the record shall include i                      the method used to reduce the data."                                  ,
j    REOUEST FOR RELIEF:
Reliefis requested on the basis that the proposed altematives would provide an acceptable level ofquality and safety.
There is no means of measuring the differential pressure or the flow rate generated by each of these pumps individually. Installation ofindependent means of measurement for each pump is considered impracticable and would be costly and burdensome to Vermont Yankee.
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I 1
Vcrm:ct Ycckee Nucl:cr P:wcr Stati:n                            Inservica Testing Prcgram        ,
RELIEF REOUEST Number: RR-P02, Revision 0 (Sheet 2 of 2)
ALTERNATE METHOD:
Differential pressure and flow rate parameters will be measured across both HPCI pumps as an integral unit. Vibration monitoring will be performed for each pump individually. Both pumps will be inspected and repaired as necessary if any abnormal conditions in differential pressure or flow rate occur.
USNRC EVALUATION STATUS:
Relief was granted in the September 1993 SER [ Reference (s)) for Relief Request RR-P02, Revision 0.
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Verm:nt Ycnkea Nucl:er P wer Stati:n                                  Ins:rvics Testing Program      .
RELIEF REOUEST l
Number: RR-P03, Revision 1 (Sheet 1 of 2)
SYSTEM: High Pressure Coolant Injection l
COMPONENTS:
Pump Number              Safety Class          Drawing Number                  Dwg. Coord.
P44-1A                          2                G-191169 Sh 2                      G-11 P44-1B                          2                G-191169 Sh 2                      G-10            l P44-1A and P44-1B are the High Pressure Coolant Injection (HPCI) main (high pressure) and              .
booster (Iow pressure) pumps, respectively. 'Ihey have the safety functions to operate in series to    I provide 1) adequate core cooling and reactor vessel depressurization following a small break          !
loss of coolant accident, and 2) reactor pressure control during reactor shutdown and isolation.
l EXAM OR TEST CATEGORY:
Differential Pressure (dP).
CODE REOUIREME T: Part 6 Para. 4.6.1.2(a) " Range" "The full-scale range of each analog instrument shall not be greater than three times the reference value."
Para. 4.6.2.2 " Differential Pressure" "When determining differential pressure across a pump, a differential pressure gauge or transmitter that provides direct measurement of pressure difference'or the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe, may be used."
l REOUEST FOR RELIEF _1                                                                  -
Reliefis requested on the basis that the proposed alternatives would provide an acceptable level ofquality and safety.
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  . . _      .          - _    - . _ . _ _          _ _ _ . _          _  _ _ _ . _ _ _                      _ _ _ _ _ _ . ~
        - Wrmont Yankee Nucle:r Pcwer St:tica                                          Inservics Testing Program BELIEF REOUEST l
Number: RR-P03, Revistor.1 (Sheet 2 of 2) l        REOUEST FOR RELIEF (cont.):
        - Differential pressure across the HPCI pumps is determined by the difference between pressure l        measurements taken at a point in the inlet pipe and at a point in the discharge pipe as allowed by Paragraph 4.6.2.2 of Part 6 of the Code. The installed HPCI pump inlet pressure indicators are
!        designed to provide adequate inlet pressure indication during all expected operating and post accident conditions. The full scale range,85 psig, is sufficient for a post accident condition when the suppression chamber is at the maximum pressure. This, however, exceeds the full-scale range l        limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 26 psig, Limit = 78 psig).
l        The suction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure. The installed gauges are calibrated to within +/- 1.17%
L        _ accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be +/- 0.99 psi. This is considered to be suitable for determining that adequate NPSH is available for HPCI pump operation.
l        Pump discharge pressure during testing is approximately 1170 psig, which results in a calculated differential pressure of approximately 1144 psig. The resulting inlet pressure inaccuracy of +/-
0.99 psi represents an error in differential pressure measurement of +/- 0.08% (0.99 psi /1144
        - psid = 0.00086). This is consistent with Table 1 of Part 6 of the Code, which requires that
;        instrument accuracy for differential pressure be better than 2% of full-scale.
ALTERNATE METHOD:
!        Differential pressure will be measured using the existing station system installed inlet pressure
(        indicators.
!        USNRC EVALUATION STATUS:
Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-P03, Revision 1.                                                                              ,
6 Revision 19                                                                      Section 4 Page 16 of 31
 
Verm:nt Yenk:e Nucl=r P wer St:tien                                  Inservic Testing Prrgrcm RELIEF REOUEST Number: RR-PO4, Revision 0 (Sheet 1 of 3)
SYSTEM: High Pressure Coolant Injection COMPONENTS:                                                                                          I Pump Number            Safety Class            Drawing Number                Dwg. Coord.
P44-1A                        2                    G-191169 Sh 2                  G-11 P44-1 A is the High Pressure Coolant Injection (HPCI) main (high pressure) pump. The main pump has the safety function to operate in series with the booster pump, P44-1B, to provide 1)        :
adequate core cooling and reactor vessel depressurization following a small break loss of coolant    l accident, and 2) reactor pressure control during reactor shutdown and isolation.
j EXAM OR TEST CATEGORY:
Vibration Velocity (Vv).
CODE REOUIREMENT: Part 6 Para. 5.2(d)    " Test Procedure"
                  " Pressure, flow rate, and vibration (displacement or velocity) shall be determined and compared with corresponding reference values. All deviations from the reference values shall be compared with the limits given in Table 3 and corrective action taken as specified in para. 6.1."
REOUEST FOR RELIEF:
Reliefis requested on the basis that the proposed alternatives would provide an acceptable level of quality and safety.
Past testing and analysis performed on the HPCI System by Vermont Yankee, the pump manufacturer, and by independent vibration consultants has revealed characteristic pump vibration levels which exceed the acceptance criteria stated in Table 3 of Part 6 of the Code. This testing and analysis meets the intent of Paragraph 4.3 and footnote 1 of Part 6 of the Code.
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Vcrment Ycnkea Nuclear Pcwer Stati:n                                        Ins 2rvica Testing Program RELIEF REOUEST Number: RR-P04, Revision 0 (Sheet 2 of 3)'
REOUEST FOR RELIEF (cont.h 1
i ne root causes of the higher vibration levels have been determined to be:
a)    ' An acoustical resonance in the piping connecting the low pressure (LP) and high pressure (HP) pumps, and _                                                                                                                  ,
              ' b)      The presence of a structural resonance in the horizontal direction on the HP pump.
These resonance conditions are design related and have existed since initial pump installation.
They have been documented over a number of years of operating experience.                                                                j i
i
                ' An additional past contributor to the higher vibration levels was the excitation resulting from the                                      J blade pass frequency from the previously installed four vane impeller in the low pressure (LP) pump. In an effort to reduce / eliminate this effect, the four vane impeller was replaced with a five vane impeller during the 1989 refueling outage. This replacement significantly_ reduced vibration levels in both the LP and HP pumps. However, due to the resonance effects referenced above, the                                          j HP pump vibration levefs remain higher than the acceptance criteria stated in Table 3 of Part 6 of                                      I the Code.                                                                                                                                j Although existing vibration levels in the HP pump are higher than standard acceptance criteria,                                          I they are acceptable and reflect the unique operating characteristics of the HPCI pump. It has been concluded that there are no major vibrational concems that would prevent the HPCI pump from                                              i performing its intended function.
1 ALTERNATE METHOD:                                                                                                                      i To allow for practicable vibration monitoring of the HPCI HP pump, altemate vibration acceptance criteria are required. Full spectrum vibrational monitoring will be performed during
                ; each quarterly test and the following criteria will be used for the HP pump:
Test Parameter              Accentable Ranne              Alert Ranne          Reauired Action Ranne                                  ;
V,                        s 2.5 Vr              > 2.5 Vr to and                > 6 Vr but not              including 6 Vr                    or
                                                  > 0.675 in/sec,                    but not          > 0.70 in/sec.
I
                                                                              > 0.70 in/sec.
In addition, the resonance peaks will be evaluated during each test and will have an Acceptable Range upper limit of 1.05 Vr and an Alert Range upper limit of 1.3 Vr.
He standard acceptance criteria of Table 3 of Part 6 will be applied to the LP pump.
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F
;. Vcrm:nt Yc kee Nuclear P w:r St:ti:a                          Inservice Testing Prcgram I
1 RELIEF REOUEST                                                            ,
i Number: RR-PO4, Revision 0 (Sheet 3 of 3)
;    USNRC EVALUATION STATUS:                                                                                      )
Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-P04,
!    Revision 0.
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Verm:nt Yenkee Nuclear Power Station                                Inservice Testing Program i
RELIEF REOUEST Number: RR-P05, Revision 1 (Sheet 1 of 2)
SYSTEM: Core Spray COMPONENTS:
Pump Number            Safety Class          Drawing Number                      Dwg. Coord.
P46-1A                            2                  G-191168                            J-l1 P46-1B                            2                  G-191168                            J-14 P46-1 A & B are the low pressure Core Spray pumps. They have the safety function to operate to provide adequate core cooling following a loss of coolant accident and reactor depressurization.
EXAM OR TEST CATEGORY:
DifTerential Pressure (dP).
CODE REOUIREMENT: Part 6 Para. 4.6.1.2(a) " Range" "The full-scale range of each analog instrument shall not be greater than three times the reference value."
l    Para. 4.6.2.2      " Differential Pressure" l                      "When determining differential pressure across a pump, a differential pressure gauge or transmitter that provides direct measurement of pressure difference or the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe, may br/used."
REOUEST FOR RELIEF:
Reliefis requested on the basis that the proposed altematives would provide an acceptable level l    of quality and safety.
i    Differential pressure across the Core Spray pumps is determined by the difference between i    pressure measurements taken at a point in the inlet pipe and at a point in the discharge pipe as allowed by Paragraph 4.6.2.2 of Part 6 of the Code. The installed Core Spray pump inlet pressure indicators are designed to provide adequate inlet pressure indication during all expected operating and post accident conditions. The full scale range,60 psig, is sufficient for a post accident condition when the suppression chamber is at the maximum pressure. This, however, exceeds the full-scale range limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 7.5 psig, Limit = 22 psig).
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Verment Yankee Nuclezr Pcwer St: tion                                Ins:rvice Testing Program
                                                  . RELIEF REOUEST Number: RR-P05, Revision 1 (Sheet 2 of 2)
REOUEST FOR RELIEF:
The suction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure. The installed gauges are calibrated to within +/- 1.6%
accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be +/- 0.96 psi. This is considered to be suitable for determining that adequate NPSH is available for Core Spray pump operation.
Pump discharge pressure during testing is approximately 240 psig, which results in a calculated differential pressure of approximately 232.5 psig. The resulting inlet pressure inaccuracy of +/-
0.96 psi represents an error in differential pressure measurement of +/- 0.41% (0.96 psi /232.5 psid = 0.0041). This is consistent with Table 1 of Part 6 of the Code, which requires that instrument accuracy for differential pressure be better than 2% of full-scale.
ALTERNATE METHOD:
Differential pressure will be measured using the existing station system installed inlet pressure indicators.
USNRC EVALUATION STATUS:
Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-P05, Revision 1.
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    ..  . .      - - -      . - - . - . _ ~ _                      . . - - . - - -                .- -        - - - - - - -
Verment Yankee Nuclecr Power Stction                                                        Inservice Testing Program RELIEF REOUEST Number: RR-P06, Revision 1(Sheet 1 of 2)
SYSTEM: Reactor Core Isolation Cooling COMPONENTS:
Pump Number                            Safety Class                Drawing Number                  Dwg. Coord.
P47-1A                                              2                  G-191174 Sh 2                          F-08 P47-1 A is the Reactor Core Isolation Cooling (RCIC) pump. It has the safety function to operate to provide makeup water to the reactor vessel during shutdown and isolation in order to prevent the release ofradioactive materials to the environs as a result ofinadequate core cooling.
EXAM OR TEST CATEGORY:
I Differential Pressure (dP).
CODE REOUIREMENT: Part 6 4
Para. 4.6.1.2(a) " Range" "The full-scale range of each analog instrument shall not be greater than three times the reference value."
  'i Para. 4.6.2.2            " Differential Pressure" "When determining differential pressure across a pump, a differential pressure gauge or transmitter that provides direct measurement of pressure difference or the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe, may be used."
: REOUEST FOR RELIEF:
Reliefis requested on the basis that the proposed alternatives would provide an acceptable level ofquality and safety.
              - Differential pressure across the RCIC pump is determined by the difference between pressure measurements taken at a point in the inlet pipe and at a point in the discharge pipe as allowed by Paragraph 4.6.2.2 of Part 6 of the Code. The installed RCIC pump inlet pressure indicators are designed to provide adequate inlet pressure indication during all expected operating and post accident conditions. The full scale range, 85 psig, is sufficient for a post accident condition when the suppression chamber is at the maximum pressure. This, however, exceeds the full-scale range
              - limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 20 psig, Limit = 60 psig).
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Vcrm:nt Ycnkee Nucl:cr Paw:r St.:ti:n                                Ins:rvics Tcsting Prcgram RELIEF REOUEST Number: RR-P06, Revision 1(Sheet 2 of 2)
REOUEST FOR RELIEF:
The suction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure. The installed gauges are calibrated to within +/- 1.17%
accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be +/- 0.99 psi. This is considered to be suitable for determining that adequate NPSH is available for RCIC pump operation.
Pump discharge pressure during testing is approximately 1130 psig, which results in a calculated differential pressure of approximately 1110 psig. The resulting inlet pressure inaccuracy of +/-
0.99 psi represents an error in differential pressure measurement of +/- 0.09% (0.99 psi /1110 psid = 0.00089). This is consistent with Table 1 of Part 6 of the Code, which requires that instrument accuracy for differential pressure be better than 2% of full-scale.
ALTERNATE METHOD:
Differential pressure wil,1 be measured using the existing station system installed inlet pressure indicators.
USNRC EVALUATION STATUS:
Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-P06, Revision 1.
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Vcrm::t Ycnkee Nucirr Pawar St:tica                                    Inservice Testing Program RELIEF REOUEST                                                            ,
Number: RR-P07, Revision 0 (Sheet 1 of 1)
THIS RELIEF REQUEST WAS DELETED IN REVISION 15 OF THE IST PROGRAM.
i This RR number is being maintained for traceability to the Third Interval IST Program Submittal                    !
SER's.                                                                                                            :
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i Revision 19                                                                        Section 4 Page 24 of 31
 
Verment Yenk:e Nucler Pswer Stati::n                                              Inservice Testing Program l
RELIEF REOUEST Number: RR-P08, Revision 0 (Sheet 1 of 2)                                                      l l
SYSTEM: Reactor Building Closed Cooling Water                                                                                    i COMPONENTS:
[ PumpNumber                        Safety Class          Drawing Number                            Dwg. Coord.
: P59-1 A                                    3              G-191159 Sh 3                                A-07 P59-1B                                    3              0-191159 Sh 3                                B-07 l-        These pumps are the Reactor Building Clol sed Cooling Water (RBCCW) pumps. They have a safety function to provide cooling water to the safety related cooling loads served by the RBCCW system.
EXAM OR TEST CATEGORY:
Differential Pressure (dP).
CODE REOUIREMENT: Part 6 Para. 4.6.1.2(a) " Range" "The full-scale range of each analog instrument shall not be greater than three times the reference value."
i Para. 4.6.2.2            " Differential Pressure" "When determining differential pressure across a pump, a differential pressure gauge or transmitter that provides direct measurement of pressure difference or the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe, may be used."
REOUEST FOR RELIEF:
Reliefis requested on the basis that the proposed alternatives would provide an acceptable level                                  ;
ofquality and safety.                                                                                                            !
Differential pressure across the RBCCW pumps is determined by the difference between pressure measurements taken at a point in the inlet pipe and at a point in the discharge pipe as allowed by Paragraph 4.6.2.2 of Part 6 of the Code. The installed RBCCW pump inlet pressure indicators, with a full scale range of 30 psig, are designed to provide adequate inlet pressure indication during all expected operating and post accident conditions. This, however, exceeds the full-scale range limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 6.5 psig, Limit = 19 psig).
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                            .w.~n--                    e        ,    -e  -                ,,        -m . r    -,-          -      -
 
I Verm::t Ycnkee Nuclear Pcwer St:ti:n                                                                                      Inservice Testing Program RELIEF REOUEST Number: RR-P08, Revision 0 (Sheet 2 of 2)
BEQUEST FOR RELIEF (cont.):
The saction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure. The installed gauges are calibrated to within +/- 0.4%
accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be +/ .12 psi. This is considered to be suitable for determining that adequate NPSH is available for RBCCW pump operation.
Pump discharge pressure during testing is approximately 80 psig, which results in a calculated differential pressure of approximately 73.5 psig. The resulting inlet pressure inaccuracy of +/ .12 psi represents an error in differential pressure measurement of +/- 0.16% (.12 psin3.5 psid =
0.0016). This is consistent with Table 1 of Part 6 of the Code, which requires that instrument accuracy for differential pressure be better Gian 2% of full-scale.
ALTERNATE METHOD:
Differential pressure wil,1 be measured using the existing station system installed inlet pressure indicators.
USNRC EVALUATION STATUS:
Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-P08, Revision 0.
I Revision 19                                                                                                                    Section 4 Page 26 of 31
 
Vcrment Ycnkee Nuclear Power Station                                                  Inservice Testing Program RELIEF REOUEST                                                                                              ,
Number: RR-P09, Revision 0 (Sheet 1 of 4)
SYSTEM: Diesel Fuel Oil-COMPONENTS:
i PumpNumber                Safety Class              - Dawing Number                      Dwg. Coord.
P92 1A                                3                      G-191162 Sh 3                              E-05 l
P92-1B                                3                      G-191162 Sh 3                              D-05 i
These pumps are the Diesel Fuel Oil Transfer pumps. They have a safety function to provide
            . diesel fuel oil to the diesel oil day cank during Emergency Diesel Generator operations.
EXAM OR TEST CATEGORY:
Flow Rate (Q).
;              CODE REOUIREMENT: Part 6 Para. 4.6.5      " Flow Rate Measurement" "When measuring flow rate, use a rate or quantity meter installed in the pump test circuit. If a meter does not indicate the flow rate directly, the record shall i                                    include the method used to reduce the data."
Para. 5.1            " Frequency ofInservice Tests" "An inservice test shall be run on each pump, nominally every 3 months,
;                                    except as provided in paras. 5.3, 5.4, and 5.5."
l l              REOUEST FOR RELIEF:
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l              Relief is requested on the basis that compliance with the Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety and that the proposed alternatives would provide an acceptable level of quality and safety.
During quarterly inservice testing, pump flow rate cannot be directly measured.                                                                          !
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:i Vermant Yankee Nucleir Power Statisn                                        Inservice Testing Prcgram RELIEF REOUEST j                                          Number: RR-P09, Revision 0 (Sheet 2 of 4) l i
REOUEST FOR RELIEF (cont.h
!          'Ihe Emergency Diesel Generator fuel oil supply system consists of two parallel trains, one for each diesel. Fuel oil is supplied directly to th' diesel fuel block from the 800-gallon day tank.                    !
Makeup to each diesel day tank is accompl'.,ned automatically from the 75,000-gallon storage tank by operation of the respective Diesel Fuel Oil Transfer pump. The diesel day tank is sized
;          for three (3) hours of continuous full load operation, based on a diesel fuel oil consumption rate                    l of approximately 3.4 gpm. The Diesel Fuel Oil Transfer pumps are positive displacement pumps                          l l          with a design capacity of approximately 8.7 gpm.                                                                      I p          It is considered impracticable to directly measure pump flow rate on a quarterly basis. There is j          no flow rate instrumentation installed in the Fuel Oil Transfer system. Sufficient straight sections L          of piping are required to properly measure flow rate, through the use of either permanently or E          temporarily installed instrumentation, such as non-intrusive flow measurement devices. The only
[          sufficient straight sections of piping exist in the buried sections of the supply headers.
Installation of flow rate instrumentation or a pump test loop would require significant system                        !
1          redesign and modification, which would be costly and burdensome to Vermont Yankee.
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Diesel Fuel Oil Transfer pump flow rate can be determined indirectly by measuring the level change in the diesel day tank versus the pump operating time required to make that change.
}          However, in order to allow for evaluation of the test results against the acceptance criteria of j          Table 3 of Part 6 of the Code, the test must be performed with the respective Emergency Diesel Generator secured. This eliminates the unknown variability of the diesel fuel oil consumption rate.
In addition, in order to provide measurement accuracy comparable with Table 1 of Part 6 of the                        l Code, the automatic pump start feature on low diesel day tank level must be disabled and the diesel day tank volume reduced prior to the test through operation of the respective Emergency                        l Diesel Generator.
Disabling the automatic start feature of the Diesel Fuel Oil Transfer pump on low diesel day tank level lessens the ability of the Emergency Diesel Generator to operate automatically without                          ;
operator assistance, reduces the availability of an engineered safety system, and requires entry                      ,
          ~ into a Vermont Yankee Technical Specifications Limiting Condition of Operation, with the required alternate testing requirements.
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p.-
                                                                                                                        ----,y
 
Vcrment Yenkee Nucle:r Pcwer Statica                                  Inservice Testing Program l
RELIEF REQUEST i
l                                Number: RR-P09, Revision 0 (Sheet 3 of 4)
ALTERNATE METHOD:
During quarterly inservice testing of each Diesel Fuel Oil Transfer pump, it will be verified that the pump is capable of supplying fuel oil to the respective diesel day tank at a flow rate greater than that required by the operating Emergency Diesel Generator. This is verified by an increase in diesel day tank level during the diesel surveillance testing. In addition, full spectrum vibrational monitoring and measurement of pump discharge pressure will be performed with the results evaluated against the acceptance criteria of Table 3 of Part 6 of the Code.
Once each operating cycle the flow rate of each Diesel Fuel Oil Transfer pump will be determined indirectly by measuring the level change in the diesel day tank versus the pump operating time required to make that change. This will be performed with the respective Emergency Diesel Generator secured, the automatic pump start feature on low diesel day tank level disabled, and the diesel day tank volume reduced prior to the test through operation of the respective Emergency Diesel Generator. This testing will provide measurement accuracy comparable with Table 1 of Part 6 of the Code and the results will be evaluated against the acceptance criteria of Table 3 of Part 6 of the Code. As with the quarterly testing, full spectrum vibrational monitoring a"nd measurement of pump discharge pressure will be performed with the results evaluated against the acceptance criteria ofTable 3 of Part 6 of the Code.
Such testing is considered commensurate with the pump type and service and provides an acceptable level of quality and safety, based on the following:
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              ,,.        _                -                        e
 
Vermant Yenkes Nuclerr Power St2tien                                      Inservice Testing Program RELIEF REOUEST Number: RR-P09, Revision 0 (Sheet 4 of 4) l l  ALTERNATE METHOD (cont.h a)      A review of the pump design flow rate versus the diesel fuel oil consumption rate indicates
!          an excess capacity of approximately 60 percent. As such, operational readiness of the l          pumps is still assured with up to 60 percent degradation, provided that pump bearing l          vibration is not excessive. Assurance of acceptable pump bearing vibration levels is l          provided through the full spectrum vibrational monitoring.
i b)      A review of Vermont Yankee maintenance records and industry experience, as documented in NPRDS, indicates that the pumps are highly reliable and that the above testing methods are acceptable for assessing pump operational readiness and detent' ag potential degradation.
At Vennont Yankee, four (4) failures have occurred in twenty (20) years of plant operations. Of these failures, three (3) were related to electrical components and one (1) was related to high bearing vibrations. In addition, minor shaft seal leakage has been noted            :
and corrected.
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l          The industry experience is consistent with Vermont Yankee. For similar pumps in similar                I applications, fifteen (15) failures have been reported via NPRDS. Of these failures, nine (9) were related to excessive seal leakage, four (4) were related to electrical components and two (2) were related to high bearing vibrations.
Each of the above failure modes is adequately monitored during the quarterly inservice testing through visual inspection of the pump seals, proper starting and operation of the                l pump upon low diesel day tank level, and full spectrum vibrational monitoring.
f USNRC EVALUATION STATUS:                                                                        -
Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-P09, Revision 0.
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Vcrm::t Yc;kee N clear Pow r St:ti:n                            Inservice Testing Program RELIEF REOUEST Number: RR-PIO, Revision 1 (Sheet 1 of 1)
THIS RELIEF REQUEST WAS DELETED IN REVISION 18 OF THE IST PROGRAM.
This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
e Revision 19                                                                Section 4 Page31 of 31
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    . _. ~      - .      . - _ . - _ _ ___ _                                          _ _ . _ . _ _ . . . _ _ . . . _ .
Vcrmat Ycakee Nuclear Pcwer Stati::n                                      Ins:rvica Tcsting Prcgrcm i
5.0 Valve' Inservice Testing Program 5.1  Scope The Third-Interval Valve Inservice Testing (IST) Program establishes testing requirements -
to assess the operational r**dinaa of certain Safety Class 1,2, and 3 valves and pressure
                        - reliefdevices, including their actuating and position indicating systems The active or passive Safety Class 1,2, and 3 valves included are those which are required            !
to perform a specific functionin:
;                        a)          Shutting down the reactor to the cold shutdown condition, b)          Maintaining the reactor in the cold shutdown' condition, or c)        ' Mitigating the consequences of an accident.
l The Safety Class 1,2, and'3 pressure relief devices included are those for protecting systems or portion of systems which perform a required function in:
a)          Shutting down the reactor to the cold shutdown condition, L                          b)          Maintaining the reactor in the cold shutdown condition, or
                        - c)          Mitigating the consequences of an accident.
The following are excluded fmm the above, provided that they are not required to perform a specific function as specified above:
                          'a)          Valves used only for operating convenience such as vent, drain, instrument, and test valves; i                          b)          Valves used only for system control, such as pressure regulating valves; l
                          -)c        ' Valves used only for system or component maintenance.
!                        : Extemal control and protection systems responsible for sensing plaht conditions and providing signals for valve operation are also excluded from the above.
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Vcrmrt Ycnkee Nucirr Pr.wer Strti:a                                  Inservice Testing Prcgrrm 5.2  Valve Program Listing Table 5-1, " Valve Listing" lists all valves and pressure relief devices included in the Third-Interval ValveIST Program.
This Table identifies all valves and pressure relief devices subject to inservice testing, the inservice test requirements, testing frequency, and any applicable relief requests and/or      !
remarks. Table 5-1 is sorted by Drawing. The column headings in Table 5-1 are listed and        ;
explained below:                                                                                ;
1 Drawing The Flow Diagram which depicts the valve or pressure relief device. If the valve or pressure relief device appears on multiple Flow Diagrams, then the primary Flow Diagram identifieris listed.
Drawing Title l
The title of the Flow Diagram.
4 Valve Number The unique number that identifies the valve or pressure relief device. The valve number corresponds to the MPAC Database utilized at Vermont Yankee.
Nomenclature The common name for the valve or pressure relief device.
Dwg Coor The coordinate location (e.g., D-05) on the Flow Diagram where the valve or pressure relief devic.e appears.
Safety Class The safety class of the valve or pressure relief device as it appears on the Flow Diagram.
The safety classification of the valve or pressure relief device shown on the Flow Diagrams were determined in accordance with the Vermont Yankee Safety Classification Manual.
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Verm:nt Ycnkea Nucle r Pawar St:ti:n                                    Ins:rvics Testing Prcgram 5.2  Valve Program Listing (cont.)
OM Cat The valve category as defined by Paragraph 1.4 of Part 10 of the Code. All categories are identified for those valves which have more than one applicable category (i.e. A/C for category C valves that also have leakage requirements).
A:      Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required function (s).
B:    Valves for which seat leakage in the closed position is inconsequential for fulfillment of their required function (s).
C:    Valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves) for fulfillment of their required function (s).
D:    Valves which we actuated by an energy source capable of only one operation, such as rupture disks or explosively actuated valves.                                    ,
Active / Passive The valve classification as defined by Paragraph 1.1 of Part 10 of the Code.
Act Those valves which are required to change obturator position to accomplish their required function.
Pass Those valves which maintain obturator position and are not required to change obturator position to accomplish their required function.
Size (Inch)
The nominal pipe size of the valve, in inches.
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          . _                    .-. _ .. _ _                    _      ~ _ _ _ . _ . _ _ . _ . . . _ . _ . - .                          - - _ _
f-a i .'        Verm=t Ye:kee Nucle:r Pcwsr StIti::n                                                  -Ins:rvica Testing Program                      I Body L                      'Ihe valve body style designator where:                                                                                      ,
,                            WAY -          for 3-Way Valves L                                BL              for BallValves                                        ,
f                                BTF.            for Butterfly Valves CK? .            for simple CheckValves EFC              for Excess Flow CheckValves GA              for Gate Valves
!                                GL              for Globe Valves GSC            - for Globe Stop Check Valves .
RD-              for Rupture Discs .
RV              for ReliefValves.
SQUIB -          for explosively W-3 valves i                                SRV              for Safety /ReliefValves .
L l                      Actuator-The type of actuator provided with the valve body where:
AO      -
for Air Operated EXP              for Explosive Charge .
HO                for Hydraulically Operated                                                                        ;
MAN              for Manually Operated                                                                              j I
                                . MO-AC            for Motor Operated, AC powered motor MO-DC            for Motor Operated,DC powered motor SA                for Self Actuated (i.e. Relief Valves, etc.)
SO-              for Solenoid Operated NormalPosition This field details the valve's position during normal plant operation (if the subject system is L                        required to be in a standby condition during normal power operation, the valve's normal                                      4
+                        position is the position of the valve when the system is in it's standby condition), where:
C      for Closed LC for Locked Closed O.      for Open LO for Locked Open
;-                              O/KLfor Open, Key Locked L                                O/C for Open or Closed (dependent on system demand) l                                T-      for Throttled i1 Revision 19 -                                                                                        Section 5 Page 4 of 179 i-
 
Vcrm::t Yc:::kso Nucirr Pcwer Stati:n                                    Inservice Testing Pr: gram Safety Position The position a valve or pressure-relief device is required to function in shutting down the reactor to the' cold shutdown condition, maintaining the reactor in the cold shutdown y              condition, or mitigating the consequences of an accident.
i                      C    for Closed function O    for Open function O/C for both Open or Closed functions l              Test Type (and Stroke Direction) l-            The test type is an abbreviation of the type of test required to be performed and the stroke l
direction in which the test is performed.
l LJ    OM Category A Valves, which are containment isolation valves tested in accordance with the requirements of OM-10 subsection 4.2.2.2 and 10 CFR 50 Appendix J on a fixed frequency. Analysis ofleakage rate and corrective j                            action is in accordance with OM-10 subsection 4.2.2.3 (e) and (f).
l                      LJB OM Category A Valves, which are containment isolation valves tested in accordance with the requirements of OM-10 subsection 4.2.2.2 and 10 CFR
:                            50 Appendix J using Option B performance criteria to establish variable test frequencies. Analysis ofleakage rate and corrective action is in accordance with OM-10 subsection 4.2.2.3 (e) and (f).
LT OM Category A Valves, which perform a function to limit leakage to a
!                            specific amount and are tested in accordance with the requirements of OM-10 subsection 4.2.2.3.
LEF . Category A Excess Flow Check Valves, which perform a function to limit leakage to a specific amount and are tested in accordance with the requirements of OM-10 subsection 4.2.2.3. Satisfactory completion of excess flow check valve leakage testing also satisfies both the open and close valve L                            exercise requirements of OM-10 subsection 4.3.2.2.
L                      STC Active Category A and B Power-Operated Valves, whiefi are full-stroked tested in the closed direction and the stroke times are measured and evaluated in accordance with Paragraph 4.2.1 of Part 10 of the Code.
L                    STO Active Category A and B Power-Operated Valves, which are full-stroked tested in the open direction and the stroke times are measured and evaluated in accordance with Paragraph 4.2.1 of Part 10 of the Code.
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l~ Vermcnt Ycnkea Nuclear Pawar St:tirn                                  Inservice Testing Prsgr:m Test Type (cont.)
SC Active Category A and B Non-Power-Operated Valves and Category C Check Valves, which are full-stroked tested in the closed direction in accordance with Paragraphs 4.2.1 and 4.3.2 of Part 10 of the Code.
SO Active Category A and B Non-Power-Operated Valves and Category C Check Valves, which are full-stroked tested in the open direction in accordance with Paragraphs 4.2.1 and 4.3.2 of Part 10 of the Code.
PSC Active Category A and B Valves and Category C Check Valves, which are partial-stroked tested in the closed direction in accordance with Paragraphs 4.2.1 and 4.3.2 of Part 10 of the Code.
PSO Active Category A and B Valves and Category C Check Valves, which are partial-stroked tested in the open direction in accordance with Paragraphs 4.2.1 and 4.3.2 of Part 10 of the Code.
PIT Valves with remote position indicators are verified in accordance with Paragraph 4.1 ofPart 10 of the Code.
FST Active Category A and B Valves with fail-safe actuators, tested in accordance with Paragraph 4.2.1.6 of Part 10 of the Code.
ET OM Category D Explosively Actuated Valves, which are tested in accordance with Paragraph 4.4.1 of Part 10 of the Code.
RD OM Category D Rupture Discs, which are replaced in accordance with Paragraph 4.4.2 of Part 10 of the Code.
CD OM Category C Check Valves, which are disassembled in accordance with paragraph 4.3.2.4(c) of Part 10 of the Code.
SP    OM Category C Relief and Safety Relief Valves are tested in accordance with Paragraph 4.3.1 of Part 10 of the Code.
SKIDActive Category A, B and C skid-mounted components or component subassemblies in which testing of the major component is an acceptable means        for verifying the operational readiness of the skid-mounted and component subassemblies in accordance with NUREG 1482, Paragraph 3.4.
N/A For passive valves with no testing required.
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Vcrm:nt Ycekee Ncci:cr Pcwsr Sthtim                                            . Inservics Testing Prcgram l
l.
l Test Frequency L                                                  >
L                      The test performance frequency associated with each test type will be specified where:
1-1                              IM for every 1 Month l                              6M for every 6 Months' 1Y    for every 1 Year 2Y for every 2 Years 5Y for every 5 Years 10Y for every 10 Years CS for Cold Shutdown .
L                              OC' for Once Per Operating Cycle D
                              'Q      for Quarterly RO forReactor Refueling Outage
                            . N/A for Not Applicable Var for Variable IAW Appendix J Option B performance criteria l
CSJ/ROJ/RR The Cold Shutdown Justification / Refuel Outage Justification or Relief Request number                        ,
associated with the subject valve or pressure relief device and test type or test frequency, .
                      . where applicable.
Remarks .
When appropriate, clarifying comments or other remarks will be included for the affected valve, pressure relief device, test type or test frequency.
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                                                                                                                                                                                                                                                                  ,Eq Vcrm:nt Ycnkee Nrclear Psw:i:r Statio2                                                                                                                                                                                        Eservice Testi g Program Table 5-1 Valve Listing '
  - Drawing: 5920-271                          DrawingTitle: NeutronMonitoring System '
Dwg Safety OM Act / Slee                                                                my  Act Nona Safety FaEl TestTest CSJ/ROJ                                                            h6 Valve Number          Nomienclature Coor Class Cat Pass (inch)                                                                        Pos  Pos Posl Type Freg                                                      RR BY-7-1              Neutron Monitoring          C 2                    A Act .375                                                    BL  SO    C    C                FC FST- Q                                            n/a    Note 6 Systan11P hbe Ball                                                                                                                                                          U          2Y                  n/a                                '
Valve                                                                                                                                                                  PE 2Y                                Wa S7C                  Q                  n/a BY-7-2              Neutron Monitoring          C-07          2            A Act .375                                                    BL  SO    C    C                FC FST Q                                              n/a    Note 6 SystanTIP hbe Ball                                                                                                                                                          U          2Y                  n/a                                i
                                                                                                                                                                                                                                                                          ~
Valve                                                                                                                                                                  PE 2Y                                Wa S1C                  Q                  n/a BV-7-3              Neutron Morutonng            C-07          2          A Act .375                                                    BL  SO    C    C                FC FST' Q.                                            n/a    Note 6 SystenTip TubeBall                                                                                                                                                          LJ          2Y                  n/a Valve                                                                                                                                                          - PIT 2Y                                      Wa                                  :
STC                  Q                  n/a                                ,
S-7-1                Neutron Moniering            C-07          2          D  Act .375 SQUIB EXP                                                    O    C                n/a - ET                        RO                  n/a                                -
SystanTiphbe Shear Valve S-7-2                Neutron Monitoring          C-07          2          D  Act .375 SQUIB EXP                                                    O    C                n/a ET- RO                                            n/a                                i SystemTip Tube Shear                                                                                                                                                                                                                                ,
Valve                                                                                                                                                                                                                                              i n/a . ET..                      RO                                                        I s-7-3                Neutron Monitoring          C-07          2          D Act .375 SQU1B EXP                                                    O. C                                                                      n/a Systan 71p'ITibe Shear                                                                                                                                                                                                                            l Valve                                                                                                                                                                                                                                            .
I f
Revision 19                                                                      Drawig : 5920-271                                                                                                                                    Section 5  Page 8 of 179        !
i
 
  - Vcrmont Yankee Nuclear Power Station                                                                                                                              Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191159 Sh 1                    Drawing *Iltle: Senice WaterSystem Dwg Safety OM Act / Size Body                                    Act                      Nonn Safety Fail Test Test CSJ/ROJ                                                            hah Valve Number          Nomenclatner Coor Class Cat Pass (inch)                                                                  Pos  Pos Pos Type Freq      RR FCV-104-17A      , SW Supply to Screen    D-04  3      B  Act  4    GA                                  HO                        C    C    FC FST      Q    n/a                                        Note 8 Wash Flow ControlValve                                                                                                              STC    Q    n/a FCV-104-17B        SW Supply to Screen    E-04  3      B  Act  4    GA                                  HO                        C    C    FC FST      Q    n/a                                        Note 8 Wash Flow ControlValve                                                        .                                                    S1C    Q    n/a PCV-104-17C        SW Supply to Screen    F-04  3      B  Act  4    GA                                  HO                        C    C    FC FST      Q    n/a                                      Note 8 Wash FlowControlValve                                                                                                                STC    Q    n/a FCV-104-17D        SW Supply to Screen    F-04  3      B  Act  3    GA                                  HO                        C    C    FC FST      Q    n/a                                      Note 8 Wash Flow ContmlValve                                                                                                                STC    Q    n/a FCV-104-17E        SW Supply to Screen    G-04  3      B  Act  3    GA                                  HO                        C    C    FC FST      Q    n/a                                      Note 8                              ,
Wash FlowControlValve                                                                                                                STC    Q    n/a PCV-104-69A        RHRSW PCV for SW to    J-13  3      B  Act  8    GL                                  AO                        C    O    FO FST      Q    n/a                                        Note 8 A-EDG and RRUs 5,7                                                                                                                  S1D    Q    n/a PCV-104-69B        RHR PCV for SW to B-    B-13  3      B  Act  8    GL                                  AO                        C    O    FO FST      Q    n/a                                      Note 8 EDG AND RRUs 6,8                                                                                                                    S1D    Q    n/a SE-70-4A            RHRSW Pump Motor        K-10  3      B  Act  1    GA                                    SO                      C    O    FO FST      Q    n/a                                                                          .
Cooling coilSupply                                                                                                                  S10    Q    n/a Valve SE-70-4B            RHRSW Pump Motor        K-10  3      B  Act  1    GA                                    SO                      C    O    FO FST    Q      n/a Cooling CoilSupply                                                                                                                  STO  Q      n/a Valve SE-70-4C            RHRSW Pump Motor        K-10  3      B  Act  1    GA                                    SO                      C    O    FO FST    Q      n/a Cooling Coi! Supply                                                                                                                  SiO  Q      n/a Valve SE-70-4D            RHRSW Pump hlotor      K-10  3      B  Act  1    GA                                    SO                      C    O    FO FST    Q      n/a i
Cooling coil Supply                                                                                                                  STO  Q      n/a Valve SP-70-3A            A Service WaterStrainer H-05  3      B  Act  2    BL                                  AO                        C    C    FC FST    Q      n/a                                    Note 8 Backwash Valve                                                                                                                      STC  Q      n/a Revision 19                                                    Drawing : G-191159 Sh 1                                                                                  Section 5                                                    Page 9 of 179
 
t P
Vcrmont Yankee Nuclear Power Station                                                                                                                                                                              Inservice Testing Program
                                                                                                        - Table 5-1 Valve Listing Drawing : G-191159 Sh 1 -                              Drawing Tkle: Semcc Water System Dwg Safety OM Act / Size                                                      wy    . Act Norma Safety Fa8 Test Test CSJ/ROJ hah Valve Museber          Noemenclature Coor Class Cat Pass (isnk)                                                                  Pos    Pos              Pos Type  Friq                              RR                                                            ,
SP-43B                B SanceWaterStramer C-05                      3      B                  Act                              2        BL'    AO    C      C                FC FST        Q                              n/a    Note 8                                                ,
BackwashValve                                                                                                                                                S7C        Q                              n/a SR-%13A              RHRSW Pump Motor                    L-09      3      C Act                                            .75        RV      SA    C    O/C n/a SP                      10Y                              n/a                                                          i Cooling Relief Valve                                                                                                    .
SR-78-13B            RHRSW Panp Motor                    L-09      3      C Act                                            .75        RV      SA    C    O/C n/a SP                      10Y                              n/a Cooling ReliefValve                                                                                                                                                                                                                                                .!
SR-%I3C              RHRSW Panp Motor                    L-09      3      C Act                                            .75        RV      SA    C    O/C n/a SP                      10Y                              n/a Cooling ReliefValve SR-%13D              RHRSW Pump Motor                    L 09      3      C                    Act                          .75        RV      SA    C    O/C n/a SP                      10Y                              n/a Cooling ReliefValve SR-42A              SWReliefValve                        I-08    3      C Act                                                1      RV      SA    C    O/C . n/a SP                    10Y                              n/a                                                          [
SR-79-25            SW ReniefValve                      C-08      3      C Act                                                1      RV      SA    C    O/C n/a SP                      10Y                            ' n/a                                                          [
!    V78-130A            CW Pump Cooling SW                  C-05      3      B                  Act                              3      GA    MAN    O      C                n/a SC        Q                              n/a    Note 8                                                l Supply                                                                                                                                                                                                                                                                ,
t V78-130B              CW Pump Cooling SW                  I-05      3      B                    Act                            3      GA    MAN    O      C                n/a SC_        Q                            _ n/a    Note 8 Supply                                                                                                                                                                                                                                                                j V70-13A              SW Supply to the A                  J-07      3      B                  Act                            24        GA    MAN    O    O/C n/a SC                      RO ROI-V16 Note 8 HenderIsoldion V70-13B              SW Supply to the B                  B-07      3    B                    Act                            24        GA    MAN    O    OC n/a SC                      RO ROJ-V16 Note 8 HenderIsolation V79-15A              SW Supply to the A                  J-08      3      B                  Act                            12        GA    MAN    O      C                n/a SC        RO ROJ-V17 Note 8 RBCCW Heat Exchanger                                                                                                                                                                                                                                                  j V70-15B              SW Supply to tiie B                  B-08      3      B                  Act                            12        GA    MAN    O      C                n/a SC        RO ROJ-V17 Note 8 RBCCW Heat Exchanger l
V70-16B              Altanate Cooling to SW C-09                    3      B                  Act                            24        GA    MAN    C    O/C n/a SO                      RO ROJ-V21 Note 8                                                                              ,
Supply Revision 19                                                                                      Drawing : G-191159 Sh 1                                                                                                      Section 5                  Page 10 of 179
_ . _    _  __mm_._..a        _ _ _ _ . __-_.___.____m.____-_---_*_.____-____-__.____.i.____2___..__.m_..                _-_.  .________m__m.u.            _. _.________-__.____._______m_          _ . _ _ _ . _ _ _ _ n___+-_      __  _ _ _ _ _ _ +
 
a l
Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                                    Insenvice Testing Program                                                !
1 Table 5-1 Valve Listing                                                                                                                                                                                  j Drawing: 0-191159 Sh 1                              Drawing 11tle: Semce Water System :
Dwg Sa % OM Act / h                                                                Body                        Act                Nonn Safety fab Test Test CSJ/ROJ                                                                hah                  'I Valve Nunnber                    Nommenclature Coor Class Cat Pass (inch)                                                                                                            Pos  Pos Pos Type Freg                        RR V79-184                  AltCooling WaterLine        C-09 ~3                        B          Act                      1                  GA                    MAN                    C  O/C n/a SC              RO ROJ-V21 Note 8 Vent                                                                                                                                                                                    SO    RO ROJ-V21                                                                                f V79-187A                  Gland SealSupply to SW J-06        3                        B          Act 1.25                                    GA                    MAN                    O    C        n/a SC        RO ROJ-VI8 Note 8 -                                                                        ~
Panps A and B                                                                                                                          .
V79-187B                  Gland SealSupply to SW B-06        3                        B          Act 1.25                                    GA                    MAN                    O    C . n/a SC            RO ROJ-VI8 Note 8                                                                          l Pumps C and D V79-19A                  SW Supply Hcnder            H-09  3                        B          Act                    24-                  GA MO-AC O                                        O/C FAI PIT 2Y                            n/a                                                                    1 C.+++          - t Valve                                                                                                                                                          SE Q                        n/a                                                                    i i                                                                                                                                                                                                                      SM Q                        n/a V7519B                    SW Supply Hender            C-09  3                        B          Act                  24                  GA MO-AC ' O                                      O/C FAI PIT ~ 2Y                          n/a CrossconnectValve                                                                                                                                                                  sm - Q                      n/a N        Q
* V79-1A                    Savice Water Peng          C-02  3                        C          Act                    14                  CK                        SA                O/C  O/C n/a PSO            Q ROJ-V14 Note 10 Discharge Check Valve                                                                                                                                                                    SC  RO ROJ-V14 SO    RO ROJ-V14 V70-1B                    Service WaterPanp          B-02  3                        C          Act                    14                  CK                        SA                O/C  O/C n/a PSO            Q ROJ-V14 - Note 10                                                                        i Discharge Check Valve                                                                                                                                                                  SC    RO ROJ-V14 SO    RO ROJ-V14                                                                                ,
t V79-IC                    Service Water Pump          K-02  3                        C          Act                    14                  CK                        SA                O/C  O/C n/a PSO            Q ROJ-V14 Note 10 Discharge Check Valve                                                                                                                                                                  SC    RO ROJ-V14 SO    RO ROJ-V14 V70-1D                    ServiceWaterPump            J42    3                        C          Act                    14                  CK                        SA                O/C  O/C r/a PSO            Q ROJ-V14 Note 10 Discharge Check Valve                                                                                                                                                                  SC    RO ROJ-V14 SO    RO ROJ-V14 V70-20                    SWSupply Valve to          H-11  3                        B          Act                  20                  GA MO-AC O                                          C        FAI PIT 2Y                      n/a Turbine Building Cooling                                                                                                                                                            SE        Q                  n/a                                                                    i Loads Revision 19                                                                                        Drawing : G-191159 Sh 1                                                                                                                  Section 5                                  Page 11 of 179 i
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                      Inservice Testing Program Table 5-1 Valve Listing                                                                                                                                                                            .j Drawing: G-191159 Sh 1                          Drawleg
 
==Title:==
Service WaterSystem Dwg Safety OM Act ! Size Body                                      Act None Safety fab Test Test CSJ/ROJ                                                              h&                                                    t Valve Number                Nomenclature Coor Class Cat P.e:s (inch)                                              Pos  Pos Pos Type Freg                                        RR V7424B                  Alternate Cooling Supply C-12            3 B Act 2.5                          GA            MAN  C    O    n/a SO                      Q                      n/a    Note 22 to RBCCW                                                                                                                                                                Valve also appears on G-191159 Sh3 V7&27                    SW to Firewater          D-02            3 B Act    1.5                        GL          -MAN  LO    C    n/a SC                    Q                        n/a    Note 8 m ___ ,..g Line V70-281A          18B SW Sydan Vacuurn            J-09            3 C Act    2                    .CK                SA  C  OC n/a SC                    RO ROJ-V28 BreakerCheck Valve                                                                                                    SO            RO ROJ-V28                                                                                                        I WS-281B          18B SW Sydan Vacuum              B-09            3 C Act . 2                        CK            SA  C  OC n/a SC                    RO RGJ-V28 BreakerCheckValve                                                                                                    SO            RO ROJ-V28                                                                                                        ,
1
  - V70 281C          isB SW System Vacuum            J-09            3 C Act    2                        CK            SA  C  OC n/a SC- RO ROJ-V28                                                                                                                          ;
BreakerCheck Valve                                                                                                  SO RO ROJ-V28 V70-281D          18B SWSystem Vacuum              C-09            3 C Act    2                        CK            SA  C  OC n/a SC                    RO ROJ-V28 BreakerCheck Valve                                                                                                    SO            RO ROJ-V28                                                                                                        .
V70-29                    Alternate Cooling to SW D-13            3 B Act    3                        GA            MAN  C    O    n/a SO                    Q                        n/a    Note 22 Supply                                                                                                                                                                  Valve also appears on G-191159 Sh 3 V79-29A                  Alternate Cooling to SW D-13            3 B Act    3                        GA            MAN  C    O    n/a SO                    Q                        n/a    Note 22                                                                      ,
Supply                                                                                                                                                                  Valve also appears on G-191159 Sh 3 V70-2A                    SWPump Discharge        C-03            3 B Act    14                      GA            MAN  O-  OC n/a SC                  RO ROJ-V16 Note 8 Isolation Valve                                                                                                                                                                                                                                        ;
i V70-2B                    SW PumpDischarge        B-03            3 B Act    14                        GA            MAN  O  OC ' n/a SC                RO ROJ-V16 - Note 8                                                                                                i Isolation Valve,                                                                                                                                                                                                                                    i V70-2C                    SW Pump Discharge      J-03            3 B Act    14                        GA            MAN  O  OC n/a SC                  RO ROJ-V16 Note 8 IsolationValve V70-2D                    SW Pump Discharge      J-03            3 B Act    14                        GA            MAN    O  OC n/a SC                  RO ROJ-V16 Note 8 Isolation Valve                                                                                                                                                                                                                                      ;
I Revision 19                                                            Drawing : G-191159 Sh 1                                                                                              Section 5          Page 12 of 179
 
m Vcrmrt Yc;kee Nrclear Pcwcr St: tion                                                                                        Inservice Testing Program Table 5-1 Valve Listing Erawing: G-191159 Sh l                          DrawingTitle: Service WaterSystem Nomenclature          Dwg Safety OM Act / Size My      Act    Norm Safety Fail Test Test CSJ/ROJ                    hah Valve Number Coor Class Cat Pass (inch)                Pos  Pos Pos Type Freg          RR V7042B                    Attemate Cooling Supply C-12  3    B    Act 2.5    GA  MAN      C    O    n/a SO            Q    n/a        Note 22 to RDCCW                                                                                                        Valve also appears on G-191159 Sh 3 V70 36A                  Altemate Cooling Supply C-13  3    B    Act  3    GA . MAN      C    O    n/a SO            Q    n/a        Note 22 to RBCCW                                                                                                        Valve also appears on G-191159 Sh 3 V70,36B                  Alternate Cooling Supply C-13  3    B    Act  3    GA    MAN      C    O    n/a SO          Q    n/a        Note 22 to RBCCW                                                                                                        Valve also appears on G-191159 Sh 3 V7048A                    RIIRSW Pump Discharge K-12    3    C    Act  12    CK    SA      C  O/C n/a SC            Q    n/a Check Valve                                                                        SO        Q    n/a V70,38B                  RIIRSW Pump Discharge B-12    3    C    Act  12    CK    SA      C  O!C n/a SC            Q    n/a CheckValve                                                                          SO        Q    n/a V70-40A                  RIIRSW Pump Discharge K-12    3    C    Act  12    CK    SA      C  O/C n/a SC            Q    n/a CheckValve                                                                          SO        Q      n/a V70-40B                  RIIRSW Pump Discharge A-12    3    C Act      12  CK    SA      C  O/C n/a SC            Q      n/a CheckValve                                                                          SO        Q      n/a V70-42A                  RIIRSWAltanate          K-13  3    B    Act  8    GA    MAN      C    O    n/a SO          Q      n/a        Notc 8 Cooling to SW Supply V70-42B                  RHRSW Altemate          B-13  3    B    Act  8    GA    MAN      C    O    n/a SO          Q      n/a        Note 8 Cooling to SW Supply V70-43A              IBA SW Discharge Loop        J-12  3    C Act      8    CK    SA      O  O/C n/a PSO          Q      n/a IIender Check Valve                                                                SC    RO ROJ-V32 SO    RO ROJ-V32 V70 43B              18A SW Discharge Loop        B-12  3    C Act      8    CK    SA      O  O/C n/a PSO          Q      n/a IIca&r Check Valve                                                                SC    RO ROJ-V32 SO    RO ROJ-V32 Revision 19                                                          Drawing : G-191159 Sh 1                                        Section 5    Page 13 of 179
 
Vcrmont Yankee Nuclear Power Station -                                                                                                                                                                          Inservice Testing Program Table 5-1 Valve Listing Drawing: 'G-191159 Sh 1                                Drawing
 
==Title:==
' Service Water System -
Dwg Safety OM Act / Size My                                      Act          Nona Safety fab Test Test CSJ/ROJ                                                                                  hah Valve Namber                    Nomenclature Coor Class Cat Pass (inch)                                                          Pos                  Pos Pos Type Freg                            RR V70-504                        Alternate Cooling to SW D-12        3      B Pass 2            GA                          MAN                  C                  C  n/a n/a                            n/a-    n/a Supply V70,511B                  IRB SW System Vacuum            H-12    3      C Act      2        CK                          SA                  C                O/C n/a SC                            RO ROJ-V28 Breaker CheckValve                                                                          .                                                  SO                            RO ROJ-V28 V70-5 1C                ISB SW System Vacuum            H-12    3      C    Act    2        CK                          SA                  C                O/C n/a SC                            RO ROJ-V28                                                                                                i BreakerCheck Valve                                                                                                                            SO                            RO ROJ-V28 V705A                        SW X-connection to Fire J-03        3      B Pass    20        GA                          MAN                  O                  O  n/a n/a                            n/a    n/a Systan V70-5B                        SW X-connection to Fire C-03        3      B Pass    20        GA                          MAN                  O                  O  n/a n/a                            n/a    n/a Systan V704                          SW ScreenWash              F-03    3      B    Act    8        GA                          MAN                  O                  C  n/a SC                            Q      n/a                            Note 8 Alternate Cooling / Isolation Valve Revision 19                                                                    Drawing : G-191159 Sh 1                                                                                                              Section 5                              Page 14 of 179
__ _        __._m. _.___- . _ _ _ . _ _ _ _ _ _      ____._-.._______.____..____._-___m_            . . _ _ _ _ _ . _ . _ _ . -          __...______.__..__.________m                      __._____.___._____;_._.____-_
 
Vermont Yankee Nuclear Power Station                                                                                Inservice Testing Program Table 5-1 Valve Listing                                                                    ,
Drawing : G-191159 Sh 2                    Drawing
 
==Title:==
Service WaterSystem Dwg Safety OM Act / Sire Body        Act  Nona Safety Fail Test Test CSJ/ROJ              RemW Valve Nuunber        NomencInture Coor Class Cat Pass (inch)                    Pos  Pos  Pos Type Freg    RR FCV-104-28A        Diesel Generator A        H-05  3      B    Act    8    GL    AO      C  O    FO SKID Q        n/a      Note 12 Cooling WaterInlet
(
FCV-104-28B .      DieselGenerator B        D45    3      B-  Act    8    GL    AO      C  O    FO SKID - Q      n/a      Note l2                        r CoolingWaterInlet                                            .                                                                            +
i  PCV-104-73A    18B DieselGeneratorA          J-04  3      B    Act    8    GL    HO      O  O    FO SKID Q        n/a      Note l2 ServiceWaterPump                                                                                                                          ;
i PCV-194-73B    18B DieselGenerator B          B-04  3      B    Ac:    8    GL    HO      O. O    FO SKID Q        n/a -  Note 12 Service Water Pump                                                                                                                        ,
Disclurge                                                                                                                                  ;
SB-70-1            SW To Main C*~          D-09 NNS B          Act  24    BW  MAN O/C      OC n/a SC        CS CSJ-V16 Note 8                            ,
Ducharge Block Valve                                                                    SO  CS CSJ-V16                                    ;
t SR-78-16A          DieselGeneratorJacket    I-06  3      C Act      1    RV    SA      C  OC ' n/a SP      10Y    n/a WtrCoolerSafety Relief Valve SR-76-16B          Diesel Generator Jacket  C-05  3      C    Act    1    RV    SA      C  O/C n/a SP      10Y    n/a                                    i WtrCoolerSafety Rehef                                                                                                                      l f
Valve RHRHX ServiceWater              *      *    *    *      *    *      *  *    *    *    *
* V10-89A =                                  H-01
* See G-191172 for valve .
Outlet Valve                                                                                                info and test i%-.~a.          l V16 89B a          RHR HX Scrvice Water      E-01
* See G-191172 forvalve OutletValve                                                                                                info and test requirements    f SWDucherge to Cooling D-07                                GA  MAN OC      OC n/a SC        CS CSJ V16 Note 8 V79-11                                              3      B    Act  14                                                                                      .
TowerBasinIsolation                                                                    SO. CS CSJ-V16                                      r Valve          =
i v70-16A            Alt. Cing Deep Basin to  D-07    3      B    Act  24    GA  MAN      C  OC n/a - SO      RO ROJ-V21 Note 8                            ?
RHRSW Pump Suct. Iso.                                                                                                                      [
Valve                                                                                                                                      -
MAN OC                        CS CSJ-V16 Note 8 V70-17            Alternate Cooling to SW D-06    3      B    Act  20    GA                O    n/a SO Supply
. Revision 19                                                      Drawing : G-191159 Sh 2                                Section 5    Page 15 of 179          ;
I I
 
Vermont Yankee Nuclear P;wer Statior                                                                                                                                                                                                                                              Inservice Testi;g Prograin Table 5-1 Valve Listing                                                                                                                                                                                                                                                  ;
Drawing: ' G-191159 Sh 2                                                Drawing'lltle: Semce WaterSystem Dwg Safety OM Act / Size My                                Act                          Nons Safety fab Test Test CSJ/ROJ                                                                                                                                                  h6 Valve Nussber I                    Mommsclature Coor Class Cat Pass (inch)                                                                  Pos  Pos Pos Type Freg                                                                                                      RR V7s-17A                            #1 West Cing Tower SW D47                      3      B Pass                6        GL          MAN                                  T  O' n/a SC RO~                                                                                                            n/a                                    Note 9 DistributionTray Valve                                                                                                                                                          SO . RO                                                                        ' n/a                                      Note 22 V7s-173                            #1 West Cing TowwSW D-07                        3      B Pass                6        GL      -
MAN                                  T  O . n/a SC                                                              RO                                              n/a                                    Note 9 -                  i
                                                  ~ DistributionTrayValve                                                                                                                                                            so, RO                                                                              n/a                                    Note 22 6-                  MAN                                  T              n/a SC                                                      RO
,                V70-17C                            #1 West Cing Towa SW D-07                      3    .B  Pass                        GL                                                  O                                                                                                                        n/a                                    Note 9                    !
DistributionTray Valve                                                                                                                                                          SO                                  RO                                              n/a                                    Note 22 -
V70-17D                          #1 West Cing Tower SW D-07                      3      B Pass                6        GL.        MAN                                  T-  O          n/a SC 'RO                                                                                                  n/a                                    Note 9 DistributionTray Valve                                                                                                                                                    .SO RO                                                                                    n/a                                    Note 22 i
V76-Is                            SW Discharge Hender                      E47    3      B  Act              20        GA        MAN                                  O  O/C n/a ' SC                                                              CS CSJ-V16 Note 8                                                                                              .!
IsolationValve V70-283                          SW Supply to RRU-9                      B-03  3      B  Act 1.25                    GA        MAN                                  O-  C          n/a SC                                                          Q                                            n/a .                                  Note 8 Isolation Valve V70-206                          SW to RRITs 17A and                      J-03  3      B  Act              2          GA        MAN                                  O-  C          n/a SC                                                          Q                                          n/a                                    Note 8
!                                                    17B, Isolation Valve                                                                                                                                                                                                                                                                                                                  i s
V76-252B          ~ 18B SW System vacuum                                  G-05  3      C  Act                2        CK              SA                              C  O/C n/a SC                                                                RO ROJ-V28                                                                                                        ,
Bienker CheckValve                                                                                                                                                              SO                                RO ROJ-V28                                                                                                        !
V76252C              isB SW System Vacuum                                . G-05  3      C  Act                2        CK              SA                              C  O/C n/a - SC                                                            RO ROJ-V28
;                                                    Breaker CheckValve                                                                                                                                                              SO                                RO ROJ-V28 .
V76 414                          SW to Red Monitor from D-08 NNS B                        Act            .75        GA        MAN O/C                                  C.      .n/a 3C                                                            Q                                          n/a -                                    Note 8 SW Discharge to Deep                                                                                                                                                                                                                                                                                                                  ;
Basin Revision 19                                                                                  Drawing : G-191159 Sh 2                                                                                                                                                                                      Section 5 - Page 16 of 179 2
___._.m- . _ . _ .    ._.m._.____.__.________.______.______._____m                                    _ _ _ _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ . _ _
 
Inservice Testing Program Vermont Yankee Nuclear Power Station -
Table 5-1 Valve Listing Drawing: G-191159 Sh 3                                                      Drawing'I1tle: RCW Cooling Water System Dwg Safety OM Act / Size My                          Act Norm Safety fab Test Test CSJ/ROJ                                        RemW Valve Number                    Nonneoclatuit Coor Class Cat Pass (inch)                                  Pos          Pos Pos Type Freg                      RR RV-70-117A                RBCCW Drywell Piping M-10 2                                        C Act .75                        RV    SA  LC          OC n/a SP          10Y                      n/a TherinalReliefValve SR-70-1A                  SW ReliefValve                                      B-04    3    C  Act    1                    RV    SA    C          OC n/a .SP        10Y                      n/a SR-70-1B                  SW ReliefValve                                      C-04    3    C Act      1                    RV    'SA    C          OC n/a SP          10Y                      n/a                                              '
SR-79-6A                SW ReliefValve                                      J-05    3    C  Act      1                    RV. ~  SA    C          OC n/a SP          10Y                    n/a SR-78-6B                SW ReliefValve                                      I-05    3    C Act      1                    RV    SA    C          OC n/a SP          10Y                    n/a V70-106                  Rad Waste Building Inlet P-02                                3    B  Act    2                    GA    MAN    O                  C n/a SC    Q                      n/a      Note 8 V70-107                  RadWaste Building                                    P-05    3    B  Act    2                    GL    MAN    O                  C n/a SC    Q                      n/a      Note 8 Outlet                                                                                                                                                                                                                  t V7o-113        iss Prunary contanunent                                      K-08    2    AC Act      8                    CK    SA    O                  C n/a LJB Var                      nha RCWSupplyIsolation                                                                                                                        SC  RO ROJ-V24 Valve V76-113D                Test Connection for                                  L-08    2    B Pass    .75                    GA    MAN  LC                  C n/a n/a  n/a                    n/a
,                            Penetration X-23 V79-117        18B Prunary Contauunent                                      L-12    2    A Act      8                    GA MO-AC O                      C FAI LJB Var                    n/a
>                            RBCCW Return Valve                                                                                                                        PIT 2Y                    n/a S'IC CS CSJ-Vol V19-117D                Test Connection for                                M-12    2    B Pass    .75                    GA    MAN  LC                C  n/a n/a  n/a                    n/a                                              j Penetration X-24 V70-24A                  RBCCWcooling to CRD N-02                                    3    B  Act    2.5                    GA    MAN    O        O/C n/a SC            Q                    n/a      Note 8 and B/D RHRPumps Alternate Cooling Supply O-03                                *    *    *    *                      *      *    *                  *  *    *  *                        *
* See G-191159 Sh I for V70-24B =
to RBCCW                                                                                                                                                                      valve info and est                        i requirennents V70-28                  RBCCWcooling to CRD O-10                                    3    B Pass    3                    GA    MAN  C                C  n/a n/a  n/a                  n/a      Note 8 end RHRPurnps                                                                                                                                                                                                            .
Revision 19                                                                                      Drawing : G-101159 Sh 3                                                                          Section 5    Page 17 of 179 t
 
Vermont Yankee Nuclear Power Station                                                                                                                                                          . Inservice Testing Program ~
Table 5-1 Valve Listing                                                                                                                                    ,
Erawhag: G-191159 Sh 3 -                                      DrawingTitle: RCW Cooling WaterSystem Dwg Safety OM Act / Size My                            Act None Safety fab Test Test CSJ/ROJ                                                    h6 Valve Number                              Nomienclature Coor Class Cat Pass (inch)                                    Pos  Pos' Pos Type Freg                                          RR V79-28A                                RBCCW cooling to CRD O-10          3'  B    Act    3    GA                      MAN  O~  OC n/a SC                                            Q'    n/a    . Note 8 and RHRPiunps Alternate Cooling Rettun Q-10      *  *    *    *        *                    *    *    *        *-                    *                  *
* V79-29 *                                                                                                                                                                                              -
* See G-191159 Sh I for                  ;
fanRBCCW                                                                      .                                                                                valveinfo and test requu==en                              -
,                    V73 29A
* AlternateCooling Return P-10      *  -*    *    *        *                    *    *    *        *                      *                  *-      *
* See G-191159 Sh I for i                                                                                                                                                                                                                                                                      !
fanRBCCW                                                                                                                                                        valveinfo and est W                                        i I
V7930A              18B                C"'i Pump 1A Cooler    1,4      3  B    Act    I    ~ GA                    MAN  O    C    N/A SC                                          Q      n/a      Note 23 Ira iss CRD Pump 1B Cooler                                      Act          GA                      MAN  O    C    N/A SC.                                                                                                  :
V7saeB                                                        M-4      3  B          1                                                                                            Q      n/a    - Note 23 V79J1A                isB CRD Pump 1A Cooler                    M-4      3  B    Act    1    GL-                    MAN  O    C'  N/A SC                                          Q      n/a      Note 23 outlet                                                                                                                                                                                                    t V7041B              Is'B CRD Pump IB Cooler                  N-4      3  B    Act    1    GL                      MAN  O    C    N/A SC                                          Q      n/a      Note 23                                  !
Outlet i                      V7042A                                  RBCCWcooling to        P-02      3  B    Act  2.5    GA                      MAN  O  O/C n/a SC.                                          Q      n/a      Note 8                                    ;
Radweste and AE RHR                                                                                                                                                                                      ;
Pumps                                                                                                                                                                                                    i Attemate Cooling Supply P-03      *  *    *    *        *                    *    *    *        *                      *                    *-      *
* See G-191159 Sh I for V7sJ2B =
to RBCCW                                                                                                                                                      valve info and test .
requirements                              !
Altemate Cooling Supply O-02      *  *    *    *        *                    *    *    *        *                      *                    *      *
* See G-191159 Sh I for V7646A*                                                                                                                                                                                                                                          l to RBCCW                                                                                                                                                      valve info and test requirements Attemate Cooling Supply P-02      *  *    *    *        *                    *    *    *        *                      *                    *      *
* See G-191159 Sh I for V7046B =
!                                                            to RBCCW                                                                                                                                                      valve info and test                        t requirements                              -
2 i
Revision 19                                                                          Drawing : G-191159 Sh 3                                                                                      Section 5      Page 18 of 179                    i
 
Vcrmont Yankee Nuclear Power Station '                                                                            Inservice Testing Program -  '
i Table 5-1 Valve Listing I Drawing: ' G-191159 Sh 3 '            Drawing 'I1tle: RCW Cooling Water System Dwg Safety OM Act/ Size My                  None Safety Fail Test Test CSJ/ROJ        h4 Valve Number          Nemeenclatore                                          ' Act Coor Class Cat Pass (inch)                  Pos 'Pos- Pos Type Freg      RR
  . V70-95A            RBCCW Pump Discharte A-07  3      C Act    12    CK-    SA  O/C  OC . n/a - SC    Q    . n/a -
CheckValve                                                                        SO    Q      afa V7s 95B            RBCCWPump Discharte B-07    3      C Act ' 12      OC      SA  O/C  OC n/a SC        'Q_    n/a                      :
Check Valve                                              .                        SO    Q      n/a i
i 1
f T
i i
3 L
t Rivision 19                                                    Drawing : G-191159 Sh 3                                Section 5 Page 19 of 179 ;
 
V;rmont Yankee Nuclear Power Station                                                                                LInservice Testing Program Table 5-1 Valve Listing Drawing: - G-191159 Sh 5                    Unning
 
==Title:==
Recuculation Pmnp Cooling Water                                          ,
Valve Number                                Dwg Safety OM Act / Size                    Norus Safety Fall Test Test CSJ/ROJ Nomenclature Coor Class Cat Pass (inch)    M      . Act Pos  Pos Pos Type Freq      RR hah .
SI,2-2-7A          Recirculation PumpInst  G-02    2                I A/C Act        EFC      SA    O    OC n/a LEF RO ROJ-VOI Excess FlowCheck Valve SI,2-2-7B          Recirculation PumpInst  G 02    2    A/C Act    1  EFC      SA    O    OC n/a LEF RO ROJ-Vol Excess FlowCheckValve St,2-24A            Recirculation PumpInst                A/C Act G-02    2                1  EFC      SA    O    O/C n/a LEF RO ROJ-Vol Excess FlowCheckValve 51,2-24B                                                  A/C Act Recirculation Pump 1nst  G-02    2                1  EFC      SA    O    O/C n/a LEF RO ROJ-Vol Excess Flow CheckValve l
Revision 19                                                    Drawing : G-191159 Sh 5                                  Section 5 Page 20 of 179
 
  - _ _ _ _ _ _ _ _ =        .        .__ - _ _ _ _ _ _ _ _ - . _ _ _ _ - _ _ - _ - . ._ _ _______ - __-__ __.                                                                                                                    _ _----          _____- __.            - _ _ _ _  - - _ _ _ _ _ - - _ _ _ _ -
Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                                                    Inservice Testing Program -
Table 5-1 Valve Listing Drawing : G-191160 Sh 3                                                                              DrawingTitle: Instrument AirSystem Dwg Safety OM Act / Size My                                                                        Act Norm Safety Fall Test Test CSJ/ROJ                                          Remarks Valve Number          Nomenclatuit Coor Class Cat Pass (inch)                                                                              Pos        Pos Pos Type Freq          RR SR-72-5          isa CAC Air /N2 Receiver                                                                E-14  3                    C Act IXI.5 RV                                                          SA  C          O  N/A SP          10Y-    n/a ReliefValve Mt-151                Compressor Suction Test E-17                                                            2                    B Pass                                              1              GL MAN  LC          C  n/a n/a          n/a    n/a Connection V72-152              Dnun/ rest Connection                                                              L-13  2                    B Pass                                        .75                  GA MAN  LC          C  n/a n/a          n/a    n/a                                                            ,
V72-152C            Dram /restConnection                                                              L-18  2                    B Pass                                        .75                  GA MAN  LC          C  n/a n/a ' n/a            n/a V72-153A            Check ValveTest                                                                    L-15  2                    B Pass                                        .75                  GA MAN  LC          C  n/a n/a          n/a    n/a .
Connection V72-28A              Isolation to Outboard                                                            L-15 NNS B                                      Act                            1                GL MAN  O          C  n/a SC          CS CSJ-V17                                                            !
MSIVs V72-28B              Isolation to Outboard                                                              L-16 NNS B                                    Act                              i              GL MAN  O          C  n/a SC          CS CSJ-V17 MSIVs V72-28D        19  Isolation to Outboard                                                            K-16 NNS B                                      Act                            1                GL MAN  C          O  n/a SO          CS CSJ-V17
* MSIVs V72-28E        19  Isolationto Outboard                                                              K-16 NNS B                                      Act                            1                GL MAN  C          O  n/a SO          CS CSJ-V17 MSIVs V72-38A        18B PCAC CompressorInlet                                                              E-17  2                    A Act                                              2                GL  AO  O          C  FC FST            Q      n/a ContammentIsolation                                                                                                                                                                                            LJB Var              n/a Valve                                                                                                                                                                                                          PE 2Y              da S1T'          Q      n/a V72aB          18B PCAC CompressorInlet                                                              F-17  2                    A Act                                              2                GL AO    O          C  FC FST Q                n/a                                                            !
ContainmentIsolation                                                                                                                                                                                          LIB Var              n/a Valve                                                                                                                                                                                                          PE 2Y                da S71'        Q      n/a V72-89B              DrywellInstnnnent Air                                                            K-14  2              A/C Act                                                2                CK  SA  O            C  n/a LJ          2Y    n/a                                                            '
Supply CheckValve                                                                                                                                                                                              SC          RO ROJ-V22 V72-89C              Drywellinstrument Air                                                            K-15  2              A/C Act                                                2                CK  SA  O          C  n/a LJ          2Y    n/a Supply Check Valve                                                                                                                                                                                              SC          RO ROJ-V22 Revision 19                                                                                                                                                Drawing : G-191160 Sh 3                                                                          Section 5                  Page 21 of 179                    ;
 
Vermont Yankee Nuclear Power Station                                                                                                                                                                                                                                Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191160 Sh 5                                                                      DrawingTitle: Senice AirSystem Dwg Safety OM Act / Size My                          'Act      Norm Safety Fail Test Test CSJ/ROJ                                                                                                                    hah Valve Number                    Nomenclature Coor Class Cat Pass (inch)                                        Pos          Pos Pos Type Fng                                                          RR SR-724A          ISB SA/IA Air Receiver                                                                    G-9                    3 C Act 2X3        RV        SA        C            O                N/A SP                10Y                                n/a ReliefValve SR-724B          ISB SA/IAAirReceiver                                                                        J-9                  3 C  Act 2x3      RV        SA        C            O                N/A SP                10Y                                n/a ReliefValve t
Revision 19                                                                                                                              Drawing : G-191160 Sh 5                                                                                                      Section 5                                                Page 22 of 179
 
Vcrmont Yc kee N clear Pcwcr St; tion                                                                                                            Inservice Testi g Program Table 5-1 Valve Listing Drawing: G-191160 Sh 7                            Drawing
 
==Title:==
DiesciGenerator Staning Air System Valve Number                                          Dwg Safety OM Act / Size                              Norm Safety Fail Test Test CSJ/ROJ Nomenclature                                                    Body  Ad                                                        h6 Coor Class Cat Pass (inch)                            Pos  Pos Pos Type Freq              RR
  .      AS-24-1A                    DG Startmg Air Engme      B-16      3    B Act              1.5  GL    SO      C    O    FC PSO 6M RR-V03 InletValve                                                                                        PSO IM RR-V03 S'IO OC RR-V03 AS-24-1B                    DG Starting Air Engine    B-03      3    B      Act        1.5  GL . SO        C    O    FC PSO 6M RR-V03 InletWve                                                                                          PSO 1M RR-V03 STD OC RR-V03 AS-24-2A                    DG Starting AirEngine      B-17      3    B      Act        1.5  GL    SO      C    O    FC PSO 6M RR-V03 InletValve                                                                                        PSO IM RR-V03 STO OC RR-V03 AS-24-2B                    DG Startmg Air Engine      B-03      3    B      Act        1.5  GL    SO      C    O    FC PSO 6M RR-V03 Inlet Valve                                                                                      PSO IM RR-V03 STO OC RR-V03 AV-24-1A                    DG Starting Air Engine    B-17      3    B      Act .1875 GA            SO      O    C    FO SC            1M RR-V03 Inlet Vent Valve STC 6M RR-V03 AV-24-1B                    DG Starting Air Engine    B-03      3    B      Act .1875 GA            SO      O    C    FO SC            IM RR-V03 Inlet Vent Valve                                                                                  STC 6M RR-V03 SR-72-6A                    DG Starting Air Receiver E-15        3    C Act              .75  RV    SA      C  O/C n/a SP              10Y    n/a ReliefValve SR-724B                      DG Startmg Air Receiver E-13          3    C Act              .75  RV    SA      C  O/C n/a SP              10Y    n/a ReliefValve                                                                                                                                              I SR-724C                      DG Starting Air Reciew E-07          3    C      Act        .75  RV    SA      C  O/C n/a SP              10Y    n/a ReliefValve I
SR-724D                      DG Starting Air Reciever E 05        3    C      Act        .75  RV    SA      C  O/C n/a SP              10Y    n/a ReliefValve .
V72-1018A      18B DG Startmg Air Receiver G-11                    3    C      Act        .75  CK    SA    O/C    C    N/A SC              Q    n/a Inlet Check Valve V72-1918D      18B DG Starting AirReceiver              F-8        3    C      Act        .75  CK    SA    O/C    C    N/A SC              Q    n/a InletCheck Valve Revision 19                                                                        Drawing : G-191160 Sh 7                                              Section S  Page 23 of 179
_ . . ___ J
 
Vcrmont Yankee Nuclear Power Station '                                                                                                                                                                                                                                                                            Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191160 Sh 7                                                                              DrawingTitle: Diesel Generator Starting Air System Dwg Safety 0M Act / Size Body                                                                      Monm Safety fab Test Test CSJ/ROJ                                                                                                    g,g                                    i Valve Number              Nomenclature                                                                                                                                                    Act Coor Class Cat Pass (inch)                                                                              Pos                    Pos Pos Type Freg                                                                    RR V7242AX            Service Airto DG                                                                    D-14        3 B Pass                              2                  GA          MAN                  LC.                      C            n/a da                                                Wa                n/a Starting Air Cross ConnectValve V7242BX            Sernce Airto DG                                                                    D-06      '3 B Pass                              2                  GA          MAN                  LC                      C            n/a n/a                                              n/a              n/a Starting Air Cross ConnectValve                                                                                                                                                                                                                                                                                                                                                        ,
t i
R:: vision 19                                                                                                                Drawing : G-191160 Sh 7                                                                                                                                                                              Section 5    Page 24 of 179                          -
_ _ _ _ - _ _ - _ = _ - - _ . _ - _ _ _ _ - _ _                                                                      _ _ _ _ . _ _ - _ _ _ - - _ _      -                - _ _ _ _ - _ -
 
Vcrm:nt Ycckee Nzclear Pcw;r Station                                                                                                            Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191160 Sh 8                      Drawing
 
==Title:==
Instrument AirSystem Dwg Safety OM Act / Size Body                Act Norm Safety Fail Test Test CSJ/ROJ                                                                                  hah Valve Number          Nomenclature Coor Class Cat Pass (inch)                        Pos            Pos Pos Type Freq              RR SE-105-2A          N2 Supply 3-Way Vent      C-06  3      B Pass .75 3-WAY SO                    O            O  FO n/a              n/a      n/a Valve                                                                                                                                                                                                          ,
SE-105-2B          N2 Supply 3-Way Vent      C-12  .3      D Pass    .75 3-WAY SO                O            O  FO n/a              n/a      n/a Valve SR-72-10A          N2 Supply ReliefValve      C-05  3      C    Act  .75 -  RV          ~ SA      C          O/C n/a SP            10Y        n/a SR-72-10B          N2 Supply ReliefValve      C-04  3      C Act    .75    RV            SA      C          O/C n/a SP            10Y        n/a SR-72-9A            N2 Supply ReliefValve      F-05  3      C Act    .75    RV            SA      C          O/C n/a SP            10Y        n/a SR-72-9B          N2 Supply ReliefValve      F-04  3      C Act    .75    RV            SA      C          O/C n/a SP            10Y        n/a V72409              InewAir to Reactor Fe04          3    A/C Act .375        CK            SA    O              C  n/a LT              2Y      n/a Building Railroad Airlock                                                                              SC            Q      n/a V72410              Instrument Airto Reactor Fe04    3    A/C Act .375        CK            SA    O              C  n/a LT              2Y      n/a Building Ralread Airlock                                                                                SC            Q      n/a t
Revision 19                                                        Drawing : G-191160 Sh 8                                                          Section 5                                                        Page 25 of 179
 
Vcrmont Ycnkee Nrclear Pcwcr Stntion                                                                                                                                          I: service Testi g Program Table 5-1 Valve Listing Drawing: G-191162 Sh 2                                Drawing
 
==Title:==
Fuel Oil-Miscellaneous Systems Dwg Safety OM Act / Size Body                      Act        Norm Safety fab Test Test CSJ/ROJ                                                                          hah Valve Number                      Nomenclature Coor Class Cat Pass (inch)                                      Pos              Pos Pos Type Freg                          RR LCV-198-2A        19            DieselOilDay Tank        E 08    3    B  Act    1.5          GA          AO            C            O/C FC FST                        Q        n/a LevelControlValve                                                                                                                    SO    Q        n/a STE    Q        n/a STO  Q        n/a LCV-198-2B      19            DieselOilDay Tank        C-08    3    B  Act    1.5            GA          AO          .C              O/C FC FST                        Q        n/a LevelControlValve                                                                                                                    SO  Q        n/a SIC  Q        n/a STO  Q        n/a SR-78-3A                        DieselFuelOilTransfer    E 06 - 3      C Act      .75            RV          SA            C            O/C n/a SP                      10Y        n/a Pump Discharge Relief Valve SR-78,3B                      DieselFuelOilTransfa    D-06    3    C Act      .75            RV          SA            C            O/C n/a SP                      10Y        n/a Pump Discharge Relief Valve V78-10A                        LCV-3 Inlet FO Storage  E-07    3    B Pass      1.5          GA        MAN          LC                    C                n'a n/a  n/a      n/a Building FO Pump Room V78-11                        LCV-3 Bypass FO          F-07    3    B Pass      1.5          GA        MAN            C              .C                    n/a n/a  n/a      n/a Storage Buikling FO Pump Room V78-2                          FuelOilStorageTank      E 02    3    C Act        4            CK          SA            C                    C                n/a CD  RO        rJa FillLine Check Valve V78-28A            19          DieselFuelOilTransfer    E-06    3    C Act 1.25                CK-        SA            C                  O                n/a SO    Q        n/a Pump Discharge Check Valve V78-28B            19          Diesel FuelOilTransfer  D-06    3    C    Act 1.25            CK          SA          C                    O                n/a SO    Q        n/a Pump Discharge Check Valve                                                                                                                                                                                                                -
V78-41A                        DK)lland Pnmmg Pump G-11        3    C    Act                  CK          SA          C                    C                n/a SKID 1M        n/a            Note 12 Discharge Check V78-41B                        DK)IIand Pnmmg Pump E-11        3    C Act                    CK          SA          C                    C                n/a SKID 1M        n/a            Note 12 Discharge Check Revision 19                                                                Drawing : G-191162 Sh 2                                                                                  Section 5                          Page 26 of 179
 
Vermont Yankee Nuclear Power Station                                                                                                                                          Inservice Testing Program:
Table 5-1 Valve Listing Drawing: G-191162 Sh 2                  DrawingTitle: Fuel Oil-Miscellaneous Systems Dwg Safety OM Act / Size My                                Act                                    Norm Safety fab Test Test CSJ/ROJ                                                                                                hah -
VaheNumber          Nomendature                                                                                                                                              RR Coor Class Cat Pass (inch)                                                                              Pos      Pos Pos Type Freq
  . V78-42A            DK) Engme DrivenFuel G-12 3        C Act            CK                            SA                                              C O/C Wa SKID IM      n/a                                    Note 12 Pump Discharge Check V78-42B            DK) Engine DrivenFuel D-12    3    C    Act          CK                            SA                                              C O/C n/a SKID IM      n/a -                                  Note 12 PanpDischarge Check                                                        ,
V7s-9              FuelOilTransfer Pump  E-06  3      B Pass      2    GA                      MAN                                                LC      C  n/a n/a  n/a    n/a Recuc.
r l
1 Revision 19                                                  Drawing : G-191162 Sh 2                                                                                              Section 5                                                                            Page 27 of 179
_____..____.______.______.____._.____.___________.____._.__....___.__.____.m                            _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ , _ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _
 
Vermont Yankee Nuclear Power Station                                                                                  Inservice Testing Programa Table 5-1 Valve Listing-                                                        -
~ Drawing: . G 191165                          Drawing 11tle: Sampling System DWE Safety OM Act / Sine                  Norne Safety fab Test Test CSJ/ROJ                g ,,,,,g, Valve Meanber        Neuseectature Coor Class Cat Pass (inch)
M      Act Pos  Pos Pos Type Freg    RR
' FCV-IS-160
* RHRReturn Line Ptocess G-16 ' *          *
* See G-191172 forvalve Sampling Valve                                                                                                  info and test reque--se 750199-75A-1
* CAD SampleTorus            D-17  *-    *    *    *    *      *      *    *    *  *    *      *
* See W-E-75-002 for -
InboardIsolationValve                                        .                                              . valve info and test requiresnents
                                                        *      *    *    *    *      *      *    *      *  *    *      *
* See W-E-75-002 for F50-199-75A-2
* CAD SampleTorus            D-17 OutboardIsointionValve                                                                                        valveinfo and test requis--ee 750199-75A-3
* CAD SampleTorus            D-17  *      *    *    *    *      *      *              *
                                                                                                                                    .* See W-E-75-002 for Inboard 1solationValve                                                                                        valveinfo and test requirements CAD SampleTorus            D-17  *      *    *    *    *      *      *    *      *  *    -*      *
* See W-E-75 402 for Pso.to9-75A-4 a OutboardIsolationValve                                                                                        valveinfo and test requiresnents CAD Sample Lower            D-16  *      *    *'    *    *      *      *    *    *  *    *      *
* See W-E-75 402 for FSO-199-75B-1
* DrywellinboardIsolation                                                                                  . valve info and test Valve                                                                                                    - requiresnents
* See W-E-75-002 for FSO 199-75B-2 =    CAD SampleLower            D-16 DrywellOutboard                                                                                                valveinfo and test IsolationValve                                                                                                requirements psO.199-75C-1 a    CAD Sample Mid              C-15  *      *    *    *    *      *      *    *    *  *    *      *
* See W-E-75-002 for .
DrywellInboardIsolsiion                                                                                      . valve info and test Valve                                                                                                          requiresnents FSO-199-75C-2 a    CAD Sample Mid              C-15  *      *          *
* See W-E-75-002 for :
DrywellOutbosid                                                                                              valve info and test IsolationValve                                                                                                requirements FSO-199-75D-1
* CAD Sample Upper          B-15  *      *    *    *    *'    *      *    *    *  *-  -*    *
* See W-E-75-002 for DrywellInboardIsolation                                                                                      valve info and test -
Valve                                                                                                        requiresnents Revision 19                                                      Drawing : G-191165                                      Section 5        Page 28 of 179 '
 
Vcrmont Yankee Nuclear Power Station                                                                                                              Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191165                            DrawingTitle: SamplingSystem Dwg Safety OM Act / Size Body                Act Norm Safety Fail Test Test CSJ/ROJ                                                                        hah Valve Number            Nomenclature Coor Class Cat Pass (inch)                        Pos        Pos Pos Type Freq                    RR FSO-199-75D-2
* CAD Sample Upper        B-15  *      *    *    *              *    *      *            *  *                    *  *    *
* See VY-E-75-002 for DrywellOutboard                                                                                                                                          valve info and test Isolation Valve                                                                                                                                            requirements CAD CAM Return                *      *    *    *              *    *      *          *  *                    *  *
* FSO-109-76A
* F-19                                      .
* See VY-E-75 002 for ContammentIsolation                                                                                                                                      valve info and test Valve                                                                                                                                                    requirements CAD CAM Return                *    ~*    *    *              *    *      *          *  *                    *  *
* FSO-107-76B
* G-19
* See VY-E-75-002 for ContainmentIsolation                                                                                                                                      valveinfo and test Valve                                                                                                                                                    requiremerds PAS-101              Post Accident Samping  K-14  2      A Pass .375              GL  AO      C          C  FC U                    2Y    n/a                          Note 13 System Jet Pump Sample Valve PAS-102              Post Accident Sampling  K-16  2      A Pass .375              GL  AO      C          C  FC U                    2Y    n/a                          Note 13 System Jet Pump Sample Valve PAS-103              PostAcci* ntSampling    L-14  2      A Pass .375              GL  AO      C          C  FC U                    2Y    n/a                          Note 13 System Jet Pump Sample Valve PAS-104              PostAccidentSampling    K-16  2      A Pass .375              GL  AO    C            C  FC U                    2Y    n/a                          Note 13 System Jet Pump Sample Valve PAS-106              Post Accident Sampling  L-16  2      A Pass .375              GL  AO    C            C  FC LT                    2Y    n/a                          Note 13 System Pmge Valve                                                                                                                                      Valve also appears on G-191169 Sh 1 PAS-108C            Post Accidat Sampling    K-15  2    A/C Pass .375              CK  SA    C            C  FC U                    2Y    n/a                          Note 13 Systcm Jet Pump Sample Check Viv PAS-199C              Post Accident Sampling  L-15  2    A/C Pass .375              CK  SA    C            C  FC U                    2Y    n/a                        Note 13 System Jet Pump Sample Check Viv PAS-114              Drain ValveIsolation    L-15  2      B Pass .375              GL  MAN  LC            C  n/a rva                  n/a  n/a Revision 19                                                        Drawing : G-191165                                                                Section 5                                            Page 29 of 179
 
Vcrmont Yankee Nuclear Power Station                                                                            Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191165                        Drawing Thie: Sampling System Dwg Safety OM Act / Size Body      Act  Nonn Safety Fail Test Test CSJiROJ            g,g Valve Number          Nomenclature                                                                                RR Coor Class Cat Pass (inch)                Pos  Pos Pos Type Freg PAS-115            Drain LineIsolation      L-15  2    B Pass .375    GL    MAN    LC    C    n/a n/a    n/a    n/a PAS-117            Jet Pump 1 Sample Line  I-13  2    B Pass .375    GL    MAN    LC    C    n/a n/a    n/a    n/a Test Connection PAS-118            Jet Pump 1 Sample Line  I-13  2    B Pass .375    GL  . MAN    LC  C    n/a n/a    n/a    n/a TestConnection PAS-120            JetPump 2 Sample Line    I-12  2    B Pass .375    GL    MAN      LC  C    n/a n/a    n/a    n/a Test Connection PAS-121            Jet Pump 2 Sample Line  I-12  2    B Pass .375    GL    MAN      LC  C    n/a n/a    n/a    n/a Testconnection SL-2-3-21B        Nuclear BoilerVessel    C-13  1    A/C Act    1  EFC    SA      O  O/C n/a LEF RO ROJ-V01 InstExcess FlowCheck Valve SI,2-3-21D        NuclearBoilerVessel      C-13  1    A/C Act    1  EFC    SA      O  O/C n/a LEF RO ROJ-Vol Inst Excess FlowCheck Valve
* See VY-E-75-002 for VG-23
* CAD Rad Monitor          G-16 Supply Contamment                                                                                      valve info and test Isolation Valve                                                                                        4m VG-26 =            CAD Rad Monitor          G-15  *    *    *    *    *      *      *  *    *    *    *      *
* See VY-E-75-002 for Supply Contamment                                                                                      valve info and test Isolation Valve                                                                                        4m Revision 19                                                    Drawing: G-191165                                    Section 5    Page 30 of 179
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                    Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191167                                Drawing
 
==Title:==
NuclearBoiler Dwg Safety OM Act / Size Body                  Act        Nonn Safety Fail Test Test CSJ/ROJ                                                          Remah Valve Number              Nomenclature Coor Class Cat Pass (inch)                                  Pos  Pos Pos Type Freg                                                      RR FCV-2-17                RxVesselHem!Steen          B-06  2    B Pass      1  GL                  AO          C    C            FC PIT 2Y                                                n/a    Note 14 Space Vent Flow Control Valve FCV-2-18                Rx VesselHead Steen      B-05    1    B Pass      1  GL
* AO          C    C          FC PIT 2Y                                                  n/a    Note 14 Space Vent FlowControl                                                                                                                                                                                        ,
Valve FCV-2-20                Rx VesselHemiSeal          C-06  1    B Pass      1  GL                  AO          O    O          FO PIT 2Y                                                  n/a    Note l4 LeakageFlowControl Valve FCV-2-21                RxVesselHemiscal          C-05  2      B Pass      1  GL                  AO          C    C          FC PIT 2Y                                                  n/a    Note 14 LeakageFlowControl Valve FCV-2-39          18B RxRecue SarnpleLine        L-04  2    A Act    .75  GL                  AO          C    C          FC FST                                  Q                n/a    Note 20 Flow Control / Isolation                                                                                                  LJB Var                                  n/a Valve                                                                                                                    PIT 2Y                                    n/a STE                      Q                N/A FCV-2-40          18B Rx Recire SampleLine        L-03  2    A Act    .75  GL                  AO          C    C          FC FST Q                                                  n/a    Note 20 FlowControl/ Isolation                                                                                                  LJB Var                                    n/a valve                                                                                                                    pg.g.                2Y                  da STC                    Q                  N/A-RV-2-71A                Nuclear Boiler            D-08    1    C Act 6X10 SRV                      SA        C  O/C n/a SP                                        SY ROJ-V02 Note 7 Safety /ReliefValve                                                                                                                                                                                          ,
RV-2-71B                Nuclear Boile            G-03    1    C  Act 6X10 SRV                    SA          C  O/C n/a SP                                        SY ROJ-VD2 Note 7 Safety /ReliefValve RV-2-71C                Nuclear Boiler -          G-08    1    C  Act 6X10 SRV                    SA          C  O/C n/a SP                                        SY ROJ-V02 Note 7 Safety /ReliefValve RV-2-71D                Nuclear Boiler            11-0 8  1    C  Act 6X10 SRV                    SA          C  O/C n/a SP                                        SY ROJ-V02 Note 7 Safety /ReliefValve sir 2-23                NB FlowLimiting Valve C-03      2      C Pass    1  EFC                  SA        O    O          n/a n/a                                n/a                  n/a Revision 19                                                          Drawing : G-191167                                                                                                      Section 5  Page 31 of 179
 
    - Vcrmont Yankee Nuclear Power Station                                                                                                                  Inservice Testing Program                              .
Table 5-1 Valve Listing Drawing: G-191167                                _ DrawingTitle: . Nuclear Boiler Vdve Neuaber                  Nomenclature          Dwg Safety OM Act / Size      my            Act Nem Safety fab Test Test CSJ/ROJ                                              hm Coer Class Cat Pass (inch)                          Pos  Pos      Pos Type Freg                RR Sb2-381A                  NB FlowLinutmg Valve E-04          2    C Pass ' 1      EFC          .SA    O    O        n/a n/a  n/a              ' n/a                                          ,
Ste2-3clB                  NB Flowtimitmg Valve D-04          2    C Pass        1  EFC          SA    O    O        n/a n/a  n/a                n/a                                          .j Str2 301E                  NB FlowLimitmg Valve E44          2    C Pass        1  EFC          SA    O    O        n/a n/a  n/a                n/a l
                                                                                                              ~
SL2-381F                  NB FlowLimitag Valve D-04          2    C Pass        1  EFC          SA    O    O        n/a n/a n/a                  n/a Sb2-385A                  NuclearBoilerVessel      M-02    2  NC Act          1  EFC          SA    O    (#C n/a LEF RO ROJ-V01                                                                ,
Ind Excess FlowCheck Valve                                                                                                                                                                      i 51,2-345B                  Nuclear BoilerVessel      M-02    2  A/C Act        1  EFC          SA    O    OC n/a LEF RO ROJ-V01 Ind Excess FlowCheck                                                                                                                                                      ;
,                                        Valve sir 242A                    Nuclear Boiler Vessel        I-13 2  A/C Act        1  EFC          SA    O    C        n/a LEF RO ROJ-Vol                                                          i Ind Excess FlowCheck Valve                                                                                                                                                                    .
SI,242B                    NuclearBoilerVessel          I-13 2  A/C Act        1  EFC          SA    O    C        n/a LEF RO ROJ-V01                                                          !
Ind Excess FlowCheck Valve Ste242C                    NuclearBoilerVessel        J-13  2  A/C Act        1  EFC          SA    O    C        n/a LEF RO ROJ-VD1 IndExcess FlowCheck                                                                                                                                                      ,
Valve                                                                                                                                                                    !
Ste242D                  NuclearBoilerVessel        J-13  2  NC Act          1  EFC          SA    O    C      ' n/a LEF RO ROJ-Vol                                                          ;
l Ind Excess FlowCheck Valve                                                                                                                                                                    ,
sir 244A                  Nuclear BoilerVessel      K-13    2  A/C Act        1  EFC          SA    O    OC n/a LEF RO ROJ-VD1 Ind Excess FlowCheck Valve                                                                                                                                                                    l Ste244B                    Nuclear Boiler Vessel    K-13    2  NC Act          1  EFC          SA    O    O/C n/a LEF RO ROJ-V01 Ind Excess FlowCheck I
Valve Str244c                    Nuclear Boilcr Vessel    K-13    2  NC Act          1  EFC          SA    O    O/C n/a LEF RO ROJ-V01                                                                !
I                                        IndExcess FlowCheck Valve Revision 19                                                            Drawing : G-191167                                                              Section 5                  Page.32 of 179    ,
t f
 
4 Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                                    Inservice Testing Program -
Table 5-1 Valve Listing
        ' Crawing: G-191167                                            Drawing
 
==Title:==
NuclearBoiler Dwg Safety OM Act / Sire Body                                                                Act                              Norm Safety Fail Test Test CSJ/ROJ                                                                                                                      hah Valve Number                  Nomenclature Coor Class Cat Pass (inch)                                                                                                      Pos  Pos Pos Type Fral                                RR
    - - SL2-64D                      NuclearBoilerVesel                L-13    2  A/C Act                          1            EFC                                    SA                            O  O/C n/a LEF RO ROJ-Vol Ind Excess FlowCheck Valve SU2-73A                    NuclearBoiler Vesel                F-12    2  A/C Act                          1            EFC SA                            O  O/C n/a LEF RO ROJ-VO1 Ind Excess Flow Check Valve                                                                                                                                                                                                                                                                                                                                ;
Sb2-73B                    NuclearBoiler Vesel                F-12    2  A/C Act                          1            EFC                                  SA                              O  O/C n/a LEF RO ROJ-VO1                                                                                                                                        :
Ind Excess FlowCheck Valve                                                                                                                                                                                                                                                                                                                                .
I SU2-73C                    Nuclear Boiler Vessel            G-12      2  A/C Act                          1            EFC                                    SA                            O  O/C n/a LEF RO ROJ-V01 Ind Excess Flow Check Valve SL2-73D                    NuclearBoilerVessel              G-12      2  A/C Act                          1            EFC                                  SA                              O  O/C da LEF RO ROJ-V01 Inst Excess FlowCheck                                                                                                                                                                                                                                                                                                                ,
Valve sb2-73E                    Nucicar Boiler Vessel              G-12    2  A/C Act                          1            EFC                                  SA                              O  O/C n/a LEF RO ROJ-V01 IndExcess FlowCheck Valve SL2-73F                    NuclearBoilcr Vessel              G-12    2  A/C Act                          1            EFC                                    SA                            O  O/C                    LEF RO ROJ-Vol Inst Excess FlowCheck Valve SL2 73G                    Nuclear Boiler Vessel            H-12      2  A/C Act                          1            EFC                                  SA                              O  O/C n/a LEF RO ROJ-V01 Inst Excess FlowCheck Valve SL2-73H                    Nuclear BoilerVessel              H-12      2  A/C Act                          1            EFC                                  SA                              O  O/C n/a LEF RO ROJ-V01 Inst Excess FlowCheck                                                                                                                                                                                                                                                                                                                l Valve          .
SR-2-14A                    SRV Exhaust Line                  M-12 NNS C                          Act      3            CK                                    SA                              C    C    n/a SC              RO ROJ-V27 Vacuum Breaker SR-2-14B                    SRV ExhaustLine                  M-12 NNS C Act                                3            CK                                    SA                              C    C    n/a SC              RO ROJ-V27 Vacuum Breakcr Revision 19                                                                                          Drawing : G-191167                                                                                                                                    Section 5                                                                              Page 33 of 179
 
                                                                                                                                                                                                                                    -Inservice Testing Program Vermont Yankee Nuclear Power Station'-
Table 5-1 Valve Listing -
Erawing: G-191167                                              Drawing
 
==Title:==
NucicarBoiler                                                                                                                                                          ;
F-    afdy OM Acd Size Body                                      Nonn Sddy fab M                                              M NW                            Rennarks            -
Valve Naasber                  Nomenclature                                                                                Act                                                                                  RR G*. j Class Cat Pass (nich)                                        Pos. Pos ' Pos Type Freg                                                                                        ,
SR-2-14C                    SRVExhaustLine                    M-12 NNS C                        Act      3            %    SA        C          O      n/a SC RO ROJ-V27 .'                                                                        '
Vacuum Breaker I
SR-2-14D                    SRV Exhaust Line                  M-12 NNS - C                      Act      3            m    SA        C          C      n/a SC. RO ROJ-V27 VacuumBreaker                                                                                '
SR-2-14E                    SRV Dishage Line .                  L-12    3      C 'Act                -10            N~  SA        C        OC n/a SP . 10Y                                                    n/a                              j Vacuum Relief Valve SR-2-14F                    SRVDischarge Line .                L-12    3      C                Act . 10              m    SA      C        O/C n/a SP                                            10Y          n/a Vacuum ReliefValve SR-2-14G                    SRVDischarBe Line                  L-12    3      C              Act      10          N    SA      C        ~ OC n/a SP                                            10Y        n/a t
Vacuum ReliefValve                                                                                                                                                                                                      i SR-2-14H                    SRV Discharge Line                  L-12    3      C              Act      10          m    SA        C        OC n/a SP                                              10Y        n/a Vacuum ReliefValve SR-2-141                    SRV Discharge Line                  L-12    3      C              Act      10          m    SA        C        OC n/a SP                                              10Y        n/a Vacuum ReliefValve                                                                                                                                                                                                      t SR-2-14J                    SRV DischargeLine                  L-12    3        C Act                  10          N    SA      .C        OC n/a SP                                              10Y        n/a                          ~;
Vacuum ReliefValve SR-2-14K                    SRVDischarge Line                  L-12    3        C Act                  10          m    SA        C-      OC n/a SP                                              10Y        n/a Vacuum R,wrValve L-12    3        C Act                    10          N    SA        C        OC n/a SP                                              10Y        n/a SR-2-14L                    SRV Discharte Line Vacuum ReliefValve NuclearBoiler                      D-08      1        C Act 6X8 SRV                            SA        C        OC n/a SP                                                5Y      n/a -
SV-2-7eA                                                                                                                                                                                                                                            i Safety /ReliefValve H-08              C Act 6X8 SRV                            SA        C        OC n/a SP                                                SY      n/a                              l SV-2-70B                    NuclearBoiler                                1 Safety /ReliefValve V2-27A                      Reactor Feedwater                  F-03    1  AC Act                        16        m    SA        O        OC n/a LJ                                                  2Y      n/a                              l InjectionLine Check                                                                                                                      SC                                RO _. ROJ-VD3                              (
I Valve                                                                                                                                    SO                                    Q ROJ-V03 V2-27B                      Reactor Feedwater                  H-02      2        C            Act      16        &    SA        O            C  n/a SC                                            RO ROJ-VU3                                :
InjectionLine Check Valve                                                                                                                                                                                                                  j
                                                                                                                      . Drawing : G-191167                                                                                                Section 5 Page 34 of 179 Revision 19
  . . _ _ _              _ _ _ _ _ _ _ _                    ______________ _ _                    _ _ _ _ _ _ _ _ _ _                                  ___            __                            _ _ __ ___ _                                    ________________t
 
Vermont Yankee Nuclear Power Station                                                                                                                                                                                                                                                  Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191167                                  Drawing Tide: Nuclear Boiler Dwg Safety OM Act / Size My                                                                                                                Act                        Norm Safety Fail Test Test CSJ/ROJ                                      %g Valve Number              Nomenclature Coor Class Cat Pass (inch)                                                                                                                                                  Pos                          Pos Pos Type Freq        RR V2-28A -                Reactor Feedwater            F-05    i                NC Act 16 CK                                                                                                      SA                                O                        O/C n/a LJ          2Y    n/a Injection Line Check                                                                                                                                                                                                                                  SC  RO ROJ-V03
.                          Valve                                                                                                                                                                                                                                                SO  Q ROJ-V03 V2-2sB                  Reactor Fcedwater          H-05    1                A/C Act                                              16                        CK , SA                                                              O                        O/C n/a IJ          2Y    n/a Injection Line Chak                                                                                                                                                                                                                                  SC  RO ROJ-V03 Valve                                                                                                                                                                                                                                                SO  Q ROJ-V03 V2400G                . NBS Globe Valve              F 04    2                      B Pass 1.00                                                                  GL                          MAN                                    C                            C    n/a n/a  n/a    n/a V2400H                  NBS Globe Valve              E-04    2                      B Pass 1.00                                                                GL                          MAN                                    C                            C      n/a n/a  n/a    n/a                      !
V247A                    MSRV ActuatorNitrogen B-08          2                  A/C Act                                                1                      CK                                SA                            O/C                                C    n/a LT  2Y    n/a Supply CheckValve                                                                                                                                                                                                                                    SC  RO ROJ-V04 V2 37B                  MSRVActuatorNitrogen G-09            2                  NC Act                                                  1                      CK                                SA                            O/C                              C      n/a LT  2Y    n/a                      '
Supply Check Valve                                                                                                                                                                                                                                    SC  RO ROJ-V04 V2,37C                  MSRVActuatorNitrogm G-09            2                  A/C Act                                                1                      CK                                SA                            O/C                                C    n/a LT  2Y    n/a Supply Check Valve                                                                                                                                                                                                                                    SC  RO ROJ-V04 V2 37D                  MSRV Actuator Nitrogen H-09          2                  NC Act                                                  1                      CK                                SA                            O/C                                C    n/a LT  2Y. n/a supply Check Valve                                                                                                                                                                                                                                    SC  RO ROJ-V04 V2 39AA          188 Penetration X-41              le04    2                  NC Act                                                .5                        CK                                SA                                C                        O/C n/a LJB Var            n/a ThermalReliefValve                                                                                                                                                                                                                                    SC  RO ROJ-V29 SO RO ROJ-V29 V2 41                  Recire SampleTest Line M-03          2                      B Pass                                            75                        GL                          MAN                                  LC                              C      n/a n/a  n/a    n/a TestConnection V2-53A                  Rx Recirculation Pump        1,09    1                    B                  Act                          28                        GA MO-AC O                                                                                        C      FAI PIT 2Y      n/a DischargeIsolation Valve                                                                                                                                                                                                                            SE CS CSJ-V04 V2-53B                  Rx Recirculation Pump      L-09    1                    B                  Act                          28                        GA MO-AC O                                                                                        C      FAI PIT 2Y      n/a                      i Discharge Isolation Valve                                                                                                                                                                                                                          STC CS CSJ-V04 V2-54A                  Rx Recirculation Pump      L-09    1                    B                  Act                            4                        GA MO-AC O                                                                                        C      FAI PIT 2Y      n/a Discharge Bypam Valve                                                                                                                                                                                                                              STC CS CSJ-V04 Revision 19                                                                                                Drawing : G-191167                                                                                                                                                              Section 5 Page 35 of 179
 
Vcrmont Yankee Nuclear Power Station                                                                                        Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191167                                  DrawingTitle: NuclearBoiler
                                                        'Dwg Safety OM Act / Size  y~,    gc,  Nonn Safety Fail Test Test CSJ/ROJ            ' hah Valve Number                    Nomenclature Coor Class Cat Pass (inch)              Pos  Pos  Pos Type Freq      RR
. V2-54B                        Rx Recirculation Pump  L 09  1    B  Act    4  GA MO AC O        C    FAI PIT 2Y          n/a Ducharge BypassValve                                                            SE CS CSJ-V04 V2-74                          Main Steam Line Drain  E-10  1    A Act      3  GA MO-AC C        C    FAI U        2Y    n/a contanunentIsolatim                                    .                        PIT 2Y          n/a valve                                                                            STC            n/a Q
V2-74A                        Penetration X-8 Hermal D-10    2  A/C Act    .5  CK    SA      C  O/C n/a W          2Y    n/a ReliefValve                                                                      SC      RO ROJ-V29 SO      RO ROJ-V29 Y2-75                          TestConnection Between F-12    2    B Pass    .75  GL    MAN    LC  C    n/a n/a      n/a    n/a Valves V2-74 and 77 V2-77                        Main Steam Line Drain  E-13  1    A Act      3  GA MO-DC C        C    FAI U        2Y    n/a Contammentlsolation                                                              PIT 2Y          n/a Valve                                                                            STC            Wa Q
V240A                        Main SteamIsolation    D-10  1    A Act      18  GL    AO    O    C    FC FST        Q    n/a    Note 1 valve                                                                            u      2Y    n/a PIT 2Y          n/a STC      Q    n/a V240B                        Main SteamIsolation    G-12  1    A Act      18  GL    AO    O    C    FC FST        Q    n/a    Note 1 Valve                                                                            U      2Y    n/a PIT 2Y          n/a STC      Q    n/a V240c                        Main SteamIsolation    G-12  1    A Act      18  GL    AO    O    C    FC FST        Q    n/a    Note 1 Valve                                                                            U      2Y    n/a
                                                -                                                                PIT 2Y          n/a STC      Q      n/a V240D                        Main SteamIsolation    H-12  1    A Act      18  GL    AO      O    C    FC FST        Q      n/a    Note 1 Valve                                                                            u      2Y    n/a PIT 2Y          n/a STC      Q      n/a Revision 19                                                            Drawing : G-191167                                      Section 5    Page 36 of 179
 
Inservice Testing Program Vermont Yankee Nuclear Power Station Table 5-1 Valve Listing Drawing: G-191167                              Drawing T tle: NuclearBoiler Norsa Safety fab Test Test CSJ/RO Nomenclatur,                Dwg Safety OM' Act / Size Body                        Act                                                                                                      Renearts Valve Numher                                      Coor Class Cat Pass (inch)                                  Pos        Pos Pos Type Freg                        RR V242A              MSIVActuatorNitrogen B-10 2 A/C Act                                1    CK            SA  O/C          C      n/a LT-                  2Y    n/a Supply CheckValve                                                                                                                    SC  RO ROJ-V05 -
V242B              MSIVActuatorNitros;en B-lO            2                  A/C Act  1    CK            SA  O/C          C      n/a ,LT                  2Y    n/a Supply Check Valve                                                                  .                                                SC  RO ROJ-V05 V242C              MSIVActuatorNitrogen B-lO            2                  A/C Act  1    CK            SA  O/C          C      n/a LT                    2Y    n/a Supply Chak Valve                                                                                                                    SC  RO ROJ-V05 V242D              MSIV Actuator Nitrogen B-10          2                  A/C Act  1    CK            SA  O/C          C-      n/a LT                  2Y    n/a Supply CheckValve                                                                                                                    SC  RO ROJ-VOS V243A              Steam Line A Test              D-12  2                  B Pass 35      GL          MAN      LC      C        n/a n/a                  n/a    n/a Connection V243B              SteamLine B Test              G-12  2                  B Pass 35      GL          MAN      LC      C        n/a n/a                  n/a    n/a Connectior V243C              Steam LinekTest                H-12    2                  B Pass  .75    GL          MAN      LC      C        n/a n/a                  n/a    n/a Connection V243D              Steam Lir.:D Test              I-12  2                  B Pass 35      GL          MAN      LC      C        n/a n/a                n/a    n/a Connection                                                                                                                                                                                                    ;
Main Steamisolation            D-13                      A Act    18    GL            AO            O  C        FC rsr                  Q    n/a                          Note 1 V246A                                                    1 Valve                                                                                                                                LJ  2Y    n/a                                                          i PIT 2Y      n/a S'It  Q    n/a V246B            Main SteamIsolation            G-12  1                  A Act    18    GL            AO            O  C          FC FST Q                      n/a                          Note 1 i
valve                                                                                                                                LJ  2Y    n/a PIT 2Y      n/a                                                          !
                                    .                                                                                                                      STC  Q    n/a                                                          ;
v246C              MainSteamIsolation            G-12  1                  A Act    18    GL            AO            O  C          FC FST                  Q    n/a                          Note 1                          l Valve                                                                                                                                LJ  2Y    n/a PIT 2Y      n/a STC  Q    n/a i
Drawing : G-191167                                                                  Section 5                                    Page 37 of 179 Revision 19
 
Vermont Yankee Nuclear Power Station                                                                                                                                  Inservice Testing Program Table 5-1 Valve Listir>g                                                              ,
Drawing: G-191167                                                                          Drawing
 
==Title:==
Nuclear Boiler Valve Namber                Nomenclature Dwg Safety OM Act / Size Body          Act  Norn Safety Fail Test Tes: CSJ/ROJ              hah Coor Class Cat Pass (inch)                  Pos  Pos  Pos Type Freg      RR V246D              MainStearnIsolation -                                                    H-12    1    A Act - 18 .GL          AO    O    C    FC FST Q              n/a    Note 1 Valve                                                                                                                                  U    2Y        n/a PIT 2Y          n/a STC    Q        n/a V247A              MSIVActuatorAir                                                          B-13    2    A/C Act      1  CK      SA    O/C  C    n/a LT    2Y        n/a Supply CheckValve                                                                                                                      SC  RO ROJ-V05 V247B              MSIVActuatorAir                                                          B-13    2    A/C Act      1  CK      SA    O/C  C    n/a LT    2Y        n/a Supply CheckValve                                                                                                                      SC  RO ROJ-V05 V247C              MSIVActuatorAir                                                          B-13    2    A/C Act      1  CK      SA    O/C  C    n/a LT    2Y        n/a Supply Check Valve                                                                                                                    SC  RO ROJ-V05 V247D              MSIVActuatorAir                                                          B-13  2    A/C Act      1 -CK      SA    O/C  C    n/a LT    2Y        n/a Supply CheckValve                                                                                                                      SC  RO ROJ-V05 V2-94A              FeedWater Line ATest                                                      F44    2    B Pass    .75  GL  MAN      LC    C    n/a n/a    n/a      n/a Connection                                                                                                                                                                          ,
V2-74B              FeedWater B Test                                                        H-04    2    B Pass    .75  GL  MAN      LC    C    n/a n/a    n/a      n/a Connection V2-96A              ReactorFeedwater                                                        H-03    1    A/C Act      16  CK      SA    O  O/C n/a LJ      2Y        n/a InjectionLine Check                                                                                                                    SC  RO ROJ-V03 Valve                                                                                                                                  SO    Q ROJ-V03 v2-96B              Reactor Feedwater                                                        F-03  2    C    Act    16  CK      SA    O    C    n/a SC    RO ROJ-V03 Injection Line Check Valve
                                                                                                                                                                                                                          ~
V2-98A              NBS Globe Valve                                                          N-03    2    B Pass 1.00      GL  MAN      C    C    n/a n/a    n/a      n/a V2-988              NBS GlobeVal e                                                          N-12    2    B Pass 1.00      GL  MAN      C    C    n/a n/a    n/a      n/a                            ,
Revision 19                                                                                                    Drawing : G-191167                                          Section 5    Page 38 of 179
 
Vcrmont Yankee Nuclear Power Station                                                                                Inservice Testing Program
                                                                  ' Table 5-1 Valve Listing Crawing : G-191168                        Drawir.g
 
==Title:==
Core Spray System Valve Number          Nomenclature        Dwg Safety OM Act / Size Body        Act    Nonn Safety Fail Test Test CSJ/ROJ            g,g Coor Class Cat Pass (inch)                    Pos  Pos  Pos Type Freq    RR
- SI,14-31 A        . CoreSprayInst Excess    F-07    2    A/C Act      1  EFC    SA      O  O/C n/a LEF RO ROJ-VO1 FlowCheck Valve S1,14-31B          Core sprayInstExcess    E-07    2    A/C Act      i  EFC    SA      O  O/C n/a LEF RO ROJ-V01 Flow CheckValve SR-14-20A          Cor- Spray Pump        F-11    2      C Act      1.5  RV    SA      C  O/C n/a SP        10Y    n/a DiscLvge ReliefValve SR-14-20B          Core Spm Pump          D-12    2      C Act      1.5  RV    SA      C  O/C n/a SP        10Y    n/a DischargeIWiefValve V14-10A            Core Spray Pump        I-Il    2      C  Act    to    CK    SA      C  O/C n/a SC        Q    n/a Discharge Check Valve                                                                SO    Q    n/a V14-10B            Core Spray Pump        I-14    2      C Act      10    CK    SA      C  O/C n/a SC        Q    n/a Discharge Check Valve
* SO          n/a Q
V14-11A            Core Spray Injection  G-09    2      B  Act    8    GA MO-AC O        O    FAI PIT 2Y        n/a.
Valve                                                                                STO          n/a Q
V14-11B            Core Spray Injection    C-09    2      B  Act    8  GA MO-AC O          O    FAI PIT 2Y        n/a Valve                                                                                STO          n/a Q
V14-12A            Core Spray Injection  G-08    1      A Act      8  GA MO-AC C        O/C FAI IJ 2Y            n/a    Note 21 IsolationValve                                                                        LT 2Y      n/a PIT 2Y      n/a STE    Q    n/a STO    Q    n/a V14-12B            Core Spray Injection  C-08    1      A Act      8  GA MO-AC C        O/C FAI LJ 2Y          n/a    Note 21 Isolation Valve                                                                      LT 2Y      n/a
                                      -                                                                    PIT 2Y      n/a STC    Q    n/a STO    Q    n/a V14-13A        19  Core Spray Injection  F-06    i    A/C Act    8    CK    SA      C  O/C n/a CD        RO ROJ-V34 Note 21 Check Valve                                                                          LT    2Y    n/a SC    Q    n/a Revision 19                                                    Drawing : G-191168                                      Section 5    Page 39 of 179
 
' Vcrmont Yankee Nuclear Power Station                                                                                                                                  Inservice Testing Program -
Table 5-1 Valve Listing Drawing : G-191168                              DrawingTitle: Core Spray System Dwg Safety OM Act / Size Body                                          Act Nonn Safety Fall Test Test CSJ/ROJ                    hah Valve Number              Nomenclature                                                                                              Pos  Pos Pos Type Fng              RR Coor Class Cat Pass (inch)
V14-13n          19      Core Spray Inicction            D-06  1        A/C Act                                  8  CK        SA    C  O/C c/a CD          RO ROJ-V34 Note 21                      ;
Check Valve                                                                                                                    LT    2Y        n/a SC    Q          n/a Core Sprayinjection Line F-05          1        B Pass                                  8  GA      . MAN  LO    O      n/a PIT 2Y            n/a    Note 14
  .V14-14A Valve Core SprayInjectionLine E-05                    B Pass                                  8  GA      MAN  LO    O      n/a PIT 2Y            n/a    Note 14 V14-14B                                                        1 Valve V14-16A                Core Spray to RIIR              L-11  2        B Pass                                  4  GA      MAN    C    C      n/a n/a    n/a        n/a System Isolation Valve V14-16B                Core spray to RIIR              M-11  2        B Pass                                  4  GA      MAN    C    C      n/a afa    n/a        n/a SystemIsolationValve V14-22A        18A Condensate Transfer                  I-09  2        C                                  Act  2    CK      SA    C    C      n/a SC      OC RR-V14 Note 11 itsh Check Valve V14-22B          18A Condensate Transfer                B-10    2        C                                  Act  2    CK      SA    C    C      n/a SC      OC RR-V14 Note 11 FlushCheck Valve V14-23A          isA Condensate Transfer                1-09  2        C                                  Act  2    CK        SA  C    C      n/a SC      OC RR-V14 Note ll Flush Check Valve V14-23B          18A CondensateTransfer                B 09    2        C                                  Act  2    CK        SA  C    C      n/a SC      OC RR-V14 Note 11 FlushCheckValve V14-26A          19    CoreSpray PumpTest              F-10  2        B                                  Act  8    GL MO-AC C        O/C FAI PIT        2Y        n/a LineIsolation Valve                                                                                                          STC      Q        n/a STO      Q        n/a 19      Core Spray PumpTest            E-10  2        B                                  Act  8    GL MO-AC C        O/C FAI PIT 2Y                n/a V14-26B LineIsolation Valve                                                                                                          STC      Q        n/a S1D      Q        n/a V1440A                  Core Spray Injection            F-07  2        A Pass                                  .75  GA      MAN    C    C      n/a LT      2Y        n/a    Note 21 Check Valve Bypass Valve Drawing : G-191168                                            Section 5    Page 40 of' 179 R; vision 19
          ' ' " -      --          --        s  . - _ __          _ _ ,  , _ , _ _ , _ _ , _ , , _ , _ _ _            _ _ _
 
Vcrmont Yankee Nuclear Power Station                                                                                                                        Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191168                                    DrawingTitle: Core Spray System Dwg Safety OM Act / Size My                                      Act  Norm Safety Fail Test Test CSJ/ROJ                hah -
Valve Number                      Nomenclature Coor Class Cat Pass (inch)                                                Pos  Pos Pos Type Freg      RR
- V14,30B                        Core Spray Injection    D-07                        2              A Pass .75    GA    MAN    C    C    n/a LT    2Y    n/a    Note 21 Check Valve Bypass Valve V14,33A                    18A Core Spray Discharge    H-11                        2                C  Act    1  CK      SA    O/C  C    n/a SC    OC RR-V13 Note 11 Pressuization Line CheckValve V14,33B                    isA Core Spray Docharge      H-15                        2                C  Act    1  CK      SA    O/C  C    n/a SC    OC RR-V13 Note ll L      imtionLine CheckValve V14-5A                          Core Spray Pump        H-12                        2                B  Act    3    GA MO-AC O        O/C FAI PIT 2Y          n/a Mmunum Flow Valve                                                                                                STC    Q    n/a STO    Q    n/a V14-5B                          Core Spray Pump        H-13                      2                B  Act    3    GA MO-AC O        O/C FAI PIT 2Y          n/a Minimum Flow Valve                                                                                              STC    Q    n/a STD    Q    n/a V144A                          Test Connection          K-04                      2                B Pass  .75  GL    MAN    LC    C    n/a n/a    n/a    n/a V144B                          Test Connection          1,04                      2                B Pass  .75  GL    MAN    LC    C    n/a n/a    n/a    n/a                                          ,
V14-7A                          Core Spray Pump Suction K-11                      2                B  Act    12  GA MO-AC O/KL O/C FAI PIT          2Y    n/a Valve                                                                                                            STE    Q    n/a V14-7B                          Core Spray Pump Suction L-11                      2                B  Act    12  GA MO-AC O/KL O/C FAI PIT 2Y              n/a Valve                                                                                                            STC    Q    n/a V14443A                        Test Connection        H-07                        2                B Pass  .75  GA MAN LC          C    n/a n/a n/a      n/a V14443B                        TestConnection          C-07                      2                B Pass  .73  GL    MAN    LC    C    n/a n/a    n/a    n/a V14-8A                          Core Spray Supply From K-12                        2                B Pass    12  GA    MAN    LC    C    n/a n/a    n/a  n/a CSTIsolation Valve V14-8B                          Core Spray Supply From L-14                        2                B Pass    12  GA    MAN    LC    C    n/a n/a    n/a  n/a CSTIsolation Valve Revision 19                                                                                              Drawing : G-191168                                    Section 5          Page 41 of 179
 
Vcrmont Yankee Nuclear Power Station                                                                                                Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191169 Sh 1                            DrawingTitle: High Pressure Coolant Injecten System Dwg Safety OM Act / Size                          Norm Safety Fail Test Test CSJ/ROJ Valve Number                  Nomenclature                                        My      Act                                                              hah Coor Class Cat Pass (inch)                          Pos Pos  Pos Type Freq      RR FCV-23-42                  IIPCISteam Line Drain    K-13 NNS B Act            1    GL      AO          O  O/C FC FST -Q              n/a PotIsolationvalve                                                                          PIT 2Y          n/a STE    Q        n/a STO    Q        n/a FCV-23-43                  HPCI Steam Line Drain  K-14 NNS B        Act    1    GL      AO          O  OC FC FST        Q        n/a PotIsolationvalve                                                                          PIT 2Y          n/a STC  Q        n/a STO  Q        n/a LCV-23-53                  MnStm DminTrap          H-14    2      B  Act    1    GL      AO          C  O    FC FST    Q        n/a
* Bypass & Stramer                                                                            PIT  2Y        n/a Blowo!TTrap Bypass da STC  Q STO  Q        n/a                                                i PAS-106*                  Post Accident Sampling  J-05  *      *    *      *      *      *          *  *    *    *    *        *
* See G-191165 forvalve System Purge Valve                                                                                                    info and test requirements S-23-6                      HPCITurbme Exhaust      I-06  2      D  Act    16    RD      SA          C  O/C n/a RD      SY        n/a Line Rupture Dise S-23-7                    HPCITurbine Exhaust      H-06 NNS D        Act    16    RD SA          C  O/C n/a RD      SY        n/a                                                t Line Rupture Disc SL23-37A                  Nuclear BoilerVessel    F-05  2    A/C Act    .75  EFC      SA          O  O/C n/a LEF RO ROJ-Vol Inst Excess FlowCheck                                                                                                                                          .
valve SL2347B                    Nuclear BoilerVessel    F-05  2    A/C Act    .75  EFC      SA          O  O/C FC LEF RO ROJ-V01 InstExcess FlowCheck                                                                                                                                            i Valve sb2347C                    Nuclear BoilerVessel    F-05  2    A/C Act    .75  EFC      SA          O  O/C FC LEF RO ROJ-VOI
* Inst Excess FlowCheck Valve                                                                                                                                                            ,
Sb2347D                    Nuclear Boiler Vessel    F-05  2    A/C Act    .75  EFC      SA          O  O/C FC LEF RO ROJ-VO1 Inst Excess Flow Check                                                                                                                                          j Valve 1
Revision 19                                                            Drawing : G-191169 Sh 1                                          Section 5 - Page 42 of 179
 
Vcrmont Yankee Nuclear Power Station -                                                                                        Inservice Testing Program                                ,
Table 5-1 Valve Listing Drawing: G-191169 St.1                      Drawing
 
==Title:==
High Pressure Coolant Injection System Dwg Safety OM Act / Size Body                  Act Norm Safety Fail Test Test CSJ/ROJ                  he Valve Number          Nomenclature l                                              Coor Class Cat Pass (inch)                          Pos  Pos Pos Type Freg      RR SSC-23-12    IsB IIPCITmbme Exhaust          I-03    2. A/C Act                20    GSC  SA  C  O/C n/a LJ      2Y    n/a Stop CheckValve                                                                                SC  RO ROJ-V25 SO    Q    n/a SSC-23-13          IIPCI TurbmeExhaust      J-04    2    C Act                    2  GSC .SA    C    O    n/a CD    RO    n/a Drain Stop Check Valve                                                                        PSO    Q    n/a V23-14              IIPCISteamSupply Valve F-13      2    B        Act        10    GA MO-DC C      O    FAI PIT 2Y        n/a STO    Q    n/a V23-15              IIPCI Steam Supply        D-04      1  A Act                10    GA MO-AC O    O/C FAI LJ      2Y    n/a inboard containment                                                                            PIT 2Y      n/a Isolation Valve                                                                              STC    Q    n/a S10    Q    n/a V23-153A            HPCITorus Supply Line L-03        2    B Pass            .75      GL  MAN  LC    C    n/a n/a    n/a    n/a Drain Valve V23-16        18B IIPCI Steam Supply          D-05      1  A Act                10    GA MO-DC O    O/C FAI LJB Var        n/a Inboanicontainment                                                                            PIT 2Y      n/a Isolation Valve                                                                              STC          n/a Q
STO  Q      n/a V23-160A      18B IIPCI Steam Supply          E-05    2    A Pass 1.75                GL  MAN  LC    C    n/a LJB Var      n/a Drain Valve V23-17              HPCI Pump Suetion        D-Il    2    B        Act        14    GA MO-DC O    O/C FAI PIT 2Y          n/a Valve from Condensate                                                                        STC  Q      n/a StorageTank                                                                                  STO  Q      n/a V23-18              IIPCI Pump Discharge to G-05      2    C        Act        14    CK    SA  C  O/C n/a SC      CS CSJ-V06 Feedwater Check Valve                                                                          SO  CS CSJ-V06 V23-19              HPCI Discharge to        G-06    2    B        Act        14    GA MO-DC C      O    FAI PIT 2Y      n/a Feedwaterlsolation Valve                                                                      STO  Q    n/a V23-20              IIPCI Pump Discharge    G-08    2    B        Act        14    GA MO-DC O      O    FAI PIT 2Y      n/a Valve                                                                                        STO  Q    n/a Revision 19                                                            Drawing : G-191169 Sh 1                                  Section 5      Page 43 of 179
 
Vcrmont Yankee Nuclear Power Station                                                                                                                            Inservice Testing Program Table 5-1 Valve Listing Erawing: G-191169 Sh 1                      DrawingTitle: High Pressure Coolant Injection System Valve Number          Nomenclature            Dwg Safety OM Act / Size                            My      Act        Norm Safety Fail Test Test CSJ/ROJ                      Remarks Coor Class Cat Pass (inch)                                                  Pos  Pos  Pos Type Freq            RR V23-20B        IRA Pressunzing and Vent        G.07    2      C Act                            1 CK      SA            C    C    n/a SC          OC RR-V13 Note 11 Valves HPCIto RX Keep Fill V23-21              HPCI PumpTest Return      Fe07    2      B  Act                          10  GL MO-DC C C    FAI PIT 2Y                n/a Valve to Condensate                                                                                                          STE            n/a Q
StorageTank V23-25              HPCI Pump Mmunum          F-09    2      B  Act                          4  GL MO-DC C                O/C FAI PIT 2Y                  n/a Recire Valve                                                                                                                STC  Q        n/a STO  Q        n/a V23-26B            HPCI Exhaust Dmin to        J-04    2      B Pass                          .75  GL    MAN            LC    C    n/a n/a        n/a        n/a TorusTest Connection Valve V23-27A            HPCI Test Connection      E-04    2      B Pass                          .75  GL    MAN- LC              C    n/a n/a        n/a        n/a V23,32        isA IIPCI Pump Suction          E-11    2      C Act                            14 CK      SA          O/C O/C n/a SC            OC RR-VIS Note 11 CheckValve from Cond.                                                                                                        SO  Q        n/a StorageTank V23-56              HPCI'nnbine Exhaust        J-05    2      C Act                            2  CK      SA          O/C  C    n/a CD          RO        n/a Drain CheckValve                                                                                                              LT 2Y        n/a PSO  Q        n/a SC RO ROJ-V25 V23-57              IIPCITorus Suction        F-10    2      B  Act                          16 GA MO-DC C                O/C FAI PIT          2Y        n/a ContainmentIsot Valve-                                                                                                      STC  Q        n/a Outbd                                                                                                                        STD            n/a Q
V23-58              HPCI Torus Suction        L 04    2      B  Act                          16 GA - MO-DC C              O/C FAI PIT 2Y                  n/a ContainmentIsolation                                                                                                        STC  Q        n/a Valve                                                                                                                    STO              n/a Q
V23-59A            HPCI Torus Supply Test I OS        2      B Pass                          .75 GL    MAN            C    C    n/a n/a        n/a        n/a Connection Valve V23-61              HPCI Torus Suction        Ie06    2      C  Act                          16 CK      SA            C    O    n/a CD          RO        n/a Check Valve Revision 19                                                            Drawing : G-191169 Sh 1                                                                      Section 5      Page 44 of 179
 
A-  .
i Vcrmont Yankee Nuclear Power Station -                                                                                                Inservice Testing Program Table 5-1 Valve Listing
      - Drawing: G-191169 Sh 1                              DrawingTitle: High Pressure Coolant Injection System Dwg Safety OM ' Act / Slae My                      None Safety fab Test Test CSJ/ROJ -                              hah Valve Number                      Nomenclature                                                  Ad                                          RR Coor Class Cat Pass Onch)                          Pos  Pos Pos Type Freq V2342                          IIPCIPumpMuumum        J-10  2      C Act      4    m-              SA    C  O/C n/a ' CD . RO                  n/a Recire CheckValve                                                                        PSO    Q                da V2343A                          IIPCITestCormection en I-03  2    B Pass    .75  GL      MAN          LC    C    n/a n/a n/a                  n/a Toms Exhaust                                                .
V2345                    19    IIPCIhExhaust          I-03  2    NC Act      20    m              SA    C  O/C n/a LJ        2Y              n/a CheckValve                                                                                    SC RO ROJ-V25                                                    '
SO Q                n/a V23445                    tan 11PCITurbine Exhaust      I-2  2    A/C Act      3    m                SA  C  O/C N/A LT        2Y              n/a          Hisis nozzle checkvalve VacuumBreaka                                                                              PSO      Q              n/a          design. '
SC RO ROJ-V33 SO RO ROJ-V33 V23446                    isB IIPCITurbmeExhaust        I-2  2    A/C Act      3    m            . SA    C  O/C N/A LT        2Y              n/a          Disisnozzle checkvalve          '
Vacuum Breake                                                                            PSG    Q              n/a          design.
SC RO ROJ-V33 SO RO ROJ-V33 a
Drawing : G-191169 Sh 1                                                        Section 5 - Page 45 of 179 Revision 19
 
t Vcrmont Yankee Nuclear Power Stalion                                                                                                                                                                    Inservice Testing Program -
Table 5-1 Valve Listing Drawing: G-191169 Sh 2                    Drawing
 
==Title:==
High Pressure Coolant Injection System Nomenclature          Dwg Safety OM Act / Size My                        Act          Nonn Safety Fail Test Test CSJ/ROJ                                                                          gg Valve Number Coor Class Cat Pass (inch)                                        Pos  Pos Pos Type Freq                                                                    RR HPCI-CONTROL        HPCISteam Supply        F-13  2      B    Act                10 GL        HO            O    O                    FC PIT 2Y                                                      n/a    Note 12 Turtune Controlvalve                                                                                                                          SKID Q                                n/a HPCI-STOP          HPCITurbine Stop Valve F-15    2      B    Act                10 GA        HO            C  O/C FC PIT 2Y                                                                        n/a    Note 12 SKID Q                                n/a LCV-23-39          IIPCI Gland SealReturn M-11    3      B    Act                  1 GL      AO              C  O/C FC FST . Q                                                                        u/a Level contDmValveto                                                                                                                                PIT 2Y                            n/a Radwade STC                            Q    n/a STO                            Q    n/a LCV-23-40          HPCI Gland SealReturn M-11      3      B    Act                  1 GL      AO              C  O/C FC . FST                                                                    Q    n/a LevelCont Dm Valve to                                                                                                                              PIT 2Y                            n/a Radwade STC                            Q-    n/a S'IO                          Q    n/a LCV-23-54          HPCI Drain to Gland      I-12  2      B    Act                1  GL      AO              C    O                  FC FST -Q                                                        n/a Seal C1=d-""                                                                                                                                      PIT 2Y                            n/a STC                            Q    n/a S'IO                            Q    n/a PCV-23 50    IsB Pressure ControlValve      J-12  2      B    Act                2  GL      HO            O    O                  FO SKID Q                                                        n/a CoolingWaterto Lube Oil Cooler SR-23-34            HPCI Safety Valve      D-09    2      C Act                  1.5 RV      SA            C    O/C n/a SP                                                                    10Y  n/a SR-23-66            HPCI Booster Pump        J-12  2      C Act                  1.5 RV      SA            C    O/C n/a SP                                                                    10Y  n/a Gland SealCond. Line ReliefValve V23-130            HPCI Gland SealTube      L-11    2      C Act                    2  CK      SA            C    O                n/a SKID Q                                                        n/a    Note 12 Side Return Check Valve V23-131            HPCI Gland Seal Cond. L-11    2      C Act                    2  CK      SA              C  O!C n/a SKID Q                                                                        n/a    Note 12 Shell Side Return Check Valve i
Rtvision 19                                                      Drawing : G-191169 Sh 2                                                                                                                    Section 5    Page 46 of 179
 
                          . Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                                                                                Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191169 Sh 2                                      Drawing
 
==Title:==
High Pressme Coolant Injection System Dwg Safety OM Act / Size My                  Act          None Safety Fail Test Test CSJ/ROJ                                                                                                                                                          y ,,g-Valve Number          Nomenclature Coor Class Cat Pass (mach)                                        Pos                                    Pos Pos Type Freq                                                                              RR V23-148A            HPCI Steam Rmg/ Chest                      G-14  3      C Act              1-  CK    SA                O/C                                            O                              n/a SKID Q                                                    n/a                                Note 12 Drain Check Valve V2314sB              IIPCISteam Rmg/ Chest                      G-14  3      C Act              1    CK    SA          'O/C                                                O                              n/a SKID Q                                                  n/a                                Note 12 .
Drain Check Valve                                                                      .
V23-50A              IIPCI Gland SealCond.                      J-10  2      B            Act  2    GA    AO                      C                                        O                              FO PIT 2Y                                                    n/a                                Note 12 Supply Valve                                                                                                                                                                                                      SKID Q                              n/a I
s b
Revision 19                                                                                      Drawing : G-191169 Sh 2                                                                                                                                                              Section 5                          Page 47 of 179 ;
 
Vcrmont Yankee Nuclear Power Station                                                                                                              Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191170                            Drawing
 
==Title:==
Control Rod Drive Ilydraulic System Dwg Safety OM Act / Size My                                      Act Nonn Safety Fail Test Test CSJ/ROJ            Remah Valve Number            Nomenclature
                                                                          , Ct,or Class Cat Pass (inch)                                          Pos  Pos Pos Type Freq      RR CV4-126            CentrolRod Drive Scram C-16          2        B  Act              1                      GL AO    C    O    FO FST RO ROJ-V06 Note 16 Valve (Typicalof 89)                                                                                              PIT 2Y        n/a                                i S1D RO ROJ-V06 CVa-127            ControlRod Drive Scram C-18          2        B  Act        .75                          GL AO    C    O    FO FST RO - ROJ-V06 Note 16 Valve (Typicalof 89)                                                                                              PIT  2Y      n/a STO RO ROJ-V06 LCV-3-33A    18B Scram Discharge Volume D4)7            2        A Act              2                        BL AO    O    C    FC FST Q          n/a DrainLevelControlValve                                                                                              LT 2Y        n/a PIT 2Y        n/a STU  Q      n/a LCV-3-33B    18B ScramDischarge Volume D-03            2        A Act              2                        BL AO    O    C    FC FST    Q      n/a Drain Level ControlValve                                                                                          LT  2Y      n/a PIT 2Y        n/a STE  Q      n/a LCV 3-33C    18B f,crumDischarge volume D-08            2        A Act              2                        BL AO    O    C    FC FST Q          n/a DrainLevelControlValve                                                                                            LT 2Y        n/a PIT 2Y        n/a STC  Q      n/a LCV 3-33D    18B ScramDisclunge Volume D-03            2        A Act              2                        BL AO    O    C    FC FST    Q      n/a Draini.evel control Valve                                                                                          LT 2Y        n/a PIT 2Y        n/a STC  Q      n/a PCV-3-32A    isa Scram DL%e Volume A-09                2        A Act                1                      BL AO    O    C    FC FST    Q      n/a VentPressureC9ntrol                                                                                                LT 2Y        n/a Valve                                                                                                            PIT 2Y        Wa SIC Q        n/a Revision 19                                                          Drawing : G-191170                                                              Section 5    Page 48 of 179
 
a Vcrmont Yankee Nuclear Power Station                                                                                                                                              ' Inservice Testing Progrann                        .
Table 5-1 Valve Listing                                                                                                    .
Drawing: G-191170                                                                  DrawingTitle: Control Rod Drive Hydraulic System ~
Valve Numiber              Neuneoclature Dwg Way OM Act / h            Body    Act      Nenn W    M    h          h                  WM                          g,,,,,g, .
Coor Class Cat Pass (inch)                        Pos Pos - Pee Type Freq                                RR                                    e PCY442a              IRB Scram DechargeVolume A-01                                            2      A Act        1    BL . AO        O  C    FC FST Q                                        n/a                                  i VatPresnue Control                                                                                                            LT 2Y                                    n/a                                  i Valve                                                                                                                          PIT 2Y                                    Wa S'It              Q                        n/a                                  -
50,1-12e                CRD ManualControl                                          D-17    2      B  Act    .5    GA      SO        .C  C    FC' FST RO ROJ-V06 Note 17 ExhaustValvegypical                                                                                                          STC RO ROJ-V06 of89)                                                                                                .
5 0,3-121                CRD ManualControl                                          D-18    2      B  Act    .5    GA      SO        C  C    FC FST RO ROJ-V06 . Note 17 ExhaustValve Fypical                                                                                                          STC RO ROJ-V06                                                                  ,
of89)
S 4 3-122                CRD ManuelControl                                            C-18  2      B  Act    .5    GA      SO        C  C    FC FST RO ROJ-V06 Note 17 WithdrawalValve                                                                                                              31C RO ROJ-V06 Gypicalof 89)
SO3-123                  CRD ManualControl                                            C-17  2      B  Act    .5    GA      SO        C  C    FC FST RO ROJ-V06 Note 17 Insertion Valve Fypical                                                                                                      - STC RO ROJ-V06                                                                I' of89)
. V3-114                    Scram ExhaustTo                                              C-18  2      C Act      .75    CK      SA        C  OC n/a SC                RO ROJ-V06 Note 18                                                i Discharge Volume Check                                                                                                        SO' RO - ROJ-V06                                                                i (Typicalof 89)
V3-115                  CRD Charging WaterTo B-16                                          2    AC Act      .5    CK      SA      O/C  C    n/a LT              RO ROJ-V06 Note 19                                                i Accumulator Check                                                                                                              SC            RO ROJ V06 UYPi calof 89)                                                                                                                                                                                                ,
V3-13e                  Drive WaterInsert High                                      B-14    2      B Pass    .75    GL    MAN        C  C    n/a n/a            n/a                        ria                                ' ~f Point VentUypical of 89)
V3-132                    Drive WaterWithdrawal A-14                                          2      B Pass    .75    GL    MAN        C  C    n'a n/a            n/a                        n/a IIigh Point Vent,(Typical                                                                                                                                                                                      j of89)
V3-137                    Drive Water Supply                                          B-17    2      C  Act    .5    CK      SA  'OC      C    n/a SC            RO ROJ-V06 CheckValve(Typicalof 89)
Revision 19                                                                                              Drawing : G-191170                                                                        Section 5    Page 49 of 179
 
              - Vcrmont Yankee Nuclear Power Station                                                                                                                                                I: service Testing Prograna '                      ,
Table 5-1 Valve Listing Drawing: G-191170                                                  DrawingTkle: ControlRod Drive Hydraulic System Dwg Safety OM Act / Sise                                            Neran Safety fab Test Test CSJ/ROJ ValveNussber                          Neunenclature -
Coor Class Cat Pass (inch)
                                                                                                                                                %      Act Pos    Pos  Pos Type Freg                RR h6 v3-13e                                CRD Cooling Water                B-16  2      C Act .5                                &        SA    O/C    lC    n/a SC            Q            n/a      Note 3 supply Check valve                                                                                                                                                                            :
(rypicalof 89)                                                                                                                                                                                l V3-162A                              Scrum Ducharge Volume A-09            2    A/C Act                          1        CK      SA    O      C    n/a LT          2Y            n/a VaitCheck Valve                                                                                                                      RO ROJ-V12 SC V3-162B                              ScramDischarge Volume A-01            2    A/C Act                          1        CK      SA    O      C    n/a LT          2Y            n/a Ventcheck Valve                                                                                                          SC          RO - ROJ-V12 V34e8A                              Recire Pump SealPurge            F-12  2      B Pass                        .75        GL    1(AN      C      C    n/a n/a          n/a            n/a                                        ,
Valves                                                                                                                                                                                        ,
B Pass                                        M Ai!'          C                                                                              !
v3-4ess                              Recirc Pump SealPurge            F-12  2                                    .75        GL              C          n/a n/a . n/a                    n/a Valve v3-4 tea                            Recirc Pump SealPurge            F-13  2      B Pass                        .75        GL    MAN      C    .C    n/a n/a          n/a            n/a Valve                                                                                                                                                                                          .
i V3-4 ten                            Recirc Pump ScalPurge            F-13  2      B Pass                        .75        GL    MAN      C      C    n/a n/a          n/a            n/a                                        ,
Valve V3-412A                        18B Recirculshon Pump Seal            E-12  2    A/C Act                        .75        CK      SA    O/C    C    n/a IJB Var                      n/a
;                                                        Purge Supply Check                                                                                                      SC          RO ROJ-V07
.                                                        Valve v3 412B                        ISB Recirculshon Pump Seal E-12            2    A/C Act                        .75        CK      SA    O/C    C    n/a LJB Var                    n/a
.,                                                        Purge Supply Check                                                                                                      SC RO ROJ-V07
:                                                        Valve V3-413A                        18B Recirculshon Pump Seal            E-12  2    A/C Act                        .75        CK      SA    O/C    C    n/a LJB Var                    n/a Purge Supply Check                                                                                                      SC          RO ROJ-V07 Valve V3-413B                        18B Recirculation Pump Seal          E-12  2    A/C Act                        .75        CK      SA    O/C    _C    n/a LJB Var                    n/a Purge Supply Check                                                                                                      SC          RO ROJ-V07 Valve                                                                                                                                                                                          ;
t i
Revision 19                                                                                                    Drawing : G-191170                                                            Section S        Page 50 of 179        !
l
 
Vermont Yankee Nuclear Power Station                                                                                                                                                                                                                                                                                    Inservice Testing Program          '
Table 5-1 Valve Listing
              . Drawing: G-191171                                                            Drawing'I1tle: Stanchy Liquid Control System .
Dwg Safety OM Act / Size My                                                                                                      Act                  None Safety fab Test Test CSJ/ROJ                                                              g ,,, g Valve Nuanber      ' Nesmenclature Coor Class Cat Pass (inch)                                                                                                                                  Pos                    Pos Pos Type Freg                                  RR S-11-14A          SLCInyctan(Squib)                                                G-03                  '2                    D Act - ' l.5 SQUIB EXP                                                                                          C                      O. . n/a Er- 2Y                                - n/a -  Note 4 -
Vdve                                                                                                                                                                                                                                                                                                                                  3
              -S-11-14B          SLCInpctan(Squib)                                                H-03                      2                D Act                                  1.5 SQUIB 'EXP                                                              C                    O                  n/a- ET                2Y      n/a    Note 4 Valve .                                                                                                                                                                                        .                                                                                                                                      .
SR-1139A          SLC Discharge Relief                                              G-08                      2                  C              Act                      1                  RV                        SA                          C                  O/C n/a SP                                  OC RR-VD8 Valve SR-1139B          SLC Dacharge Relief                                              K-08                  '2                    C. Act                                  1-                RV                        SA                        C                  O/C n/a SP                                  OC RR-VD$                              -
,                                Valve V11-16            SLCInjecten Pqnng                                                H-03                      1                C              Act                  1.5                  CK                        SA                        C                  O/C n/a SC                                  RO ROJ-V08 j                                CheckValve                                                                                                                                                                                                                                                                                SO  RO ROJ-VD8 V11-17            SLCInjecten Piping                                                I-02                      1                C Act                                1.5                  CK                        SA                        C                  O/C n/a SC                                  RO ROJ-V08 CheckValve                                                                                                                                                                                                                                                                                SO  RO ' ROJ-V08                            ,
VII-Is            SLCInjecten Valve                                                  I-02                      1                P Pass                                1.5 '                GA                    MAN                          LO                      O                n/a PIT '- 2Y                  n/a -  Note 14 V1136              SLCTest Connection                                                I-03                    2                B Pass                              .75                    GL                    MAN . LC                                              C                n/a - n/a              n/a    n/a V11-43A            SLC Pump Ducherge                                                H-07                      2                C Act                                1.5                  CK                        SA.                        C~                O/C n/a SC                                    Q      n/a CheckValve                                                                                                                                                                                                                                                                                SO    Q      n/a V11-43B            SLC Pump Dacharge                                                  J-07                    2                C Act                                1.5                  CK                        SA                        C                  O/C n/a SC                                    Q      n/a                            ^
CheckValve                                                                                                                                                                                                                                                                              -SO    'Q      n/a i
D Revision 19                                                                                                                                      Drawing : G-191171                                                                                                                                                        Section 5    Page 51 of' 179  i
 
m Vermont Yankee Nuclear Power Station                                                                                                                                                                                  Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191172                                                                  Drawing
 
==Title:==
Resminal Heat Renovat System 1
Dwg Safdy N      Act / h                          None Safety Fall Test Test CSJ/ROJ                                                                                                            '
Valve Number                      Nomenclature                                                                          Body    Act                                                                                            Read Coor Class Cat Pass (inch)                          Pos          Pos Pos Type Fng                                          RR                                                                  !
        .                MV-10-16e                        RHRReturnLine Process F-15                                  2      B  Act .75              GL      AO    C                C                FC FST                        Q      n/a    Valve also appears on G-                                  f SanPling Valve                                                                                                                                      PIT                2Y        n/a    191165                                                    [
STC                  Q        n/a -
j RV-19-210A                      Rdief Valve -                                        E-12    1    A/C Pass            .5 '  RV . SA      C                C                n/a U                      2Y        n/a                                                                !
RV-18-210B                      ReliefValve                                          E-06    1    A/C Pass            .5    RV      SA  -C                C                n/a U                      2Y        n/a SR-10-35A                        RHRPump Ducharge                                    D-02  2      C Act              1    RV      SA    C            OC da- SP                                      10Y        n/a                                                                ,
ReliefValve SR-10,35B                        RHRPump Ducharge                                    D-15  2      C Act              1    RV      SA    C            OC n/a SP                                      10Y .      n/a                                                                ,
RdiefValve                                                                                                                                                                                                                                            !
GR-10 40                        RHRShutdownCooling                                  G-07  2      C Act              1    RV      SA    C            O/C n/a SP                                      10Y        n/a                                                                l Suction Line ReliefValve                                                                                                                                                                                                                              ;
SR-19-72A                      RHR ReliefValve                                      L-07  2      C Act              1    RV      SA    C            OC n/a SP                                      10Y        n/a                                                                ,
SR-19-72B                      RHR Rdief Valve '                                    L-11  2      C Act              1    RV      SA    C            OC n/a SP                                      10Y        n/a                                                                ;
SR-19-72C                        RHR ReliefValve                                      J-07  2      C Act              1    RV      SA    C            O/C n/a SP                                    10Y          n/a                                                                i SR-19-72D                      RHR ReliefValve                                      J-10  2      C Act              1    RV      SA    C            OC n/a . SP                                    10Y        n/a                                                                .
SR-1940A                        RIR Heat Exchanger                                  L-03  2      C Act              4    RV      SA    C          OC n/a SP                                      10Y          n/a "Ihbe Side Relief Valve SR-19-80B                      RHR HeatExchanger                                    L-14  2      C Act              4    RV      SA    C          OC n/a SP                                      10Y          n/a Tube Side ReliefValve SR-16-86A                        RHRIIest Exchanger                                  L-03  2      C Act              1    RV      SA    C          OC n/a SP                                      10Y          n/a
* ShellSideReliefValve                                                                                                                                                                                                                                -!i SR-19-86B                        RHR HeatExchanger                                    L-14  2      C Act              1    RV      SA    C          O/C n/a SP                                      10Y          n/a                                                                i ShellSide ReliefValve V10-13A                        Suppression PoolRHR                                  L-08  2      B  Act            20    GA      CK  O/KL OC FAI PIT 2Y                                                        n/a Purnp Suction Valve                                                                                                                                  STC                Q        n/a                                                                !
STO                Q        n/a Revision 19                                                                                                Drawing : G-191172                                                                                          Section 5    Page 52 of 179
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                                                                                                                          Inscryice Testing Program Table 5-1 Valve Listing Krawing : G-191172                                                                        Drawing
 
==Title:==
Residual Heat Removal System Valve Number        Nomenclature Dwg Safety OM Act / Size My                                                                                                                                                      Act Nona Safety Fail Test Test CSJ/ROJ                        hah Coor Class Cat Pass (inch)                                                                                                                                                              Pos Pos Pos Type Freq                      RR
.          V10-133            Suppression PoolRIIR                                                      I,09                        2                              B Act                                                              20                                    GA MO-AC O/KL OE FAI PIT 2Y                                  n/a Pump Suction Valve                                                                                                                                                                                                                                                                  STC  Q                  n/a STD  Q                  n/a V16-13c            Suppression PoolRHR                                                      J-08                        2                              B                          Act                                    20                                    GA MO-AC O/KL O/C FAI PIT 2Y                                  n/a Pump Suction Valve                                                                                                                                                                                                                                                                  STC  Q                  n/a STO  Q                  n/a V16-13D            Suppression PoolRIIR                                                      J-09                        2                              B                          Act                                    20                                    GA MO-AC O/IG, O/C FAI PIT 2Y                                  n/a Pump Suction Valve                                                                                                                                                                                                                                                                  STC  Q                  n/a                            ,
STO  Q                  n/a V19-15A            Recirculation Loop                                                        K-07                        2                              B                          Act                                    20                                    GA MO-AC C            O/C FAI PIT 2Y                          n/a Supply Valve to RHR                                                                                                                                                                                                                                                                  STC  Q                  n/a Pump suction                                                                                                                                                                                                                                                                        STO                      da Q
V16-15B          Recirculation Loop                                                        K-10                      2                                B                          Act                                    20                                    GA MO-AC C            O/C FAI PIT 2Y                          n/a Supply Valve to R11R                                                                                                                                                                                                                                                                STC  Q                  n/a Pump Suction S1D  Q                  Wa V10-15c            Rairculation Loop                                                        J-07                        2                              B                          Act                                    20                                    GA MO-AC C            O/C FAI PIT 2Y                          n/a Supply Valve to RIIR                                                                                                                                                                                                                                                                STC  Q                  n/a Pump Suction                                                                                                                                                                                                                                                                        STO                      n/a Q
I V10-15D            Recirculation Loop                                                        J-10                      2                                B                          Act                                    20                                    GA MO-AC C            O/C FAI PIT 2Y                          n/a Supply Valveto RIIR                                                                                                                                                                                                                                                                  STC Q                    n/a Pump Suction                                                                                                                                                                                                                                                                                                  da STO Q V19-16A            RHRPump Discharge                                                        I-05                      2                                B                          Act                                        4                                GA MO-AC O            O/C FAI PIT 2Y                          n/a                            i MiniFlow Retum to                                                                                                                                                                                                                                                                    STC Q                  n/a Suppression Pool                                                                                                                                                                                                                                                                    STO                    n/a Q
V16-16B            RHR Pump Discharge                                                        I-12                      2                              B                          Act                                      4                                  GA MO-AC O            O/C FAI PIT 2Y                          n/a MiniFlowReturn to                                                                                                                                                                                                                                                                    STC Q                  n/a Suppression Pool                                                                                                                                                                                                                                                                    STO                    Wa Q
I Revision 19                                                                                                                                                                          Drawing : G-191172                                                                                                                          Section 5 Page 53 of 179
                                                                                                              - _ . _ _ - _ - _ _ - _ - - _ _ - _ - - _ _ _ - - = _ _ _ _ - _ _ _ _ _ _ - _ . _ - - _ _ _ _ - _ - _ _ - - - _ _ _ - - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _
 
Vermont Yankee Nuclear Power Station -                                                                                                                                                              Inservice Testing Program Table 5-1 Valve Listing Erawing : G-191172                                                              Drawing
 
==Title:==
- Residual Heat Removal System Nomenclature                                    Dwg Safety OM Act / Size                    my            ge,  Norma Safety            Fail Test Test CSJ/ROJ                                                  hah          i Valve Number -
Coor Class Cat Pass (inch)                                        Pos                Pos  Pos Type Fng            RR V10-17          1sB Recarc Supply to RHR                                          G 08    1      A Act                    20 GA MO-DC C                              O/C . FAI LJB Var              n/a                            Note 21 Pump Suct. Outbd.                                                                                                                          .
LT    2Y          n/a Isolation Valve                                                                                                                                        PE 2Y                Wa                                                          >
                                                                                                                                                ~
STC CS CSJ-V08 STO CS CSJ-V08 V19-17Al                  V10-17 Bonnet Vent                                      G-08    2      B  Act                  .5 GL          MAN      C                O/C n/a SC        CS CSI-V18 Valve V18-18          IsB Recire Supply to RHR                                          F-08    1      A Act                    20 GA MO-AC C                              O/C FAI LJB Var                n/a                            Note 21                      '
Pump SuctionInbd                                                                                                                                        LT 2Y              n/a IsolationValve                                                                                                                                        PE 2Y-              da STC CS CSJ-V08 STO CS CSJ-V08
* V10-182                  RHRSW to RHR                                            I-02    2      C Pass                    10 CK            SA      C                n/a  n/a n/a      n/a          n/a -
Emergency FillCheck Valve V10-183                    RHRSW to RHR                                            J-02    2      B Pass                    10 GA MO-AC C                              C  FAI PIT 2Y                n/a -
Emergency FillIsolation                                                                                                                                                                                                                  [
Valve V10-184                  RIIRSW to RIIR                                          J-02    2      B Pass                    10 GA MO-AC C                              C  FAI PIT 2Y                n/a Emergency FillIsolation Valve V10-18A        18B Penetration X-12                                              F-08    2      A/C Act                  .50 CK            SA C                O/C n/a LJB Var                n/a                            Note 21 "Ihennal ReliefValve                                                                                                                                    LT 2Y              n/a SC    RO ROJ-V29 SO RO ROJ-V29                                                                    ,
V10-18A5      18B V10-18 Bonnet Relief                                          F-08    2      A/C Act                  .50 CK            SA      C                O/C n/a LJB Var                n/a                            Note 21 Valve                                                                                                                                                  LT 2Y                n/a SC RO ' ROJ-V29 SO RO ROJ-V29 V10-198B      18B Process Sampling Valve                                        E-14    2      A Pass                  .75 GL          MAN      LC                  C  n/a LJB Var              n/a e
Revision 19                                                                                            Drawing : G-191172                                                                              Section 5                                    Page 54 of 179
 
Vcrmont Yankee Nuclear Power Station                                                                                Inservice Testing Program Table 5-1 Valve Listing Crawing: G-191172                            DrawingTitic: Residual Heat Removal System Dwg Safety OM Act / Size hdy          Act  Nonn Safety Fail Test Test CSJ/ROJ        Remah Valve Number            Nomenclature Coor Class Cat Pass (inch)                  Pos  Pos Pos Type Freq      RR V10-19A                RHRMuumumFlow          1,05  2      C Act      3  CK      SA    O/C O/C n/a CD        RO    n/a CheckValve                                                                          PSO    Q    n/a V10-19B                RIRMmunum Flow          L-12  2    C Act        3  CK      SA    O/C  O/C n/a CD      RO    n/a CheckValve                                                  .                      PSO    Q    n/a V10-19C                RIIR Minimum Flow      J-05  2    C Act        3  CK      SA    O/C  O/C n/a CD      RO    n/a CheckValve                                                                          PSO    Q    n/a V10-19D                RIIR MaumumI' iw        J-12  2    C    Act    3    CK      SA    O/C  O/C n/a CD      RO    n/a Check Valve                                                                        PSO    Q    n/a V10-20                RIIRLoop Crossconnect H-05    2    B Pass      20  GA MO-AC C          C    FAI PIT 2Y        n/a Valve V10-206A              RIIR Suppression Pool  I-08  2    B Pass    .75  GA    MAN      C    C    n/a n/a    n/a    n/a Suction Dmin V10-206B              RIRSuppression Pool    I-09  2    B Pass    .75  GA    MAN      C    C    n/a n/a    n/a    n/a Suction Line Drain V10-25A              RIIRto Recirc Loop      E-06  1    B    Act    24  GA MO-AC O          O    FAI PIT 2Y        n/a Isolation Valve                                                                    STO  Q      n/a V10-25B              RHRto Recirc Loop      E-12  1    B    Act  24    GA MO-AC O          O    FAI PIT 2Y        n/a Isolation Valve                                                                    STO  Q      n/a V10-26A      ISB RHRTo Containment            C-07  2    A Act      12  GA MO-AC C        O/C FAI LJB Var        n/a Spray Isolation Valve                                                              PIT 2Y      n/a STC  Q    n/a STO  Q    n/a                        i V10-26B      18B RIIRTo Contamment            C-10  2    A Act      12  GA MO-AC C        O/C FAI LJB Var        n/a sprayIsolation talve                                                                PIT 2Y      n/a STC  Q    n/a STO  Q    n/a R:. vision 19                                                    Drawing : G-191172                                      Section 5 Page 55 of 179
 
w Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                                                                                                                  Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191172                        DrawingTitle: ResidualHeatRemovalSystem Dwg Safety OM Act / Size My                                                                                                                                                                                                                Act Nonn Safety Fail Test Test CSJ/ROJ                                      hah Valve Number        Nomenclature Coor Class Cat Pass (inch)                                                                                                                                                                                                                        Pos  Pos Pos Type Freg      RR
  - V10-27A            RHR to Recire Loop      D46 1                                                                                                  A Act ' 24                                                                                                                    GL MO-AC C      O/C FAI U        2Y    n/a    Note 21 Isolation Valve                                                                                                                                                                                                                                                                            LT  2Y    n/a PIT 2Y      n/a STC    Q    n/a STO    Q    n/a V10-27B          RHR to Recire Loop      D-12                                                          1                                        A Act                                                                                  24                                    GL MO-AC C      O/C FAI U        2Y    n/a    Note 21 Isolation Valve                                                                                                                                                                                                                                                                            LT  2Y    n/a PIT 2Y      n/a STC    Q    n/a i
STO    Q    n/a V10,31A      Isa RIIRTo Contamment          C-08                                                        2                                        A Act                                                                                    12                                  GA MO-AC C      O/C FAI LJB Var        n/a Spray Isolation Valve                                                                                                                                                                                                                                                                    PIT 2Y      n/a STC    Q    n/a STD    Q    n!a V10 31B      18B RHRTo Contamment            C-10                                                        2                                        A Act                                                                                    12                                  GA MO-AC C      O/C FAI LJB Var        n/a spray Isolation Val ~                                                                                                                                                                                                                                                                    PIT 2Y      n/a STC    Q    n/a STO    Q    n/a V10-34A      18B RHR SuppressionPool        E-03                                                        2                                        A Act                                                                                    10                                  GL MO-AC C      O/C FAI UB Var          n/a cooling Supply Valve                                                                                                                                                                                                                                                                      PIT 2Y      n/a STC    Q    n/a                                                          ,
STO    Q    n/a V10-34B      18B RIIR SuppressionPool        E-14                                                      2                                        A Act                                                                                    10                                  GL MO-AC C      O/C FAI UB Var          n/a
.,                      Cooling Supply Valve                                                                                                                                                                                                                                                                      PIT 2Y      n/a STE  Q      n/a STO  Q      n/a V10-36A      18A RHRPump Discharge              J43                                                      2                                        C Act                                                                                        1                              CK    SA  O/C  C    n/a SC    OC RR-V13 Note 1I Ihking Line Check Valve Revision 19                                                                                                                                                                                Drawing : G-191172                                                                                                            Section 5              Page 56 of 179
 
Vcrmont Yankee Nrclear Paw:r Station                                                                                                                                                      Inservice Testing Program Table 5-1 Valve Listing Crawing: G-191172                                                        Drawing
 
==Title:==
ResidualHeat Removal System Dwg Safety OM Act / Size Body                                              Act Nona Safety fab Test Test CSJ/ROJ          hah Valve Nuanber        Mouncociature Coor Class Cat Pass (inch)                                                        Pos  Pos Pos Type Freg      RR VisJ6B        IsA RHRPump Ducharge                                              J-14                    2    C Act                    1          &    SA  O/C  C-  . n/a SC- OC RR-V13 Note ll P.      a; LineCheck t
Valve VitJ8A        18B Suppresmon Chamber                                          E-04                      2    A Act                    4          GL MO-AC C O/C FAI UB Var -      n/a RHRSpray Ring Supply                                                                                                                                          PIT 2Y    n/a 4
Valve                                                                                                                                                        g    q    g,                            -
STO  Q    n/a                          +
V16J8B        IsB Suppresnon Chamber                                          F-13                      2    A Act                    4          GL MO-AC C      OC FAI UB Var          n/a                          >
RHRSpray Ring Supply                                                                                                                                          PE 2Y      Wa                            i Valve                                                                                                                                                        g    q    g,                            ;
S10 Q      n/a VISJ9A        18B RHRCont                                                      D-04                      2    A Act                    12          GA MO-AC C      O/C FAI LJB Var        n/a Spray /Suppresson Pool                                                                                                                                      - PIT 2Y    n/a                          .
t Cooling Supply Valve -                                                                                                                                      g q        g, S10  Q    n/a                          ,
V1009B        IsB RHRCont                                                      D-13                      2    A Act                    12          GA MO-AC C      OC FAI LJB Var        n/a                            ,
Spray /Suppresson Pool                                                                                                                                      PR 2Y      n/a Cooling Supply Valve                                                                                                                                        g    q    g, STO  Q    n/a V16 46A            RHRto RecireInjection                                      Fe07                      1  AC Act                    24          &    SA    C  OC n/a LT        2Y    n/a    Note 21 Check Valve                                                                                                                                                  SC  Q    n/a                            !
SO  CS CSJ-V14 V16 46B              RHRto RecireInjection                                      E-10                      1  AC Act                    24          &    SA    C  OC n/a LT -2Y          n/a    Note 21 Check Valve                                                                                                                                                  SC  Q    n/a SO  CS CSJ-V14        _
V10-48A              RHRPump Discharse                                          L-05                      2    C Act                    16          &    SA  OC    OC n/a PSO      Q  CSJ-VIS CheckValve                                                                                                                                                  SC  Q    n/a                          '[ '
SO  CS CSJ-VIS Revision 19                                                                                                            Drawing : G-191172                                                    Section 5    Page 57 of 179
                                                                                                                                . . . . . . _ _ . . -    _ ~ _ _ _
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191172                          a. wing
 
==Title:==
Residual Heat Removal System swg Safety OM Act / Sire                                  Body          Act Nonn Safdy Faa Ted h                      N OJ                  Remarks Valve Number          Nomenclature lCoor Class Cat Pass (inch)                                                    Pos  Pos        Pos Type Freg              RR V10-48B            RIIRPump Discharge        L-13    2      C Act 16                                          CK    SA  O/C  O/C n/a PSO                  Q        CSJ-V15 Check Valve                                                                                                                          SC  Q          n/a SO  CS CSJ-VIS V10-48C            RHRPump Discharge        J-05    2      C    Act    16                                  CK . SA    O/C  O/C n/a PSO                  Q        CSJ-V15 Chcck Valve                                                                                                                          SC  Q          n/a SO  CS CSJ-V15 V10-48D            RIIRPump Discharge        J-13    2      C    Act    16                                  CK    SA  O/C  O/C n/a PSO                  Q        CSJ-VIS Check Valve                                                                                                                          SC  Q          r/a SO CS CSJ-V15 V10-52A            RHRContainment Spray      C-08    2      B Pass      .75                                  GL    MAN    C    C        n/a n/a          n/a        n/a Loop A Test Connection V10-52B            RHRContainment Spray C-10        2      B Pass      .75                                  GL    MAN    C    C        n/a n/a          n/a        n/a Loop B TestConnection V10-57        I8B RHR Loop Crossconnect H-13        2      B    Act    4                                  GA MO-DC C        C        FAI PIT          2Y          n/a To RadWasteIsolation                                                                                                                STE  Q          n/a Valve V10-65A            RIIRIIX Bypass Valve      J-03    2      B    Act    20                                  GL MO-AC O      O/C FAI PIT 2Y                          n/a STC  Q          n/a STO  Q          n/a V1M5B              RIIR HX Bypass Valve    K-15    2      B    Act    20                                  GL MO-AC O        O/C FAI PIT 2Y                          n/a                                              -
STC  Q          n/a STO  Q          n/a V10-66        18B RIIRLoop Crossconnect H-13          2      B    Act    4                                  GA MO-AC C          C        FAI PIT 2Y                  n/a To RadWaste Isolation                                                                                                              STC  Q          n/a Valve V10-78A            RIIR "A" Injection Line  F-06    2      B Pass      .75                                GL      MAN  C    C        n/a n/a          n/a        n/a Test Connection V10-78B            RIIR"B"lajection Line    F-12    2      B Pass      .75                                GL      MAN  C    C        n/a n/a          n/a        n/a Test Connection Revision 19                                                        Drawing : G-191172                                                                                    Section 5      Page 58 of 179
 
L S
Vcrinont Yankee Nuclear Pcwcr Station                                                                                                                    I service Testi;g Program Tabic 5-1 Valve Listing Drawing: G-191172                                                DrawingTitle: ResulualHeatRemovalSystem Dwg Safety OM Act / Sise                                Noma Safety Fall Test Test CSJ/ROJ                Resad                    l Valve Number              Noamenclature.
Coor Class Cat Pass (inch)
M        Act Pos    Pos- Pos Type Fatg      RR V1081A              RHRto Recire Loop                              E-07  2                B Pass 24          GA- MAN        LO    O    n/a PIT 2Y          n/a -  Note 14
: InjectionValve                                                                                                                                                                      r V1681B              RHRto Recire Loop                              E-10  2~              B Pass      24    GA      MAN    !O-    O    n/a PIT    2Y-    n/a    Note 14 InjectionValve                                                                                  ,
                                                                                                                                                                                                          ~
V1684-              Test Connection Between G-09                          2                B Pass    .75 '  GL      MAN    C'    C    n/a n/a    n/a    n/a V10-17 and 18 V1689A              RHRHX Savice Water                            M-01  3                B  Act      12    GL MO-AC -C          O/C FAI PIT      2Y_    n/a    Valve also appears on G-        '!
OutletValve                                                                                                              . STC  Q      n/a    191159 Sh 2                    -[
S10    Q      n/a                                      i V1649B              RHRHX Service Water                            M-17  3                B  Act      12    GL - MO-AC C        O/C FAI PIT 2Y            n/a    Valve also appears on G- -
OutletValve                                                                                                                SIC Q        n/a    191159 Sh 2 STO - Q^      n/a '                                    l Vio-91A          . Test Connection                                E-07  2                B Pass    .75    GA      MAN    LC    C. n/a n/a    n/a    n/a Vio-91B            Test Connection                                E-11  2                B Pass    35'    GA      MAN    LC    'C    n/a n/a    n/a    - n/a Vie-95A            Test Connection                              -D-04  2                B Pass 35          GA      MAN    LC    ~C  . n/a . n/a  n/a    n/a V10-95B            Test connection                              D-14  2                B Pass    .75    GA . MAN      LC    C-  n/a n/a    n/a    n/a                                      I a    VIS-96A            Test ''*-                                      C-08  2                B Pass    .75    GA      MAN    LC    C . n/a n/a . n/a        n/a                                      j Vio.968            Test connection                              C-10  2                B Pass    .75    GA      MAN    LC    C    n/a ~ n/a  n/a    n/a                                    ~
I Revision 19                                                                                    Drawing : G-191172                                              Section 5    Page 59 of 179            .
i
 
f Vcrmont Yankee Nuclear Power Station                                                                                                                                                                  Inservice Testing Pmgram.
                                                                                                                                                                                                                                      ~
                                                                                                                    ~ Table 5-1 Valve Listing                                                                                                                          'i Drawien: G-191173 Sh 1                                  Drawing Tkle: ' Fuel Pool Cooling & Cleanup System Valve Namnber '        Nomenclature                      Dwg                W                  OM ActI h      Body      ~ Act None      W                    M        M                M WM                                  .
g,,,,,g,-
Coer Class Cat Pass (inch)                                                    Pos  Pos                  Pos      Type            Fng    RR
      -  - V19-18              FuelPoolDenunerahmer - I-13                                          3'        C' Act    6    CK        SA        O  .C                      n/a SC ~ .Q                      n/a -
Return CheckValve V19-21A '            FuelPoolCooling Return A-07                                          2        .C  Act  6    CK        SA        O  .O'                      n/a SO                    Q      n/a                  ~
to FuelPool Check Valve .
V19-21B              FuelPoolCooling Retum A-07.                                          2        C  Act  6    CK      'SA        O '-  O                      n/a .SO                  Q .. n/a to FuelPoolCheck Valve i          V19-220              NoonalFuelPool                        G.07                          3        B . Act  8    GA MO-AC O                C                    FAI PIT 2Y                          n/a .
Coohng Subsystem Isolation Valve 3It - Q-                  n/a 3
V19-221              Nonnal FuelPool -                    G-08                          3        B' Act    8    GA MO-AC O                C                    FAI PIT 2Y                          n/a Cooling Subsystem                                                                                                                                        STC . Q .-                n/a
                              ' Isolation Valve V19-224              FuelPool C--                  =r-"  I-12                          3        C ' Act  6    CK-      'SA        O    C                      n/a SC                    RO ROJ-V23 Retum CheckValve V19-45              U Gate Valve F/D Bypass K-0i                                        3        B Pass    4    GA        M A'4      C    C                      n/a n/a - n/a                    n/a t
          .V19-53              UGate Valve RX WellL H-05                                          3          B Pass    6~    GA        MAN        C. C                      n/a n/a - n/a                    n/a f
Recirc Valve -
                                                                                                                                                                                                                                                                        'i I
i t
I
                                                                                                                                                                                                                                                                        -l Revision 19                                                                                              Drawing : .G-191173 Sh 1                                                                        Section 5 ' Page 60 of 179                            ;
_--_        _          __ - _        - _                _ _ - _ _ _. --- - __                                              -____-___J
 
Vcrmont Yankee Nuclear Power Station                                                                                                                    Inservice Testing Program -
Table 5-1 Valve Listing Drawing: G-191173 Sh 2                        Drawing
 
==Title:==
FuelPoolCooling& Cleanup System Dwg Safety OM Act / Size Body                            Act Nonn Safety Fail Test Test CSJ/ROJ                                                                        Rema h Valve Number          Nomenclature Coor Class Cat Pass (inch)                                        Pos  Pos Pos Type Freq                        RR f.V19-232A          Standby FuelPoolHeat        C-07          3 C Act            1                RV    SA          C O/C. n/a SP 10Y                                Wa ExchangerFPC Side ReliefValve RV19-232B          Standby FuelPoolHeat        F-07          3 C  Act          1                RV.
* SA          C O/C n/a SP                  10Y              n/a ExchangerFPC Side ReliefValve RV70-260A          Service Water Relief        D-08          3 C Act          .75                RV    SA          C O/C n/a SP                  10Y              n/a Valve RV70-260B          ServiceWaterRelief          F-08          3 C Act          .75                RV    SA          C O/C n/a SP                  10Y              n/a Valve V11226              Standby FPCS Manual          C-13          3 B Pass          6                GA  MAbi          C  C        n/a n/a          n/a              n/a Isolation- ESS Pump                                                                                                                                                .
Cross-tie                                                                                                                                                                                                        i V19-230A          Standby FuelPool            G-10          3 C  Act          6                CK    SA          C O/C n/a SC                    Q              n/a Cooling Pump Discharge                                                                                                      SO  Q              n/a CheckValve                                                                                                                                                                                                        i V19-230B            Standby FuelPool            H-10          3 C Act          6                CK    SA          C O/C n/a SC                    Q              n/a Cooling Pump Discharge                                                                                                      SO  Q              n/a Check Valve                                                                                                                                                                                                      ,
V70-244A      1sn SW System Vacuum            B-10          3 C Act          2                CK    SA          C O/C n/a SC                  RO ROJ-V28 BreakerCheckValve                                                                                                          SO  RO ROJ-V28 V70-244B      18B SW System Vacuum            B-10          3 C Act          2                CK    SA          C O/C                      SC  RO ROJ-V28 Breaker CheckValve                                                                                                          SO  RO ROJ-V28 V70-257A            SFPC Hx ScrviceWater        C-10          3 B  Act          4                GL MO-AC C            O        FAI PIT 2Y                      n/a outlet                                                                                                                STC      Q            n/a Hrottling/IsolationValve                                                                                              g          g            g V70-257B            SFPC IIx ServiceWater      F-10          3 B  Act          4                GL MO-AC C            O        FAI PIT 2Y                      n/a Outlet                                                                                                                STC        Q            n/a nrottling/ Isolation Valve                                                                                          g          q            g, Revision 19                                                        Drawing : G-191173 Sh 2                                                                                Section 5                                  Page 61 of 179
 
Vermont Yankee Nuclear-Power Station                                                                                                                                                                                      Inservice Testing Program Table 5-1 Valve Listing Crawing: G-191174 Sh 1                                                        Drawing
 
==Title:==
Reactor Core Isolation Cooling System Valve Number                                            Nomenclature                Dwg Safety OM Act / Size My            Act          Nonn Safety Fall Test Test CSJ/ROJ                                                                      h6 Coor Class Cat Pass (inch)                            Pos                Pos Pos Type Freq                                          RR                                                                                                                -
  . FCV-13-34                                              RCIC Main Steam Drain K-17 NNS B Act                    1    GL        AO              O                  O/C FC FST Q                                                    n/a to Condenser Valve                                                                                                                                PIT 2Y                    n/a                                                                                                          .
STC              Q          n/a S10              Q          n/a FCV-13435                                              RCIC Main Steam Drain L-17 NNS B                Act    1    GL        AO              O                  O/C FC FST                                            Q          n/a                                                                                                          .
to Condenser Valve                                                                                                                                PIT 2Y                    n/a STC              Q          n/a S'ID              Q          n/a LCV-13,32                                              RCIC Steam DrainTrap            H-17  2    B  Act  .75    GL        AO              C                  O/C FC FST                                            Q          n/a Bypass Valve                                                                                                                                    PIT 2Y                    n/a STC              Q          n/a STO              Q          n/a                                                                                                          -
Sb13-55A                                              RCIC Instrumentation            B-08  2  NC Act    .75  EFC        SA              O                  O/C n/a LEF RO ROJ-Vol Excess FlowCheck Valve SL13-55B                                              RCIC Instrumentation            C-08  2  NC Act    .75  EFC        SA              O                  O/C n/a LEF RO ROJ-V01 Excess FlowCheck Valve Sb13-55C                                              RCIC Instrumentation            B-08  2  NC Act    .75  EFC        SA              O                  O/C n/a LEF RO ROJ-V01 Excess FlowCheck Valve SL13-55D                                              RCIC Instrumentdion            C-08  2  NC Act    .75  EFC~        SA              O                  O/C n/a LEF RO ROJ-V01 Exces FlowCheck Valve SSC-13-10                                              RCIC Barometric Cond            K-09  2    C  Act    2    GSC        SA              C                  O  n/a SO                                          Q        n/a Vacuum Pump Disch                                                                                                                                                                                                                                                                        ,
Stop Check Valve SSC-13-9                                          18B RCIC Steam Exhaust              K-03  2  A/C Act    S  GSC          SA              C                  O/C n/a LJ                                          2Y        n/a stop Check Valve                                                                                                                                  SC          RO ROJ-V26 SO            Q      n/a                                                                                                              i V13-143A                                              RCIC Pump SuctionTed N-09              2    B Pass    .75  GL      MAN              LC                  C  n/a n/a                                          n/a      n/a Connection Revision 19                                                                                            Drawing : G-191174 Sh 1                                                                                                          Section 5    Page 62 of 179 x__      - - - _ - _    -.--,a-,-----u--      - - - - - - . _ -_ _ - - - - - _ - - - - - -        ._--_---,__.----,-.u---  - - _ _ , - _ - - - - - - _ _ - - - - - - - - - - _ - - - - _ _ _ . . , - - -
 
Vermont Yankee Nuclear Power Station                                                                                                                                                                                                          Inservice Testing Program 7                        i Table 5-1 Valve Listing Drawing: G-191174 Sh 1                                                            Drawing flete: Reactor Core Isolation Cooling System                                                                                                                                                          _
D                  ' Safety OM Act / Sise                                                                              Norm Safety fab Test Test CSJ/ROJ Valve Nussber                  Nonsenclature la'        a            r Class Cat Pass (inch)
M    Act Pos  Pos Pos Type Freg    RR h6 V13-15                      RCIC Steam Supply                                              E47                              1                      A Act                                              3  GA MO-AC O    OC FAI IJ      2Y    n/a                                              !
Inbo.ra Contamment                                                                                                                                                                                      PIT  2Y-    n/a                                              !
Isolation Valve                                                                                                                                                                                                      Wa STC  Q                                                    .[
STO  Q    n/a                                              !
V13-15eA -            188 SteamLine Drain Root                                            Fe09                            2                      A Pass                                              1 GL. MAN  LC    C    n/a IJB Var    n/a                                              i Valve                                                                                                                                                                                                                                                                  r V13-16                18B RCIC Steam Supply                                              F,09                              1                      A Act                                            3  GA MO-DC O    O/C FAI IJB Var        n/a Outboard Contamment                                                                                                                                                                                      PIT 2Y      n/a                                              5 IsolationValve                                                                                                                                                                                          g    q      g,                                                t STD  Q      n/a                                              l
              .V13-1s                    Cond nsate Supply to                                          E-14                              2                      B                  Act                          6  GA MO-DC O    OC FAI PIT 2Y          n/a                                              l RCIC Pump Suction                                                                                                                                                                                        SIC Q      Wa                                              I Valve                                                                                                                                                                                                  3.gg  q      g,                                                [
v13-19                18A Condensate supply to                                            E-14                              2                      C Act                                            6  CK'  SA  OC  OC n/a - SC    OC RR-VIS Note 11 RCIC Pump Suction                                                                                                                                                                                        SO  Q      n/a Check Valve
:              V13-29                    RCIC Pump Discharge                                            G-10                              2                      B                  Act                            4  GA MO-DC O      O    FAI PIT  2Y    n/a Isolationvalve                                                                                                                                                                                          STO  Q      n/a i'              v13-2eB              18A n- -- .:.- Valve Keep G-11                              2                      C                  Act                            1  CK  SA    C    C    n/a SC    OC RR-V13 Note 1I                                        f FillSystem                                                                                                                                                                                                                                                            [
V13-21                    RCIC InjectionIsolation G-09                                                                    2                      B                  Act                            4  GA MO-DC C      O    FAI PIT 2Y      n/a                                              i Valve                                                                                                                                                                                                  STO  Q      n/a                                              ,
V13-22                      RCIC Injection Check                                          G-09                            2                        C                  Act                            4  CK  SA    C  OC n/a SC      CS CSJ-V10 Valve              .                                                                                                                                                                                    SO  CS CSJ-VIO
;              V13-27                      RCIC Pump Discharge                                            I-I1                            2                      B                  Act                            2  GL MO-DC C    OC FAI PIT 2Y        n/a Minimum FlowValve                                                                                                                                                                                      STC 'Q      n/a                                                f STO  Q    n/a
[
Revision 19                                                                                                                                                              Drawing : G-191174 Sh 1                                                  Section 5  Page 63 of 179
 
                                                                                                                                                                                                                                                                  ~
Vcrmont Yankee Nuclear Power Station                                                                                                                                                              JInservice Testing Program Table 5-1 Valve Listing
              ' Erawing: G-191174 Sh 1                                                          DrawingTitle: Reactor Core Isolation Cochng System Dwg Safety OM Act / Size Body                                      Norun Safety fab Test Test CSJ/ROJ                                                            '
Valve Number                                              Nomenclature Coor Class Cat Pass (inch)
Act Pos        Pos Pos Type Freg              RR
                                                                                                                                                                                                                                  ' hh VI3-29                                              RCIC Panp Discharge        J-10    2    C Act              2                CK      SA          C        OC n/a CD                RO      n/a -
Mmunum FlowCheck                                                                                                        PSO                  n/a Valve Q
V13,30                                                RCIC PumpDischarge          E-10    2  B. Act            4                GL' MO-DC C C  FAI PIT 2Y                . n/a '
Retun to Con &nute                                                                                                      SE                    Wa Storage Tank Q
V13 38                                              RCIC Vacuum Pump          K-11      2  C Act                2              ' CK -    SA          C        OC n/a SC~ RO ROJ-V26 DischarEe Check Valve                                                                                                    SO            Q      n/a
.              ' V13,39                                                Supp PoolSupply to          F-13    2  B    Act            6                GA MO-DC C                    OC FAI PIT 2Y                    n/a                                            ,
I RCIC Pump SuctInbd                                                                                                      SK                    n/a IsolValve Q
gm            q      g,                                            *
,                V1340                                                Suppression Pool Supply N-11        2  C    Act            6                CK      SA          C          O    n/a CD            RO      n/a to RCIC PumpSuction                                                                                                                                                                          l CheckViv.                                                                                                                                                                                      ,
V13-41                                              Supp PoolSupply to        N-10      2  B    Act            6                GA MO-DC C                    OC FAI PIT 2Y                    n/a RCIC Pump SuetInbd                                                                                                      STC                  n/a Isol Valve Q
g              q      g, V13-43A                                              RCIC Pump SuctionTest N-11          2  B Pass            .75                GL    MAN            C          C . n/a n/a            n/a    n/a .                                          1 Connection V13-46A                                              RCIC Main Steam Line      E-08      2  B Pass            .75                GL    MAN          LC          C  n/a n/a            n/a    n/a Test Connection                                                                                                                                                                              !
2 V13-Se                          19                  RCIC Tube Exhaust          K-08      2  AC Act              8                CK      SA          C          OC n/a LJ                2Y    n/a CheckValve                                                                                                              SC            RO ROJ-V26 SO            Q    n/a V13-52B                                              RCIC Pump Ditharge        K-09      2  B Pass            .75              GL    MAN          LC            C  n/a n/a            n/a    n/a                                            -
Test Connection                                                                                                                                                                              l t
V13-53A                                              RCIC TurbmeExhaust        K-08      2  B Pass .75                          GL    MAN          LC            C  n/a n/a            n/a    n/a Tedconnection                                                                                                                                                                                l I
i Revision 19                                                                                          Drawing : G-191174 Sh 1                                                                          Section 5  Page 64 of 179                    :
i I
 
  . Vcrmont Yankee Nuclear Power Station                                                                                      Inservice Testing Program            ,
Table 5-1 Valve Listing Drawing : . G-191174 Sh I                  Drawing'Iltle: Reactor Core Isolation Cooling System Valve Number            Nomenclature          Dwg Safety OM Act / Size My              Act  Norna Safety Fan Test Test CSJ/ROJ Remah Coor Class Cat Pass (inch)                      Pos  Pos Pos Type Freq        RR V13420          18B ' RCIC 'Ibrtune Exhaust  K-8      2    A/C Act      2      CK      SA      C    O/C N/A LT      2Y      n/a      Disisnozzle checkvalve Vacuum Brmker                                                                            PSO            n/a      design.
Q SC  RO ROJ-V33 SO  RO ROJ-V33 V13421          isB RCIC Turbine Exhaust      K-8    .2    A/C Act      2      CK      SA      C    O/C N/A LT      2Y      n/a      Thisisnozzle checkvahe VacuumBreaker                                                                            PSO            n/a      design.
Q SC  RO ROJ-V33 SO  RO ROJ-V33 i
L
                                        ^
r Drawing : G-191174 Sh 1                                      Section 5        Page 65 of 179 I Revision 19                                                                                                                              ,
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                                                                                          inservice Testing Program Table 5-1 Valve Listing Drawing : G-191174 Sh 2                    Drawing 11tle: Reactor Core Isolation Cooling System i
Dwg Safety OM Act / She My                                                                                                                                                                                          Norma Safety Fall Test Test . CSJ/ROJ Valve Number          Nomenclature                                                                                                                                                                                                                          Ad                                                hah Coor Class Cat Pass (inch)                                                                                                                                                                                            Pos  Pos  Pos Type Freg      RR LCV-13-12          RCIC Baro Cond      .
L-10  3                                  B                                    Act                                                      1                                          GA                          AO  C    O/C FC FST Q              n/a condensate Pump Disch                                                                                                                                                                                                                                          PIT 2Y        n/a Dmin LCV                                                                                                                                                                                                                                                      g      q      g, SIO    Q      n/a LCV-13-13          RCIC Baro Cond          L-10  3                                  B                                  Act                                                      1                                          GA                          AO  C    O/C FC FST        Q      n/a Condensate Pump Disch                                                                                                                                                                                                                                          PIT  2Y      n/a Drain LCV                                                                                                                                                                                                                                                                    da S'PC    Q STO    Q      n'e PCV-13-23          Cooling Wcier to        H-06  2                                  B                                  Act                                                    2                                              GL                        AO  O    O    FO SKID Q          n/a    Note 12 Barometric Condenser RCIC-CONTROL      RCIC Turbine Govenung D-12      2                                  B                                  Act                                                    2                                            GL                          HO  O    O/C FAI PIT      2Y    n/a    Note 12 Valve                                                                                                                                                                                                                                                          SKID Q        n/a S-13-3              RCIC Tu:bine Steam      E-11  2                                  D                                  Act                                                    8                                            RD                          SA  C    O/C n/a RD        SY    n/a Exhaust Rupture Disc S-13-4            RCIC Turbine Steam      E 09 NNS D                                                                    Act                                                    8                                            RD                          SA  C    O/C n/a RD        SY    n/a Exhaust Rupture Disc SR-13-25          RCIC Pump Suction        C-07  2                                  C                                  Act                                                      1                                          RV                          SA  C    O/C n/a SP        10Y    n/a ReliefValve SR-13-26          RCIC Pump Discharge      I-07  2                                  C                                  Act                                                      1                                          RV                          SA  C    O/C n/a SP        10Y    n/a Line to Bammetric Cond ReliefViv SR-13-27            RCIC Bammetric          J-14  3                                  C                                  Act                                              1.5                                                RV                          SA  C    O/C n/a SP .10Y          n/a CondenserReliefValve V13-1              RCIC TurbineTrip &      D-14  2                                  B                                  Act                                                    2                                            GL MO-DC O                            O/C FAI PIT 2Y          n/a    Note 12 Throttle Valve                                                                                                                                                                                                                                                RE Q          Wa V13-131            RCIC Steam Supply Valve E-15    2                                  B                                  Act                                                    3                                            GL MO-DC C                            O/C FAI PIT 2Y          n/a S'IC    Q    n/a S~IO  Q      n/a Revision 19                                                                                                                  Drawing : G-191174 Sh 2                                                                                                                                              Section 5    Page 66 of 179 j
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                      . Inservice Testing Program            ;
Table 5-1 Valve Listing Drawing: G-191174 Sh 2                    DrawingTitle: Reactor Core Isolation Cooling System Nomenclature            Dwg Safety OM Act / Sire Body                                      Act Nonn Safety Fall Test Test CSJ/ROJ                                                          h2 Valve Number Coor Class Cat Pass (inch)                                                                          Pos                Pos Pos Type Freg
_ RR V13-132            RCIC Ptunp Discharge      G-06                          2 B- Act                  2 GL MO-DC C                                                  O/C FAI PIT 2Y            da                                ,
Valve to Baronutric                                                                                                                                        ,c iC    Q      n/a '
* STO      -Q'      n/a V13-133            RCIC T wornetric Cond      K-10                          2 C Act                    2 CK    .SA                                ~C                  O/C n/a SKID Q            n/a      Note 12 Conderde Purnp Disch CheckValve V13-70            RCIC Baro Cond            K-13                          3 C Act 1.25                CK        SA                                C                O  n/a SKID Q            n/a      Note 12 Condensate PumpDisch                                                                                                                                                                                          .
CheckValve 1
i 4
i Revision 19                                                                      Drawing : G-191174 Sh 2                                                                                        Section S      Page 67 of 179  l
__________________________________j
 
Vcrmont Yankee Nuclear Power Station                                                                                Inservice Testing Program'
                                                                                                                                                                      ~
Table 5-1 Valve Listing Drawing: G-191175 Sh 1                    Drawing
 
==Title:==
Primary Containmem & Atmosphere Control Valve Namber                                Dwg Safety OM Act / Size                  Norum Safety Fail Test Test CSJ/ROJ NoacacIntare                                        My    Act                                                  g,g Coor Class Cat Pass (lack)                  Pos  Pos  Pos Type Freg    RR SB-16-19-10        PCAC Supp Chamber        J-13  2      A Act      18  BTF    AO      C      C  FC FST Page Supply ContIsol Q    n/a valve U    2Y    n/a PE 2Y      Wa STC    Q    n/a SB-16-19-11A        PCACVacuum Relief      K-15    2    A/C Act    20  BTF    AO      C    O/C FO FST Q            n/a    Note 15 From Secondary U    2Y    n/a ContammentIso Valve PE    2Y    Wa SP  6M    n/a STC    Q    n/a STO    Q    n/a SB-16-19-11B        PCAC Vacuum Relief      M-15    2    A/C Act    20  BTF    AO      C    OC FO FST Froen Secondary Q    n/a    Note 15 CoatammentIso Valve U    2Y    n/a pg gy        g, SP  6M    n/a STC    Q    n/a STO    Q    n/a SB-16-19-23        PCAC Contamment        H-15    2      A Act      6    BTF    AO      C    C    FC FST Purge Supply Q    n/a ContammentIso Valve U    2Y    n/a pg gy        g, STC    Q    n/a SB-16-194          PCAC to SBGT            D-01    2      A Act      8    BTF    AO      O    C    FC FST Q          n/a    Valve also appears on G-ContammentIsolation Valve U    2Y    n/a    191238 PE 2Y        da STC  Q      n/a SB-16-194A          PCAC Drywellburge &      F-02    2      A Act      3    BTF    AO      C    C    FC FST Q        n/a Vent Outlet Bypass Cont Iso 1 Valve U    2Y    n/a PE 2Y      da                                            ;
j                                                                                                              STC  Q    n/a Revision 19                                                      Drawing : G-191175 Sin 1                                Section 5    Page 68 of 179
                                                                                                                                                          . _ _ _ . -  1
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                                                                  Inservice Testing Program Table 5-1 Valve Listing Crawing: G-191175 Sh 1                  DrawingTide: Primary Containment & Atmosphere Control Dwg Safety OM Ad/ Sk                                                                        Body    Act  Norm Safety Fait Test Test CSJ/ROJ                                                                                                              h6 Valve Number        Nomenclature Coor Class Cat Pass (inch)                                                                                  Pos            Pos Pos Type Freq                                                                                          RR 58-16-1945        PCAC Supp Chb Prg A    L 03              2                              A Act                                3    B'IF    AO    O                  C                      FC FST                                            Q                                n/a VentLine BypassInbd                                                                                                                                                                                    W                        2Y                                n/a ContIsol Viv                                                                                                                                                                                        pg 2y                                                        ga S'IC                          Q                                n/a SB-16-19-7        PCAC Purge & Vent      D-01                2                              A                          Act      18  BTF    AO    C                  C                      FC FST                                            Q                                n/a ExhaustContamment                                                                                                                                                                                      U                        2Y                                n/a IsolationValve                                                                                                                                                                                      PE 2Y                                                        da STC                            Q                              n/a SB-16-19-7A        PCAC DrywellPurge &    Fe02                2                              A Act                                18  BTF    AO    C                  C                      FC FST Q                                                                            n/a Vent Outlet ContIsol                                                                                                                                                                                    U                        2Y                                n/a Valve                                                                                                                                                                                                PIT ' 2Y                                                      n/a S'IU                          Q                              n/a SB-16-19-7B      PCAC Supp Chb Purge & K-03                  2                              A Act                                18  BTF    AO    C                  C                      FC FST. Q                                                                          n/a VentOutletInbd Cont                                                                                                                                                                                    U                        2Y                                n/a IsolValve                                                                                                                                                                                            PIT 2Y                                                        n/a STC                            Q                              n/a SB-16-19-8        PCAC Drywell Air Purge I-12                2                                A Act                                18  B'IF    AO    C                  C                      FC FST Q                                                                            n/a Inlet ContammentIsol                                                                                                                                                                                  U                        2Y                                n/a Valve                                                                                                                                                                                                PIT 2Y                                                        n/a STC                            Q                                n/a SB 16-19-9        PCAC AirPurge Supply    I-16              2                                A Act                                18  BTF    AO    C                  C                      FC FST Q                                                                          n/a From Rx Bldg ContIsol                                                                                                                                                                                  U                        2Y                                n/a Valve                                                                                                                                                                                              PIT 2Y                                                        n/a STC                            Q                              n/a V16-19-12A        PCAC Vacuum Relief      K-16              2                        A/C Act                                    20    CK      SA    C            O/C n/a U                                                                    2Y                                n/a From Secondary                                                                                                                                                                                        SC                          Q                              n/a ContaimnentCheckViv                                                                                                                                                                                  SO                                                          n/a Q
SP                      6M                                n/a Revision 19                                                                                                                Drawing : G-191175 Sh 1                                                                                                                                      Section 5  Page 69 of 179 i
 
      ' Vcrmont Yankee Nuclear Power Station                                                                                                                                    Inservice Testing Program ~                    :
Table 5-1 Valve Listing Drawing: G-191175 Sh I                                        DrawingTitle: Primary Containment & Atmosphere Control -
Dwg SafetyI OM Act / Slee My              Norum Safety Fall Test Test CSJ/ROJ                                                                      '
Valve Number              Nomenclature                                                              Act                                                                                    h6 Coor Class Cat Pass (inch)                  Pos    Pos  Pos Type Freg                                        RR
  .      V16-19-12B              PCAC Vacuum Relief                    M-16 2 A/C Act            20  m      SA      C-  O/C - n/a LJ 2Y                                            n/a From Secondary                                                                                                                                        n/a SC-              Q ContammentCheck Viv                                                                                                                                  da SO'              Q
* SP          6M                                . n/a                                  ,
V16-19-13A              DrywellAirLock                          H-06  2      A Pass    1.5    BL    MAN    LC    C  n/a LJ              2Y                                n/a Equalizing Vent                                                                                                                                                                              !
V16-19-13B              Drywell Airlock Vent                    H-06  2      A Pass    1.5    BL    MAN    LC    C  n/a - LJ            2Y                                n/a                                  I V16-19-19B              PCAC Globe Valve                      M-16    2      B Pass    .75    GL    MAN    LC    C  n/a n/a            n/a                              n/a                                    i i                                                                                                                                                                                                                              i i        V16-19-20A              PCAC Globe Valve                        K-16  2      B Pass    .75    GL    MAN    LC    C  n/a n/a            n/a                              n/a                                  -)
V16-19-21A              PCACTest Connection                    K-01  2      B Pass    .75    GL    MAN    LC    C  n/a ' n/a          n/a                              n/a                                    .
V16-19-22B              PCACTestconnechon                      I-13  2      B Pass .75      GL    MAN    LC    C  n/a . n/a          n/a                              n/a V16-19-56                Drywell Air Lock                        I-06  2      B Pass    .75    GL    MAN    LC    C  n/a n/a            n/a                                n/a Preammzabon Valve                                                                                                                                                                            !
V16-19-5A                DrywellTo Suppresnon                    J 08  2    A/C Act      18  m      SA      C    OC n/a LT                2Y                                n/a                                    ;
Chamber Downcorner                                                                                    SC                                              n/a Vacuum Breaker Q                                                                    i SO'              Q                              da                                    !
:                                                                                                                                        SP          6M                                  n/a V16-19-5B                DrywellTo Suppresnon                    J-08  2    A/C Act      18  m-    SA      C    O/C n/a - LT            2Y                                n/a                                    ,
Chamber Downcomer                                                                                    SC              Q                              n/a                                    +
Vacuum Brunkcr SO              Q                              Wa SP          6M                                  n/a
        - V16-19-5c              DrywellTo Suppression                  J-08  2    A/C Act      18  m      SA    C    O/C n/a LT              2Y                                n/a Chamber Downcomer                                                                                    SC                                              n/a Q.
Vacuum Breaker                                                                                                                                                                                t SO              Q                              Wa SP.        6M                                  n/a                                    f l                                                                                                                                                                                                                                i Revi:sion 19                                                                          Drawing : G-191175 Sh 1                                                                    Section 5  Page 70 of 179
 
                                                                                                                                                                                                                =
Vcrmont Yankee Nuclear Power Station                                                                                                                              Inservice Testing Prograin i
Table 5-1 Valve Listing '
    ~ Drawing: G-191175 Sh I                  Drawing
 
==Title:==
Pnmary Containment & Atmosphere Control                                                                                                                        ,
Neuneoclatute        Dwg Safety OM Act / Sise      g                    3,g  Nerna Safety fab Test Test CSJ/ROJ                                                hd Valve Nussber Coor Class Cat Pass (inch)                                  Pos                  Pos                  Pos Type Freg      RR                                                ,
                                                                                                                                                                                                                              ^
  ,  V16-19-5D          DryweRTo Suppresson    K-08  2    A/C ' Act - -18    CK                  SA    C                  OC n/a LT                          2Y-      n/a ChamberDowncomer                                                                                                                  SC      Q.      n/a VacmanBreaker                                                                                                                                                                                      i SO    -Q        Wa
:                                                                                                                                                          SP    6M        n/a                                              !
.    ' V16-19-5E          DryweRTo Suppreamon    J-08  2    A/C Act      18    CK ' SA                    C                OC n/a LT                          2Y      n/a                                              !
ChamberDownmmer                                                                                                                  SC    Q        n/a          ,                                    [
                        . VacumnBreaker                                                                                                                    go    q        g,                                                j SP- 6M        - n/a                                              !
V16-19-5F          DryweRTo suppreamon    J-08  2    A/C Act      18 -  CK                  SA -  C                O/C n/a LT                          2Y      n/a .                                            !
ChamberDownmmer                                                                                                                  SC    Q        Wa-                                              !
Vacuum Breaker SO    Q        Wa SP    6M        n/a                                              j
.      V16-19-5G          DrywellTo Suppresnon  J-08  2    A/C Act      18    CK                  SA    C                O/C n/a LT                          2Y      n/a                                            ;i Chamber Downmmer                                                                                                                  SC              n/a Q
Vacuum Breaker SO-    Q        da                                                !
SP    6M        n/a                                              ;
V16-19-5H          DrywellTo Suppresson  J-08  2    A/C Act      18    CK                  SA    C                O/C n/a . LT                      2Y        n/a ChamberDowncomer                                                                                                                  SC    Q        n/a VacuumBreaker SO    Q        Wa                                                !
SP - 6M        n/a                                              l
.,    V16-19-51          DrywenTo Suppresson  K-08    2    A/C Act      18  CK                    SA    C                OC n/a LT                          2Y        n/a                                            -[
Chamber Downmmer                                                                                                                  SC              n/a i
VacuumBreaker Q                                                          [
da i
SO    Q.                                                        [
SP    6M        n/a V16-19-5J          DryweRTo Suppresson    J-08  2    A/C Act      18  CK                    SA    C                OC n/a . LT                          2Y      n/a ChamberDowncomer                                                                                                                  SC    Q.      n/a                                                !
Vacuum Breaker                                                                                                                  go      q.      g,-                                                l SP    6M    - n/a i
Drawing : G-191175 Sh 1                                                                                  Section 5 - Page 71 of 179 Revision 19 I
_ _ - _ _ _ _ - .            _ _ - _ _ _ - - _ _ _ _ _ _ _ _ _ _ -                        _ - _ - _ - _ _ _ - - _ _ - _ - - _ _ _ . - - -t
 
Vcrmont Yankee Nuclear Power Station                                                                                                            Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191175 Sh 1                      Drawing
 
==Title:==
Primary Containment & Atmosphere Control Valve Number        Noamenclature Dwg Safety OM Act / Size Body                        Act    Nonn Safety Fail Test Test CSJ/ROJ                          hah Coor Class Cat Pass (inch)                                    Pos      Pos Pos Type Freg            RR
  ,              V16-20-20          PCAC Contammatt            H-12        2 A Act                  1      GA      SO      O        C      FC FST      Q        n/a Page Makeup Outbd                                                                                                U    2Y        n/a ContIsol Valve                                                                                                  PR    2Y        da STC    Q        n/a V16-20-22A        PCAC Contamment            H-11          2 A Act                  1      GL      SO      C        C      FC FST      Q        n/a Purge Makeup ContIsol                                                                                            U    2Y        n/a
* Valve                                                                                                            PIT 2Y          n/a STC    Q        n/a V16-20-22B        PCAC Contamment            H-12        2 A  Act                1      GL      SO      O        C      FC FST      Q        n/a PurgeMakeup ContIsol                                                                                            U    2Y        n/a                                                                      ;
Valve PE 2Y          Wa S'IU    Q        n/a V16-20-28          Torus MakeupTest            I-11        2 B Pass 35                      GA  MAN        C        C      n/a n/a    n/a      n/a Connection V16-20-30          Drywell MakeupTest          I-12        2 B Pass 35                      GL  MAN        LC        C      n/a n/a    n/a      n/a                                                                      ;
Connection                                                                                                                                                                                                l j                  V20-400A          Torus Drain Valve          N-09          2 B Pass              2        GL' MAN        LC        C      n/a n/a    n/a      n/a V20 40eB          Toms DrainValve            N-07          2 B Pass              2        GL  MAN        LC        C      n/a n/a    n/a      n/a Revision 19                                                        1)rawing : G-191175 Sh 1                                                          Section S Page 72 of 179                                                ;
i
 
                - Vcrm:ntYcrkeeN clearPow rStation                                                                                                                                                                                                                                                    Inservice Testing Program Table 5-1 Valve Listing
;                ' Drawing: G-191175 Sh 2                                                                                                    Drawing'Iltle: Pnmary Containment & Atmosphere Control Valve Number                                Nomienclatum Dwg          W    OM Act / h                                  Body                'Act              Norum Safety                  fab Test Test CSJ/ROJ Pos Type Freg          RR g,,g                          ,
Coor          Class Cat Pass (inch)                                                                        Pos                  Pos                                                                              ;
  .              SOV-7-107 '    188 NeutonMonstonng                                                                                        C-10          '3-  A Act          1"                          -GL                  SO'                      O.                C  FC FST        Q        n/a        . New Valve confonns with              !
SysteinTip Purge                                                                                                                                                                                                                      IJ . 2Y-      n/a .        RG 1.97,                              s
,                                                      IsolationValve                                                                                                                                                                                                                      pg.g.. 2Y        Wa STC      Q      ' n/a                                                !
SR-16-19-77    18B Nitrogen Supply Safety                                                                                  A-11          3    C Act IXI.5 RV ' SA -                                                                      C.                O- N/A SP        10Y    .N/A RdiefValve V7-1            ISB Neutron Monitoring                                                                                      D-08          2  A/C Act        .5                              CK                SA                  OC                      C  n/a IJ        2Y        n/a ~
SystemTe PurgeIm.                                                                                                                                                                                                                    SC    R O R O J- V I1 CheckValve t
I i
i t
4 i
Revision 19                                                                                                                                                Drawing : G-191175 Sh 2                                                                                                          Section 5          Page 73 of 179                  !
i
[
 
_ _ ~ . .                                                .._ _ . _                                                                      -._. . . . . _ _          ._    -m .
5 Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                                                                                      Inservice Testing Progrant Table 5-1 Valve Listing                                                                                                                                                                                                              y Krawing: G-191177 Sh 1                        Drawing 11tle: RadwasteSystems
* Dwg Safety OM Act / She My                                                                Act Norm Safety fab Test Test CSJ/ROJ                                                                                                                          %
Valve Number    _  Nomenclature Coor Class Cat Pass (inch)                                                                        Pos    Pos Pos Type Freg                                                                                                          RR
. RV-2682A          Pen.X-18"IhennalRelief A-03                  2      C Act 35                            RV                                        SA  C    OC n/a SP                                                                                        10Y '                    n/a Valve RV-20-94A          Pen.X-19'IhennalRelief F-03                  2      C Act                        35    RV-                                      SA  C    OC n/a .SP                                                                                      10Y                      . n/a                                        i Valve V2S319A            Rx Bldg MoorDrain -                    D-06  2      B Pass                        1.5  GA
* MAN                                      LC      C        n/a n/a                                                                                  n/a                    n/a PumpTo Suppression                                                                                                                                                                                                                                                                                                    ;
PoolIso Valve
  - V2S319B          Rx Bldg MoorDrain                      D-06  2      B Pass                        1.5  GA                                      MAN  LC      C        n/a n/a                                                                                  n/a                    n/a                                        '
PanpTo Suppresnon PoolIso Valve Rx Bldg Floor Drain                                                                      GA                                      MAN  LC      C        n/a n/a                                                                                  n/a                    n/a                                        '!
V20,319C                                                  C-08  2      B Pass                        1.5 PumpTo Suppression PoolIso Valve V20J19D            Rx Bldg FloorDrain                      C 08  2      B Pass                        1.5  GA                                      MAN  LC      C        n/a n/a                                                                                  n/a                    n/a Pump To Suppression PoolIso Valve V20-75A          Test Connection                        B44  2      B Pass 35                          GA                                      MAN  C      C        n/a n/a                                                                                  n/a                    n/a V20-79A          Test Connection                        B-04  2      B Pass                        .75  GA                                      MAN  C      C        n/a n/a                                                                                  n/a                    n/a                                        i V2S82            DrywellFloorDrain                      B-04  2      . A Act                        3    BL                                        AO  O      C        FC FST                                                                                      Q                  n/a Sump Contaime.ent                                                                                                                                                                                    LJ                                            2Y                      n/a IsolationValve                                                                                                                                                                                  PE 2Y                                                                    Wa                                          .
S'It Q                                                                      n/a V20-83            Drywen FloorDmin                        B-05  2      A Act                          3    BL                                        AO  O      C        FC FST Q                                                                                                        n/a Sump Contamment                                                                                                                                                                                      LJ                                            2Y                      n/a -
Isolation Valve                                                                                                                                                                                  pg .2y                                                                    g, STC                                                    Q                    n/a V20-92A          Test Connection                        G-04  2      B Pass                        .75  GA                                      MAN  C      C        n/a n/a                                                                                  n/a                    n/a                                        .
V20-93A          Test Connection                        G-04  2      B Pass 35                          GA                                      MAN  C      C        n/a n/a                                                                                  n/a -                  n/a Revision 19                                                                              Drawing : G-191177 Sh 1                                                                                                                                                                                Section 5            Page 74 of 179        i
 
m Vcrmr.t Yc2kee Nrclear Pdwer Statio1                                                                                                                                                                                            Inservice Testing Program -
Table 5-1 Valve Listing Drawing:- G-191177 Sh 1 -                                                                          DrawingTitle: Radwaste Systems .
Dwg Safdy OM Act / Size My              Nerna Safety fab Test Test CSJ/ROJ                                                    hd Valve Number          Nonnenclature                                                                                                            Act Coor Class Cat l Pass (inch)              Pos  Pos Pos Type Frest                                                .RR V2694                DrywellE;We Drain G-04                                                                          2_  A Act        3  BL'  AO. O. C-                FC FST                                    Q      n/a Sump Contma""'                                                                                                                                                                                W      2Y    n/a I883"'i** M'                                                                                                                                                                              PIT 2Y            n/a STC          Q      n/a                                ,
v20-95              Drywell E r ;--- =^ Drain G-05                                                                  2    A Act        3-  BL    AO      O    C                FC FST Q                                        n/a Sump contammet                                                                                                                                                                              U        2Y    n/a -                            4 I8838'i'" M'                                                                                                                                                                              PIT 2Y            n/a                                ,
STC          Q      n/a s
P L
k t
t i
s Revision 19                                                                                                                      Drawing : G-191177 Sh 1                                                                            Section 5 Page 75 of 179 i
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                        Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191178 Sh 1                              Drawing 11tle: Reactor Water Cleanup System Nomenclature Dwg Safety OM Act / Size Body                            Act .
Norma Safety                                    fab                                Test Test CSJ/ROJ          hah Valve Number Coor Class Cat Pass (inch)                                            Pos        Pos                                  Pos Type Freq                                    RR
  .            V12-15        IBB ReactorWaterCleanup                D-02  1-          A Act    4        GA    MO-AC O                                C                                FAI IJB Var                                      n/a ContammentIsolation                                                                                                                                                                          PIT 2Y      n/a .
Valve                                                                                                                                                                                                  da
                                                                                                                                                                                                                          - 3.TC      Q.
V12-16                RWCU Dram / rest                D-03  1            B Pass    75      GL . MAN                      C            C                                    n/a n/a                                n/a    n/a Cw      tini V12-18        isB ReactorWater Cleanup              D-03    1            A Act    4        GA MO-DC O                                  C _ FAI UB . Var ~                                                                  n/a ContammentIsolation                                                                                                                                                                        PIT 2Y      n/a Valve                                                                                                                                                                                    STC            Wa Q
V12-28A              RWCU Pump Discharge            D-08  3            C Act    3        m                  SA        OC            C                                    n/a CD                                  RO    n/a                                :
CheckValve V12-28B              RWCU Pump Discharge            G-08  3            C Act    3        m                  SA        O/C          C                                    n/a CD                                  RO    n/a                                ,
CheckValve V1242                RWCU Flowto                    B-05  2            C Act    4        m                  SA        O/C          C                                    n/a CD                                  RO    n/a '
Feedwater System Isolation Check Valve V1242A                RWCU Flow to                    B45    3-          C  Act    4        &                  SA        O/C          C                                    ri/a CD                                  RO    n/a                                '
FeedwaterSystem Isolation Check Valve k
Revision 19                                                                    Drawing: G-191178 Sh 1                                                                                                                          Section 5 Page 76 of 179 m______..--_-_______a__m        ____w. __-_.__-m.m_---___m.a._____1m_______.-_______.____o-______..-_____-____mm.
e.w-_-_u
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                  Inservice Testi:g Program Table 5-1 Valve Listing Drawing: G-191237 Sh 2                          Drawing'I1tle: HVAC 'nubine, Service & Cortrol Room Building Dwg Safety OM Act / Size My                                                        Act Norm Safety fab Test Test CSJ/ROJ                    hah Valve Number                Nomenclature Coor Class Cat Pass (inch)                                                                Pos  Pos Pos Type Freg            RR
  . SACC-1A-                  Cent Room HVAC        I-03  3      C Act 1375 N                                                          SA  O/C  O    Wa SKID : Q          Wa CHECK                      Chiller Refriguant                                                                                                                                                                    !
Piping Check Valve SACC-1B.                  Cont RoomHVAC          I-04  3      C Act 1375 CK                                                          SA  O/C  O    da SKID Q            Wa                                  I
      ' CHECK                    ChilkrRefrigerant                                                                                        -
Piping Check Valve SCW-46A                    SAC-1 Temperature      B-6    3      B  Act    2 3-WAY AO                                                        O    O    FO FST    Q          Wa ControlValve Heating                                                                                                          m      q          g, and Vmt Room SCW-65A                    HVAC ExpansionTank    D-04    3      B  Act  .75                          GL                            MAN  C    C    Wa SC    Q          Wa IsolationValve                                                                                                                                                                        .
SCW-8A                    ControlRoomHVAC        E-05  3      C  Act    3                          CK                              SA  'O    O    Wa SO    Q          Wa Chilled WaterPump Disch CheckValve SR-SACC-1A-1              Cont Room HVAC        H-03  3      C Act    .75                          RV                              SA  C  O/C Wa SP      10Y          Wa Chiller Refrigerant Pipmg ReliefValve SR-SACC-1A-2              Cont Room HVAC        H-03  3      C Act    .75                          RV                              SA  C  O/C da SP      10Y          Wa Chiller Refrigerant Pipmg ReliefValve SR-SACC-1B            Cont Room HVAC        H-04  3      C Act 1.25                            RV                              SA  C  O/C da SP      10Y          Wa Chiller Refrigerant                                                                                                                                                                    '
Pipmg ReliefValve Revision 19                                                          Drawing : G-191237 Sh 2                                                                                    Section S    Page 77 of 179 i
_ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _                        __      ___ _.__            - . - ~ .  .    . - . -
 
Vcrmont Yankee Nuclear Power Station                                                                          Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191238                      DrawingTitle: HVAC - Reactor Building Dwg Safety OM Act / Size                Norm Safety Fail Test Test CSJ/ROJ Valve Number        Nomenclature                                    My      Act                                            hah Coor Class Cat Pass (inch)                Pos  Pos Pos Type Freq      RR SB-1-125-1A      Standby GasTreatment  G-08  2      B Act    12  BTF    AO    C    O    FO FST Q          n/a TrainInlet Valve                                                                    PIT 2Y    n/a STD    Q    n/a SB-1-125-1B        Standby GasTreatment  G-07  2      B  Act  12    BTF    AO    C    O    FO FST      Q    n/a TrainInlet Valve                                                                  - PIT 2Y    Wa STO    Q    n/a SB-1-125-2A        Standby Gas T'entment  HM    2      B  Act  12    BTF    AO    O  O/C FO FST Q            n/a TrainInlet Valve                                                                  PIT 2Y      n/a STC  Q      n/a STD  Q      Wa SB-1-125-2B        Standby GasTreatment  HM    2      B  Act  12    BTF    AO    C  O/C FO FST Q            n/a TrainInlet Valve                                                                  PIT 2Y      n/a STC  Q      n/a STO  Q      n/a SB-1-1254A        Standby GasTreatmmt    G4    2      B  Act  12    BTF    AO    O    O    FO FST    Q      n/a Train Discharge Valve PIT 2Y      n/a STO  Q      n/a SB-1-1254B        Standby Gas Treatment  G4    2      B  Act  12    BTF    AO    C    O    FO FST    Q      n/a Train Discharge Valve PIT 2Y      n/a STO  Q      n/a SB-1-125-4A        Standby Gas Treatment  H-07  2      B  Act  12    BTF    AO    C  O/C FC FST Q            n/a Train Dilution Valve                                                              PIT 2Y      n/a STC  Q      n/a
                                    .                                                                  STO  Q      n/a SB-1-125-4 B      Standby Gas Treatment  }{ 4  2      B  Act  12    BTF    AO    C  O/C FC FST Q            n/a Train Dilution Valve                                                              PIT 2Y      n/a STC  Q      n/a STO  Q    n/a Revision 19                                                Drawing : G-191238                                      Section 5 Page 78 of 179
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                                            Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191238                                  Drawing 11tle: HVAC-Reactor Building Dwg Safety OM Act / Size Body                                          Act              Norm Safety fab Test Test CSJ/ROJ                                                                    hah Valve Number        Nomenclature Coor Class Cat Pass (inch)                                                                        Pos                                    Pos Pos Type Freg                    RR SB-t-125-5        Standby Gas Treatmmt                            G-06                                              2 B  Act  4    BTF    AO                          C                                O/C FC FST                        Q    n/a Train Xconn Valve                                                                                                                                                                                                    PIT 2Y    n/a STC  Q    n/a STO  Q    n/a                                  1 SB-10              RX Building Supply                              H 08                                              2 B  Act  54    BTF    AO                          O                                        C                FC FST  Q    n/a Isolation Valve                                                                                                                                                                                                      PIT 2Y    n/a STC  Q    n/a SB-11              RxBldg Exhaustto Stack G-08                                                                        2 B  Act  54    BTF    AO                          O                                        C                  FC FST Q      n/a See Cond IsolationValve                                                                                                                                                                                              PIT 2Y    n/a STC  Q    n/a 5 8-12            Rx Bldg Exhaustto Stack G-09                                                                      2 B  Act  54    BTF    AO                          O                                        C                  FC FST Q      n/a Sec cond IsolationValve                                                                                                                                                                                              PIT 2Y    n/a                                  ,
STC  Q    n/a 58-16-194
* PCAC to SBGT                                      F-06
* See G-191175 forvalve ContammentIsolation                                                                                                                                                                                                                    info and test requirements Valve SB 9              RX Building Supply                              H-09                                              2 B  Act  5A    BTF    AO                          O                                        C                  FC FST Q      n/a Isolation Valve                                                                                                                                                                                                      PIT 2Y    n/a                                  ,
STE  Q    n/a SGT-7A            Standby Gas Treatmmt                              F-07                                            2 C  Act  12  CK    SA                          C                                O/C n/a SC                        Q    n/a Train Discharge Check                                                                                                                                                                                                SO  Q    n/a Valve SGT-7B            Standby GasTreatment                              F-06                                            2 C Act  12    CK    SA                          C                                O/C n/a SC                        Q    n/a Train Discharge Check                                                                                                                                                                                                SO  Q  n/a Valve Revision 19                                                                                                                Drawing : G-191238                                                                                                      Section 5    Page 79 of 179          ,
 
Vcrmont Yankee Nuclear Power Statio a                                                                                                                                                Inservice Testing Program Table 5-1 Valve Listing
              ' Drawing : G-191267 Sh 1                    Drawing
 
==Title:==
Nuclear Boiler Vessel Instrumeni2ation Dwg Safety OM Act / Size Body                    Act Norm Safety FaR! Test Test CSJ/ROJ                                                                hah Valve Number .        Nomenclature Coor Class Cat Pass (inch)                              Pos                  Pos Posl Type Freq                                          RR SL2-3-11            Nuclear Boiler Vesel      C-06    2    AC Act          1    EFC            SA    O                  O/C n/a LEF RO ROJ-VO1 Ind Excess FlowCheck Valve Sb2-3-13A          Nuclear BoilerVessel      D-06    2    AA: Act        1    EFC SA    O                  O/C n/a LEF RO ROJ-V01 Ind Excess FlowCheck Valve SL2-3-13B          Nuclear Boiler Vessel    C-12    2    A/C Act        1    EFC            SA    O                  O/C n/a LEF RO ROJ-V01 Ind Excess FlowCheck Valve sb2-3-15A          Nuclear BoilerVessel      D-06    2    A/C Act        1    EFC            SA    O                  O/C n/a LEF RO ROJ-Vol Inst Excess Flow Check Valve s b2-3-15B        Nuclear Boiler Vessel    D-12    2    AC Act          1    EFC            SA    O                  OC n/a LEF RO ROJ-V01 Inst Excess FlowCheck Valve sb2-3-17A          Nuclear Boiler Vessel    E-06    2    A/C Act        1    EFC            SA    O                  OC n/a LEF RO ROJ-VO1 InstExcess Flow Check Valve s b 2-3-17B        Nuclear Boiler Vessel    E-12    2    AC Act          1    EFC            SL    O                  O/C n/a LEF RO ROJ-VO1 Inst Excess FlowCheck Valve SL2-3-19A          Nuclear BoilerVessel      F-06    2    A/C Act        1    EFC            SA    O                  OC n/a LEF RO ROJ-VO1 Inst Excess FlowC;eck Valve                                                                                                                                                                                              ,
sb2-3-19B          Nuclear BoilerVessel      F-12  2    AC Act          1    EFC            SA    O                  OC n/a LEF RO ROJ-VO1 Inst Excess FlowCheck Valve          .
SL2-3-21 A        Nuclear Boiler Vessel    H-06    1    A/C Act        1    EFC            SA  O                  O/C n/a LEF RO ROJ-VO1 Inst Excess FlowCheck Valve s b 2-3-21B
* Nuclear Boiler Vessel    H-06
* See G-191165 for valve Inst Excess Flow Check                                                                                                                                                  info and test requirements Valve Revision 19                                                        Drawing : G-191267 Sh 1                                                                                            Section 5    Page 80 of 179
 
                                                                                                                                                                                                                                                                                        'h
        - Vcrmont Yankee Nuclear Power Station                                                                                                                                                                                        Inservice Testing Pargram-Table 5-1 Valve Listing
                                                                                                                                                                                                                                                                                            ?
Drawing: G-191267 Sh 1                                        Drawing'I1tle: . NuclearBoilerVesselInstannensation yg y,g                                    y          g,,      Dwg Safety OM Act / Sise                                      wy                            .- Act Nenn Safety fab Test Test CSJ/ROJ                                    h6 Coer Class Cat Pass (inch)                                                                                      Pos        Pos Pos Type Freg            RR' E2-3-21C                            NuclearBoila Vessel        H-12    1        A/C Act                                  1  EPC                          -SA                O.        OE n/a LEF RO ROJ-Vol Inst Excess FlowCheck                                                                                                                                                                                                                  ,
                                                  - Valve
                                                                                                                    *                        *-      *                                *          *          *    *
* See G-191165 forvalve sb2,3-21D =                        - Nuclear Boiler Vessel      H-12 -*- ~*                                                                                *..
IndExcess FlowCheck                                                                                                                                                                                    ido W M sequim                  I Valve                                                                                                                                                                                                                                  ,
sb2-3-23A                            NuclearBoiler Vessel        G-06    1        AE Act                                  1-  EFC                              SA            O          OC n/a LEF RO ROJ-V01 IndExcess FlowCheck Valve                                                                                                                                                                                                                                  i 51,2-3-23 8                          Nuclear Boiler Vessel      G-06    1        AC Act                                  1  -EFC                              SA            O          OE n/a LEF RO ROJ-V01 IndExcess FlowCheck                                                                                                                                                                                                                    3 Valve SI,2-3-23C                          NuclearBoila Vessel        G-12    1        AC Act                                  1  EFC                                SA            O          OE n/a LEF -RO ROJ-Vol -
IndExcess FlowCheck                                                                                                                                                                                                                    ;
Valve sb2-3-23D                          . NuclearBoilaVessel          G-12    1        AC Act                                  1  EFC '                            SA            O          OE n/a LEF RO ROJ-V01 Ind Excess FlowCheck Vdu SI,2-3-25                            NuclearBoilerVessel        14      2        AE Act                                  .1  EPC                                SA            O          OE n/a LEF RO ROJ-V01                                                          ,
Ind Excess FlowCheck                                                                                                                                                                                                                .;
Vd e 51,2-3-27                            Nuclear Boiler Vessel      14      2        AC Act                                  .I  EFC                              SA            O          OC n/a ' LEF RO ROJ-Vol IndExcess Flow Check                                                                                                                                                                                                                  .
Valve 51,2-3-31A                          NuclearBoiler Vessel        F4      1        AE Act                                  1  EFC                              SA            O          O/C - n/a LEF RO ROJ-Vol IndExcess Flow Check Valve                .                                                                                                                                                                                                              _,
51,2-3-31B                          Nuclear Boiler Vessel      FM      1        AC Act                                  1  EFC                              SA            O          OE n/a LEF RO ROJ-Vol Ind Excess FlowCheck Valve                                                                                                                                                                                                                                  ,
51,2-3-31C                          Nuclear Boila Vessel        FM      1        NC Act                                  1  EFC                              SA            O          OE n/a LEF RO ROJ-VD1 Inst Excess FlowCheck Valve                                                                                                                                                                                                                                  .
Revision 19                                                                                        Drawing : G-191267 Sh 1                                                                                                            Section 5      Page 81 of 179          ,
 
I Vcrm=t Ycckee NzcIrr Paw;r Statin                                                                                                                                                                I: service Testing Program Table 5-1 Valve Listing Drawing: G-191267 Sh 1                    DrawingTitle: Nuclear Boiler Vessel Instrumentation Dwg Safety OM Act / Sire My                    Act              Norm Safety Fail Test Test CSJ/ROJ                                                                        hah Valve Number        Nomenclature Coor Class Cat Pass (inch)                                          Pos  Pos Pos Type Freq                                                              RR
        -              Si,2-3-31D        Nuclear Boiler Vessel    F4      1    NC Act          1    EFC          SA                  O  O/C n/a EF RO ROJ-VO1 Ind ExcessFlowCheck Valve SI,2-3-31E        Nuclear BoilerVessel    FM      1    NC Act          1    EFC SA                  O  O/C n/a EF RO ROJ-Vol Inst ExcessFlowCheck Valve SI,2-3-31F        NuclearBoiler Vessel    F4      1    A/C Act        1    EFC          SA                  O  O/C n/a LEF RO ROJ-VO1 Ind Excess FlowCheck Valve ST,2-341G          NuclearBoiler Vessel    FM      1    NC Act          1    EFC          SA                  O  O/C n/a LEF RO ROJ-V01 -
Inst Excess Flow Check Valve SI,2-3-31H        Nuclear Boiler Vessel    F4      1    A/C Act        1    EFC          SA                  O  O/C n/a LEF RO ROJ-V01 Inst Excess FlowCheck Valve SI 2-341I          Nuclear Boiler Vessel    F-12    1    A/C Act        1    EFC          SA                  O  O/C n/a LEF RO ROJ-V01 Inst Excess FlowCheck                                                                                                                                                                                                    '
Valve SI,2-3-31J        NuclearBoiler Vessel    F-12    1    NC Act          1    EFC          SA                  O  O/C n/a LEF RO ROJ-VO1 Ind Excess Flow Check Valve                                                                                                                                                                                                                    L SI,2-3-31K        NuclearBoilcr Vessel    F-12    1    A/C Act        1    EFC          SA                  O  O/C n/a LEF RO ROJ-VO1 Inst Excess FlowCheck Valve SI 2-3-31L        NuclearBoiler Vessel    F-12    1    NC Act          1    EFC          SA                  O  O/C n/a LEF RO ROJ-V01 Inst Execa Flow Check Valve          .
S1,2-3-31M        Nuclear Boiler Vessel    F-12    1    A/C Act        1    EFC          SA                  O  O/C n/a LEF RO ROJ-V01 InstExcess FlowCheck Valve 51,2-3-31N        Nuclear Boiler Vessel    F-12    1    NC Act          i    EFC          SA                  O  O/C n/a LEF RO ROJ-VO1 Inst Excess Flow Check Valve Revision 19                                                    Drawing : G-191267 Sh 1                                                                                                                      Section 5  Page 82 of 179
 
                                                                                                    >e Vcrmont Yankee Nuclear Power Station -                                                                                                                                                                            Inservice Testi:g Program Table 5-1 Valve Listing Drawing : G-191267 Sh 1                              Drawing
 
==Title:==
Nuclear Boiler Vessel Instmmentation Dwg Safety OM Act / Size My                                                Act      Nona Safety Fall Test Test CSJ/ROJ                                                                          hW Valve Numaber        - Nomenclatum                                                                                                                                                                                                                                <
Coor Class Cat Pass (inch)                                                            Pos      Pos Pos Type Freg                                          RR sir 2-3-31P .      Nuclear BoilerVessel              F-12                1    A/C Act                      1  EFC                  SA    O      O/C n/a LEF RO ROJ-VO1 InstExcess FlowCheck Valve Ste2-3-31Q          NuclearBoiler Vessel              F-12                1    A/C Act                      1  EFC SA    O.      O/C n/a LEF RO ROJ-V01 InstExcessFlowCheck Valve SI ,2-3-33          Nuclear Boiler Vessel              I-12                2    A/C Act                      i  EFC                  SA'    O      O/C n/a LEF RO ROJ-V01 Inst Excess FlowCheck Valve SI 2-3-35          Nuclear Boiler Vessel              J46                2    A/C Act                      1  EFC                  SA    O              C      n/a LEF RO ROI-VO1                                                                              I InstExcess Flow Check Valve V2 3-28A            NBVI Globe Valve                  F-06                2      B Pass 1.00                    GL        MAN              C              C      n'a        n/a            n/a              n/a v2 3-2sB            NBVIGlobe Valve                    F-11                2      B Pass 1.00                    GL        MAN              C              C      n/a n/a                    n/a              n/a r
r i
I F
i Revision 19                                                                                  Drawing : G-191267 Sh 1                                                                                                  Section 5                        Page 83 of 179 t
_ _ _ _ _ _ .          __.m_.m      . _ _ _ . . _        .m  __ _ _ _ _ . _      m_  _ _._.._.m..m._. _ . _ . -      .___._.._.____._._-.._._m_            _ _ . . _ _ . _ _ . _ _ _ .
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                  Inservice Testing Program -
Table 5-1 Valve Listing Drawing: G-191267 Sh2 '                      Drawing
 
==Title:==
Nuclear Boiler Vessel Instnamentation Valve Number                Nomenclature    Dwg Safety OM Act / Size Body                                            Act                        Nonn Safety Fall Test Test CSJ/ROJ                hah Coor Class Cat Pass (inch)                                                                            Pos  Pos Pos Type Freq              RR V2-3-430A        Reference Leg Backfill      C-09            2 NC Act .375            CK                                SA                        C    C    n/a U      2Y            n/a Inlet Check Valve                                                                                                                                  SC  RO ROJ-V15 V2 3-430B        Reference Leg Back Fill      E-09            2 NC Act .375            CK                              SA                        C    C-  n/a U      2Y            n/a Inlet Check Valve                                                                              .                                                    SC  RO ROJ-VIS -
V2,3-432A        Reference Leg Back Fill      C-10            2 NC Act .375            CK                              SA                        C    C    n/a U      2Y            n/a CheckValve                                                                                                                                          SC  RO ROJ-V15 V2,3-432B        Reference Leg Back Fill      E-10            2 NC Act .375            CK                              SA                        C    C    n/a U      2Y            n/a CheckValve                                                                                                                                          SC  RO ROJ-V15 V2 3-433A        Reference Leg Back Fill      F-09            2 NC Act .375            CK                          -SA                            C    C    n/a U      2Y.            n/a Inletcheck Valve                                                                                                                                    SC  RO ROJ-V15 V2,3-433B        ReferenceLeg Back Fill      H-09            2 NC Act .375            CK                              SA                        C    C    n/a U      2Y            n/a Inlet Check Valve                                                                                                                                  SC  RO ROJ-V15 V2-3-435A        Referenceleg Back Fill      F-10            2 NC Act .375            CK                              SA                        C    C    n/a U      2Y            n/a InletCheck Valve                                                                                                                                    SC  RO ROJ-V15 V2 3-435B        Reference Leg Back Fill      H-10            2 NC Act .375            CK                              SA                        C    C    n/a U      2Y            n/a InletCheck Valve                                                                                                                                    SC  RO ROJ-VIS -
V2 3-444A        Penetraten X-28A Test        C-10            2  B Pass .375            GL                        MAN                              C    C    n/a n/a    n/a            n/a Connection V2-3-444B        Penetration X-28D Test      E-10            2  B Pass .375            GL                        MAN                              C    C    n/a n/a    n/a            n/a Connection V2,3-447A        PenetrationX-29A Test        F-10            2  B Pass .375            GL                        MAN                              C    C    n/a n/a    n/a            n/a Connection V2-3-447B        Penetration X-29D Test      H-10              2  B Pass .375            GL                      MAN                              C    C    n/a n/a    n/a          n/a Connectic,n V2 3-448A        Penetration X-28A Test      C-10            2  B Pass .375            GL                      MAN                              C    C    n/a n/a    n/a          n/a Connection V2 3-448B        Penetration X-28D Test      E-10            2  B Pass .375            GL                      MAN                              C    C    n/a n/a    n/a          n/a Connection Revision 19                                                              Drawing : G-191267 Sh 2                                                                                          Section 5 Page 84 of 179
 
y Vcrmont Yankee Nuclear Power Station                                                                                                          Inservice Testing Program Table 5-1 Valve Listing Drawing : . G-191267 Sh 2                  Drawing
 
==Title:==
Nuclear Boiler Vessel Instrumentation Dwg Safety OM Act / Size My                                        Norma Safety fab Test Test CSJ/ROJ                        hah Valve Number          Nomenclature                                                          Act Coor Class Cat Pass (inch)                                            Pos  Pos  Pos Type Freq        RR
-      V2 M 51A            P setration X-29A Test  F-10              2 B Pass .375        GL    MAN                  C    C    n/a n/a  n/a            n/a Connection V2 M 51B            Men X-29D Test          H-10              2 B Pass .375        GL    MAN                  C    C    n/a n/a  n/a            n/a Connection A
Revision 19                                                            Drawing : G-191267 Sh 2                                                                  Section 5  Page 85 of 179
 
Vcrmont Yankee Nuclear Power Station                                                                                                                Inservice Testi g Program Table 5-1 Valve Listing Crawing : VY-E-75-002                            Drawing 11tle: Containmerit Ats.,.y:a Dilution System Dwg Safety OM Act / Size My                          Act      Norma Safety Fall Test Test CSJ/ROJ                      hah Valve Naumber          Nonnenclatum Coor Class Cat Pass (inch)                                      Pos  Pos  Pos Type Ferg            RR PSO *-475A-1      CAD SampleTorus                  J 2                B Act  1              GA        SO      C    OC FC ' FST          Q.          'n/a    Note 5 InboardIsolationValve                                                                                                  PIT 2Y          n/a    Valve also appears on G-STC    Q          n/a -  -191165                      ,
STD .Q              n/a                              '
FSO 199-75A-2      CAD SampleTorus                  J-14        2        B Act  1              GA        SO      C    O/C FC - FST Q                  n/a-    Note 5 OutboardIsolationValve                                                                                                PIT 2Y            n/a    Valve also appears on G-STC    Q          n/a    191165                    -
STO ' Q            n/a FSO-199-75A-3      CAD Supply Torus                J-14        2        B Act  1              GL        SO      C    O/C FC FST Q                    n/a    Note 5 Inboard Isolation Valve                                                                                                PIT 2Y          n/a    Valve also appears on G-STC    Q          .n/a    191165                    >
STD    Q          n/a FSO-199-75A-4    CAD SupplyTorus                  J-14        2        B Act  1              GL        SO      C    O/C FC FST          Q          n/a    Note 5 OutboardIsolationValve                                                                                                PIT 2Y            n/a    Valve also appears on G- :i STC    Q          n/a    191165.
S1D      Q          n/a                              ;
FSO-199-758-1    CAD Sample Lower                I-12        2        B Act  1              GA        SO      O    O/C - FC FST        Q          n/a    Note 5 DrywellInboardIsolation                                                                                              PIT 2Y            n/a    Valve also appears on G-Y"I''                                                                                                                                  n/a STC    Q                  191165                      ,
                                                                                                                                                                                                  ~
STO    Q            n/a FSO 109-75B-2    CAD Sample Lower                I-12        2        B Act  1              GA        SO      O~  O/C FC FST          Q            n/a    Note 5 DrywellOutboard                                                                                                      PIT 2Y            n/a    Valve also appears on G-  (
Isolation Valve                                                                                                    STC                  n/a    191165 Q                                              ;
S1D      Q            n/a FSO 109-75C-1    CAD Sample Mid                  G-12        2        B Act  1              GA        SO      .O    O/C FC FST          Q            n/a    Note 5 DrywellInboaniIsolation                                                                                              PIT 2Y            n/a    Valve also appears on G- 1 Valve                                                                                                            STC                  n/a    191165 Q                                              ; ~
STO      Q            n/a r
Revision 19                                                                  Drawing : VY-E-75-002                                                          Section 5    Page 86 of 179 -  :
 
Vcrmont Yankee Nuclear Power Station '                                                                                                                                                                            Inservice Testing Program -            .
Table 51 Valve Listing Irawing: - VY-E-75402                                                                  Drawing litle: 1 Containment Atmosphere Dilution System Dwg Safety OM Act / Size My                  Act          Norm Safety fab Test Test CSJ/ROJ                                        hs              i Valve Number                    Nomenclature                                                                                                                                                                                                          _
Coor Class Cat Pass (inch)                                  Pos                  Pos Pos Type Freat          RR F50-199-75C-2            CAD SampleMid                                                              G-12      2 B        Act          1    GA    SO            O.            'OC FC FST. Q                      n/a -    Note 5 -                    f DaywellOuttmard                                                                                                                                                            PIT 2Y          n/a      Valve also appears on G-    !
Isolation Valve                                                                                                                                                            SK Q            n/a      191165
,                                                                                                                                                                                                                    SIO Q            n/a FSO 199-75D-1          CAD Sample Upper                                                            G-12      2 B        Act          1    GA-  SO            O                    OC FC FST          Q          n/a      Note 5                      ;
DrywellInboardIsolation                                                                                                                                                    PIT 2Y          n/a      Valve also appears on G-Valve                                                                                                                                                                      STC  Q          n/a . 191165 STO  Q          n/a                                  ,
FSO-199-75D-2            CADhieUpper                                                                G-12      2 B        Act          1    GA    SO-            O                    O/C FC FST        Q          n/a    . Note 5                      ;
DrywellOutboard                                                                                                                                                            PIT 2Y          n/a '    Valve also appears on G-    ;
IwlationValve                                                                                                                                                              STC            n/a Q                  191165
                                                                                                                                                                                                                . S'ID    Q          n/a F50-199-76A  isB CAD CAM Return                                                                    L-13      2 A Act                1    GA    SO.          -O                    OC FC FST          Q          n/a      Valve also appears on G-ContammentIsolation                                                                                                                                                        IJB Var        n/a      191165                      '
Valve                                                                                                                                                                      PE 2Y          da STC  Q          n/a STD    Q          n/a F50-199-76B  IsB CAD CAM Reten                                                                    L-13      2 A Act                1    GA    SO            O                    OC FC FST          Q          n/a      Valve also appears on G-      ,
ContammentIsolation                                                                                                                                                        LJB Var        n/a      191165                        !
Valve                                                                                                                                                                      PE 2Y'          Wa STC    Q'        n/a STD - Q            n/a                                    '
NG-11A                  CAD N2 Supply                                                              H-09        2 A Act                1    GL    SO            C                    OC FC FST          Q          n/a                                    i ContammentIsolation                                                                                                                                                        IJ . 2Y        n/a
                                                            ~
Valve                                                                                                                                                                      PE 2Y          Wa S'It    Q          n/a                                    ,
STO    Q          n/a                                  j l
i Revision 19                                                                                                                Drawing : VY-E-75-002                                                                    Section 5          Page 87 of 179    !
 
Vcrmont Yankee Nuclear Power Station                                                                                                                                                                            Inservice Testizg Program
                                                                                                                                                              - Table 5-1 Valve Listing Drawing: VY-E-75-002                                                                          Drawing
 
==Title:==
Containment Atmosphere Dilution System Dwg Safety OM Act / Size Body                                      Act  Nonn Safety Fail Test Test CSJ/ROJ                        g,g Valve Number                                                    Nomenclature Coor Class Cat Pass (inch)                                                Pos          Pos Pos Type,Freq      RR
  -                          NG-11B                                        CAD N2 Supply                                    H-08        2              A Act            1                GL  SO    C            O/C FC FST Q              n/a contammentIsolation                                                                                                                                      U  2Y      n/a Valve                                                                                                                                                PU 2Y        da STC    Q      n/a SID Q          n/a NG-12A                                        CADN2 Supply                                    J-09      2                A Act            1                GL  SO    C            O/C FC FST Q              n/a ContammentIsolation                                                                                                                                    U  2Y      n/a Vdve                                                                                                                                                  PIT 2Y        n/a STE    Q      n/a STD    Q      n/a NG-12B                                        CADN2 Supply                                    J-08        2              A Act            1                GL  SO    C            O/C FC FST Q              n/a ContammentIsolation                                                                                                                                    U  2Y      n/a Valve                                                                                                                                                PIT 2Y        n/a STC    Q      n/a STD    Q      n/a NG-13A                                        CADN2 Supply                                    1-09      2                A Act            1                GL  SO    C            O/C FC FST Q              n/a C au.                        ntIsolation                                                                                                              U  2Y      n/a Valve                                                                                                                                                PIT 2Y        n/a STC    Q      n/a STD    Q      n/a NG-13B                                        CADN2 Supply                                    H 09        2                A Act            1                GL  SO    C            O/C FL FST        Q      n/a ContammentIsolation                                                                                                                                    U  2Y      n/a Valve                                                                                                                                                PE 2Y        n/a STC    Q    n/a
                                                                                                                .                                                                                                                STO      Q    n/a NG-19                                          ManualValve                                    H-10      2                B Pass          1                GL  MAN    LC            C  n/a n/a n/a        n/a NG-20                                          Manual Valve                                    J-08      2                B Pass          1                GL  MAN    LC            C  n/a n/a      n/a  n/a PSV-NG-34A                                    Pressure Relief Valve                          B-03      2                C  Act          .5                RV  SA    C            O/C n/a SP        10Y  n/a                                              ,
PSV-NG-34B                                    Pressure Relief Valve                          G-03        2                C  Act          .5                RV  SA    C            O/C n/a SP        10Y  n/a Revision 19                                                                                                                        Drawing : VY-E-75-002                                                              Section 5 Page 88 of 179
 
Vcrmont_ Yankee Nuclear Power Station                                                                                                                                                                                                                                                                                              Inservice Testing Program Table 5-1 Valve Listing Drawing: VY-E-75-002                                                                        Drawing
 
==Title:==
Containment Atmosphere Dilution Systen Dwg Safety OM Act / Size                                                                                                                    Norm Safety Fail Test Test CSJ/ROJ                                                                                                                                    '
Vdve Number                                            - Nomenclature Coor Class Cat Pass (inch)
M      Act Pos                          Pos Pos Type Freq                                      RR
                                                                                                                                                                                                                                                                                                                                                                            %,g SS-75A                                                IsolationValve                            L-14                              2                      B Pass .75                                    GL  MAN                                  LC                              C                      n/a n/a            n/a    n/a VC-12A                                                VG-8A Test Connection                    H-12                              2                      B Pass                        1              GL  MAN                                  LC                              C.                    n/a n/a            n/a    n/a VG-12B                                                VG-8B Test Connection                      I-14                            2                      B Pass                        1              GL  MAN                                    C                            C                      n/a n/a            n/a    n/a .                                                                        l VG-13                                                Torus RootIsolation                        J-13                            2                      B Pass                        1              GL ' MAN                                  LC                              C                      n/a n/a            n/a    n/a Supply to ID102 Monitor VG-17A                                                Test Connection                          C-14                            2                      B Pass                        1              GL  MAN                                LC                              C                      n/a n/a            n/a    n/a VG-17B                                                Torus CAD Vent Line                      F-14                              2                      B Pass                        1              GL  MAN                                    C                            C                      n/a n/a            n/a    n/a                                                                          '
Test Connection VG-19                                                TorusCam/ID102                            J-14                            2                      B Pass                        1              GL  MAN                                LC                              C                      n/a n/a            n/a    n/a AnalyzerTest Connection VG-21                                                CAM sampleLine From                      G-18                              2                      B Pass                        1              GL  MAN                                    C                            C                      n/a n/a            n/a    n/a Drywell/rosusAtmos VG-22A                                                CADTo SBGTSystem                          B-16                              2                      A Act                          1              GL MO-AC - C                                                        O/C FAI LJ                                      2Y      n/a contammentisolation                                                                                                                                                                                                                                              PIT  2Y      n/a Valve                                                                                                                                                                                                                                                            STC          Wa Q
STD  Q      n/a VG-22B                                              CADTo SBGT System                        E-16                              2                      A Act                          1              GL MO-AC C                                                          O/C FAI LJ                                      2Y      n/a ContammentIsolation                                                                                                                                                                                                                                              PIT  2Y      n/a Valve                                                                                                                                                                                                                                                            STC          n/a Q
STO  Q      n/a VG-23                                            IsB CAD Rad Monitor                            J-19                            2                      A Act                          1              GL      SO                                O                        O/C FC FST                                      Q      n/a    Valve also appears on G-Supply Contamment                                                                                                                                                                                                                                                LJB Var      n/a      191165 IsolationValve                                                                                                                                                                                                                                                    Prr 2Y      da STC  Q      n/a STO  Q      n/a VG-24                                                CAD 11202 Analyzer                        L-11                              2                      B                  Act        1              GL      SO                                O                        O/C FC FST                                      Q      n/a    Note 5 ReturnIsolation Valve                                                                                                                                                                                                                                            PIT  2Y      n/a STC  Q      n/a STO  Q      n/a Revision 19                                                                                                                                                                    Drawing : VY-E-75-002                                                                                                                                  Section 5    Page 89 of 179 i
__._____.________.__.__._______________m_                                              _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                          _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . ____.                              _ _ _ _ _ _ _ _ _ _ _ _              _ _ _ _ _ _ _ _ _ _ ,
 
Vcrmont Yankee Nuclear Power Station                                                                                                        Inservice Testing Program Table 5-1 Valve Listing Drawing : VY-E-75-002                              Drawing
 
==Title:==
Containment Atmosphere Dilution System Valve Number                    Nomenclature      Dwg Safety OM Act / Size Body                      Act Nonn Safety Fail Tes; Test CSJ/ROJ              hah Coor Class Cat Pass (inch)                              Pos  Pos Pos Type Freg        RR
    .                VG-25                    CAD H202 Analyzer          L-11    2      B Act            1            GL  SO    O  O/C FC FST Q              n/a    Note 5 ReturnIsolation Valve                                                                              PIT 2Y        n/a                                                i STC      Q    n/a STO      Q    n/a VG-26            IsB CAD Rad Monitor                  J-19    2      A Act            1            GL  SO    O  O/C - FC FST        Q    n/a    Valve also appears on G-Supply Containment                                                                                  LJB Var        n/a . 191165 IsolationValve PIT 2Y        n/a                                                I STC      Q    n/a STO      Q    n/a VGJ2                    CheckValve                M-15    2      C Pass          .75            CK  SA    C    C    n/a n/a      n/a    n/a VG-33                    CADII202 Analyzer          L-11    2      B    Act          1            GL  SO    O  O/C FC FST Q              t./a  Note 5                                      i RetumIsolationValve                                                                                PIT 2Y        n/a STC      Q    n/a STD      Q    n/a VG 34                  CADII2O2 Analyzer          L-11    2      B    Act          1            GL  SO    O  O/C FC FST Q              n/a    Note 5 RetumIsolation Valve                                                                                PIT 2Y        n/a STC      Q    n/a STD      Q    n/a                                                '
VG 35                    VG-18 Test Connection      K-12    2      B Pass            1            GL MAN  LC    C    n/a n/a r./a        n/a VG 37                    Sample StationInlet        K-17    2      B Pass .375                    GL MAN    C    C    n/a n/a n/a        n/a Isolation.
VG 38                    Sample Station Outlet      L-17    2      B Pass .375                    GL MAN    C    C    n/a n/a      n/a    n/a Isolation VG3)                      Outletlsolation*            L-18    2      B Pass .375                    GL MAN    C    C    n/a n/a      n/a  n/a VG-41                    H2/02 MonitorRetumto L-16          2      B Pass            1            GL MAN  LC    C    n/a n/a      n/a  n/a RB Ventilation System VG-82                    112/02 MonitorRetum to K-16 NNS B Pass                      1            GL MAN  LC    C    n/a n/a      n/a  n/a RB Ventilation System VG-78                    TestConnection            G-17    2      B Pass          .75            GL MAN  LC    C    n/a n/a      n/a  n/a Revision 19                                                                  Drawing : VY-E-75-002                                              Section 5    Page 90 of 179                      -
 
V:rmont Yankee Nuclear Power Station                                                                                                                                                                                  Inservice Testing Program Table 5-1 Valve Listing
            ' Drawing: VY-E-75-002                      Drawing
 
==Title:==
Containment Atmosphere Dilution System Nomenclature          Dwg Safety OM Act / Size My                                  Act                                                Norm Safety fab Test Test CSJ/ROJ                                                              Researks Valve Number Coor Class Cat Pass (inch)                                                                                                Pos                    Pos Pos Type Freg        RR
.            VG-79            H2K)2 Mon. Return Line H-15              2 B Pass .75                      GL    MAN                                                                LC                    C        n/a n/a  n/a    n'a to Torus /RB Vent.Sys.
Test Conn VG.80                                        K-17          2 B Pass            .75          GL    MAN                                                                LC                    C        n/a n/a  n/a  'n/a VG-9A            CADTo SBGTSystem          H-12          2 A Act              1          GL " SO                                                                        C              ' O/C FC FST        Q    n/a .
ContammentIsolation                                                                                                                                                                        LJ  2Y    n/a Valve PE  2Y    da                                                    ,
STE  Q    n/a STO  Q    n/a VG          CADTo SBGT System          I-14          2 A Act              1          GL              SO                                                            C                O/C FC FST          Q    n/a ContainmentIsolation                                                                                                                                                                      Ly '2Y    n/a valve                                                                                                                                                                                    PE 2Y      da STC  Q    n/a                                                  <
STO  Q    n/a Revision 19                                                        Drawing : VY-E-75-002                                                                                                                                  Section 5              Page 91 of 179
 
      , m . _        _ .    -___                    . _ _ _ _ _ . _ _ _ . . . _                              _      _ . _ _  _
l i
              ' Vernent Ycnkee Nuclear Power Station -                                  Inservice Testing Program                  !
L
                    - 53  Valve Notes                                                                                              1
                          .l.      Full stroke ' exercising and timing tests of the MSIVs are accomplished quarterly when reactor power is decreased to less than 75 percem. At least twice a week, the L                                  . MSIVs are also exercised by partial closure and subsequent reopening.                          I 1
: 2.      This Note was deleted in Revision 19 of the IST Program.
l
: 3.      Testing of CRD Cooling Water Supply Check valve, V3-138, is not required when                    !
the corresponding control rod has been declared inoperable and its directional control          !
l                                  valves disarmed in accordance with the provisions of Technical Specifications                    l L                                  3.3.A.2.                                                                                      -l
[
l                          4.      At least once during each operating cycle, the Standby Liquid Control system shall            .l l                                  be verified operable by: a) Initiating one of the SLC loops, excluding the primer                ,
l chamber and inlet fitting, and verifying a flow path from the pump to the reactor                i vessel. Both loops shall be tested over the course of two operating cycles. (T.S.                !
;                                  4.4.A.2) b) Testing of both trigger assemblies removed from the system (each l                                  refueling outage) by installing in the test block to verify operability. c) Testing of l >
the replacement trigger assemblies by installing one of the assemblies in the test L                                  block and firing it using the installed circuitry. Replacement triggers shall be from the sanic batch as the test assembly. The unfired replacement triggers, taken from the same batch shall be installed into the explosive valves. (T.S. 4.4.A.3 and 4.6.E)
: 5.        Only one valve in each CAD sample line or H202 analyzer line is required to be operable in accordance with Technical Specifications Table 4.7.2.b.
i
: 6.        Positive verification of full opening of the Transversing In-Core (TIP) Ball Valves, l                                  BV-7-1 through 3 is shown by successful insertion of the TIP Probe through the                  ;
L                                    valve. Positive verification of full closing of the valve is shown during each                  1 Refueling Outage by successful leak testing (LJ). This testing is in compliance with Paragraph 4.1 of Part 10 of the Code which states "Where local observation is not possible, other indications shall be used for verification." Local observation of valve position would require disassembly of the valve enclosures as the limit switches are contained within the enclosures.
: 7.      ' The Nuclear Boiler Safety / Relief Valves, SV-2-70A & B and RV-2-71 A through D will be tested in accordance with the requirements of OM-1 only.
i                          8.        These valves form the Alternate Cooling System boundary alignment and are
'                                    otherwise included in the IST Program per based on a commitment to NRC.
 
==Reference:==
OP-2181; NRC Inspection Report 94-03, dated 3/4/94.
I L
L Revision 19                                                                    Section 5 Page 92 of179
 
Wrm=t Ycnkoa Nucirir Power Ststian                                    Ins:rvica Testing Prcgram
            -5.3  Valve Notes (Con't)
: 9. The Cooling Tower SW Distribution Tray valves, V70-17A through V70-17D shall be cycled once each refueling as part of augmented testing to the 1994 Service Water System Self Assessment Report. These valves are not required to be exercised in accordance with the requirements of 10 CFR 50.55a.
: 10. The Service Water Pump Discharge Check Valves, V70-1A through ID, are part-stroke exercised open on a quarterly basis during plant operation during the regularly scheduled quarterly service water pumps tests. These valves are full stroke exercised open during refueling outages.
I1. The RHR and Core Spray Keep-Fill Check Valves (V10-36A, V10-36B, V14-33A, and V14-33B) are verified closed on an operating cycle basis utilizing a non-intrusive technique.
The Core Spray Discharge Flushing Line Check Valves (V14-22A, V14-22B, V14-23A and V14-23B) are verified closed on an operating cycle basis utilizing a non-intrusive technique.
The HPCI and RCIC Keep-Fill Check Valves (V23-20B and V13-20B) are verified closed dn an operating cycle basis utilizing a non-intrusive technique.
The HPCI and RCIC Pump Suction Valves (V23-32 and V13-19) are verified closed on an operating cycle basis utilizing a non-intrusive technique,
: 12. These valves are skid-mounted. NUREG 1482, Section 3.4 states that the testing of l                          the major component is an acceptable means for verifying the operational readiness of the skid-mounted component and component subassemblies if the licensee documents this approach in the IST program. The scope of skid-mounted components additionally includes components that are not mounted on the skid, but which function much the same as skid mounted components.
: 13. These valves are post-accident sampling (PASS) valves. NUREG 1482, Section 4.4.2 states that PASS valves that perform a containment isolation ftmetion are l                          required to be included in the IST Program.                            ,
I
: 14. These valves are Category B passive valves. NUREG 1482, Section 4.2.6 states that the code does not restrict the verification cf remote position indication to only active L                          valves. OM-10, Table 1, indicates that the licensee mu::t also verify the position for
                          . Category B passive valves.
i Revision 19                                                                    Section 5 Page 93 of179 i
 
I  Vermtat Ycnkee Nuclear Pcwer St tian                                          Ins:rvice Testing Program' l
l        5.3 : Valve Notes (Con't) 1 L
: 15. The performance of pressure sensing instrumentation testing for PCAC Vacuum Relief from Secondary Containment Iso Valves, SB-16-19-11A and 11B, is                      i performed (OP 4376) as required by OM-1 subsection 3.3.2.3 and Technical Specification 4.7.A.5.a.                                                                    '
: 16. The Control Rod Drive Scram Inlet and Outlet Valves, CV-3-126 and CV-3-127, will be tested in accordance with the requirements of Tech. Spec Surveillance 4.3.C.1        !
after refueling outages and prior to operation above 30% power,
: 17. The CRD Manual Control Insertion, Withdrawal and Exhaust Valves, SO-3-120, 121,122 and 123 are verified operable in accordance with the weekly rod testing            ;
,                      performed in accordance Tech. Spec. Surveillance 4.3.A.2 during power operations.
                        'Ihe closure operation of these valves and the control rod drives are verified after refueling outages and prior to operation above 30% power per Tech. Spec.
Surveillance 4.3.C.1.
: 18. The Scram Exhaust To Discharge Volume Check Valves, V3-114, will be tested in accordance with the requirements of Tech. Spec Surveillance 4.3.C.1 after refueling outages and prior to operation above 30% power.
: 19. The CRD Charging Water to Accumulator Check Valves, V3-115, closure verification will be performed by the accumulator pressure decay test (OP 4111) during refueling outages.
l                  20. The Reactor Recirculation Sample Line Flow Control / Isolation valves, FCV-2-39 l                        and FCV-2-40, had direct position indication installed to meet R.G.1.97 and OM-10.
l                        (EDCR 97-406/RFO-20,1998).
l
: 21. These valves are PIV's, they are subject to leak testing commensurate with                    i nominal operating reactor vessel pressure.
I
: 22. These manually operated valves are required to open for the Alternate Cooling l                        Mode (ACS) of the Service Water System.
: 23. These manually operated valves are required to close for the Alter'nate Cooling Mode (ACS) of the Service Water System. Valves were added per commitment to BMO 97-61.
l
  . Revision 19                                                                        Section 5 Page 94 of179 l                _
 
Verm:st Yckee Nucle:r Pcwer St:ti:n                                    Ins;rvico Testing Prcgram COLD SHUTDOWN JUSTIFICATION Number: CSJ-V01, Revision 2 (Sheet 1 of 1)
SYSTEM: Reactor Building Closed Cooling Water COMPONENTS:
Valve Number          OM Cat.          Safety Class      Drawing Number            Dwg. Coord.
V70-117                      A                2            G-191159 Sh 3                L-12 Valve V70-117 is the reactor building closed cooling water retum containment isolation valve. This valve has a safety function in the closed position to provide primary containment isolation.
JUSTIFICATION:
This valve cannot be full-stroke exercised closed during nonnal (power) operation since shutting this valve would stop cooling water flow to vital primary containment equipment, including the primary containment air coolers and the reactor recirculation pumps.
This valve will be stroke timed closed during Cold Shutdowns in accordance with Paragraphs 4.2.1.2(c), (f), (g) and (h) of the code.
t f
l t
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Vcrm=t Yc kee N: clear Pcwer St tin                            Itservica Testing Prcgram COLD SHUTDOWN JUSTIFICATION Number: CSJ-V02, Revision 1 (Sheet 1 of1)
THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 18 OF THE IST PROGRAM.
This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
Revision 19                                                                            Section 5 Page 96 of179
 
1 Vsrm:nt Yenkee Nucle:r Pcwer St:ti:n                            Ins:rvice Tcsting Prcgram i
COLD SHUTDOWN JUSTIFICATION                                                j Number: CSJ-V03, Revision 1 (Sheet 1 of 1) 1 THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 15 OF THE IST                                I PROGRAM.                                                                                              l 1
This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
Revision 19                                                            Section 5 Page 97 of179 4
 
l l      Vcrm:nt Yenkee Nrcle:r Pcwcr St: tic                                    Inservice Testing Prcgrcm COLD SHUTDOWN JUSTIFICATION l-                                      Number: CSJ-V04, Revision 2 (Sheet l of1) l SYSTEM: Nuclear Boiler COMPONENTS:
l Valve Number          OM Cat.          Safety Class      Drawing Number          Dwg. Coord.
V2-53A                        B                  1              G-191167                  L-09 V2-53B                        B                  1              G-191167                  L-09 V2-54A                        B                  1              G-191167                  L-09
[      V2-54B                        B                  1              G-191167                  L-09 These valves are the reactor recirculation pump discharge isolation and bypass valves. They have a safety function in the closed position to limit primary system coolant loss following a LOCA and to ensure low pressure coolant injection flow is properly directed to the reactor.
1 JUSTIFICATION:                                                                                            !
l These valves cannot be , exercised closed during reactor power operation since cycling these valves        l
                                                                                                                  ~
l    - would result in a reactor recirculation pump trip.
l These valves will be stroke timed closed during Cold Shutdowns in accordance with Paragraphs 4.2.1.2(c), (f), (g) and (h) of Part 10 of the Code.
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Vcrm:st Yeckee Nucle r Pcwer St:ti:n                            Inservice Testing Pmgram COLD SHUTDOWN JUSTIFICATION Number: CSJ-V05, Revision 2 (Sheet 1 of1)
SYSTEMI Co:e Spray COMPONENTS:
Valve Number      OM Cat.        Safety Class      Drawing Number        Dwg. Coord.
V14-13A                A/C                1                G-191168              F-06 V14-13B                A/C                1                G-191168              D-06 These valves are the Core Spray injection check valves. They have a safety function in the open position to pass core spray injection flow to the reactor, and in the closed position for primary containment and pressure isolation.
THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 19 OF THE IST PROGRAM.
This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.                  .
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l Vcrment Ycnkes Nuclear Pswer St ti:n                                      Inservice Testing Pr: gram    I COLD SHUTDOWN JUSTIFICATION Number: CSJ-V06, Revision 1(Sheet 1 of1)
SYSTEM: High Pressure Coolant Injection
  . COMPONENTS:
Valve Number        OM Cat.        Safety Class          Drawing Number          Dwg. Coord.
V23-18                    C                  2                G-191169 Sh 1              G-05 This valve is the High Pressure Coolant Injection (HPCI) discharge to Feedwater Line "A" check valve.
The valve has a safety function in the open position to pass HPCI flow to the reactor and in the closed  l position to prevent backflow feedwater into HPCI piping.
JUSTIFICATION:
This valve cannot be exercised open during normal (power) operation since flow through this valve must be injected into the reactor coolant system. This would thermally shock the reactor nozzles and cause a positive reactivity excursion. Manual operation of the valve is not possible since the valve is located in the steam tunnel which is inaccessible during power operations.
This valve will be manually exercised open and closed during Cold Shutdowns when the steam tunnel is accessible in accordance with 4.3.2.2(c), (f), (g) and (h) of Part 10 of the Code.
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l Vcrm:nt Ycakee Nucl=r Pswer St tica                              Ins:rvice Testing Program COLD SHUTDOWNJUSTIFICATION Number: CSJ-V07, Revision 0 (Sheet 1 of 1) l THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 18 OF THE IST
,  PROGRAM.
. This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal .      j SER's.
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Verm:nt Ycnke3 Nucle:r Pswer St:ti:n                                    Inservice Testing Prcgrcm COLD SHUTDOWN JUSTIFICATION Number: CSJ-V08, Revision 2 (Sheet 1 of1)
SYSTEM: Residual Heat Removal COMPONENTS:
Valve Number        OM Cat.          Safety Class          Drawing Number      Dwg. Coord.
V10-17                    A                  2                  0-191172            G-08 V10-18                    A                  2                  G-191172            F-08 i
These valves are the Residual Heat Removal (RHR) shutdown cooling supply isolation valves. They have a safety function in the closed position to provide primary containment and pressure isolation, and in the open position to provide RHR pump suction during shutdown cooling operation.
JUSTIFICATION:
These valves cannot be stroke timed open during reactor power operation since there is a 100 psig            l interlock that prevents opening these valves during power operation. This interlock is required to prevent overpressurization of the lower pressure rated RHR shutdown cooling subsystem.
These valves will be stroke timed open and stroke timed closed during Cold Shutdowns in accordance with Paragraphs 4.2.1.2(c), (f), (g) and (h) of Part 10 of the Code.
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L      Verment Ycnkee Nucle r Power St: tion                            Inservics Testing Progr::m i
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COLD SHUTDOWN JUSTIFICATION                                                    '
i Number: CSJ-V09, Revision 1 (Sheet 1 of 1)
THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 15 OF THE IST PROGRAM.
    ' This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
Revision 19                                                          Section 5 Page 103 of179 l'
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Vcrmr.t Yerkee Nucle:r P:wcr Stati::n                                Inservica Testing Pr: gram COLD SHUTDOWN JUSTIFICATION Number: CSJ-V10, Revision 2 (Sheet 1 of 1)
SYSTEM: Reactor Core Isolation Cooling COMPONENTS:
Valve Number          OM Cat.          Safety Class    Drawing Number          Dwg. Coord.
V13-22                      C                  2            0-191174 Sh 1              G-09 This valve is the Reactor Core Isolation Cooling (RCIC) discharge to Feedwater Line "B" check valve.
  ,'Ihe valve has a safety function in the open position to pass RCIC flow to the reactor and in the closed position to prevent backflow into the RCIC system.
JUSTIFICATION:
This valve cannot be exercised open during normal (power) operation since flow through this valve must be injected into the reactor coolant system. This would thermally shock the reactor nezzles and cause a positive reactivity excu;sion.
This valve is located in the steam tunnel which is inaccessible during power operations. Additionally, there is no means to manually exercise this valve.
  'Ihis valve will be exercised open and closed during Cold Shutdowns in accordance with Paragraphs 4.3.2.2(c), (f), (g) and (h) of Part 10 of the Code.
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i Vcrm:nt Ycnkee Nuclear P wcr St:ti:n                            Inservica Testing Prcgram COLD SHUTDOWNJUSTIFICATION Number: CSJ-Vil, Revision 1 (Sheet 1 of1)                                  j i
THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 18 OF THE IST PROGRAM.
l This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
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l-Vcrm::t Ycnkes Nuclz:r Power St: tina                            Inservice Tcsting Pr: gram COLD SHUTDOWNJUSTIFICATION Number: CSJ-V12, Revision 1 (Sheet 1 of 1)
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l THIS COLD SHUTDOWN JUSTIFICATION DELETED IN REVISION 18 OF THE IST PROGRAM.
This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal    i SER's.
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Verm:2t Yer;kee Ntcizr Psw:r Stiti:2                            Ins:rvics Testing Program      l COLD SHUTDOWN JUSTIFICATION Number: CSJ-V13, Revision 1 (Sheet 1 of1)
THIS COLD SHUTDOWN JUSTIFICATION DELETED IN REVISION 18 OF THE IST PROGRAM.
This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
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i Revision 19                                                            Section 5 Page 107 of179 4
 
Vcrm=t Yenkee Nuclesr P:wer Stati::s                                  Inservic Tcsting Progr:m COLD SHUTDOWN JUSTIFICATION Number: CSJ-V14 Revision 1 (Sheet 1 of 1)
SYSTEM: Residual Heat Removal COMPONENTS:
Valve Number          OM Cat.          Safety Class  Drawing Number            Dwg. Coord.
V10-46A                    NC                  1            0-191172                  E-07 V10-46B                    NC                  1            G-191172                  E-10 These valves are the Low Pressure Coolant Injection (LPCI) injection check valves. They have a safety function in the open position to pass LPCI flow to the reactor, and in the closed position for primary containment and pressure isolation.
JUSTIFICATION:
These valves cannot be exercised open during normal (power) operation since the Residual Heat Removal (RHR) pump discharge cannot overcome reactor pressure. Manual exercising is not possible during plant operation be,cause the valves are located inside the inerted drywell and are not accessible during plant operation.
These valves will be exercised open with flow during Cold Shutdown in accordance with Paragraphs 4.3.2.2(c), (f), (g) and (h) of Part 10 of the Code.
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      . . - _ . - -            . - . .-        --.~ - - - .              _ - . - - - - - - . -                                      - -
I Vcrmest Ycnkee Nuclerr Pcwer Statian                                                  Inservica Testing Pr: gram              i
                                                                                                                                          'i l                                              COLD SHUTDOWN JUSTIFICATION Number: CSJ-V15 Revision 1 (Sheet 1 of 1)                                                      ;
i SYSTEM: Residual Heat Removal                                                                                                  1 l
COMPONENTS:
            . Valve Number              OM Cat.            Safety Class    Drawing Number                    Dwg. Coord.
        - V10-48A                        C                    2                  G-191172                        L-05 V10-48B                        C                    2                  G-191172                        L-13 V10-48C -                      C                    2                  G-191172                        J-05 V10-48D .                      C                    2                  G-191172                        J-13 These valves are the RHR pump discharge check valves. These valves have a safety function to open to pass RHR pump' discharge flow for all modes of RHR/LPCI system operation. These valves also
        ~ have a safety function to close to prevent the backflow of water through an idle RHR pump ~.
Justification:
It is not practical to perfonn a full-stroke open exercise of these valves on a quarterly basis during plant operation. These valves are exercised during the performance of the quarterly RHR pump surveillance.                            !
During plant operation, the only practical flow path for these pumps is in the torus to torus flow path.
The RHR pumps do not have sufficient head to flow to the recirculation loops with the reactor coolant            .
system at normal operating pressure. Typical RHR pump flowrates in the. torus to torus flow                                    {
        . configuration are approximately 6,500 gpm for the RHR pump test. The required design accident condition flow rate to perform a full-stroke exercise is 7,300 gpm which can only be achieved when the                          !
RHR system is in the vessel to vessel flow configuration.
These valves will be part-stroke open exercised quarterly during plant operation and will be full-stroke
: open exercised during cold shutdowns in accordance with Paragraphs 4.3.2.2(b), (f), (g) and (h) of Part 10 of the Code.                                                                                                  -
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  ..m            . _.              _ _ _ _.        . _ _ _ = _ . _ _ _ _ _ _ . _ . _ _                                      _ .___
Vcrmant Ycnkee Nucher Pcwcr Ststica                                                Insarvice Testing Prcgram l
COLD SHUTDOWN JUSTIFICATION l
Number: CSJ-V16, Revision 0 (Sheet'l of 2) l SYSTEM: Service Water l                COMPONENTS:
l                  Valve Number              - OM Cat.              Safety Class -      Drawing Number        Dwg. Coord.
V70-11                            B                            3          G-191159 Sh 2            D-07 V70-17                            B                            3          G-191159 Sh 2            D-06 SB-70-1                          B                        NNS-          G-191159 Sh 2            D-09
              . V70-18                            B                          -3            G-191159 Sh 2            E-07 Valve V70-11 is the SW Discharge to Cooling Tower Basin Isolation Valve. The safety function of this valve is to open to provide water to the Cooling Tower Basin to prevent the development of ice in the basin.
Valve V70-17 is the Altemate Cooling to SW Supply valve. The safety function of this valve is to open to provide flow to the Cooling Tower spray header to provide an attemate cooling path for the Service Water System.                    ,
Valve SB-70-1 is the SW Discharge to Main Condenser Discharge Block Valve. The safety function of this valve is to open to provide a flow path to the river. These valves have an active function to change position in order to provide a path for flow to the Cooling Tower when the Service Water System is
              - required to be in the Altemate Cooling mode of operation.
Valve V70-18 is the Service Water Header Discharge Isolation Valve. The safety function of this valve is to close to maintain inventory of vital cooling water when the Service Water System is in the Altemate Cooling mode ofoperation.
JUSTIFICATION:
It is no' practicable to full or part stroke exercise these valves quarterly during normal (power) operation for the following reasons.
The Service Water system is designed with two discharge flow paths - main condenser discharge block and cooling tower. The discharge flow path is selected based on environmental conditions.
l, Service Water is discharged to the cooling tower deep basin when Connecticut River temperature is less than 45*F to keep the deep basin from freezing. The deep basin cannot be allowed to freeze, l
;                because it contains water inventory necessary for alternate cooling mode operation of Service Water
!                system. Service Water is discharged to the condenser discharge block when Connecticut River temperature is greater than or equal to 45*F. This discharge path causes less back pressure in the
[                discharge line and increases flow through the Emergency Diesel Generator Jacket Water Coolers.
i            :  The flow increase is necessary to compensate for higher river water temperature.
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                                    -F g- y              -    ,--                                                  ,                      -,--%      .y  -m,,
 
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!      Verm:nt Ycnkee Nuclear P wer St::ti:n                                Inservic: Testing Pr: gram COLD SHUTDOWN JUSTIFICATION Number: CSJ-V16, Revision 0 (Sheet 2 of 2)
V70-11, V70-17, SB-70-1 and V70-18 are large (20" and 24") manual valves and must be operated as a set because their positions are interdependent. For example, allowing V70-11 and SB-70-1 to be open at the same time, except for the minimum time required for system lineup changes, could drain the deep basin inventory. Closing V70-18 with Service Water discharge lined-up to the main condenser discharge block will isolate Service Water from the safety-related cooling loads and closing V70-18 with Service Water discharge lined-up to the cooling tower will isolate turbine
      - building cooling loads.
These valves will be full stroked open and close during cold shutdown in accordance with Paragraph      j
      ' 4.212(c) (f) and (g) when Service Water cooling loads are more managable 1
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                                                                                                                              )
Verm:nt Yankee Nucle:r Pswer St:ti:n                                              Insarvice Testing Program COLD SHUTDOWN JUSTIFICATION Number: CSJ-V17 Revision 0 (Sheet 1 of 1)
SYSTEM: Instrument Air COMPONENTS:
l l            Valve Number        OM Cat.              Safety Class          Drawing Number            Dwg. Coord.
V72-28A                    B                  NNS                  G-191160 Sh 3                L-15 L
V72-28B -                  B                  NNS                  G-191160 Sh 3                L-16 l          V72-28D -                  B                  NNS                  G-191160 Sh 3                K-16 V72-28E                    B                  NNS.                G-191160 Sh 3                K-16 V72-28A and V72-28B have a safety function to close to isolate the Instrument Air (IA) system from
: l.          the outboard MSIVs. Following an Appendix R fire event in the control room and cable spreading                    .
I          room, V72-28A and V72-28B are closed to isolate the air supply and V72-28D and V72-28E are opened to vent the residual air contained in the piping from the air supply isolation valves to the MSIV accumulators. This action prevents the MSIVs from inadvertently re-opening if a hot short were to occur in the MSIV solenoid circuitry.
 
==Reference:==
Minor Modification 96-34.
V72-28D and V72-28E l$ ave a' safety function to open to vent the residual air contained in the IA                  ,
system supply to the outboard MSIVs (V2-86A, V2-86B, V2-86C and V2-86D). Following an                              1
:          Appendix R. fire event in the control room and cable spreading room, V72-28A and V72-28B are                      i i
closed to isolate the air supply and V72-28D and V72-28E are opened to vent the residual air contained l          in the piping from air supply isolation valves to the MSIV accumulators. This action prevents the
;          MSIVs from inadvertently re-opening if a hot short were to occur in the MSIV solenoid circuitry.
 
==Reference:==
Minor Modification 96-34.
l Justification:
l V72-28A and V72-28B cannot be exercised closed and cannot be exercised open during power l          operation on a quarterly basis exercising these valves would isolate / vent instrument air to the MSIV accumulators. Instrument Air pressure is required to maintain the MSIVs in the open position. The loss ofinstmment air pressure would cause the MSIVs to go to the closed position and result in a reactor power transient.                                                                                .
V72-28A and V72-28B will be full-stroke closed ar.d V72-28D and V72-28E will be full-stroke opened during Cold Shutdowns in accordance with Paragraphs 4.2.1.2(f) & (g) of Part 10 of the Code, i
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Verm=t Yerkes Nucle:r P wer St:tien                                    Ins:rvice Testing Prcgram            j i
i COLD SHUTDOWN JUSTIFICATION l
l                                Number: CSJ-V18, Revision 0 (Sheet 1 of 1)
SYSTEM: ResidualHeatRemoval COMPONENTS:
Valve Number          OM Cat.        Safety Class      Drawing Number            Dwg. Coord.          I V10-17Al                      B                2                G-191172                G-08              ;
l Valve V10-17Al is the V10-17 outboard containment isolation valve bonnet pressure locking relief I
device. This is a manual globe type valve. The safety function of this valve is to open to alleviate bonnet pressure locking of V10-17 in an Appendix R scenario.
JUSTIFICATION:
l It is not practical to full or part-stroke open V10-17Al dtr ing power operation. Opening V10-17Al is a      '
potential personnel / contamination hazard due to the release of high pressure (1000 psig) contaminated fluid. During cold shutdown, V10-17 bonnet pressure will equalize with reactor pressure and opening V10-17Al is not a personnel hazard.
V10-17Al will be full-stroke opened during Cold Shutdowns in accordance with Paragraphs 4.2.1.2(f)
  & (g) ofPart 10 of the Code.
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Vcrm:nt Yankee Nucirr Power Statinn                            Ins;rvice Testing Pr: gram REFUELING OUTAGE JUSTIFICATION l
Number: ROJ-V01, Revision 2 (Sheet 1 of 3)
SYSTEM: Nuclear Boiler High Pressure CoolantInjection Reactor CoreIsolation Cooling Recirculation Pump Cooling Water COMPONENTS:-
Valve Number      OM Cat.        Safety Class    Drawing Number          Dwg. Coord.      I SL-13-55A              NC                2          0-191174 Sh 1              B-08 SL-13-55B              NC                2          G-191174 Sh 1              C-08 SL-13-55C              NC                2          G-191174 Sh 1              B-08 SL-13-55D              NC                2          G-191174 Sh 1.              C-08 SL-14-31 A              NC                2-            G-191168                F-07 SL-14-31B              NC                2            G-191168                E-07        !
SL-2-62A                A/C              2            G-191167                I-13 SL-2-62B                NC                2            G-191167                I-13 SL-2-62C                A/C    -        2            G-191167                J-13 SL-2-62D                A/C              2            G-191167                J-13 SL-2-64A              NC                2            G-191167                K-13        j SL-2-64B              NC                2-            G-191167                K-13 SL-2-64C              A/C              2            G-191167                K-13 SL-2-64D              NC                2            G-191167                L-13 SL-2-73A              A/C              2            G-191167                F-12        j SL-2-73B              A/C              2            G-191167                F-12 SL-2-73C              A/C              2            G-191167                G-12 SL-2-73D              NC                2            G-191167                G-12 SL-2-73E              A/C              2            G-191167                G-12 SL-2-73F              A/C              2            G-191167                G-12 SL-2-73G              A/C              2            G-191167                H-12        i SL-2-73H              A/C              2            G-191167                H-12 SL-2-2-7A              NC                2          G-191159 Sh 5 -            G-02 SL-2-2-7B              A/C              2          G-1911.!9 Sh 5            G-02 SL-2-2-8A              NC                2          G-191159 Sh 5              G-02 SL-2-2-8B -            A/C              2          G-191159 Sh 5              G-02 SL-2-3-11              A/C              2          G-191267 Sh 1              C-06 SL-2-3-13A            A/C              2          G-191267 Sh 1              D-06 l    SL-2-3-13B            A/C                2          G-191267 Sh 1              C-12
;    SL-2-3-15A            NC                2          G-191267 Sh 1              D-06
    - Revision 19                                                        Section 5 Page 114 of179
 
4
    ' Vermcat Yankee Nuclerr Pawsr Stitisn                                  Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V01, Revision 2 (Sheet 3 of 3)
Valve Number          OM Cat.        Safety Class        Drawing Number        Dwg. Coord.
SL-2-305A                A/C                    -- 2          G-191167                  M-02 SL-2-305B -              A/C                      2            G-191167                  M-02 SL-23-37A                A/C                      2          G-191169 Sh 1              F-05 SL-23-37B                A/C                      2          G-191169 Sh 1              F-05 SL-23-37C                A/C                      2          G-191169 Sh 1              F-05~
    . SL-23-37D                A/C                      2          G-191169 Sh 1              F-05 f
l These valves are instrumentation line excess flow check valves. They are required to be verified operable in accordance with Vermont Yankee Technical Specification 3.7.D.1.
JUSTIFICATION:
These valves cannot be exercised closed during normal (power) operation since closing these valves would isolate instrumentation required for power operation. These valves can only be verified to closed by leak testing performed during the primary system inservice pressure test performed each refueling outage. This teg cannot be repeated during each Cold Shutdown since the reactor vessel is not pressurized during Cold Shutdowns.
These valves will be exercised open and closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.3 and 4.3.2.2(e) (h) of Part 10 of the Code.
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[                                                                                                                        i Revision 19                                                                Section 5 Page 116 of179
 
L                                                                                                                                !
4 L          Verm:nt Ycnk 3 Nucle r Pawsr St:tias                                      Ins:rvics Testing Pr: gram -
REFUELING OUTAGE JUSTIFICATION T mber: ROJ-V02, Revision 1(Sheet 1 of1) l          SYSTEM: Nucle 6          . .x r i                                                                                                                              ;
COMPONENTS:
L            Valve Number          OM Cat.        Safety Class          Drawing Number              Dwg. Coord.
RV-2-71A                      C              -1                    G-191167                    D-08                ;
RV-2-71B                    C                1-
                                                                        ~
G-191167                    G-08                i RV-2-71C -                  C                1                    G-191167                    G-08                l RV-2-71D                      C                1                    0-191167                    H-08 Valves RV-2-71 A through D are the nuclear boiler main steam safety / relief valves. ney have a safety              )
  ..      function in the open position for. Automatic Depressurization System (ADS) operation and for                        l overpressure protection, and in the closed position to maintain reactor coolant inventory.                          !
l JUSTIFICATION:
Stroke testing of these valyes quarterly during power operation is not recommended. As recommended                  i I
          . by NUREG-0737 and the corresponding study by the BWR Owners Group (BWR Owners Group Evaluation of NUREG-0737, Item II.K.3.16, " Reduction of Challenges and Failures of Relief Valves"),                j
          - the exercising of these valves should be minimized to reduce the number of challenges to safety / relief            ;
valves.
1 ne failure of any relief valve to close during stroking at power operation would cause an uncontrolled rapid depressurization of the primary system (stuck open relief valve transient) along with an undesired positive reactivity excursion.
          ' These valves can only be tested with primary system pressure greater than 100 psig, therefore, they cannot be exercised during cold shutdowns or during refueling outages. Exercising these valves at each start-up from cold shutdown (or quarterly) would produce additional stress cycles on the nuclear boiler system which could lead to a low cycle fatigue failure. These valves will be exercised during plant startup after each refueling outage in accordance with Paragraph 4.2.1.2(h) of Part 10 of the Code and              1 Paragraph 3.4.1.l(d) of Part 1 of the Code.                                                  ,
his Refueling Outage Justification is for clarification purposes only.
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          ; Revision 19                                                                        Section 5 Page 117 of179
                  ,  ._ _,                          _                _ . _ ,          _~ - . _ - -
 
4
!                      Vermsnt Yankee Nucleer Pcwsr Ststi::n                                                          Inservics Testing Prcgram L
j-                                                        REFUELING OUTAGE JUSTIFICATION t
c                                                                                  ..                .            .    .
Number: ROJ-V03, Revision 2 (Sheet 1 of 2) t;
;                      SYSTEM: NuclearBoiler COMPONENTS:
i                      - Valve Number                OM Cat. Safety Class                          Drawing Number            Dwg. Coord.
V2-27A -                        A/C-              2                                      G-191167                F-03 V2-27B                          C.              2                                      G-191167                H                        V2-28A -                        NC                2                                      G-191167                F-05 9                    . V2-28B NC              .2                                      G-191167                H-05 V2-%A                          NC                2                                      G-191167.              H-03        !
V2-%B -                          C                2                                      0-191167                F-03 i
                    ' Valves V2-27A and V2-28A are the outboard and inboard containment isolation check valves for the "A" Feedwater Line, respectively. They have a safety function in'the closed position to provide                              j primary containment isolation, and in the open position to pass High Pressure Coolant Injection flow to                      i the reactor.
                    . Valves V2-96A and V2-28B are the outboard and inboard containment isolation check valves for the l
                      "B" Feedwater Line, respectively. 'Ihey have a safety function in the closed position to provide primary containment isolation, and in the open position to pass Reactor Core Isolation Cooling flow to                        !
the reactor.
Valve V2-96B is the second outboard check valve in the "A" Feedwater Line. The valve has a safety function in the closed position to prevent diversion of High Pressure Coolant Injection flow in the "A"                      ;
Feedwater Line.-                                                                                                              l Valve V2-27B is the second outboard check valve in the "B" Feedwater Line. The valve has a safety
                    ~ function in the closed position to prevent diversion of Reactor Core Isolation Cooling flow in the "B" Feedwater Line.
      '-                                                                                                                    Section 5 Page 118 of179 Revision 19
 
i l
Verment Ycnkee Nucle r Pswer Statisn                                            Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V03, Revision 2 (Sheet 2 of 2) l JUSTIFICATION:                                                                                                  l 1
i
  ' dese valves cannot be exercised closed during normal (power) operation because the feedwater system is required to maintain reactor vessel water level. Interruption of feedwater to perform the              I
,  exercise test of these valves would result in a reactor scram.
These valves can only be stroke close tested via a leak type or non-intrusive test. Testing during Cold          ;
Shutdowns is impracticable due to the significant system and test equipment configurations required.            !
:  Additionally, valves V2-27B, V2-28B and V2-96A cannot be exercised during Cold Shutdowns since this would require removing the only mechanism of reactor vessel level control (via the Reactor Water            l Cleanup System).
l  V2-27A, V2-28A, V2-28B and V2-96A will be stroke close tested each Refueling Outage during i  leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of          !
the Code.
4 4
V2-27B and V2-96B will be stroke close tested each Refueling Outage using non-intrusive testing or
;. disassembly in accordance with Paragraphs 4.3.2.2(e), (h) and 4.3.2.4(a) or (c) of Part 10 of the Code.
l  V2-27B and V2-96B were replaced during the 1996 Refueling Outage. Valve disassembly was used l  instead of a non-intrusive test for this refuel outage because:
* These valves were disassembled to facilitate installation.
    . These valves were manually stroked after installation to verify freedom of movement and blue
,        checked. These action satisfy the OM-10 stroke close requirement intent.
Revision 19                                                                        Section 5 Page 119 of179
 
Verm:nt Ycnkee Nucle:r Pcwzr Stati:n                                  Ins:rvice Testing Prcgram
                              ' REFUELING OUTAGE JUSTIFICATION Number: ROJ-V04, Revision 1 (Sheet 1 of 1)
SYSTEM: NuclearBoiler COMPONENTS:
Valve Number        OM Cat.        Safety Class        Drawing Number          Dwg. Coord.
V2-37A                    NC                2                0-191167                B-08 V2-37B                  A/C                2                G-191167                G-09 V2-37C                    NC                2                G-191167                G-09 V2-37D                    NC                2                G-191167                .H-09 These valves are the Main Steam Relief Valve (MSRV) actuator air supply check valves. They have a safety function in the closed position to ensure automatic depressurization system (ADS) capability is maintained via the MSRV accumulators on a loss of the instrument nitrogen supply.
JUSTIFICATION:
These valves are located,in the drywell and thus cannot be stroke close exercised during normal power operations or Cold Shutdowns when the drywell is inerted. 'Ihese valves can only be stroke close tested via a leak type or non-intrusive test which would reqse isolating the instrument nitrogen supply to the MSRVs. Testing during Cold Shutdowns is impracticable due to the significant system and test equipment configurations required.
These valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.3 and 4.3.2.2(e), (h) of Part 10 of the Code.
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  - Revision 19.                                                              Section 5 Page 120 of179    ;
 
L l        Verm st Ycnkes Nucle:r P:wer St:tian                                                I servico Testing Prcgram 1
REFUELING OUTAGE JUSTIFICATION                                                                      l l                                                                                                                                              i l                                        Number: ROJ-V05, Revision 1 (Sheet 1 of 1)                                                          l lx SYSTEM: Nuclear Boiler -                                                                                                            l l'        COMPONENTS:                                                                                                                          )
l Valve Number              OM Cat.              Safety Class        Drawing Number                    Dwg. Coord.
V2-82A                      NC                            2                G-191167-                          B-10 V2-82B                      A/C                            2                0-191167                          B-10
[        V2-82C                      A/C                            2                G-191167                          B-10 V2-82D                      NC                            2.                G-191167                          B    .
V2-87A                      A/C                            2                G-191167                          B-13
        . V2-87B                      A/C                            2                G-191167                          B-13 V2-87C -                    A/C                            2-                G-191167                          B-13 V2-87D                      A/C                            2                G-191167                          B-13
[
These valves are the Main Steam Isolation Valve (MSIV) actuator air supply check valves. They have a safety function in the closed position ~ to ensure MSIV capability is maintained via the MSIV accumulators on a loss o(instrument air or nitrogen supply.
JUSTIFICATION:
p        Valves V2-82A thmugh D are located in the drywell and thus cannot be stroke close tested during                                      I l        nonnal power operations or Cold Shutdowns when the drywell is inerted.
          % ves V2-87A through D are located in the main steam tunnel which is inaccessible during power                                      )
:        operadons, thus, these valves cannot be stroke close tested during normal power operations.
i        These valves can only be stroke close tested via a leak type or non-intrusive test which would require isolating the instrument air or nitrogen to the MSIVs. Testing during Cold Shutdowns is impracticable due to the significant system and test equipment configurations required.                                                            j These valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.3 and 4.3.2.2(e), (h) of Part 10 of the Code.                                ,
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i Revision 19 .                                                                          Section 5 Page 121 of179
                              , .i.,      --        - - .
                                                                              . - ~ . .                                    -i~,,- . . . . .
 
                    - Verac:t Yenkea Nucle:r Power St tion                                      Inssrvics Testing Program L
REFUELING OUTAGE JUSTIFICATION L                                                      Number: ROJ-V06, Revision 3 (Sheet 1 of 2)
L                    SYSTEM: ControlRod Drive Hydraulic                                                                        -
L                                                        ..
l-                    COMPONENTS: (Typicalof 89 each)
Valve Number ..      . OM Cat.                    Safety Class Drawing Nurnber      Dwg. Coord.
l        .            CV-3-126                    B                                2    0-191170              C                      CV-3-127                    B                                2    G-191170              C-18 SO-3-120                    B                                2    G-191170              D-17 SO-3-121                    B                                2    0-191170              D                      SO-3-122                    B                                2    G-191170              C-18 SO-3-123                    B                                2    G-191170              C-17 V3-114                      C.                                2    G-191170              C-18 V3-115                    A/C-                                2    G-191170              B-16 V3-137 -                    C                                2    G-191170              B-17 i
Valves CV-3-126 & 127 are the Control Rod Drive (CRD) scram valves. These valves have a safety l
function in the open position to pass scram accumulator discharge to the control rod drives for a reactor scram.
Valves S0-3-120 & 123 are the manual control exhaust and insertion valves, respectively, for the CRD under piston area. They have a safety function in the closed position to prevent diversion of scram accumulator discliarge into the exhaust water header or the drive water header.
Valves S0-3-121 & 122 are the manual control exhaust and withdrawal valves, respectively, for the l                    CRD over piston area. These valves have a safety function in the closed position to ensure that scram      1 exhaust flow is properly directed to the discharge volume.
Valves V3-114 are the scram exhaust to the discharge volume check valves. These valves have a safety function in the open position to pass scram exhaust flow to the discharge volume. These valves have a safety function in the closed position to prevent the scram discharge volume from operating the drive in l
1 the event that the scram discharge volume pressure should exceed reactor pressure following a scram.
[                                                                                                            .
i:                    Valves V3-115 are the charging water to the CRD accumulator check valves. These valves have a j                  ' safety function in the closed position to prevent diversion of scram accumulator discharge into the l-                    charging header.
L i-                    Valves V3-137 are the Drive Water Supply Check Valves. These valves have a safety function in the
:                  . closed position to prevent a loss ofinventory to the drive water riser L
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l              Verment Yenks Nuclesr Power Statica                                      Inservice Testing Program I
l                                            BEFUELING OUTAGE JUSTIFICATION i-Number: ROJ-V06, Revision 3 (Sheet 2 of 2) l              JUSTIFICATION:
l              Exercising valves CV-3-126, CV-3-127, V3-114 and V3-137 during power operation would require                    ,
scramming the plant solely for testing purposes. Since scram insertion times are representative of valve        i operability and stroke times, testing will be performed in accordance with Technical Specifications 4.3.C.1 and 2. These sections require that all control rods be subjected to scram-time measurements on L              a refueling outage basis and that 50% of the control rods be measured for scram times every 16 to 32 L              weeks. An evaluation is required that provides reasonable assurance that proper control rod drive perfonnance is being maintained. These tests will adequately verify valve operability and stroke times.          !
              ' . Valves SO-3-120 through 123 are verified operable at least once a week in accordance with Technical Specifications 4.3.A.2 for each partially or fully withdrawn operable control rod. For a control rod that is fully inserted, the safety function of these valves is fulfilled. Stroke testing these valves while the l              control rod is fully inserted will not result in an increase in safety or quality. All control rods drives are verified operable in accordance with Technical Specifications 4.3.B.1 each Refueling Outage, thus                i stroke testing of these valves for control rods that remained fully inserted throughout the operating            l
[              cycle will occur each Refueling Outage. This alternate test frequency is consistent with NUREG 1482,            )
l              Appendix A, NRC Staff Position 7 " Testing Individual Scram Valves For Control Rods in Boiling                  i Water Reactors."                                                                                                !
l Closure testing of V3-115 requires that the CRD pumps be stopped to depressurize the charging water              i
              . header. 'Iherefore the accumulator pressure decay test (OP 4111) will be performed during refueling
;              outages. 'Ihis altemate test frequency is consistent with NUREG 1482, Appendix A, NRC Staff l            ' Position 7 " Testing Individual Scram Valves For Control Rods in Boiling Water Reactors."
Closure testing of V3-114 requires a scram signal to be in and the scram discharge volume to be l              pressurized. This condition is beyond operating parameters as specified in Technical Specification 3.3.,
therefore testing can only be performed during a refueling outage when test conditions can be met.
These valves will be exercised as a minimum each Refueling Outage in accordance with Paragraphs                  !
l              4.2.1.2(e), (h) and 4.3.2.2(e), (h) of Part 10 of the Code.
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Verm:nt Ycnke3 Nucl22r Pswer Statica                                  Inservice Testing Pr: gram REFUELING OUTAGE JUSTIFICATION Number: ROJ-V07, Revision 2 (Sheet 1 of1)
SYSTEM: ControlRod Drive Hydraulic I
COMPONENTS:                                                                                            ,
l Valve Number        OM Cat.        . Safety Class      Drawing Number          Dwg. Coord.
V3-412A                  NC                  2                G-191170              E-12              ;
V3-412B                  NC                  2                0-191170              E-12 V3-413A                  NC                  2                G-191170              E-12              .
V3-413B                  A/C                2                G-191170              E-12              !
l These valves are the r: circulation pump seal purge supply check valves. They have a safety function in i the closed position to provide primary containment isolation.
JUSTIFICATION:
These valves can only be exercised closed via a leak type or non-intmsive test which would require      1 isolating the seal purge,to the recirculation pumps. To preclude adverse affects on seal life, the      l recirculation pumps would have to be secured. Testing during Cold Shutdowns is impracticable due to    j the significant system and test equipment configurations required.                                      l These valves will be exercised closed each Refueling Outage during leakage rate testing performed in    l accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of the Code.
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l Vcrmest Ycskee Nuct:cr P wer Stati::n                                  Inservice Testing Program i
l REFUELING OUTAGE JUSTIFICATION
['                                Number: ROJ-V08, Revision 2 (Sheet 1 of1)
SL9 TEM: StandbyLiquidControl COMPONFEIE;:.
Valve Number          OM Cat.          Safety Class        Drawing Number              Dwg. Coord.
V11-16                    C                  1                  G-191171                  H-03 Vll-17                    C                  1                  G-191171                  I-02 These valves are the Standby Liquid Control (SLC) injection line check valves. ney have a safety function in the open position to pass borated water into the reactor, and in the closed position to provide primary containment isolation.-
JUSTIFICATION:
: Exercising these valves open during power operation would require injecting borated water into the reactor coolant system. This would create a reactivity excursion and potential for reactor trip. Injection of demineralized water would require removing the SLC system from service to clean the borated solution from the piping and replacing the explosive actuated valves.
Full-stroke closed testing requires the removal of at least one explosive actuated valve.
i nese valves will be full-stroke exercised open during refueling outages when the SLC system can be                  '
tested without creating a reactivity excursion.
These valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.3.2.2(e), (h) of Part 10 of the Code.
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Verm::t Ycnkee Nuclear Pcwer Stati n                            Inservies Testing Pragram REFUELING OUTAGE JUSTIFICATION L                          Number: ROJ-V09, Revision 0 (Sheet 1 of 1)                                        t L
i THIS REFUELING OUTAGE JUSTIFICATION WAS WITHDRAWN IN REVISION 18 OF THE IST PROGRAM.                                                                                          ,
This ROJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
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il
                                                                                                    -i Term::t Ycnkee Nuclear P wer St-tin'-                            Inservice Test +ng i Program REFUELING OUTAGE JUSTIFICATION                                        j Number: ROJ-V10, Revision 1(Sheet 1 of 1)                              !
1 i
THIS REFUELING OUTAGE JUSTIFICATION WNi WITHDRAWN IN REVISION 16 OF THEIST PROGRAM.                                                                                    !
This ROJ nmnber is being maintained for traceability to the Third Interval IST Program Submittal SER's.
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l  Verm:nt Ycnkee Nuclear Pcwer St: tion                                    Inservice Testing Program I
I REFUELING OUTAGE JUSTIFICATION l
l                              Number: ROJ-Vil, Revision 3 (Sheet 1 of1) l  SYSTEM: Neutron Monitoring System COMPONENTS:
Valve Number        OM Cat.        Safety Class            Drawing Number          Dwg. Coord.
V7-1                    A/C                    2              G-191175 Sh 2                    D-08 This valve is one of two Neutron Monitoring System (NMS) Tip Purge primary containment isolation valves. This valve, in conjunction with SOV-7-107, has a safety function in the closed position to provide primary containment isolation.
JUSTIFICATION:
{
This valve can only be tested via a leak type or non-intrusive test that requires securing of the nitrogen purge to the NMS Tip system. The nitrogen purge is required during operation and Cold Shutdown to prevent condensation and corrosion in the NMS Tip system.
This valve will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of the Code.
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l  Vcrmont Yankee Nuclear Power Station                                    Inservice Testing Program l
l                                REFUELING OUTAGE JUSTIFICATION l                                Number: ROJ-V12, Revision 1 (Sheet 1 of 1)
SYSTEM: Control Rod Drive Hydraulic COMPONENTS:
Valve Number        OM Cat.        Safety Class          Drawing Number        Dwg. Coord.
l V3-162A                  NC                  2                  G-191170              A-09 V3-162B                  NC                  2                  0-191170              A-01 1
These valves are the Control Rod Drive (CRD) scram discharge volume vent check valves. They have        i a safety function in the closed position to isolate the scram discharge volume during a scram condition, thereby preventing reactor coolant inventory loss.
JUSTIFICATION:
These valves can only be exercised closed via a leak type or non-intrusive test which would require removing the CRD system from service. Testing during Cold Shutdowns is impracticable due to the significant system and test equipment configurations required.
These valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.3 and 4.3.2.2(e), (h) of Part 10 of the Cod e.                          )
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Vcrm::t Yenice Nucirr Pcw:r St: tina                            Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V13, Revision 1 (Sheet 1 of1)
THIS REFUELING OUTAGE JUSTIFICATION WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.
This ROJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
i s
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l Vermont Yankee Nuclear Power Station -                                                        Inservice Testing Program
                                      ' REFUELING OUTAGE JUSTIFICATION Number: ROJ-V14, Revision 2 (Sheet 1 of 2)
SYSTEM: Service Water i
COMPONENTS:                                                                                                                      l
            . Valve Number      OM Cat.                    Safety Class                    Drawing Number        Dwg. Coord.            ,
V70-1A                    C-                                3                        G-191159 Sh 1          C              I V70-1B                    C                                3                        G-191159 Sh 1          B-02 V70-lC                    C                              -3                        G-191159 Sh 1 -        K-02 V70-1D -                  C                                3                        G-191159 Sh 1          J-02 These valves are the station setvice water pump discharge check valves. They have a safety function m the open position to provide cooling water to systems and equipment required to operate under accident conditions and to provide an inexhaustible supply of water for standby coolant system operation. They have a function in the closed position to pmvent the diversion of cooling water through an idle station Service Water pump.
JUSTIFICATION:              ,
The maximum required accident condition flow of 6,149 gpm, (Calc. VYC-1279, Rev,0; Case 8,
        " Discharge to condenser discharge block with low system resistance and LNP"), is not achievable with the current service water system configuration. The maximum required accident condition flow is based on a single pump operating near run-out conditions due to a postulated mpture of non-seismic, non-isolated portions of the service water system concurrent with an accident. The station service water pumps do not have installed instrumentation that permits determination ofindividual flow rates for these check valves. It is not practical or possible, using maximum required accident condition flow, to verify the open position of these valves during normal operation, cold shutdown, or refueling outages. The check valves can be verified to be full open during these refueling outage tests using nonintrusive techniques. These check valves have, on a one-time basis, been verified to 4
be in their fu!! open position during normal operation using one .non-intrusive technique (radiography). The calculated flows recorded during this verification ranged between approximately 1,800 - 3,000 gpm. Thus there is reasonable assurance that these check valves are in a full open position at flows much less than the maximum required accident flow of 6,149 gpm. -
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              ,,          - ~ ,          ~.              n -,                          +                          -              a ,, --
 
Vermant Yankee Nuclear Power St2 tion                                  Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V14, Revision 2 (Sheet 2 of 2)
JUSTIFICATION (Continuedh It is impractical to verify these valves in the open position on a quarterly basis or during cold shutdown due to equipment setup, potential RT contractot coordination, and, depending on the NIT technique, equipment exposure / access considerations. The NRC has indicated in a public workshop response that "Section 4.1.4 of NUREG-1482 states that the need to set up test equipment is adequate justification to defer backflow testing of check valves to a refueling outage frequency.
Although not stated in NUREG-1482, this guidance could be applied to the use of NIT for forward flow testing of check valves as well." These valves will be verified to be in their full open position during refuel outages using nonintrusive technology.
          - It is not possible to reverse flow test these check valves on a quarterly basis or during cold shutdown 1
due to the need to secure service water pumps. Depending on seasonal cooling load requirements, all four service water pumps may be operating during power operation, and in some cases, during cold shutdown. The reverse flow test currently involves running one pump at a reference condition during refuel outages and taking credit for the adjacent idle pump check valve closure based on the running pump being capable of- meeting the reference condition and acceptance criteria.
Nonintrusive techniques niay also be used to verify valve closure in lieu of pump performance test credit.
These valves will be verified to be in the full open position using nonintrusive techniques. Full stroke exercising closed will be verified by using reverse flow during curve performance testing or nonintrusive techniques in accordance with OMa-1988, Part 10, Paragraph 4.3.2.2(e) during each refueling outage. Partial forward flow credit will continue to be taken during the quarterly pump surveillance test in accordance with OMa-1988, Part 10, Paragraph 4.3.2.2(b).
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Vermrst Yc kee Nccle:r Pcwer St:tia                                  Itservica Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V15, Revision 1 (Sheet 1 of1)
SYSTEM: Nuclear Boiler Vessel Instrumentation
      .G. OMPONENTS:
                                                                                                          ~
Valve Number        OM Cat.        Safety Class        Drawing Number          Dwg. Coord.
V-2-3-430A              NC                2              G-191267 Sh 2                    C-09 V-2-3-430B              A/C                2              G-191267 Sh 2                    E-09 V-2-3-432A              NC                2              G-191267 Sh 2                    C-10 V-2-3-432B              A/C                2              G-191267 Sh 2                    E-10 V-2-3-433A              A/C                2              G-191267 Sh 2                    F-09 V-2-3-433B              A/C                2              G-191267 Sh 2                    H-09 V-2-3-435A              NC                2              G-191267 Sh 2                    F-10 V-2-3-435B              A/C                2              G-191267 Sh 2                    H-10 These valves are the reactor vessel instrumentation reference leg back fill inlet check valves. These valves are required to close in order to prevent the reference legs from emptying in the event of a break in the non-safety related portion of the back-fill system and perform a containment isolation function.
JUSTIFICATION:
These valves cannot be exercised during power operations or during cold shutdowns since shutting these valves would isolate filling water to the reference leg lines for reactor vessel pressure and level instrumentation. The function of the reference leg backfill system is to ensure that the reactor water level reference leg fluid does not become saturated with non-condensable gases. Full closure of these valves is verified during local leakage rate tests when the test boundary is drained and vented which could introduce non-condensable gases to the reference legs.
      'Ihese valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of the Code.
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;    Vcrm:st Yankse Nucl:ar P wsr Station                                  Inservice Testing Program i
REFUELING OUTAGE JUSTIFICATION
!'                                  Number: ns V16, Revision 1(Sheet 1 of1)
SYSTEM: Service Water COMPONENTS:
Valve Number        OM Cat.          Safety Class        Drawing Number          Dwg. Coord.
V70-13A                      B                3              G-191159 Sh 1              J-07 V70-13B                      B                3-            G-191159 Sh 1              B-07
  ~
V70-2A                      B                3              G-191159 Sh 1              C-03
  , ' 70-2B B                3              G-191159 Sh 1              B-03 70-2C                    B                3              G-191159 Sh 1              J-03
    ' '70-2D                    B                3              G-191159 Sh 1              J-03 These valves are the Service Water System Header Supply Isolation Valves. The safety functon of these valves is to close in order to isolate the upstream portions of the Service Water System when transferring to the Altemate Cooling mode of operation.
l E!STIFICATION:                ,
l    It is impracticable to full or part-stroke close exercise these valves on a quarterly basis or during cold l    shutdowns. Closure of these valves could interrupt cooling flow to their respective trains of the Reactor Building Closed Cooling Water system heat exchangers (E-8-1A or E-8-1B), the RHR heat exchangers (E14-1 A or E14-1B) and the emergency diesel generator lube oil and jacket w~ater coolers.
!    Interruption of flow to these components could cause damage to equipment. These valves will be full-l    stroke exercised closed during refueling outages in accordance with Paragraphs 4.2.1.2 (e) and (h) of I
l' art 10 of the Code when cooling flow to these components can be isolated.
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i Vcrm=t Ycekee N=lrr P wer Station                                    Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V17, Revision 1 (Sheet 1 of1)
SYSTEM: Service Water COMPONENTS:
Valve Number        OM Cat.          Safety Class      Drawing Number          Dwg. Coord.
V70-15A                    B                3              G-191159 Sh 1              J-08 V70-15B                    B                3              G-191159 Sh 1              B-08 These valves are the Service Water System Header Supply Isolation Valves. The safety function of these valves is to close to eliminate Alternate Cooling Flow from bypassing the cooling tower while the Service Water System is in the Altemate Cooling mode of operation.
JUSTIFICATION:
It is impracticable to full or part-stroke exercise these valves on a quarterly basis or during cold shutdowns. Closure of either of these valves could interrupt cooling flow in their respective trains to the Reactor Building Closed Cooling Water system heat exchangers (E-8-1A or E-8-1B). The RBCCW systems provide cooling flow to components such as the RHR pump coolers, the CRD pump coolers, and the spent fuel pool heat exchangers (E9-1 A and E9-1B) which are required for the safe operation of the plant at power and cold shutdown periods. These valves shall be full-stroke exercised during refueling outages These valves will be full-stroke exercised closed in accordance with Paragraph 4.2.1.2(e), (h) of Part 10 of the Code during each refueling outage when these cooling loads can be safely isolated.
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o                                                                                                                        .
L                                                    .
Verment Ycakee N cirr Pswer Station                                    Inservice Testing Program                ;
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REFUELING OUTAGE JUSTIFICATION
;.                                      Number: ROJ-V18, Revision 1 (Sheet 1 of 1)
SYSTEM: Service Water COMPONENTS:
ValveNumber        OM Cat.          Safety Class      . Drawing Number        Dwg. Coord.
V70-187A                    B                3              G-191159 Sh 1            J-06 V70-187B                    B                3-            G-191159 Sh 1            B-06
        ' These valves are the Service Water Pump Gland Seal Supply Isolation Valves. The safety function of these valves is to close in order to provide a backup leakage barrier for the Service Water Supply Header Isolation Valves (V70-13A and V70-13B) while the Service Water System is in the Altemate Cooling mode ofoperation.
JUSTIFICATION:
        . It is impracticable to full or part-stroke exercise these valves on a quarterly basis or during cold
        ' shutdowns. The closure of either one of these valves will interrupt cooling flow to two of the Service Water Pump gland seals. Operation of the service water pumps without gland seal flow is not recommended. The Service Water Pumps are required to be operable during power operation and cold shutdowns for cooling to other loads.
These valves will be full-stroke exercised closed in accordance with Paragraph 4.2.1.2(e), (h) of Part 10 of the Code during each refueling outage when one loop of service water (two service water pumps) can be secured.
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Vermont Yankee Nuclear Power Station                              Inservice Testing Program REFUELING OUTAGE JUSTIFICATION                                              I l
Number: ROJ-V19, Revision 0 (Sheet 1 of 1)
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THIS REFUELING OUTAGE JUSTIFICATION WAS WITHDRAWN FROM THE IST PROGRAM.
This ROJ number is being maintained for traceability to the Third Interval IST Program Submittal
  . SER's.                                                                                              ;
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Verm:nt Yankee Nuclear Power Station                                Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V20, Revision 0 (Sheet 1 of 1) l THIS REFUELING OUTAGE JUSTIFICATION WAS WITHDRAWN FROM THE IST PROGRAM. -
This ROJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
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L Verm=t Yerksa Nuclear Pcwsr Station                                  Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V21, Revision 2 (Sheet 1 of1)
SYSTEM: Service Water I
COMPONENTS:
Valve Number        OM Cat.          Safety Class      Drawing Number          Dwg. Coord.
V70-16A                    B                3              G-191159 Sh 2              D-07              i V70-16B                    B                3              G-191159 Sh I              C-09 V70-184                    B                3              G-191159 Sh 1              C-09 V70-16A and V70-16B are in the RHRSW pump suction line from the cooling tower. The safety function of these is to open to supply a suction source to the RHRSW pumps from the cooling tower when the service water system is aligned for the altemate cooling mode of operation. V70-184 is used to vent piping between V70-16A and V70-16B when altemate cooling is placed in service.
JUSTIFICATION:
It is impracticable to ful,1 or part-stroke exercise these valves on a quarterly basis or during cold    i shutdowns. The suction line from the cooling towers to valve V70-16B is chemically treated to control the growth of microbiologically influenced corrosion (MIC). The opening of these valves could dilute      '
the chemical mixture in this line. Dilution of the chemical mixture in this line would reduce its effectiveness.
These valves will be full-stroke exercised closed in accordance with Paragraph 4.2.1.2(e), (b) of Part 10 of the Code during each refueling basis when the line can be retreated with chemicals.
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Vcrmont Yankee Nuclear Power Station                                    Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V22, Revision 1 (Sheet 1 of1)                                      ;
i SYSTEM: Instrument Air System COMPONENTS:
1 Valve Number        OM Cat.          Safety Class        Drawing Number            Dwg. Coord.
V72-89B                      NC                2              G-191160 Sh 3                K-14              ;
V72-89C                      NC                2              G-191160 Sh 3                K-15              l These valves are the Instrument Air to the Drywell Containment Isolation Valves. These valves have a i
safety function to close to prevent the release of fission products from the drywell to the reactor            I building in the event of an accident.                                                                          I JUSTIFICATION:
It is not practical to verify the closure function of these valves on a quarterly or cold shutdown basis.
The only means to verify closure of these valves is to perform a leakage type test or to utilize a non-l intrusive testing method. ,                                                                                    !
In order to assure closure of these valves to perform a leakage rate test or non-intmsive test, it would be necessary to isolate instrument air to the main steam isolation valves inside containment. Additionally, in order to perform a leakage type test, it would be necessary to open system drains and vents.                l Isolation of this line could result in closure of the air operated main steam isolation valves and subsequent reactor scram.                                                                                      l These valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of the Code.
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v Vermont Yankee Nuclear Power Station                                      Inservice Testing Program REFUELING OUTAGE JUSTIFICATION                                              ;
Number: ROJ-V23, Revision 1 (Sheet 1 of 1)                                  i i
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SYSTEM: Standby Fuel Pool Cooling                                                                            i COMPONENTS:
Valve Number          OM Cat.          Safety Class        Drawing Number          Dwg. Coord.          ,
Vl9-224                      C                3              G-191173 Sh 1                1-12 i
Vl9-224 is normally open during plant operation to allow cooling flow to pass to the fuel storage pool.
The safety function of this valve is to close to provide isolation capability of the non-seismic nonnal fuel pool cooling system from the standby fuel pool cooling system.
JUSTIFICATION:                                                                                              l It is not practical to full-stroke exercise this valve to the closed position on a quarterly basis or during cold shutdowns. This valve is normally open to allow cooling flow from the normal fuel pool cooling pumps to the fuel storage pool. Additionally this valve is located directly upstream of check valve          l Vl9-18. The only practical means to verify the closure of this valve is to pressurize the volume between Vl9-223, Vl9-53 and Vl9-46 and V19-224 utilizing a differential pressure or leakage type test or by performing a non-intrusive test when nonnal fuel pool cooling system flow through the demineralizer is isolated. The use of non-intrusive techniques to verify closure on a quarterly basis or      ,
during cold shutdowns is not practical. These valves are not located in an easily accessible location and    i scaffolding is required to setup the necessary equipment.
I NUREG 1482, subsection 4.1.4, states "The NRC has determined that the need to setup test equipment l
is adequatejustification to defer backflow testing of a check valve until a refueling outage".              l The closure function of this valve will be verified during refueling outages by utilizing a differential pressure or leakage type test or by performing a non-intrusive test in accordance with Paragraph 4.3.2.2(e), (h) of Part 10 of the Code, f
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Vcrm: t Yc:kee Nucle r Pcwer Stati:2                                      Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V24, Revision 2 (Page 1 of 1)
SYSTEM: Instrument Air System COMPONENTS:
I Valve Number        OM Cat.          Safety Class        Drawing Number            Dwg. Coord.        j V70-113                    A/C                2              G-191159 Sh 3              K-08            l l
This valve is the RBCCW system drywell supply line containment isolation valve. This valve has a            i safety function to close to prevent the release of fission products from the drywell to the reactor        i building in the event of an accident.
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JUSTIFICATION:
It is not practical to verify the closure function of this valve on a quarterly or cold shutdown basis. The only means to verify closure of this valve is to perform a leakage type test or to utilize a non-intrusive  l testing method.
In order to assure closure 'of this valve, it is necessary to perform a leakage rate test or non-intrusive test. Leakage type testing would require isolation of the RBCCW system supply to the drywell and opening of system drains and vents. Isolation of this line would result in a loss of cooling flow to        1 important plant equipment such as the recirculation pumps, possibly resulting in their failure.
l This valve will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of the Code.
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L Verm::nt Ycnkee Nuclear Pcwer Station                                  Inservice Testing Program I
REFUELING OUTAGE JUSTIFICATION Number: ROJ-V25, Revision 2 (Sheet 1 of1)
SYSTEM: High Pressure Coolant Injection                                                                    l COMPONENTS:
Valve Number -        OM Cat.        Safety Class        Drawing Number            Dwg. Coord.
V23-56                      C                2              G-191169 Sh 1              J-05 V23-65                    A/C                2              G-191169 Sh 1              1-03 SSC-23-12                  A/C                2              0-191169 Sh 1              I-03 V23-56 is the HPCI Turbine Drain Condensate Exhaust Line Containment Isolation Valve. This valve is normally closed during plant operation. This valve has a safety function to open to pass turbine exhaust condensate to the torus. Additionally, this valve has a safety function to close for containment isolation. The Appendix J Program exempts this valve from leak rate testing.
V23-65 and SSC-23-12 are the HPCI Turbine Steam Exhaust Line Containment Isolation Valves.
These valves are normally closed during plant operation. These valves have a safety function to open to pass turbine exhaust stqam to the torus. Additionally, these valves have a safety function to close for containment isolation and are included in the Appendix J Program for leak rate testing. EDCR 98-402        ,
modified the vacuum breaker arrangement to the extent that these valves are now exposed to the torus      I airspace, thus requiring testing per Appendix J.                                                          l JUSTIFICATION:
1 It is not practical to verify the closure function of these valves on a quarterly or cold shutdown basis.
During normal operation the HPCI steam and condensate exhaust lines are required to be available to        j support operation of the HPCI turbine. The only practical means to verify the closure of V23-56 is to      i pressurize the volume between SSC-23-13 and V23-56 utilizing a differential pressure or leakage type test or by performing a non-intrusive test. The only practical means to verify the closure of V23-65 is to pressurize the volume between SSC-23-12 and V23-65 utilizing a leakage type test during Appendix J        l testing. The only practical means to verify the closure of SSC-23-12 is to pressurize the volume between SSC-23-12 and the torus utilizing a leakage type test during Appendix J testing. Additionally, the use of non-intrusive techniques or leak rate testing to verify closure on a quarterly basis or during cold shutdowns is not practical. These valves are not located in an easily accessible location and scaffolding is required to setup the necessary equipment.
NUREG 1482, subsection 4.1.4, states "The NRC has determined that the neel to setup test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage".
The closure function of these valves will be verified during refueling outages by utilizing a differential pressure or leakage type test or, for V23-56, by performing a non-intrusive test in accordance with l Paragraph 4.3.2.2(e), (h) of Part 10 of the Code.
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Verm:nt Ycnkee Nuclear Pcwer St ti:n                                    Inservice Testing Program REITTELING OUTAGE JUSTIFICATION Number: ROJ-V26, Revision 2 (Sheet 1 of 1)
SYSTEM: Reactor Core Isolation Cooling COMPONENTS:
Valve Number        OM Cat.          Safety Clast.      Drawing Number          Dwg. Coord.
V13-38                        C                2              0-191174 Sh 1              K-11 V13-50                      A/C                2              G-191174 Sh 1              K-08 SSC-13-9                    A/C                2              G-191174 Sh 1              K-08 V13-38 is the RCIC Turbine Vacuum Pump Exhaust Line Containment Isolation Valve. This valve is normally closed during plant operation. This valve has a safety function to open to pass vacuum pump discharge to the torus. Additionally, this valve has a safety function to clo< ; for containment isolation.
The Appendix J Program exempts this valve from leak rate testing.
V13-50 and SSC-13-9 are the RCIC Turbine Steam Exhaust Line Containment Isolation Valves.
These valves are normally closed during plant operation. 'Ihese valves have a safety function to open to pass turbine exhaust steam to the torus. Additionally, these valves have a safety function to close for containment isolation and are included in the Appendix J Program for leak rate testing. EDCR 98-402 modified the vacuum breaker arrangement to the extent that these valves are now exposed to the torus airspace, thus requiring testing per Appendix J.
JUSTIFICATION:
It is not practical to verify the closure function of these valves on a quarterly or cold shutdown basis.
During normal operation the RCIC steam and vacuum pump exhaust lines are required to be available to support operation of the RCIC turbine. The only practical means to verify the closure of V13-38 is to pressurize the volume between SSC-13-10 and V13-38 utilizing a differential pressure or leakage type test or by performing a non-intrusive test. The only practical means to verify the closure of V13-50 is to pressurize the volume between SSC-13-9 and V13-50 utilizing a leakage type test during Appendix J testing. The only practical means to verify the closure of SSC-13-9 is to pressurize the volume between SSC-13-9 and the torus utilizing a leakage type test during Appendix J testing. Additionally, the use of non-intrusive techniques' or leak rate testing to verify closure on a quarterly basis or during cold shutdowns is not practical. These valves are not located in an easily accessible location and scaffolding is required to setup the necessary equipment.
l NUREG 1482, subsection 4.1.4, states, "The NRC has determined that the need to setup test equipment is adequatejustification to defer backflow testing of a check valve until a refueling outage".
The closure function of these valves will be verified during refueling outages by utilizing a differential pressure or leakage type test or, for V13-38, by performing a non-intrusive test in accordance with Paragraph 4.3.2.2(e), (h) of Part 10 of the Code.
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Vcrm::t Yorkee N clarr Pcwer Stati:n                                    Inservice Testing Pr: gram REFUELING OUTAGE JUSTIFICATION Number: ROJ-V27, Revision 0 (Sheet 1 of 1)
SYSTEM: Nuclear Boiler COMPONENTS:
Valve Number          OM Cat.          Safety Class        Drawing Number          Dwg. Coord.
SR-2-14A                    C              NNS                G-191167                  M-12 SR-2-14B                    C              NNS                G-191167                  M-12 SR-2-14C                    C              NNS                G-191167                  M-12          i SR-2-14D                    C              NNS                G-191167                  M-12 SR-2-14A through 14D are 3 inch Main Steam Relief Valve (MSRV) exhaust line vacuum breakers.              '
These valves are normally closed during plant operation. These valves have a safety function to close to direct MSRV discharge flow to the suppression pool in the event of a MSRV actuation.                      !
l JUSTIFICATION:                                                                                            !
It is not practical to verify the closure function of these valves on a quarterly or cold shutdown basis.
These valves are located in the drywell and are not accessible during normal power operations or Cold Shutdowns when the drywell is inerted. These valves can only be tested when the drywell is accessible and the reactor vessel is depressurized.
    .These valves will be manually exercised closed each refuel outage in accordance with Paragraph 4.3.2.2(e), (h) of Part 10 of the Code.
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Verme:t Yankee Nucl:cr Pcwcr St:tien                                              Inservice Testing Program REFUELING OUTAGE JUSTIFICATION t
Number: ROJ-V28, Revision 1 (Sheet 1 of 2)
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SYSTEM: Fuel Pool Cooling & Cleanup' .
Service Water                                                                                              J COMPONENTS:
Valve Number        . OM Cat.              Safety Class        Drawing Number          Dwg. Coord.
V70-244A                      C                    3                  G-191173 Sh 2                B-10 V70-244B                      C                    3                . G-191173 Sh 2                  B-10 V70-281A                      C                    3                  G-191159 Sh 1                J-09 :
V70-281B                      C                    3                  G-191159 Sh 1                B-09 V70-281C ~                    C                    3                  G-191159 Sh 1                  J-09 V70-281D                      C                    3                  G-191159 Sh 1                C-09 V70-51IB                      C                    3                  G-191159 Sh 1                H-12 V70-511C                      C                    3                  G-191159 Sh 1                H-12 V70-252B -                    C                    3                  G-191159 Sh 2                G            ;
V70-252C -                  -C                      3                  G-191159 Sh 2                0-05
      'Ihese 2" swing check valves are the Service Water System vacuum breaker check valves.
These valves have a safety function in the open direction to eliminate vacuum in the service water system that is postulated to occur following a station electrical blackout or an Appendix R postulated fire. Eliminating the vacuum minimizes the potential for system water hammer upon service water                          i Pump restart.                                                                                                            !
These vacuum breaker check valves have a safety function in the closed direction to maintain the                        !
service water system pressure boundary.
JUSTIFICATION:
Thisjustification concerns both the open and the closed position.
Open Position - The valves cannot be full flow tested in the open position based on thc current system configuration, lack of instrumentation and the absence of flow calculations establishing design flow
,    , requirements. A mechanical exerciser cannot be used to measure required full stroke opening force p'    based on interference resulting from the series pair spatial relationship. Disassembly to verify forward
!~    flow exercising is possible during refueling outages when the associated service water subsystem is made available for maintenance as part of a scheduled LCO. It is impractical to disassemble these valves on a quarterly basis or during cold shutdowns. These valves are located in the overhead and
    ~ require installation' of scaffolding to perform disassembly and inspection.
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Vermont Ycnkee Nuclear Power Station                                    Inservice Testing Program l
REFUELBG OUTAGE JUSTIFICATION Number: ROJ-V28, Revision 1 (Sheet 2 of 2)
J'USTIFICATION (Continuedh Closed Position - During normal operation these valves are closed and form the necessary service water system pressure boundary. Based on the series pair configuration, any leakage past both valves l    would be readily evident by noticing water flowing past the seat of the outboard check valve which is open to atmosphere. Stroke close testing of the individual check valves is possible however; installation of scaffolding is required to gain access to the test connections. The use of jumper hoses is also required to perform testing on the outboard valve. Drain hoses are required to test the inboard valves.
In addition, the test involves a hardship such that manual operator actions would be necessary to restore l    the system if the postulated events occurred while the test was in progress. It is impractical to test these valves on a quarterly basis or during cold shutdowns. Per NUREG 1482, Section 4.1.4, the NRC has determined that the need to set up test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.
Alternate Testing Disassembly and inspection will be used to satisfy forward and reverse flow testing. Based on the large grouping of valve pairs and the alternating refueling outage basis for scheduling individual service water subsystem LCO maintenance actions, disassemblies will be performed using a sampling program l    during refueling outages. Specifically, three pairs of valves (6 valves total) will be disassembled, inspected, and full stroke exercised during one refueling outage with the other two pairs (4 valves total) j    being disassembled, inspected, and full stroke exercised the following refueling outage. During the          .
:    disassembly, the disk will be manually exercised and the intemals of the valve will be verified to be        !
structurally sound (no loose or corroded parts). If a disassembled valve is not capable of being full stroke exercised or there is binding or failure of a valve's intemals, all other vacuum breaker check valves in both groups will be disassembled, inspected, and manually full stroke exercised during the        I l    same refueling outage. Use of non-intrusive techniques was considered for this application and determined impractical given the valve design and system application. Partial valve stroking with flow      l is not practical following reassembly. Quality disassembly, reassembly and inspection techniques provide sufficient confidence that the valves will perform their intended function when challenged.
Oma-1998, Part 10, Paragraph 4.3.2.4(c) permits disassembly every refueling , outage to verify operability of check valves. NUREG 1482 and Generic Letter 89-04, Position 2 permit the use of a sample disassembly and inspection plan when the licensee determines it is burdensome to disassemble and inspect all applicable valves each refueling outage.
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Verm=t Yc kee Nucl:cr Pcwer Station                                                            Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V29, Revision 0 (Sheet 1 of1)
SYSTEM: Residual Heat Removal Nuclear Boiler COMPONENTS:
Valve Number        OM Cat.          Safety Class        Drawing Number                                                      Dwg. Coord.
V10-18A                    A/C                2                    G-191172                                                          F-08 V10-18A5                  A/C                2                    G-191172                                                          F-08 V2-39A                    A/C                2                    G-191167                                                          L-04 V2-74A                    A/C                2                    0-191167                                                          D-10 V10-18A has a safety function to open to provide overpressure protection for Penetration X-12. V10-18A and associated piping are configured like an typical equalizing line across V10-18. V10-18A also has a safety function to close as one of the inboard containment isolation valves for Penetration X-12.
(Ref. EDCR# 96-416).
V10-18A5 has a safety function to open to provide V10-18 bonnet pressure locking protection. V10-18A5 also has a safety function to close as one of the inboard containment isolation valves for Penetration X-12. (Ref. EDCR# 96-416, ECN-1).
V2-39A has a safety function to open to provide overpressure protection for Penetration X-41. V2-39A and associated piping are configured like an typical equalizing line across FCV-2-39. V2-39A is oriented to open anytime pressure on the penetration side of FCV-2-39 is greater than reactor side of FCV-2-39. V2-39A also has a safety function to close for primary containment isolation of penetration X-41. (Ref. EDCR# 96-416).
V2-74A has a safety function to open to provide overpressure protection for Penetration X-8. V2-74A and associated piping are configured like an typical equalizing line across V2-74. V2-74A is oriented to open anytime pressure on the penetration side of V2-74 is greater than reactor side of V2-74. V2-74A also has a safety function to close for primary containment isolation of penetration X-8. (Ref. EDCR#
96-416).
JUSTIFICATION:
It is not practical to full or part-stroke exercise these valves on a quarterly basis or during cold shutdowns. These valves are located inside the drywell and are not accessible during power operation.
The stroke open and close function of these valves will be verified each refueling outage in accordance with Paragraph 4.3.2.2(e), (h) of Part 10 of the Code.
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Vermont Yankee Nuclear Power Station                            Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V30, Revision 1 (Sheet 1 of 1)
THIS REFUELING OUTAGE JUSTIFICATION WAS WITHDRAWN IN REVISION 18B OF THEIST PROGRAM.
This ROJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
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l Revision 19                                                          Section 5 Page 149 of179
 
i Verm=t Yerkee Nuclear P wer St:ti:n                                    Icservice Tcsting Prcgram REFUELING OUTAGE JUSTIFICATION Number: ROJ-V31, Revision 0 (Sheet 1 of 2)
SYSTEM: Resdinal Heat Removal, Reactor Water Cleanup, Reactor Core Isolation Cooling and High Pressure CoolantInjection COMPONENTS:
Valve Number        OM Cat.          Safety Class        Drawing Number          Dwg. Coord.
V10-19A                    C                  2                  G-191172              L-05 V10-19B                    C                  2                  G-191172              L-12 V10-19C                    C                  2                  G-191172              J-05 V10-19D                    C                  2                  G-191172              J-12 V12-28A                    C                  3              G-191178 Sh 1            D-08 V12-28B                    C                  3              G-191178 Sh 1            G-08 V12-62                    C                  2              G-191178 Sh 1            B-05            i V12-62A                    C                  3              G-191178 Sh 1            B-05 V13-29                    C                  2              G-191174 Sh 1            J-10 V13-40                    C                  2.              G-191174 Sh 1            N-11 V13-817                    C                  2              G-191174 Sh 1            K-07 V13-818                    C                2              G-191174 Sh 1            K-07            l SSC-23-13                  C                2              G-191169 Sh 1            J-04 V23-56                      C                2              G-191169 Sh 1            J-05 V23-61                      C                2              G-191169 Sh 1            L-06            I V23-62                      C                2              G-191169 Sh 1            J-10 V23-842                    C                2              G-191169 Sh 1            I-02 V23-843                    C                2              G-191169 Sh 1            I-03 V78-2                      C                3              G-191162 Sh 2            E-02 Valves V10-19A through D are RHR pump. They have a safety function in the open position to pass          i RHR flow to the suppression pool for pump protection. They have a safety function in the close position to prevent backflow through an idle RHR pump.
Valves V12-28A and V12-28B are RWCU pump discharge check valves. They havp a safety function in the closed position to prevent reverse flow in the event of a HELB upstream of the RWCU pumps.
Valves V12-62 and V12-62A are RWCU flow to Feedwater system isolation check valves. They have a safety function in the closed position to prevent gross diversion of RCIC flow and prevent reverse
;  flowin the event of a HELB upstream.
i Valve V13-29 is RCIC pump miminum flow recin:ulation line check valve. It has a safety function in the closed position to provide primary containment isolation and a safety function in the open position t
to pass RCIC flow to the suppression pool for pump protection.
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Section 5 Page 150 of179 l
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i Vcrmat Yenkee Nuclesr Powcr St:tinn                                  Inservice Testing Program 4
REFUFLING OUTAGE JUSTIFICATION Number: ROJ-V31, Revision 0 (Sheet 2 of 2)
      ' Valve V13-40 is RCIC pump suction valve from the suppression pool. It has a safety function in the open position to pass flow from the suppression pool to the RCIC pump suction. This flow path is
      ; requied aAer the CST supply has been exh==W.
      ~ Valves V13-817 and V13-818 are RCIC turbine exhaust line vacuum breakers.'They have a ' safety function in the closed position to provide primary containment isolation and a safety function in the            i
        . open position to prevent water hammet on RCIC turbine exhaust line check SSC-13-9.
        . Valves SSC-23-13 and V23-56 are HPCI turbine exhaust drain check valves. They have a safety function in the closed position to provide primary containment isolation and a safety function in the open position to pass condensate in the HPCI turbine exhaust line drain pot to the suppression pool.
Valve V23-61 is HPCI pump suction valve from the suppression pool. It has a ' safety function in the open position to pass flow from the suppression pool to the HPCI pump suction. This flow path is        .
      . requied aAer the CST supply has been exhausted.
Valve V23-62 is HPCI pump miminum flow recirculation line check valve. It has the closed position to provide primary containment isolation and a safety function in the open position to pass HPCI flow to  .
the suppression pool for pump protection.
LValves V23-842 and V23-843 are HPCI turbine exhaust line vacuum breakers. They have a' safety                    i function in the closed position to provide primary containment isolation and a safety function in the            j L          open position to prevent water hammer on HPCI turbine exhaust line check SSC-23-12.                              j l          Valve V78-2 is the Diesel Fuel Oil Storage Tank fill line check valve. It has a safety function in the close position to prevent loss of Diesel Fuel Oil Storage Tank contents int he event of failure of the NNS fillline.
JUSTIFICATION:                                                                                                  I Valves V10-19A, V10-19B, V10-19C, V10-19D, V13-29, V13-40 SSC-23-13, V23-56, V23-61 and V23-62 cannot be verified to exercise full open during normal (power) operation due to the lack of              i instrumentation for positive test results.
Valves V12-62,V12-62A,-V13-817, V13-818, V23-842, V23-843 and V78-2 cannot be individually exercised closed during nonnal (power) operation because there are two check valves in series without I
test connections.
Valves V12-28A and V12-28B cannot be verified to exercise closed during normal (power) operation
{          due to the lack ofinstrumentation for positive test results.
e
;          Each of these valve will be disassembled and irspected each refueling outage in accordance with Paragraph 4.3.2.4(c) of the Par t10 of the Code.
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    ,                y-              w      y , -_,        . - - ____y                    ___,, , , . -          .,a ,
 
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Vermnt Ycnkee Nuclear Power Station                                    Inservice Testing Program      !
I REFUELING OUTAGE JUSTIFICATION                                            I l
Number: ROJ-V32, Revision 0 (Sheet 1 of 2)
SYSTEM: Service Water COMPONENTS:
Valve Number        OM Cat.          Safety Class      Drawing Number            Dwg. Coord.
V70-43A                    C                3              G-191159 Sh 1              J-12 V70-43B                    C                3              G-191159 Sh 1              B-12 These 8" swing check valves are the Service Water System loop header discharge check valves.
l These check valves have a safety function in the open direction to provide cooling water to various ECCS room area coolers during nonnal plant operation and to the standby emergency diesel generator      1 jacket water, lube oil and after coolers when the diesel generator is inservice.
These valves have a safety function in the closed direction to prevent reverse flow during the service water alternate cooling rnode of operation. When the service water system is operating in the alternate i cooling mode, these check valves close to ensure Residual Heat Removal Service Water (RHRSW) pump flow is directed to the RHR heat exchangers, ECCS area coolers and the standby emergency diesel generatorjacket water, lube oil and after coolers.
JUSTIFICATION:
Thisjustification concems both the open and closed position.
Open Position - The design required flow through these check valves is between 900 and 1050 gpm.
when the ECCS room coolers are inservice and the diesel generator is in operation. The maximum required accident condition flow, for example, assumes higher flows through the ECCS coolers with a postulated line break to NNS number 17 room cooler. This condition brings the required accident condition flow to approximately 1900 gpm. for the "A" SW loop. The "B" SW loop is similar however a lower flow is required since a break at the NNS number 9 room cooler has not been postulated. This information was obtained from calculation VYC-1279, " Service Water Hydraulic Analysis". The design flow inputs are listed in section 4.0 of the calculation. Case #6 was used to arrive at the maximum required accident flow for these check valves. Instrumentation is not installed to measure
;  total flow through these valves. The diesel generator branch (one of up to five branches) is the only l - parallel path instrumented with a flow element (reads in percent of flow). It is not practicable to i
simulate or obtain line break conditions to pass the maximum required accident condition flow through room cooler or diesel generator branches. It is impractical to forward flow exercise these valves with j  flow on a quarterly, cold shutdown or refueling frequency.
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Verment Yankee Nuclear Power Station                                      Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V32, Revision 0 (Sheet 2 of 2)
          . Closed Position - During normal plant operation these valves continuously pass flow to supply various ECCS room area coolers and to the standby emergency diesel generatorjacket water, lube oil and after coolers when the diesel generator is inservice. It is impractical to reverse flow exercise these valves on a quarterly or cold shutdown frequency due to the extent of components that must be declared inoperable to accomplish testing. Closure testing of these valves would require shutdown of the service water pumps in their individual trains or by isolating the required flow to various ECCS room area coolers and to the standby emergency diesel generator jacket water, lube oil and after coolers.
Additionally, although impractical, with no specific frequency being established, closure testing could be performed whenever the service water system is operated in the attemate cooling mode (ACS).
l Isolation of flow to the room coolers and the diesel generator permits the disk to travel to its seat by gravity. Disassembly and inspection or non-intrusive techniques would then be required to confirm that the valves are in the closed position.
Alternate Testing Partial flow testing of these valves is satisfied quarterly. Disassembly and inspection or use of non-intrusive techniques will be used to satisfy forward and reverse flow testing. Use of either method will be' performed using a sainpling program during refueling outages. Periodic disassembly is also required for verification of internal coating integrity and system cleaning per LER-89-017, corrective                l action #2. A sampling program is justified due to the extent of system isolation and drain down
                                                                                                                                  ]
required to perform check valve disassembly combined with the need to keep certain ECCS systems                        i and the diesel generators available during refueling outages. Regarding non-intrusive testing, NUREG                  i 1482 specifies that the extensive effort to set up test equipment and the adverse impact on system                    !
operation provides sufficientjustification to defer the test to a refueling outage. Specifically, one check            I valve is disassembled and inspected or non-intrusively tested every refuel outage with the other check                !
l          valve being disassembled and inspected or non-intrusively tested the following outage. During the l          disassembly, the internals of the valve will be verified to be structurally sound (no loose or corroded parts.) If the disassembled valve is not capable of being full stroke exercised or there is binding or L          failure of the valve intemals, the other valve will also be disassembled, inspected and manually L          exercised during the same refuel outage. Regarding non-intrusive testing, if problems are found with l          the sample valve that are determined to affect the operational readiness of the valve, the other valve l          must be tested using non-intrusive techniques during the same outage. Oma-1988, Pwt 10, Paragraph 4.3.2.4(c) permits disassembly every refueling outage to verify operability of check valus. NUREG 1482 and Generic Letter 89-04, Position 2 permit the use of a sample disassembly and m        ' spection plan          I when the licensee determines it is burdensome to disassemble and inspect all applicable valves each refueling outage. NUREG 1482,4.1.2 permits the use of non-intrusive techniques using a sampling
:          program.
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Vcrm:nt Ycnkee Nucb:r Pcwer Strti:n                                  Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V33, Revision 0 (Sheet 1 of 2)
SYSTEM: Reactor Core Isolation Cooling (RCIC) and High Pressure Coolant Injection (HPCI)
COMPONENTS:
Valve Number        OM Cat.        Safety Class        Drawing Number              Dwg. Coord.
V13-820                  A/C                2            G-191174 Sh 1                K-8              i V13-821                  A/C                2            G-191174 Sh 1                K-8 V23-845                  A/C                2            G-191169 Sh 1                  I-3 V23-846                  A/C                2            G-191169 Sh 1                  I-3 I
These nozzle type check valves are utilized as the RCIC/HPCI turbine exhaust line vacuum breakers to      ;
prevent water hammer.                                                                                      l
    - The water hammer phenomenon can result when steam in the exhaust piping condenses (collapses) and causes a rapid drop in pressure in the exhaust piping. As the pressure in the exhaust piping drops    !
below the pressure in the torus, water quickly is drawn up the exhaust piping and results in the water    I hammer event. The vacuum breakers are designed to introduce air into the exhaust piping when the exhaust piping pressure decreases below the suction side pressure of the vacuum breaker. The air
    . prevents a significant vacuum from developing and thus eliminates the conditions required to initiate a water hammer event.
l l
JUSTIFICATION:
l    Thisjustification concems both the open and closed position.
Open Position - Per calculation VYC-1790, accident air-flow through the vacuum breaker line is 3909 SCFH for RCIC and 18,817 SCFH for HPCI. Verifying the maximum accident condition required flow through these valves is not possible due to the large gas volume required and extremely high flow velocities through the 3/4" test connections. Providing an adequate downstream vent to pass accident l
condition flow also presents the potential for contaminating test personnel and the surrounding area. A reduced flow air test can demonstrate that the disk exercised to the full open position at less than accident flow as detected by non-intrusive acoustic technology. It is impractical to verify these valves l
in the open position on a quarterly basis or during cold shutdown due to the need to gain component access and to set-up non-intrusive test equipment. Performance of this test requires access to overhead areas,- routing of air hoses, and set-up of several non-intrusive signal-conditioning devices.
Additionally, the specific system must be removed from service to accomplish this testing. Section 4.1.2 of NUREG-1482 permits the use of non-intrusive testing and acknowledges that relief is not l  required except as would be necessary for the testing frequency if the test interval extends beyond each refueling outage as allowed by OM-10. Partial stroke open credit can be verified quarterly by observing that the turbine exhaust pressure enters the vacuum range and retums to approximately
:    zero after the turbine is shutdown.
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l Verment Ycnkee Nuclear Pcwer Station                                  Inservice Testing Program l                                  REFUELING OUTAGE JUSTIFICATION Number: ROJ-V33, Revision 0 (Sheet 2 of 2)
Closed Position - During normal plant operation, with the RCIC/HPCI pumps in standby, these nozzle type vacuum breaker check valves are installed in series and maintained in the closed position by means of an intemal spnng. In the event one vacuum breaker is stuck open, exhaust steam will not discharge directly into the torus air space as a result of the series design concept. Additional closing force is provided by steam when the e.pplicable turbine is in operation. A seat leakage limit has been established such that the toms environment will not be adversely affected during turbine operation. It is impractical to verify these valves in the closed position on a quarterly basis or during cold shutdown due to the need to gain component access, set-up air hoses and install test equipment. Additionally, the applicable system must be removed from service to accomplish this testing. During refueling, RCIC and HPCI are not capable of being operated without a steam supply available, presenting the ideal opportunity for leak-rate / closed position testing. Section 4.1.4 of NUREG-1482 permits extension of the test interval to a refueling outage for check valves verified closed by leak testing.
Alternate Testing Partial open stroke testing of these valves is verified quarterly following shutdown of the associated turbine. RCIC Turbine Steam Discharge Line Series Vacuum Breakers V13-820/821 and HPCI l Turbine Steam Discharg'e Line Series Vacuum Breakers V23-845/846 shall be tested with air to demonstrate stroke open and stroke close capability during refueling outages. Leak tightness is demonstrated by allowing no greater than 14.3 SCFH at a test pressure of 5 psid. The open stroke verification is performed at less than accident flow using non-intrusive techniques, specifically MOVATS UDS acoustic technology. The refueling outage test frequency is allowed by OM-10.
Additionally, NUREG 1482 permits the use of acoustic technology for open stroke testing and extension of the closed exercise test interval to a refueling outage for check valves verified closed by leak testing.
i l
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i Vermant Ycnkee Nuclesr Pcwer Stetica                                    Inssrvice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V34, Revision 0 (Sheet 1 of 1)
SYSTEM: Core Spray COMPONENTS:
Valve Number -      OM Cat.          Safety Class      Drawing Number              Dwg. Coord.          ,
V14-13A -                A/C                    1            G-191168                  F-06 I
V14-13B                  A/C                    1            G-191168                  D-06 These valves are the Core Spray injection check valves. They have a safety function in the open position to pass core spray injection flow to'the mactor, and in the closed position for primary containment and pressure isolation.
i      JUSTIFICATION:          '
l Open position - These valves cannot be' exercised open during normal (power) operation since core spray pump discharge cannot overcome reactor pressure. Manual exercising is precluded during power operation since the valves pre inside the inerted drywell. Manual exercising has been performed in the past,'during cold shutdown conditions, yielding test implementation difficulty and inconsistent test L      results. Empirical data has identified that packing drag and break away torque are too. closely, related for these valves. Mechanical exerciser test methods using break-away torque criteria have the potential to INOP the valve when no degradation exists.
l  1 Disassembly and inspection will be used to satisfy forward flow testing. It is burdensome to drain
: l. portions of both Core Spray trains during each refueling outage therefore, a sample disassembly and l
inspection program has been employed as permitted by GL 89-04 Position 2. Based on a 2 valve group, disassembly will be performed during refueling outages. Specifically, one valve will be disassembled,
;      inspected, and full stroke exercised during one refueling outage while the other valve is disassembled,
;      inspected, and full stroke exercised the following refueling outage. During the disassembly, the disk will be manually exercised and the intemals of the valve will be verified to be structurally sound (no loose or corroded parts). If a disassembled valve is not capable of being full stroke exercised or there is  ;
binding or failure of a valve's internals, the other check valve in the group will be disassembled,        !
    ' inspected, and manually full stroke exercised during the same refueling outage. Use of non-intrusive l,    techniques was considered for this application and determined impractical given the valve design and E      system application. Partial valve stroking with flow is also not practical following re-assembly.
    . Quality disassembly, re-assembly and inspection techniques provide sufficient confidence that the            .
    . valves will perform their intended function when challenged.
Oma-1998, Part 10, Paragraph 4.3.2.4(c) permits disassembly every refueling outage to verify                ;
.  ' operability of check valves. NUREG 1482 and Generic Letter 89-04, Position 2 permit the use of a              !
[
sample disassembly and inspection plan when the licensee determines it is burdensome to                    i disassemble and inspect all applicable valves each refueling outage.                                        !
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Vcrm: t Ycnk:e Nucle:r P:wer St ti:n                                Inservica Testing Pr: gram RELIEF REOUEST Number: RR-V01, Revision 1 (Sheet 1 of1)
SYSTEM: Service Water COMPONENTS:
Valve Number        OM Cat.        Safety Class        Drawing Number                                    Dwg. Coord.
SE-70-4A                  B                      3      G-191159 Sh 1                                        K-11 SE-70-4B                  B                      3      G-191159 Sh 1                                        K-11 SE-70-4C                  B                      3      G-191159 Sh 1                                        K-11 SE-70-4D                  B                      3      G-191159 Sh 1                                        K-11 These valves are the Residual Heat Removal Service Water (RHRSW) pump motor cooling coil supply isolation valves. They have a safety function in the open position to provide cooling for the RHRSW pump motor during operation.
EXAM OR TEST CATEGORY:
Category B.              .
THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.
This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
Revision 19                                                              Section 5 Page 157 of 179
 
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Vcrms:t Y:nkes Nucl::r Pcwer St:ti:n                                    Ins rvice Testing Pr: gram RELIEF REOUEST Number: RR-V02, Revision 1 (Sheet 1 of 1)
SYSTEM: Service Water l
COMPONENTS:
Valve Number          OM Cat.      Safety Class    Drawing Number              Dwg. Coord.
V70-1A                      C              3            G-191159 Sh 1                  C-03 V70-1B                      C              3            G-191159 Sh 1                  B-03 l V70-1C                      C              3            G-191159 Sh 1                  I-03 l V70-1D                      C              3            G-191159 Sh 1                  H-03 These valves are the station Service Water pump discharge check valves. They have a safety function in the open position to provide cooling water to systems and equipment required to operate under accident conditions and to provide an inexhaustible supply of water for standby coolant system l operation. They have a function in the closed position to prevent the diversion of cooling water through an idle station Service Water pump.
l EXAM OR TEST CATEGORY:
L l
Category C.
THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.
This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
l l
l l
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l Vcrm=t Ycekee Nucinr P wer St:ti:n                                      hservics Testing Prcgram RELIEF REOUEST Number: RR-V03, Revision 1 (Sheet 1 of 2)
SYSTEM: Diesel Generator Starting Air COMPONENTS:
Valve Number        OM Cat.          Safety Class        Drawing Number          Dwg. Coord.
AS-24-1A                  B                  3              G-191160 Sh 7                B-16 AS-24-1B                  B                  3              G-191160 Sh 7                B-03 AS-24-2A                  B                  3              G-191160 Sh 7                B-17    '~
AS-24-2B                  B                  3              G-191160 Sh 7                B-03 AV-24-1A                  B                  3              G-191160 Sh 7                B-17 AV-24-1B                  B                  3              G-191160 Sh 7                B-03 These valves are the Emergency Diesel Generator (EDG) starting air inlet and vent valves. They have safety functions, as a set, to provide starting air to the EDO, to prevent EDG and/or piping damage after the EDG starts, and to prevent inadvertent EDO starts.                                                      ;
EXAM OR TEST CATEGORY:
Category B.
CODE REOUIREMENT: Part 10 Para. 4.2.1.1  " Exercising Test Frequency"
                    " Active Category A and B valves shall be tested nominally every 3 months, except as provided by paras. 4.2.1.2,4.2.1.5, and 4.2.1.7."
Para. 4.2.1.3  " Valve Obturator Movement" "The necessary valve obturator movement shall be determined by exercising the valve while observing an appropriate indicator, such as indicating lights which signal the required change of obturator position, or by observing other evidence, such as changes in system pressure, flow rate, level, or temperature, which reflect change of obturator position."
i Revision 19                                                                    Section 5 Page 159 of179 l
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l Vcrm:nt Ycnke: Nucler Power Strti:n                                      Inservica Testing Pr: gram RELIEF REOUEST Number: RR-V03, Revision 1 (Sheet 2 of 2)
REOUEST FOR RELIEF 1 l  Reliefis requested on the basis that compliance with the Code requirements is impractical and that the l  proposed altematives would provide an acceptable level of quality and safety.
I
  - These valves do not have remote position indication. Measuring the stroke time of these valves by observing stem travel would require disassembly of the operator.
l  Testing of the inlet valves individually would require the lifting of the power leads to the other valve.
Since the stroke timing of these valves is perfonned by the indirect indication of the respective EDG start time, to lift leads each quarter and perform the necessary EDG fast starts to verify each valve's stroke time would be an undue hardship. Because excessive EDO fast starts are a known contributor to decreased EDG reliability and owing to the criticality of the EDGs as part of the ECCS system, the
:  overall impact of testing these valves in accordance with Code requirements would be an overall decrease in plant safety. Furthermore, since the air start system is not totally redundant (e.g. they share
!  common piping, components and initiating logic), testing of these valves individually on a quarterly basis would not increase the quality and safety of the system.
l  ALTERNATE METHOD:
During EDG slow start testing performed each month, indirect indication that at least one of the two parallel air start inlet valves opens, and the vent valve closes, will be performed by ensuring the EDG starts.                                                                                                    i l
During EDG fast start testing performed every six months, indirect measurement that at least one of the    l I
two parallel air start inlet valves opens promptly, and the vent valve closes promptly, will be performed by ensuring the EDG starts within the Technical Specification limit of 13 seconds. Measuring the EDG        )
start time gives indication of possible valve degradation (as a pair) since any significant changes in valve stroke time will be identified by longer than normal EDG ttart times.
l In addition, to further assess the operational readiness of each air start inlet valve, an independent operability test is perfonned once per operating cycle. This test will be accomplisl;ed by altemately lifting the power leads to one of the two air start valves, and then measuring the EDG fast start time with the remaining valve in operation.
USNRC EVALUATION STATUS:
Relief was granted in the March 1994 SER [ Reference (u)] for Relief Request RR-V03, Revision 1.
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Verm:ct Yetkee Nucirr Psw r St:tien                                    Its:rvice Testing Program RELIEF REOUEST Number: RR-V04, Revision 1 (Sheet 1 of 1)
SYSTEM: FuelOilTransfer COMPONENTS:
Valve Number            OM Cat.      Safety Class        DrawingNumber                Dwg. Coord.
V78-2                      C                3              0-191162 Sh 2                  E-02          i Valve V78-2 is the fuel oil storage tank fill line check valve. It has a safety function in the close position to ensure fuel oil system integrity upon loss of the non-safety related fill line piping.
EXAM ORTEST CATEGORY:
Category C.                                                                                                  l l
THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.
This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.                                                                                                      I l
i Revision 19                                                                  Section 5 Page 161 of179
 
1 l
Vermrx.t Ycnkee Nuclear Pcw;r Steti:n                                Ins:rvica Testing Program i                                                                                                          i RELIEF REOUEST Number: RR-VOS, Revision 1 (Sheet 1 of1)
;  SYSTEM: Nuclear Boiler 1
COMPONENTS:
Valve Number        OM Cat.          Safety Class        Drawing Number        Dwg. Coord.
RV-2-71A                B/C                  1                G-19? 167                D-08 RV-2-71B                B/C                1                G-19[167                  G-08 RV-2-71C                B/C                  1                G-191167                  G-08 RV-2-70A                  C                  1                G-191167                  D-08 RV-2-70B                  C                  1                G-191167                  D-08 Valves SV-2-70A and SV-2-70B are the main steam safety valves. They have a safety function to            i prevent over-pressurization of the reactor coolant system.
Valves RV-2-71A through D are the main steam dual function relief valves. They have a safety function to prevent over-pressurization of the reactor coolant system and to function as part of the l
reactor coolant Automatic Depressurization System (ADS).
EXAM OR TEST CATEGORY:
!  Category C THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.
l  This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
l.
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l  Revision 19                                                              Section 5 Page 162 of179 l
 
l' Vcrm=t Ycnkee Nucirr Pewsr St:tia                                      Inservice Testing Pr: gram RELIEF REOUEST                                                      I I                                    Number: RR-V06, Revision 0 (Sheet 1 of 1) l l      SYSTEM: High Pressure Coolant Injection                                                                      l 1
COMPONENTS:
l        Valve Number        OM Cat.          Safety Class          Drawing Number              Dwg. Coord.      ;
HPCI-CONTROL              B                  2                G-191169 Sh 2                  F-13          I l
This valve is the High Pressure Coolant Injection (HPCI) turbine steam inlet Control valve. It has a          i safety function to operate to provide and regulate steam to the HPCI turbine.                                I EXAM OR TEST CATEGORY:
Category B.                                                                                                  l THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 18 OF THE IST PROGRAM.                                          j This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.                                                                                                        !
I l
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Vermrt Ycnkee Nucirr P wcr St:ti::n                                    Inservica Testing Program RELIEF REOUEST Number: RR-V07, Revision 2 (Sheet 1 of1)
SYSTEM: Control Rod Drive Hydraulic COMPONENTS:
Valve Number          OM Cat.        Safety Class        Drawing Number        Dwg. Coord.            !
V3-162A -                NC                  2                  G-191170                A-09              l V3-162B                  NC                  2                  G-191170                A-01 These valves are the Control Rod Drive (CRD) scram discharge volume vent check valves. They have          ,
a safety function in the closed position to isolate the scram discharge volume during a scram condition,  ;
thereby preventing reactor coolant inventory loss.                                                        l THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 15 OF THE IST PROGRAM.
This RR number is being maintained for traceability to the Third Interval IST Program Submittal l
SER's.
1 i
i Revision 19                                                                Section 5 Page 164 of179
 
                ' Vermmt Ye:ekea Nuclear Power Station                                                                      Inservice Testing Program RELIEF REOUEST Number: RR-V08, Revision 0 (Sheet 1 of 2)
SYSTEM: Standby Liquid Control I
COMPONENTS:
Valve Number                          OM Cat. -            Safety Class                  Drawing Number              Dwg. Coord.
SR-11-39A                                  C                            2                          G-191171                      G-08 SR-11-39B                                  C-                          2                        . O-191171
                                                                                                                                                    . K-08                        1 I
Valves SR-11-39A & B are the Standby Liquid Control (SLC) pump discharge relief valves. They have a safety function to operate to prevent overpressurization of the SLC system.
EXAM ORTEST CATEGORY:
Category C CODE REOUIREMENT: Part 1
                ' Para.1.3.4.l(b)                    " Subsequent 10 Year Periods" "All valves of each type. and manufacturer shall be tested within each subsequent 10 year period, with a minimum of 20% of the valves tested within 48 months. 'lhis 20% shall be previously untested valves, if they exist."
Para.1.3.4.1(c)(2)" Valves Not Meeting Acceptance Criteria" "Any valve exceeding its stamped set pressure by 3% or greater shall be repaired or replaced, the cause of failure shall be determined and corrected, and the valve shall successfully pass a retest before it is                                    !
returned to service.
REOUEST FOR RELIEF:                                                                                                              -
                ' Relief is requested on the basis that the proposed alternatives would provide, an acceptable level of quality and safety.                                                                                                                                            '
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        ,c                  .r- . , . .- - - - - ,              .                . , ,    =                    .        - . ,
                                                                                                                                  . a-          -              _,  - . - ,4--
 
i E
Vermsat Yenk -3 Nucir.er Pow:r St:tian                                  Inservice Testing Program i
!                                                        RELIEF REOUEST l-l                                          Number: RR-V08, Revision 0 (Sheet 2 of 2) l REOUEST FOR REIJEF(CONT.):
l Vermont Yankee Technical Specifications 4.4.A requires testing of valves SR-11-39A & B at least once every operating cycle. This testing frequency represents a six-fold increase over the testing
!      frequency required by Part 1 of the Code and, as such, yields more accurate valve degradation trending data. The testing is currently performed at the Vermont Yankee plant site.
The acceptable range of relief valve actuation given in Technical Specifications 4.4.A is 1400 psig to            !
1490 psig. The 1400 psig value ensures that a sufficient injection pressure can be established prior to lifting of the relief valve. The 1490 psig value ensures relief valve actuation prior to reaching the system design pressure of 1500 psig. 1490 psig translates into a maximum relief valve setpoint of 99%
of system design pressure as opposed to 110% allowable by the piping code. Applying the Part I tolerance af 3% to the current setpoint would unnecessarily reduce the acceptable range to 1400 psig to 1442 psig (1442 psig = 96% of system design pn:ssure).
The increased testing frequency and present setpoint requirements provide adequate assurance of the operational readiness of valves SR-ll-39A & B and, as such, no significant increase in the level of safety or quality can be expected if the subject Code requirements are imposed.
    ' ALTERNATE METHOD:                                                                                                i In accordance with Vermont Yankee Technical Specifications 4.4.A, valves SR-11-39A & B shall be tested at least once every operating cycle. The setting of the valves shall be between 1400 and 1490 psig.
USNRC EVALUATION STATUS:
Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-V08, Revision 0.              ;
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i Vermont Yankee Nuclear Power Station                                  Inservice Testing Program
!                                            RELIEF REOUEST Number: RR-V09, Revision 1 (Sheet 1 of1) ~
t SYSTEM: ResidualHeat Removal COMPONENTS:
j        Valve Number        OM Cat.      Safety Class            Drawing Number      Dwg. Coord.
l      V10-17                  A                2                      G-191172              D-06 V10-27A                A                2                      G-191172              D-06 V10-27B                A                2                      G-191172              D-12 Valve V10-17 is the Residual Heat Removal (RHR) shutdown cooling supply outboard primary I      comainment isolation valve. The valve has a safety function in the closed position to provide primary containment and pressure isolation, and in the open position to provide RHR pump suction during shutdown cooling operation.
Valves V10-27A & B are the RHR system low pressure coolant injection primary containment isolation valves. These valves have a safety function in the closed position to provide primary containment and pressure isolation, and in the open position to pass low pressure coolar:t injection water to the reactor.
USNRC EVALUATION STATUS:
l    .THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM PLAN.
This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
I d'
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Vcrm::nt Yenkee Nucirr Pcwer St:tirn                              Insarvice Testing Program RELIEF REOUEST Number: RR-V10, Revision 0 (Sheet 1 of1)                                  ,
I SYSTEM: Residual Heat Removal Service Water                                                          '
COMPONENTS:
,    Valve Number      OM Cat.        Safety Class      Drawing Number          Dwg. Coord.
V10-89A                  B              3              G-191179 Sh 2              G-01              l V10-89B                  B              3              G-191179 Sh 2              C-01              1 These valves are the Residual Heat Removal Service Water (RHRSW) flow control valves for the RHR heat exchangers. They have a safety function to provide and regulate cooling water to the RHR heat exchangers.
                                                                                                          ]
TIHS RELIEF REQUEST WAS WITHDRAWN IN REVISION 15 OF THE IST PROGRAM.
This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.
l l
Revision 19                                                            Section 5 Page 168 of179
 
Vcrm:;ft Ycnkee Nucle:r Pcwcr Stati:n                                  Ins:rvica Tcsting Prcgram RELIEF REOUEST Number: RR-Vil, Revision 0 (Sheet 1 of 1)                                ,
1 SYSTEM: Reactor Core Isolation Cooling COMPONENTS:
l Valve Number        OM Cat.          Safety Class      Drawing Number          Dwg. Coord.
RCIC-CONTROL              B                  2              G-191174 Sh 2              D-12 This valve is the Reactor Core Isolation Cooling (RCIC) turbine governor control valve. This valve has a safety function to operate to provide and regulate steam to the RCIC turbine.
EXAM OR TEST CATEGORY:
Category B.
THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 18 OF THE IST PROGRAM.
This RR number is bein'g maintained for traceability to the Third Interval IST Program Submittal SER's.
l Revision 19                                                                Section 5 Page 169 of179
 
                                                                          -- _ - -            - . . _ _ _ = _
Vermont Yankee Nuclear Power Station                                Inservice Testing Program RELIEF REOUEST Number: RR-V12, Revision 0 (Sheet 1 of1)
SYSTEM: Service Water System (SW)
COMPONENTS:
Valve Number        OM Cat.        Safety Class      Drawing Number            Dwg. Coord.
V70-43A                  C                3              G-191159 Sh 1              J-12 V7043B                    C                3          .
G-191159 Sh 1              B-12 These valves are the Service Water System loop header discharge check valves. These valves have a safety function to close to prevent the backflow of RHRSW pump discharge to the suction of the pumps when operating in the Alternate Cooling mode of operation.
EXAM OR TEST CATEGORY:
Category C USNRC EVALUATION STATUS This Relief Request was approved for use in USNRC Generic Letter 89-04, NRC Staff Position 2.
Based on comments from the NRC, Revision 1 to this request was submitted and relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-V12, Revision 1.
Following receipt of the January 1998 SER, Vermont Yankee reexamined the reasons for the request and concluded that full Code compliance can be achieved without resorting to such relief. Vermont Yankee will meet all required testing provisions as specified by OM-10 and as amplified by the NRC guidance provided within NUREG-1482. (See ROJ-V32)
THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION ISA OF THE IST PROGRAM.
This RR ntunber is being maintained for traceability to the Third Interval IST Program Submittal SER's.                                                                              -
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l l              - Vcrm:nt Yenkee Nucirr Pcwsr Stntisn                                                      Inservics Testing Pregram l  .
i RELIEF REOUEST                                                                              ,
                                                    . Number: RR-V13, Revision 0 (Sheet 1 of 3)                                                              ,
1 l                SYSTEM: ResidualHeat Removal (RHR)
Core Spray (CS)
Reactor Core Isolation Cooling (RCIC)                                      '
l High Pressure Coolant Injection (HPCI)
COMPONENTS:
Valve Number        OM Cat.            Safety Class                    Drawing Number          Dwg. Coord.
V10-36A                        C                2                                G-191172                J-03 V10-36B                        C                2                                G-191172                J                  V14-33A -                      C                2                                G-191168              ' H-ll V14-33B                        C                2                                G-191168                H-15
                .V23-20B                        C                2                            G-191169 Sh 1              - G-07 l
V13-20B                        C                2                            G-191174 Sh 1                G-11 These valves are the Residual Heat Removal, Core Spray, High Pressure Coolant Injection and Reactor Core Isolation Cooling system keep-fill check valves. These valves have a safety function to close to isolate Safety Class 2 CS, RHR, RCIC or HPCI piping from the lower pressure non-safety grade                                              i Condensate Transfer System piping in the event of a system actuation.
EXAM OR TEST CATEGORY:
Category C L                CODE REOUIREMENT: Part 10-Para. 4.3.2.1 " Exercising Test Frequency"
                  " Check valves shall be exercised nominally every 3 months, except as provided by paras. 4.3.2.2, 4.3.23,4.3.2.4 and 4.3.2.5."
l l                REOUEST FOR RELIEF:                                                                                    ,
p Reliefis requested on the basis that individual full stroke exercise testing in the closed direction on a 3 month, cold shutdown or refuel outage basis in accordance with OM-10 Para. 4.3.2.1 for these valves is burdensome and does not provide a compensating increase in safety, i
I
                - Revision 19                                                                                  Section 5 Page 171 of179
 
Vermont Yankee Nuclear Power Station                                            Inservice Testing Program RELIEF REOUEST Number: RR-V13, Revision 0 (Sheet 2 of 3)
REOUEST FOR RELIEF (CONT.h These valves are Safety Class 2 one inch lift check valves located in the keep-fill pressurization lines for the RHR, CS, HPCI and RCIC piping systems. These valves are arranged in parallel downstream of a common non-nuclear safety Condensate Transfer supply check valve. The Vermont Yankee safety analysis does not require the non-nuclear safety Condensate Transfer check valve to perform a
    . safety function in support of these systems. There are no test connections between the check valves or in any of the keep-fill pressurization lines.
The use of the series pair testing method suggested in NUREG 1482, subsection 4.1.1, " Closure Verification for Series Check Valves without Intermediate Test Connections," does not provide                                    ,
positive verification of closure of the subject check valves due to their configuration.
Individual check valve closure capability verification is presently accomplished by performing quarterly non-intrusive (radiography) testing. Indication of valve closure has been conclusive.
However, this quarterly non-intrusive testing of the subject check valves during power operations has proven to be burdensome. Among the burdens imposed by this test method and frequency of testing are:
: 1.          Increased personnel radiation exposure -- The transport, equipment setup, exposure and equipment removal account for approximately 400 mrem / year in increased personnel radiation dose.                                                                                                                    ,
i
: 2.          Large manpower requirements - The administration of radiological controls, control of the radiographic source and posting of exclusion areas during exposures at times requires the                                4 utilization of all available plant radiation controls personnel. The completion of all the radiographs typically requires two days each quarter.
: 3.          Extensive test equipment setup - The setup of the radiographic equipment and shielding of
            ' adjacent plant equipment is repeated for each valve tested.
: 4.          Potential for unexpected challenges to plant safety systems - The use of portable radioactive sources and their movements present the potential for unexpected challenges to plant safety                              ,
systems due to high radiation actuations.                                                                                i It is expected that the performance of radiography during cold shutdowns would present the additional burden of obtaining contract services on short notice.
4
      -It is also expected that performing radiography during refuel outages will present an added risk of increased radiation exposure to personnel as more people will be subject to possible exposure during refuel outages.
Revision 19                                                                          Section 5 Page 172 of179 y                                      w  -,.      . - - -        w +        -_  ,.        - -
v-.. -- .. we3        .-, -
 
l Vermant Ycnkes Nuclur Pswer Stcti::n                                    Inservice Testing Program l                                                RELIEF REOUEST t
l Number: RR-V13, Revision 0 (Sheet 3 of 3)
REOUEST FOR RELIEF (CONT.):
Vermont Yankee has investigated several alternate test methods with the following results:
l    1. Disassembly and Inspection of each valve on a refuel outage basis in accordance with OM-10,
!        Para. 4.3.2.4(c) - NRC guidance identified in Appendix A of NUREG 1482 (question group 15) and in a previously resolved Vermont Yankee IST Program Safety Evaluation anomaly discouraged the use of the disassembly and inspection method on the basis that disassembly is I
not a true substitute for opnability testing using flow.
: 2. Performing sample non-inausive testing with flow as described in NUREG 1482, subsection 4.1.2, " Exercising Check Valves with Flow and Nonintrusive Techniques" - It was determined that this testing method is not appliAle for these valves since the safety function of these            !
valves is to close on cessation or reversal of flow.
: 3. Use of other non-intrusive testing methods (ultrasonic, magnetic or acoustic) - Due to valve size, valve type and low flow rates through these keep-fill lines it is not expected that these methods would provide conclusive indication of valve closure.                                          :
l l  ALTERNATE TEST METHOD:
Since the subject check valves are of simple design, operate under mild service conditions and the maintenance history for these valves indicates that they have not been susceptible to service induced failures or significant wear, Vermont Yankee proposes to perform non-intrusive testing (radiography) on each check valve once each operating cycle within 2 months of the scheduled start of the next refueling outage. Testing once each operating cycle but not during refuel outages (relief request required) will reduce the risk ofincreased radiation exposure to personnel as fewer people will be subject to possible exposure.
The alternate " disassembly and inspection" methods described in Generic Letter 89-04, Position 2, do not use actual check valve response to determine check valve operability and so are provided as a compromise. The proposed use of non-intrusive testing provides a test result that uses a direct observation of actual check valve operation in response to changes in system param'eters. The use of non-intrusive testing in this manner more closely approximates the intent of the code. Although the same testing burden exists, the reduction in test frequency from 6 times per operating cycle to once per j  operating cycle will greatly reduce the risk of potential unexpecteo challenges to plant safety systems.
i USNRC EVALUATION STATUS Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-V13, Revision 0.
Revision 19                                                                    Section 5 Page 173 of179
 
V                                                                                                                      l Vermeet Ye2kea Nucl: r Pcwe Itstian                                    Ins:rvics Testing Program l
l                                                        RELIEF REOUEST i
!                                      Number: RR-V14, Revision 0 (Sheet 1 of 3) l SYSTEM: Core Spray (CS)
COMPONENTS:
l Valve Number          OM Cat.            Safety Class    Drawing Number                      Dwg. Coord.
l                                                                                                                      ;
V14-22A                      C                        2        G-191168                                  I-09 !
V14-22B                      C                        2        G-191168                                  C-10 i V14-23A                      C                        2        G-191168                                  I-09 !
V14-23B                      C                        2        G-191168                                  C-10 i These valves are the Condensate transfer system to Core Spray flushing line check valves. These valves have a safety function to close to isolate the high pressure Safety Class 2 CS piping from the lower            !
pressure non-safety grade Condensate Transfer System piping in the event of a CS system actuation.
EXAM OR TEST CATEGORY:
Category C                  .                                                                                  l CODE REOUIREMENT: Part 10 Para. 43.2.1 " Exercising Test Frequency"
        " Check valves shall be exercised nominally every 3 months, except as provided by paras.43.2.2, 43.23,43.2.4 and 43.2.5."
REOUEST FOR RELIEF:
Reliefis requested on the basis that individual full stroke exercise testing in the closed direction on a 3 month, cold shutdown or refuel outage basis in accordance with OM-10 Para. 43.2.1 for these valves is burdensome and does not provide a compensating increase in safety.
These valves are Safety Class 2 two inch lift check valves located in the flushing. lines between the Core Spray System and the Condensate Transfer System. These valves are arranged in series-pairs in each flushing line. During normal power operation these flushing lines are isolated. There are no test
,.      connections between the check valves or in either flushing line.
!-      The use of the series-pair testing method suggested in NUREG 1482, subsection 4.1.1, " Closure Verification for Series Check Valves without Intermediate Test Connections," does not provide
,      positive verification of closure of the subject check valves due their configuration.
L Revision 19                                                                    Section 5 Page 174 of179
 
l Verment Yenkee Nucleir Power Strtion                                              Inservice Testing Program      j RELIEF REOUEST Number: RR-V14, Revision 0 (Sheet 2 of 3)                                        l REOUEST FOR RELIEF (CONT.):
i Individual check valve closure capability verification is presently accomplished by performing                    ;
quarterly non-intrusive (radiography) testing. Indication of valve closure has been conclusive.
However, this quarterly non-intrusive testing of the subject check valves during power operations
            . has proven to be burdensome. Among the burdens imposed by this test method and frequency of testing are:
: 1.      Increased personnel radiation exposure - The transport, equipment setup, exposure and equipment removal account for approximately 400 mrem / year in increased personnel radiation              i dose.                                                                                                      )
: 2.      Large manpower requirements - The administration of radiological controls, control of the                i radiographic source and posting of exclusion areas during exposures at times requires the utilization of all available plant radiation controls personnel. The completion of all the                l radiographs typically requires two days each quarter.
: 3.      - Extensive test equi'p ment setup -- The setup of the radiographic equipment and shielding of            .
adjacent plant equipment is repeated for each valve tested.
: 4.      Potential for unexpected challenges to plant safety systems - The use of portable radioactive sources and their movements present the potential for unexpected challenges to plant safety systems due to high radiation actuations.
It is expected that the performance of radiography during cold shutdowns would present the additional burden of obtaining contract services on short notice.
1 It is also expected that performing radiography during refuel outages will present an added risk of increased radiation exposure to personnel as more people will be subject to possible exposure during refuel outages.
l          ' Vermont Yankee has investigated several alternate test methods with the following results:
: 1.        Disassembly and Inspection of each valve on a refuel outage basis in accordance with OM-10,,
Para. 4.3.2.4(c) - NRC guidance identified in Appendix A ofNUREG 1482 (question group 15) l                    and in a previously resolved Vermont Yankee IST Program Safety Evaluation anomaly
                    ~ discouraged the use of the disassembly and inspection method on the basis that disassembly is not a true substitute for operability testing using flow.
l i
l
            - Revision 19                                                                          Section 5 Page 175 of179 s                  e --
r
 
Verment Yenkee Nuclear Power Statien                                    Inservice Testing Program RELIEF REOUEST Number: RR-V14, Revision 0 (Sheet 3 of 3)
REOUEST FOR RELIEF (CONT.h
: 2.    . Performing sample non-intrusive testing with flow as described in NUREG 1482, subsection
        ' 4.1.2, " Exercising Check Valves with Flow and Nonintrusive Techniques" - It was determined that this testing method is not applicable for these valves since the safety function of these
        ~ valves is to close on cessation or reversal of flow.
ALTERNATE TEST METHOD:
Since the subject check valves are of simple design, operate under mild service conditions and the maintenance history for these valves indicates that they have not been susceptible to service ind' ed failures or significant wear, Vermont Yankee proposes to perform non-intrusive testing (radiography) on each check valve once each operating cycle.
The alternate " disassembly and inspection" methods described in Generic Letter 89-04, Position 2, do not use actual check valve response to determine check valve operability and so are provided as a compromise. The proposed use of non-intmsive testing provides a test result that uses a direct observation of actual check valve operation in response to changes in system parameters. The use of non-intrusive testing in this manner more closely approximates the intent of the code. Vermont
  . Yankee proposes to perform non-intrusive testing (radiography) on each check valve once each operating cycle within 2 months of the scheduled start of the next refueling outage. Testing once each operating cycle but not during refuel outages (relief request required) will reduce the risk of increased radiation exposure to personnel as fewer people will be subject to possible exposure.
Although the same testing burden exists, the reduction in test frequency from 6 times per operating cycle to once per operating' cycle will greatly reduce the risk of potential unexpected challenges to plant safety systems.
USNRC EVALUATION STATUS Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-V14, Revision 0.
Revision 19                                                                  Section 5 Page 176 of179 l
                                                                                                        ]
 
_ . ~ .    ._ __            .- _ . . _ _ _ _ _ _ _ _ _ _...__ _ _ _.                                                __
,            Verment Yenkes Nuclear Power Station                                        Inservice Testing Program l
l                                                                    RELIEF REOUEST                                          !
:                                                                                                                            i 1
:                                                  Number: RR-V15, Revision 0 (Sheet 1 of 3)
SYSTEM: Reactor Core Isolstion Cooling (RCIC)
!                    - High Pressure Coolant Injection (HPCI) -
i                                                                                                                            !
:            COMPONENTS:
;                Valve Number            OM Cat.                Safety Class  Drawing Number        Dwg. Coord.
1            V13-19                            C                        2      0-191174 Sh 1            E-14
__ V23-32                        -C                          2      G-191169 Sh 1            E-11 Valve V13-19 is the Condensate Storage Tank (CST) supply to RCIC Pump suction check valve. This                I
            . valve has a safety function to open to supply water from the CST to the RCIC pump suction. This valve also has a safety function to close to isolate the RCIC pump suction from the CST. When RCIC pump              j suction automatically transfers from the CST to the suppression pool, there is a short time when all RCIC pump suction MOVs are open at the same time. V13-19 is the only containment boundary between the suppression pool and the CST during this transfer of RCIC pump suction.                            l Valve V23-32 is the CST. supply to HPCI Pump suction check valve. This valve has safety function to open to supply water from CST to the HPCI pump suction. This valve also has a safety function to                I close to isolate the HPCI pump suction from the CST. When HPCI pump suction automatically                      l transfers from the CST to the suppression pool, there is a short time when all HPCI pump suction MOVs are open at the same time. V23-32 is the only containment boundary between the suppression pool and the CST during this transfer of HPCI pump suction.
EXAM OR TEST CATEGORY:
Category C CODE REOUIREMENT: Part 10
  ,          Para. 4.3.2.1 " Exercising Test Frequency"
              ". Check valves shall be exercised nominally every 3 months, except as provided.by paras.4.3.2.2, 4.3.2.3,4.3.2.4 and 4.3.2.5."
REOUEST FOR RELIEF:
Reliefis requested on the basis that individual full stroke exercise testing in the closed direction on a 3 month, cold shutdown or refuel outage basis in accordance with OM-10 Para. 4.3.2.1 for these valves is burdensome and does not provide a compensating increase in safety.
Revision 19                                                                      Section 5 Page 177 of179
 
s Vcrmant Yankee Nuclezr Power Statisn .                                Inservice Testing Program RELIEF REOUEST Number: RR-V15, Revision 0 (Sheet 2 of 3)
REOUEST FOR RELIEF (CONT.h i
Individual check valve closure capability verification is presently accomplished by performing
            . quarterly non-intrusive (radiography) testing as committed to in LER 96-01, Corrective Action #3.          ;
Indication of valve closure has been conclusive. However, this quarterly non-intrusive testing of the subject check valves during power operations has proven to be burdensome. Among the burdens imposed by this test method and frequency of testing are:
: 1.      Increased personnel radiation exposure - The transport, equipment setup, exposure and equipment removal account for approximately 400 mrem / year in increased personnel radiation
                  ' dose.
: 2.      Large manpower requirements -- The administration of radiological controls, control of the radiographic source and posting of. exclusion areas during exposures at times requires the utilization of all available plant radiation controls personnel. The completion of all the radiographs typice.lly requires two days each quarter.
: 3.      Extensive test equipment setup -- The setup of the radiographic equipment and shielding of adjacent plant equipment is repeated for each valve tested.
: 4.      Potential for unexpected challenges to plant safety systems - The use of portable radioactive sources and their movements present the potential for unexpected challenges to plant safety systems due to high radiation actuations.
It is expected that the performance of radiography during cold shutdowns would present the additional burden of obtaining contract services on short notice.
It is also expected that performing radiography during refuel outages will present an added risk of
: increased radiatbn exposure to personnel as more people will be subject to possible exposure during refuel outages.
Vermont Yankee has investigated several alternate test methods with the following results                  )
l
: 1.      Disassembly and Inspection of each valve on a refuel outage basis in accordance with OM-10,
                  . Para. 4.3.2.4(c) -- NRC guidance identified in Appendix A of NUREG 1482 (question group 15) and in a previously resolved Vermont Yankee IST Program Safety Evaluation anomaly discouraged the use of the disassembly and inspection method on the basis that disassembly is not a true substitute for operability testing using flow.                                          l l
1 i
l Revision 19                                                                      Section 5 Page 178 of179 i
1
 
Verm:nt Yetkee Nucle:r Power Station                                Inservice Testing Program RELIEF REOUEST Number: RR-V15, Revision 0 (Sheet 3 of 3) l REOUEST FOR RELIEF (CONT.):
: 2. Performing sample non-intrusive testing with flow as described in NUREG 1482, subsection 4.1.2, _" Exercising Check Valves with Flow and Nonintrusive Techniques" - It was determined that this testing method is not applicable for these valves since the safety function of these valves is to close on cessation or reversal of flow.
!  ALTERNATE TEST METHOD:
Since the subject check valves are of simple design, operate under mild service conditions and the
  . maintenance history for these valves indicates that they have not been susceptible to service induced failures or significant wear, Vermont Yankee proposes to perform non-intrusive testing (radiography) on each check valve once each operating cycle.
The alternate " disassembly and inspection" methods described in Generic Letter 89-04, Position 2, do not use actual check valve response to determine check valve operability and so are provided as a compromise. The proposed use of non-intrusive testing provides a test result that uses a direct observation of actual check valve operation in response to changes in system parameters. The use of non-intrusive testing in this manner more closely approximates the intent of the code. Vermont Yankee proposes to perform non-intrusive testing (radiography) on each check valve once each operating cycle within 2 months of the scheduled start of the next refueling outage. Testing once each operating cycle but not during refuel outages (relief request required) will reduce the risk of increased radiation exposure to personnel as fewer people will be subject to possible exposure.
Although the same testing burden exists, the reduction in test frequency from 6 times per operating cycle to once per operating cycle will greatly reduce the risk of potential unexpected challenges to plant safety systems.
i The commitment made by Vermont Yankee in LER 96-01, corrective action #3 to verify closure operability of V13-19 and V23-32 by performing quarterly radiography will be superseded upon approval of this reliefrequest.
USNRC EVALUATION STATUS Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-V15, Revision 0.
l l
Revision 19                                                              Section 5 Page 179 of179
                                                                                                          )}}

Latest revision as of 10:05, 13 November 2020

Rev 19 to Vynp IST Program Plan
ML20196A785
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 10/09/1998
From: Burke R
VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20196A777 List:
References
PROC-981009, NUDOCS 9811300149
Download: ML20196A785 (200)
v • d • e


Text

I

(

APPENDIX A INSERVICE TESTING PROGRAM PLAN Vermont Yankee Nuclear Power Station Commercial Service Date: November 29,1972 l Revision 19

_l October,1998 Prepared By: Reviewed By:

k b!. ~ -

Y.

Plant IST Coordinator C/M 0 V

~

Approved By:

DW ystem Eng

~

g Man u l /s r W1./)), O N $dV? M Pirnt Operations Review /0[67 F Plant Manag h

v , 1.

, - IM, @ _ .

l Director erations Vermont Yankee Nuclear Power Corporation Governor Hunt Road Vernon, Vermont 05354 9811300149 981120 r7 Appendix A ADOCK O gDR 1f PP 7013 Rev. 3 Page 1 of 6

APPENDIX A (Continu2d)

Vermont Yankee Nuclear Power Station inservice Testina Proaram Revision Summary R: vision Affected Number Pages Summary 13 All Third Ten-Year interval Update.  ;

1 14 5-14, 5-15 Revise valve listing for Diesel Generator Starting Air System to reflect changes made under PDCR 92-18, DCN 1. Minor revisions. _

15 Cover,1-1,1-2, 2-5, 3-1, Revise to reflect Tech Spec Amendment No.138, EDCR 3-2, 4-1 to 4-5, 4-10,92-404, EDCR 93-404, PDCR 92-016, PDCR 92-018, 4-12,4-14,4-17,4-19, CARS 93-70 and 94-06, PRO 94-18, items identified during l 4-21 to 4-23, 4-25, 4-29, revisions to implementing procedures, current status of 5-1, 5-3 to 5-11, 5-13 to each Relief Request per USNRC SEPs [ References (s) and 5-20, 5-22 to 5-30, 5-32 (u)], and minor revisions.

to 5-34, 5-36 to 5-71, 5-74 to 5-84, 5-87, 5-88, 5-91 to 5-94, 5-98 to 5-98b, 5-100, 5-102, 5-105,5-107,5-113, 5-115, 5-117, 5-119, 5-122 to 5-124, 5-126 16 Cover,4-3, 4-7 to 4-10, Revise to reflect changes made due to the responses to the 4-30, 4-31, 5-5, 5-7 to USNRC Safety Evaluation Report issued on September 3, 5-11, 5-17, 5-19, 5-20, 1994, Alternate Cooling Water System additions, items 5-27, 5-34, 5-36, 5-38 to identified during the implementation of the program, current 5-41, 5-43, 5-52, 5-53, status of each relief request and correction of typographical 5-56 to 5-59, 5-60, 5-68, errors.

5-77, 5-83 to 5-84, 5-89 to 5-90, 5-104 to 5-112, 5-107,5-113, 5-114, 5-118,5-119,5-122, 5-125 17 Cover, 5 9, 5-129 & 5-130 Revise to allow the use of the sampling disassembly technique for V70-43A and V70-43B in accordance with the guidance specified in USNRC Generic Letter 89-04, Staff Position 2.

i Appendix A PP 7013 Rev. 3 Page 2 of 6

_ . _ . .__m _ _ _ . ._ ._, _ _ ._ . _ _ _ . _ _ _ . _ . . _ . _ . _ . _ _ _ _._ __.___. _

APPENDIX A (Continu d) j l

Vermont Yankee Nuclear Power Station Inservice Testina Proaram

)

R; vision Affected Number Pages Summary ,

18 All General program revision committed to in LER 95-17 and BMO 95-07. Implemented changes due to IST program .

scope changes and IST program bases document upgrade.

implemented changes due to Appendix J Program upgrade.

implemented changes due to EDCR 93-405, PDCR 94-021, PDCR 94-022, EDCR 95-409, EDCR 96-410, EDCR 96-412, EDCR 96-416, PDCR 94-007 and Minor Mod.

96-34, 96-52. Revised program format as suggested by NUREG 1482.

-18A Cover, ii, iii, 3-3, 4-15, Revised to implement NRC SER on RR-P03, Rev.1, 4-16, 4-20 to 4-23, 5-13, RR P05, Rev.1, and RR-P06, Rev.1 to update the 5-39,5-40,5-42,5-43, improved instrument accuracy currently in use compared to 5-48,5-55,5-56, 5-62,- those accuracies considered by the NRC previously in .

5-90, 5-128,5-129, granting the original revisions of the subject relief requests.

5-148, 5-149, 5-163 t Revised to implement NRC SER on RR-V13, Rev. O, 5-172 RR-V14, Rev. O, and RR-V15, Rev. O, extending the Stroke Close testing frequency of check valves associated with keep fill / flushing lines in the RHR, Core Spray, HPCI and i RCIC Systems.

Withdrew RR-V12 and issued ROJ-V32 to justify refueling outage full stroke testing of V70-43A and V70-43B on a i sampling basis. I issued Revision 2 to ROJ-V14 based on a change to the methods to be used to verify full stroke open of Service Water Pump discharge check valves V70-1 A,1B,1C, and 1 D.

Removed HCU Rupture Disks 3-3-132 (Typical of 89) from the program scope based on a review of the applicable  ;

criteria of 10 CFR 50.55a and a 10 CFR 50.59 review I L associated with this revision. (Page 5-48) l ii Appendix A PP 7013 Rev. 3 Page 3 of 6

APPENDIX A (Centinutd)

Vermont Yankee Nuclear Power Station Inservice Testina Proaram l

l Revision Affected

( Number Pages Summary 188 Cover, iii, iv, 2-3, 2-4, 4-6, Revised Section 4, Table 4-1, Pump Listing, to include 4-7, 5-5 to 5-8, 5-12 to component specific differential pressure and vibration 5-19, 5-21 to 5-24, 5-31 requirements for P-7-1 A through P-7-1D.

to 5 38, 5-42 to 5-46, 5-48 to 5-50, 5-54 t Revised to eliminate set-point testing of the 10 Sorvice 5-58, 5 61 to 5-65, 5-68, Water Vacuum Breakers and to add a sampling c'isassembly and inspection (CD) program.

5-73,5-76,5-86,5-88, 5-89, 5-93, 5-127, 5-142, Added Instrument Air / Service Air, Containment Air and j 5-143, 5-145,5-146, Nitrogen System Relief Valves SR-72-3A/B, SR-72-5, &

5-148,5-153,5-154. SR-16-19-77 to reflect their new safety class status per BMO 96-03.

Added Appendix J, Option B and variable frequency references to qualified components to reflect Technical Specification Amendment No.152.

Added CRD Cooler SW/RCW valves V70-30A/B &

I V70-31 A/B to address BMO 97-61.

Revised Program to reflect additions and deletions to j components in the DGSA System per EDCR 97-401. l i

Added position indication testing for FCV-2-39/40 to reflect EDCR 97-406.

Revised Program to reflect SDV vent & drain valve l replacement per EDCR 97-410.  :

Revised Program to reflect TIP Purge Modifications per EDCR 97-416.

Deleted Leak Testing (LT) of RHR V10-57/66.  !

Revised Program to account for HPCl/RCIC Vacuum Breaker Modifications which added and deleted components per ll EDCR 98-402. Issued ROJ-V33.

Deleted replacement requirements for Torus Rupture Disk S16-19-1 from Program based on its Beyond Design Basis active function.

iii Appendix A PP 7013 Rev. 3

! Page 4 of 6

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l

APPENDIX A (Continuc;d)

Vermont Yankee Nuclear Power Station Inservice Testina Proaram Revision Affected Number Pages Summary l 19 Cover, iii, iv, v, 5-21, Revised Summary on page iii to reflect editorial notation of l 5-26,5-39,5-40,5-45, ROJ-V33 as part of previous entry accounting for j 5-64,5-92,5-99,5-156. HPCl/RCIC Vacuum Breaker Modifications.

'l Revised to show correct normal and safety stroke direction l for outboard MSIV Instrument Air System Isolation Valves l_ V72-28D and V72-28E.

l Revised to .specify an additional quarterly test (Manual l Stroke Open) for Diesel Oil Day Tank Level Control Valves l LCV-108-2A/2B.

l Revised to delete quarterly stroke close test for Diesel Fuel l Oil Transfer Pump Discharge Check valves V78-28A and l V78-288 based on the change in closed safety position l basis caused by actions taken in response to ER 97-1577 l and associated BMO 97-51.

j Revised to reflect a new test frequency, method of l inspection, and justification for performing component l disassembly on a sampling basis for Core Spray check j valves V14-13A/B in lieu of the previous cold shutdown l mechanical exercising test. Issued ROJ-V34 and deleted j CSJ-V05.

l Revised to specify an additional quarterly test (Stroke Time l Open) for Core Spray Tect Line Isolation Valves V14-26A l and V14-268 based on a new active safety function

~j established by EDCR 97-420.

'l Deleted Note 2 of the Valve Notes section to reflect the l transfer of responsibility from the IST Program to the PM j Program when conducting a fatigue inspection of

-l RCIC/HPCI check valves V13-50 and V23-65.

iv Appendix A PP 7013 Rev. 3 Page 5 of 6

APPENDIX A (Continued)

L TYormont Yankee Nuclear Power Station Jriservice Testina Proaram l ' Tchle of Contents j t

l 1.0 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 1 Page 1 i i

- 1.1. Purp ose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Secti on 1 Page 1 l l 1.2 Discussion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 1 Page 1 2.0 Program Plan Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 2 Page 1 l 2.1 Test Deferral Justifications . . . . . . . . . . . . . . . . . . . . . . . . . Section 2 Page 1 l 2.2 Relief Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 2 Page 2

]

2.3 Flow Diagrams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 2 Page 2 Table 2-1: List of inservice Testing Flow Diagrams . . . . . . . . . . . . Section 2 Page 3 I 3.0 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S e c ti o n 3 Pa g e 1 i

- 4.0 Pump Inservice Testing Program Plan . . . . . . . . . . . . . . . . . . . . . . Section 4 Page 1 4.1 S c o pe . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S e cti on 4 Pa g e 1 4.2 ' Pump Program Listing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 4 Page 1 l I ~ Table 4-1: Pum p listing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 4 Page 4 1 I - 4.3 Pump N otes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 4 Page 8 i i

i 4.4 Pump Relief Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 4 Page 9 l >

5.0 Valve inservice Testing Program Plan . . . . . . . . . . . . . . . . . . . . . . Section 5 Page 1 5.1 Sc ope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S e ctio n 5 Pa g e 1

5.2 Valve Program Listing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 5 Page 2 Table 5-1: Valve Listing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 5 Page 8 l

5.3 Valve N otes . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . Section 5 Page 92 l j: 5.4 Valve. Cold Shutdown Justifications . . . . . . . . . . . . . . . . . . . Section 5 Page 95 j; - 5.5 Valve Refueling Outage Justifications . . . . . . . . . . . . . . . . . . Section 5 Page 114 j; 5.6 Valve Relief Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Section 5 Page 157 s

l-v Appendix A PP 7013 Rev. 3 Page 6 of 6 i

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Verm:nt Yenkee Nucle:r Pswer Ststi::n Inservico Tcsting Pr: gram 1.0 Introduction

[

1.1 l Purpose The Third-Interval Vermont Yankee Inservice Testing (IST) Program. establishes testing requirements to assess. the operational readiness of certain Safety Class 1, 2, and 3

. pumps and valves which are required to:

a) ' Shut down the reactor to the cold shutdown condition, b) : Maintain the reactor in the cold shutdown condition, or i

c) Mitigate the consequences of an accident.

The Third-Interval IST Program is applicable for the. interval from September 1,1993 through and including August 31,2003 [ References (q) and (r)]. R 1

'Ihe Third-Interval IST Program is part of the Vennont Yankee Component Testing j Program.

.1.2 Discussion The Third-Interval Vermont Yankee IST Program was developed in accordance with the requirements of the 1989 Edition of Section XI, Division 1, of the ASME Boiler and Pressure -Vessel, Code, " Rules for-Inservice Inspection of Nuclear Power Plant Components," and 10 CFR 50.55a [ Reference (b)]. The Third-Interval IST Program l provides compliance with Vermont Yankee Technical Specifications 4.6.E.

1 In accordance with Articles IWP-1000 and IWV-1000 and Table IWA-1600-1 of the

1989 Edition of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code and 10 CFR 50.55a(bX2Xviii), the pump and valve testing requirements were based on .

the ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM-1987, " Operation and Maintenance of Nuclear Power Plants". The additional requirements described in 10 CFR 50.55a(bX2 Xvii) and the recommendations described in Generic Letter 89-04 and its supplements were also included as applicable. Request for use of the ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM-1987, with the additional requirements, was submitted by Vermont Yankee and approved by the USNRC [ References (e) and (f)].

All references to the ." Code" made within this IST Program Plan will refer to the

'ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM-1987 unless otherwise

specified.

The IST Program Plan identifies the scope of components (pumps and valves) included in the Third-Interval IST Program, the testing requirements for those components, and justifications or relief requests to support the scope and testing requirements.

Revision 19 Section 1 Page 1 of 2

-gp , - - - * .r-r i

LVcrmnt Yczkee Nctl ,cr Pcwer Stati:n Ins:rvice Testing Progrcm j 1.2 Discussion (cont.) .

The IST. Program Plan provides conformance with Article.IWA-2420 of the 1989 )

Edition of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code and 10  !

CFR 50.55a(a)(3), (f)(5) and (f)(6). J

'Ihe USNRC Safety Evaluations for the 'Ibird-Interval Vermont Yankee IST Program are  !

. provided in References Section.

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Revision 19 Section 1 Page2 of 2

Vcrm::nt Yenkee Nucle:r P.:,wer St ti:n Ins:rvics Tcsting Program 2.0 Program Plan Description The IST Program Plan is comprised of two independent subprogram plans - the Pump Inservice Testing Program Plan and the Valve Inservice Testing Program Plan.

Key features common to both Program Plans are: the Pump and Valve Listings that define the scope of the Third-Interval IST Program, Cold Shutdown and Refueling Outage Justifications, Relief Requests, and applicable Notes.

Administrative and implementing procedures, reference values, test results, and other records required to define and execute the Third-Interval IST Program are retained at Vermont Yankee.

2.1 Test DeferralJustifications In accordance with Paragraphs 4.2.1.2 and 4.3.2.2 of Part 10 of the Code, certain valves are full stroke exercised during Cold Shutdown conditions when the valve cannot be exercised during Normal Operation. When the valve cannot be exercised during Cold Shutdown conditions, then the valve is full stroke exercised during Refueling Outages.

The technical justification for exercising a valve during Cold Shutdowns or Refueling  :

Outages, rather than during Normal Operations, is provided in a Cold Shutdown or

. Refueling Outage Justification.

Valves tested during Cold Shutdowns or Refueling Outages shall be scheduled and tested in accordance with Paragraphs 4.2.1.2 and 4.3.2.2 of Part 10 of the Code.

Cold Shutdown and Refueling Outage Justifications are numbered in a "XXJ-VNN, Revision Z" format, where:

XXJ: CSJ for Cold Shutdown Justifications, ROJ for Refueling Outage Justifications.

V: for Valves.

NN: A unique sequential number, (e.g. CSJ-V03, Rev 0, would be the third Cold Shutdown Justification for Valves). ,

Z: Revision Status.

Revision 19 Section 2 Page 1 of 4

Vermet Yenk:e Nucle:r Pcwer Stati n Inservica Testing Pr:gr:m 2.2 ReliefRequests Specific requests for relief are included in accordance with 10 CFR 50.55a(a)(3), (f)(5) and (f)(6). Where conformance with the requirements of the Code have baen determined to be impracticable, alternate testing is proposed that would provide an acceptable level of quality and safety. Where conformance with the requirements of the Code would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, alternate testing is proposed that would provide useful information to assess the operational readiness of the component tested.

The Relief Requests define the component (s) and test (s) involved, the basis for relief, the proposed attemate testing, and the status of the USNRC evaluation to the Relief Request.

If testing requirements are determined to be impracticable during the course of the interval, additional or modified Relief Requests will be submitted in accordance with 10 CFR 50.55a(f)(4)(iv).

Relief Requests are numbered in a "RR-YNN, Revision Z" format, where:

RR: for Relief Request.

Y: P for Pumps, V for Valves.

NN: A unique sequential number, (e.g. RR-V09, Rev 0, would be the ninth ReliefRequest for Valves).

Z: Revision Status.

2.3 Flow Diagrams k

Table 2-1 provides a listing of those Flow Diagrams which depict the components, subsystems, and systems contained within the Third-Interval IST Program. Drawing number G-191155 explains the symbols and designations provided on the Flow Diagrams.

The Safety Classifications depicted on the Flow Diagrams are subject to the limitations stated in the Vermont Yankee Safety Classification Manual.

"For Information Only" copies of the Flow Diagrams shall be provided with each USNRC Submittal. The copies shall be current as of the date of the IST Program Plan submittal. Controlled copies of the Flow Diagrams are maintained at Vermont Yankee to ensure that all system additions and modifications are addressed in the Third-Interval IST Program.

Revision 19 Section 2 Page 2 of 4

l Vcrmrat Ycckee Nuslear Power St:tica I:s:rvica Tcsting Prcgram Table 2-1  ;

LIST OF INSERVICE TESTING FLOW DIAGRAMS (sorted by flow diagram number)

Flow Diagram System l Number Name I G-191155 Piping and Instrument Symbols G-191159 Sh 1_ Service Water System i

G-191159 Sh 2 Service Water System j G-191159 Sh 3 RCW Cooling Water System G-191159 Sh 5 Recirculation Pump Cooling Water l

G-191160 Sh 3 Instrument Air System '

G-191160 Sh 4 Instrument Air System G-191160 Sh 7 Diesel Generator Starting Air System G-191160 Sh 8 Instrument Air System l l

G-191162 Sh 2 Miscellaneous Systems-Fuel Oil G-191165 Sampling System G-191167 Nuclear Boiler

' G-191168 Core Spray System G-191169 Sh 1 High Pressure Coolant Injection System I G-191169 Sh 2 High Pressure Coolant Injection System i  !

G-191170 Control Rod Drive Hydraulic System G-191171 Standby Liquid Control System G-191172 Residual Heat Removal System r i Revision 19 Section 2 Page3 of 4 )

l Vcrmrt Ycnkee Nucle:r P:wcr St:ti:n Inservic] Testing Progrcm Table 2-1  :

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\

LIST OF INSERVICE TESTING FLOW DIAGRAMS  :

(sorted by flow diagram number) 1 Flow Diagram System Number Name G-191173 Sh 1 Fuel Pool Cooling & Cleanup System G-191173 Sh 2 FuelPool Cooling & Cleanup System G-191174 Sh 1 Reactor Core Isolation Cooling System G-191174 Sh 2 Reactor Core Isolation Cooling System G-191175 Sh 1 Primary Containment & Atmosphere Control G-191175 Sh 2 Primary Containment & Atmosphere Control G-191177 Sh 1 Rdwaste Systems G-191178 Sh 1 Reactor Water Clean Up System G-191237 Sh 2 HVAC - Turbine, Service & Control Room Building l l

G-191238 HVAC - Reactor Building G-191267 Sh 1 Nuclear Boiler Vessel 1nstrumentation i G-191267 Sh 2 Nuclear Boiler Vessel Instrumentation VY-E-75-002 Containment Atmosphere Dilution System 5920-271 Neutron Monitoring System

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Revision 19 Section 2 Page 4 of 4

l Vcrment Ycrkes Nucl:Cr Paw:r St tien Ins:rvice Testing Pr: gram 3.0 References a) License No. DPR-28 (Docket No. 50-271).

b) United States Code of Federal Regulations, Title 10 Chapter 1, Part 50, Section 50.55a (57FR34666, dated August 6,1992). I c) ASME Boiler and Pressure Vessel Code,Section XI, Division 1, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1989 Edition.

d) ASME/ ANSI Standard OMa-1988 Addenda to ASME/ ANSI OM-1987, " Operation and Maintenance ofNuclear Power Plants".

e) Letter, Mr. P.M. Sears, USNRC, to Mr. L.A. Tremblay, VYNPC, " Vermont Yankee l Nuclear Power Station, Approval of the Use of ASME/ ANSI Standard OMa-1988 With Clarification," NVY 92-161, dated September 2,1992.  ;

f) Letter, Mr. J.P. Pelletier, VYNPC, to Document Control Desk, USNRC, " Vermont Yankee Nuclear Power Corporation Inservice Testing Program Update," BVY 92-98, dated August 13,1992.

l g) Leder, Mr. J.G. Partlow, USNRC, to All Holders of Light Water Reactor Operating Licenses and Construction Permits, " Supplement to Minutes of the Public Meetings on Generic Letter 89-04", dated September 26,1991.

h) Letter, Mr. J.G. Partlow, USNRC, to All Holders of Light Water Reactor Operating Licenses and Construction Permits, " Minutes of the Public Meetings on Generic Letter 89-04", NVY 89-239, dated October 25,1989.

i) Letter, Mr. W.P. Murphy, VYNPC, to Document Control Desk, USNRC, " Response to USNRC Generic Letter 89-04: Guidance on Developing acceptable Inservice Testing Programs", BVY 89-90, dated October 3,1989.

j) Letter, Mr. S.A. Varga, USNRC, to All Holders of L*;;ht Water Reactor Operating Licenses and Construction Permits, " Guidance on Developing Acceptable Inservice Testing Programs (Generic Letter 89-04)", NVY 89-75, dated April 3,1989.

k) Letter, Mr. W.P. Murphy, VYNPC, to Dr. Thomas E. Murley, USNRC, " Response to USNRC Generic Letter 87.06: Periodic Verification of Leak-Tight Integrity of Pressure Isolation Valves", FVY 87-64, dated June 11,1987.

l Letter, Mr. R.W. Reid, USNRC, to Mr. R.H. Groce, YAEC, "NRC Staff Guidance for f

1)

Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests Pursuant to 10 CFR 50.55a(g)," dated January 10,1978.

Revision 19 Section 3 Page 1 of 3

\ .

y Vermet Ycakee Nucle:r Pcwer Statinn Ins:;rvice Testing Program -

3.0 _ References (cont.) .

m) Letter, Mr. R.W. Reid, USNRC, to Mr. R.H. 'Groce, YAEC, "NRC Staff Guidance for Complying' with Certain Provisions of 10 CFR 50.55a(g), ' Inservice Inspection

. Requirements'," dated November 17,1976.

n)- Vermont Yankee Final Safety Analysis Report.

o) . Vermont Yankee Technical Specifications.

p) . Vermont Yankee Component Testing Program Plan.

q) Letter, Mr. J.P. Pelletier, VYNPC, to Document Control Desk, USNRC, " Submittal of Vermont Yankee Nuclear Power Corporation Third-Interval Inservice Testing Program Plan and Safety Evaluation Responses," BVY 92-133, dated November 30,1992.

r) . Letter, Mr. D.H. Dorman, USNRC, to Mr. J.P. Pelletier, VYNPC, " Relief from the

. ASME Section XI Requirement to Update (On a' 120-Month Interval) the Inservice Inspection and Testing Programs at Vermont Yankee (TAC No, M85067)," NVY 93-031, dated April 6,1993, s) Letter, Mr. I).H. Dorman, USNRC, to Mr. D.A. Reid, VYNPC, " Safety Evaluation of the Inservice Testing Program Relief Requests for Pumps 'and Valves, Vermont Yankie Nuclear Power Station (TAC No. M85067)," NVY 93-151, dated September 3,1993.

, t) . Letter, Mr. D.A. Reid, VYNPC, to Document Control Desk, USNRC, " Proposed Change No.168 to the Vermont Yankee Technical Specifications - Auxiliary Electric Power System Technical Specifications and Associated Revision to the Vermont Yankee Inservice Testing Program," BVY 93-30, dated August 4,1993.

u) Letter, Mr. W.R. Butler, USNRC, to Mr. D.A. Reid, VYNPC, " Issuance of Amendment No.138 to Facility Operating License No. DPR-28, Vermont Yankee Nuclear Power Station (TAC No. M87171)," NVY 94-45, dated March 22,1994.  ;

i v) Letter, Mr. D.H. Dorman, USNRC to Mr. D.A. Reid, " Safety Evaluation of the Inservice l Test Program Relief Requests for Pumps and Valves, Vermont Yankee Nuclear Power j Station (TAC No. M85067)". l w)~ Letter, Mr. P.F. McKee, USNRC to Mr. D.A. Reid, " Safety Evaluation of Relief l Requests and Action Item Responses for the Third Interval Pump and Valve Inservice l Testing Program - Vermont Yankee Nuclear Power Station, (TAC No. M91450)," NVY j 95-88, dated June 12,1995.  ;

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. Revision 19 Section 3 Page2 of 3 I

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

. Vcrment Ycnkee Nucimr Pswer Statica Inservice Testing Prcgrcm 3.0 References (cont.)

x) Letter, Mr. P.F. McKee, USNRC to Mr. D.A. Reid, " Safety Evaluation of Relief Request RR-V12 for the Third Interval Pump and Valve Inservice Testing Program - Vermont Yankee Nuclear Power Station (TAC No. M92018)," NVY 95-100, dated July 27,1995.

y) USNRC NUREG 1482, dated April 1995, " Guidelines for Inservice Testing at Nuclear l Power Plants".

z) USNRC NUREG/CR-6396,- dated February 19%, " Examples, Clarifications, and Guidance on Preparing Requests for Relief from Pump and Valve Inservice Testing Requirements".

aa) Letter, Mr. K. N. Jabbour, USNRC to Mr. D. A. Reid, " Safety Evaluation of Relief Requests for the Third Interval Pump and Valve Inservice Testing Program - Vermont Yankee Nuclear Power Station (TAC No. M97544)," NVY 98-03, dated January 15, 1998.

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7 Revision 19 - Section 3 Page 3 of 3 t

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1 l

Vcrmert Yorkee N:cle*r Pswer Stati:n Irs:rvice Tcsting Pr:grcm 4.0 ' Pump Inservice Testing Program 4.1 . Scope The Third-Interval Pump Inservice Testing (IST) Program establishes testing requirements to assess the operational readiness of those Safety Class 1, 2, and 3 centrifugal and positive displacement pumps, provided with a Safety Class Electrical -

power source,which are required to:

a) Shut down the reactor to the cold shutdown condition, l b) Maintain the reactor in the cold shutdown condition, or c) Mitigate the consequences of an accident. j Excluded from the above are:

a) Drivers, except where the pump and driver form an integral unit and the pump bearings are in the driver; b) Pumps that are provided with a Safety Class Electrical power source solely for system' design or operating convenience.

4.2 Pump Program Listing Table 4-1, " Pump Listing" lists all pumps included in the Third-Intenal Pump IST Program.

This Table identifies all pumps subject to inservice testing, the inservice test parameters, l testing frequency, tad any applicable relief requests and/or remarks. The column l headings in Table 4-1 are listed and explained below: l Pump Number

- The unique number that identifies the pump. The pump number corresponds to the Maintenance Planning and Control (MPAC) Database utilized at Vermpnt Yankee. Table 4-1 is sorted by Pump Number.

Nomenclature The common name for the pump.

Drawing The Flow Diagram which depicts the pump. If the pump appears on multiple Flow Diagrams, then the primary Flow Diagram identifier is listed.

Revision 19 Section 4 Page 1 of 31

1 Vcrm=t Yenkee N cirr Pcwer Stati:n Ins:rvice Tcsting Pr: gram 4.2 Pump Program Listing (cont.)

Dwg Coor The coordinate location (e.g., D-05) on the Flow Diagram where the pump appears.

Safety Class The safety classification of the pump, as determined in accordance with administrative

. procedure AP 0014, " Safety Class Determination Instructions," and the Vermont Yankee Safety Classification Manual.

I Pump Type

' The pump type:

CENT for Centrifugal pumps.

VERT for Verticalline shaft pumps.  !

PD-RECIP for Positive Displacement Reciprocating pumps. I PD-ROT for Positive Displacement Rotary pumps. l Test Type

  • I The Inservice Test Parameters to be determined and recorded during testing performed in  ;

accordance with Paragraph 5 of Part 6 of the Code. The abbreviations correspond to i those provided in Table 2 of Part 6 of the Code:  !

l N for Speed,(if variable speed). j dP for differential Pressure, (for centrifugal and vertical line shaft pumps).  ;

P for discharge Pressure, (for positive displacement pumps). 1 l Q for Flow Rate. 1 Vv . for Vibration, velocity, peak. -

Test Freq The test frequency associated with each test type.

t OC for Once Per Operating Cycle l Q for Quarterly '

i l RO for Reactor Refueling Outage 4

Revisina 19 Section 4 Page 2 of 31

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Vcrm :t Yc:kee Nrcle:r Pcw r Statim- Inservics Tcsting Pregrsm ,

l 4.2 Pump Program Listing (cont.) -

ReliefRequest I

- The Relief Request number associated with the subject pump and test type or test frequency,where applicable.

Remarks Clarifying comments or other remarks related to the subject pump and test type or test j frequency, where applicable.

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f Revision 19 Section 4 Page3 of 31

Vermont Ycckee N: clear Power Statio:2 Inservice Testing Program i

Table 4-1 Punip Listing Dwg Sa W . Pump Test Test Relief Remarks Pump Number Nomenclature Drawing Coor Class Type Type Freq Request [

P-10-1 A RHR(LPCI) Pump G-191172 Ir05 2 CENT Fixed dP Q n/a

- Q Q n/a Vv Q n/a RHR(LPCI) Pump G-191172 L-12 2 CENT Fixed dP Q n/a P-10-1B ,

. Q Q n/a Vv Q .n/a P-10-1C RilR(LPCI) Pump G-191172 J-05 2 CENT Fixed dP Q n/a-Q Q n/a Vv Q n/a RHR(LPCI) Pump G-191172 J-12 2 CENT Fixed dP Q n/a P-10-1D Q Q n/a VV Q n/a Standby FuelPool G-191173 Sh 2 G-12 3 CENT Fixed dP Q n/a P-19-2A Cooling Pump Q Q n/a VV Q n/a Standby FuelPool G-191173 Sh 2 I-12 3 CENT Fixed dP Q n/a P-19-2B Cooling Pump Q Q n/a Vv Q n/a P-213-1 A RCIC Gland Seal G-191174 Sh 2 K-13 3 PD-RECIP Fixed SKID Q n/a Condensate Pump '

HPCI(High Pressure) G-191169 Sh 2 G-10 2 CENT Vari dP Q RR-P02 P-44-IA RR-P03 Pump N Q n/a Q Q RR-P02 Vv Q RR-PO4 Revision 19 Section 4 Page 4 of 31

Vcrmont Ycckee N: clear Power Statica Inservice Testing Program Table 4-1 Pump Listing-8' M Remarks -

Pump Nunber Nomenclature Drawing Speed P-44-1B HPCI(Booster) Pump G-191169 Sh 2 G-11 2 CENT. Vari dP Q RR-P02

. RR-P03 N Q n/a Q- Q- RR-P02 Vv- Q P-45-1A SLC Pump G-191171 H-OF [ . PD-RECIP Fixed P Q n/a .

Q Q n/a Vv Q n/a P-45-1B SLC Pump G-191171 Md 2 PD-RECIP Fixed P Q n/a Q Q n/a Vv Q n/a P-46-1A CS Pump G-191168 J-li 2 ' CENT Fixed dP Q. RR-POS Q Q n/a Vv Q n/a P-46-1B CS Pump G-191168 J-14 2 CENT Fixed dP Q RR-P05 Q Q n/a Vv Q n/a P-47-1 A RCIC Pump G-191174 Sh 2 F-08 2 CENT Vari dP Q RR-P06 .

N Q n/a ,

Q Q n/a VV Q n/a P-59-IA RBCCW Pump G-191159 Sh 3 A-07 3 CENT Fixed dP Q RR-P08 l

Q Q Wa VV Q n/a P-59-1B RBCCW Pump G-191159 Sh 3 B-07 3 CENT Fixed dP Q RR-P08 Q~ Q n/a Vv Q n/a a

Revision 19 Section 4 Page 5 of 31.

Vcrmont Yankee Nuclear Power Station Inservice Testirg Program Table 4-1 Pump Listing .

Pump Number Nomenclature Drawing Dwg ISafe Pump Speed Test Tat W Remarks Coor: Class Type Type Freq Request P-7-1A isB Service Water Pump G-191159 Sh I C-02 3 VERT Fixed dP RO RR-P01 Note 1

- dP Q n/a Q RO RR-Pol Vv RO RR-P01

. Vv Q n/a P-7-1B 18B Service Water Pump G-191159 Sh 1 B-02 3 VERT Fixed dP RO RR-Pol Note I dP Q n/a Q RO RR-Pol Vv RO RR-Pol Vv Q n/a P-7-IC 18B Service Water Pump G-191159 Sh 1 K-02 3 VERT Fixed dP RO RR-P01 Note I dP Q n/a Q RO P?.-P01 Vv RO R "'- J Vv Q n/a P-7-ID 18B Service Water Pump G-191159 Sh 1 J-02 3 VERT Fixed dP RO RR-P01 Note I dP Q n/a Q RO RR-Pol Vv RO - RR-P01 Vv Q n/a P-8-1A RIIR Service Water Pump G-191159 Sh 1 K-11 3 VERT Fixed dP Q n/a Q Q n/a Vv Q n/a P-8-1B RilR Service Water Pump G-191159 Sh i A-11. 3 VERT Fixed dP Q n/a Q Q n/a Vv Q n/a P-8-1C RHR Service Water Pump G-191159 Sh 1 K-11 3 VERT Fixed dP Q n/a Q Q n/a Vv Q n/a Revision 19 Section 4 Page 6 of 31

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 4-1 Pump Listing Nomenclature Drawing Dwg Sa W Pump Speed TM Test W Remarks Pump Number Freq Coor Class Type Type Request P-8-1D RHR Service Water Pump G-191159 Sh 1 B-11 3 VERT Fixed dP Q n/a Q Q n/a VV Q n/a P-87-1A HPCIGland Seal G-191169 Sh 2 K-17 3 PD-RECIP Fixed S!'ID Q n/a Condensate Pump -

P-92-1A DFOTPump G-191162 Sh 2 E-05 3 PD-ROT Fixed P Q n/a Q Q RR-P09 Q OC RR-P09 Vv Q n/a P-92-1B DFOT Pump G-191162 Sh 2 D-05 3 PD-ROT Fixed P Q n/a Q Q RR-P09 Q OC RR-P09 Vv Q n/a P-92-2A Diesel Generator DG G-191162 Sh 2 F-11 3 PD-ROT Vari SKID Q -n/a I A Engine Driven Fuel OilPump P-92-2B Diesel Generator DG G-191162 Sh 2 D-11 3 PD-ROT Vari SKID Q n/a IB Engine Driven Fuel Oil Pump SP-1 Control Room HVAC G-191237 Sh 2 E-4 3 CENT Fixed dP Q n/a Chilled Water Pump Q Q n/a Vv Q n/a Revision 19 Section 4 Page 7 of 31

Vcrmm:t Yenkee Nuclemr Power Stztien Inservice Testing Pregram 4.3 Pump Notes

1. In~ accordance with the June 12,1995 Safety Evaluation Report (Reference w) the following commitments were made relating to inservice testing of the Vermont Yankee Service Water Pumps (P7-1 A through P7-ID):

Quarterly Testing (As-found for each pump)

1. Differential Pressure Measurement (for information only)
2. Full Spectrum Vibration Signatures (for information only)
3. Overall Vibration Measurements (compared to code limits)

Once Per Operating Cycle

1. One of the four service water pumps will be disassembled, inspected and refurbished as necessary. Additionally, in no case shall a service water pump exceed a period of 4 cycles of operation without being disassembled, inspected and refurbished as necessary.

- Refuel'ing Outage l

1. Full code specified IST testing will be performed at a flow rate greater than  !

or equal to design flow. I

2. A head curve will be generated to provide information so that the performance of the pump can be compared to the degree possible with the as-found quarterly data and previous refueling outage head cutve data.

The approval of relief request RR-P01 is not subject to the performance of shutoff head testing or motor amperage monitoring as originally proposed in RR P01.

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Revision 19 Section 4 Page 8 of 31

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Verm:nt Ycnkee Nuclear Pcwer St:tisn Inservice Testing Program RELIEF REOUEST Number: RR-P01, Revision 1 (Sheet 1 of 4)

SYSTEM: Service Water l

l COMPONENTS:

i l Pump Number Safety Class Drawing Number Dwg. Coord.

P7-1A 3 G-191159 Sh 1 C-02 P7-1B 3 G-191159 Sh 1 B-02 P7-lC 3 G-191159 Sh 1 K-02 P7-ID 3 G-191159 Sh 1 J-02 l

These pumps are the station Service Water pumps. They have the safety function to provide cooling water to systems and equipment required to operate under accident conditions and to i

, provide an inexhaustible supply of water for standby coolant system operation.

EXAM OR TEST CATEGORY: 1 I

Flow Rate (Q). . l CODE REOUIREMENT: Part 6 Para. 5.1 " Frequency ofInservice Tests" "An inservice test shall be run on each pump, nominally every 3 months, except as I provided in paras. 5.3, 5.4, and 5.5." l REOUEST FOR RELIEF: l Reliefis requested on the basis that compliance with the Code requirements is impracticable and that the proposed alternatives would provide an acceptable level of quality and safety.

During normal operations, neither differential pressure nor flow rate can be fixed or directly measured. Pump vibration levels may also vary due to the inability to establish a repeatable reference condition.

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Revision 19 Section 4 Page 9 of 31

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Vermant Ycnkse Nuclerr Power Station Inservice Testing Prsgram RELIEF REOUEST Number: RR-P01, Revision 1 (Sheet 2 of 4) a REOUEST FOR RELIEF (cont.h The four Service Water pumps are vertical, two-stage, centrifugal-type pumps which are submerged in and take suction from the Connecticut River. They supply all the station Service Water System requirements. The station Service Water System is a dual header system using two parallel headers each containing two pumps. The two parallel headers supply both the turbine

, and reactor auxiliary equipment, including the Residual Heat Removal Service Water System. A header interconnection is provided downstream of the pumps. Normally, the valves in the interconnecting line are open, permitting any of the pumps to supply the cooling water to both headers and to balance system operation. In addition, a cross-tie is provided to the non-nuclear safety station Fire Protection System. The 12-inch cross tie valve is normally closed, with a 1-inch cross-tie and a restricting orifice providing pressurization of the Fire Protection System header.

The Service Water System contains both automatic temperature and flow control valves used to independently regulate the cooling provided to the various turbine and reactor auxiliary I

equipment. Due to seasonal variations in Connecticut River water temperature and level and constantly changing heat loads, the system resistance and flow rate vary. The nu.nber of station Service Water pumps in operation is also varied dependent on system requireme.its. Due to these J
variations and the need to maintain proper cooling, it is considered impracticable to establish repeatable reference values during quarterly inservice testing.

i As a result, it is impractica'cle to directly measure pump flow rate on a quarterly and cold 4 shutdown frequency. SmTicient stvight sections of piping are required to properly measure flow rate, through the use of either perma lently or temporarily installed instrumentation, such as non-intrusive flow measurement devices.

The only sufficient straight sections of piping in each of the two parallel headers exist between the intake structure and the entrance to the reactor building. Use of this piping is considered

impracticable because

a) These sections of the two parallel headers are buried piping. .

b) As discussed above, each parallel header is common to two pumps and is cross-connected to the other header. Thus, in order to measure flow rate for one pump, the parallel pump in the same header would have to be secured and the valves in the header interconnecting line closed. This would result in single pump operation for the portion of the station Service Water System supplied by the pump being tested.

Revision 19 Section 4 Page 10 of 31

Vcrm:nt Ycakee Nuclear Pcwer Statisn Inservice Testing Pr: gram RELIEF REOUEST Number: RR-P01, Revision 1 (Sheet 3 of 4)

REOUEST FOR RELIEF (cont.h c) All four station Service Water pumps are required to be operating during power operations and cold shutdowns during approximately 7 months of the year to meet cooling load requirements.

Based on the above, significant redesign and modification of the station Service Water System

would be required to obtain direct measurement of pump flow. Such redesign and modification would be costly and burdensome to Vermont Yankee.

A review of the historical test data for these pumps indicates that theses pumps are highly reliable and have not been susceptible to frequent failures. Plant operating experience has shown that the performance of the Service Water pumps degrades slowly over an extended period due to

normal system wear.

l ALTERNATE METHOD:

On a quarterly basis, during plant operation and cold shutdowns an as-found test will be performed by measuring pump differential pressure and motor vibration and the data will be j compared to the degree possible with test data taken during the refueling outage head curve data.

During each refueling outage, pump flow, differential pressure and vibration will be measured at a reference condition which will meet or exceed the required design conditions for the pump. A temporary flow test loop installed on the plant fire protection system will be utilized to directly measure pump flow. 'Ihis will provide a mechanism to assess the hydraulic condition of the pump and to detect pump degradation against the code required limits. An additional reference condition will be established with the pump at a dead head condition where pump vibration and differential pressure can be measured for comparison in the event that maintenance is required to be performed between refueling outages.

Additionally, a head curve will be generated each refueling outage to provide information so that the performance of the pump can be compared to the degree possible with the as-found quarterly test data and previous refueling outage head curve data. Overall peak and full spectrum vibration measurements will be also be taken at each of the points used to generate the head curve to provide additional operational information.

Revision 19 Section 4 Page 11 of 31

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i Vermant Yenkee Nucl:or Pcwer Statias Inservics Testing Pr gram 1 i RELIEF REOUEST

i. i Number: RR-P01, Revision 1 (Sheet 4 of 4)'

ALTERNATE METHOD (cont.h l A review of the operating history of these pumps has shown that they are highly reliable and l have not been susceptible to frequent failures. In order to provide additional assurance of proper l pump operation and mechanical condition, an enhanced maintenance / monitoring program for i these pumps will be established which will include the following:

i

1. Service water pump motor amperage will be monitored on a once per shift frequency L 'during periods when the pumps are in operation.

! ' 2. Full spectrum vibration signatures of the accessible motor bearing points will be obtained l and analyzed on a quarterly basis.

l 3. At least one service water pump will be partially disassembled, inspected and refurbished l as required every operating cycle. Additionally, in no case shall a service water pump i exceed a period of 4 cycles of operation without being partially disassembled, inspected l . and refurbished as required.

USNRC EVALUATION STATUS: i L Provisional relief was g' ranted in the September 1993 SER [ Reference (s)) for Relief Request l

- RR-P01, Revision 0. Approval of Revision 1 of Relief Request RR-P01, was granted in the June l

L 1995 SER [ Reference (w)]. Granting RR-P01 Rev.1 was not subject to monitoring pump motor l amperage each shift or refueling outage shutoff head testing as specified in the relief request. ' I l

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i Revision 19 Section 4 Page 12 of 31

Vcrm:nt Ycnkee Nucl=r P:wer Statian Inservica Tcsting Pr: gram l

RELIEF REOUEST 4 l

Number: RR-P02, Revision 0 (Sheet 1 of 2)  ;

SYSTEM: High Pressure Coolant Injection i

COMPONENTS: l l

Pump Number Safety Class Drawing Number Dwg. Coord.

P44-1A 2 G-191169 Sh 2 G-11 P44-1B 2 0-191169 Sh 2 G-10 I P44-1A and P44-1B are the High Pressure Coolant Injection (HPCI) main (high pressure) and l booster (low pressure) pumps, respectively. They have the safety functions to operate in series to l

provide 1) adequate core cooling and reactor vessel depressurization following a small break j loss of coolant accident, and 2) reactor pressure control during reactor shutdown and isolation.

! EXAM OR TEST CATEGORY:

l Differential Pressure (dP).

i Flow Rate (Q). .

CODE REOUIREMENT: Part 6 Para. 4.6.2.2 " Differential Pressure" l "When determining differential pressure across a pump, a differential pressure gauge or transmitter that provides direct measurement of pressure difference or l the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe, may be used."

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Para. 4.6.5 " Flow Rate Measurement" "When measuring flow rate, use a rate or quantity meter installed in the pump test circuit. If a meter does not indicate the flow rate directly, the record shall include i the method used to reduce the data." ,

j REOUEST FOR RELIEF:

Reliefis requested on the basis that the proposed altematives would provide an acceptable level ofquality and safety.

There is no means of measuring the differential pressure or the flow rate generated by each of these pumps individually. Installation ofindependent means of measurement for each pump is considered impracticable and would be costly and burdensome to Vermont Yankee.

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Revision 19 Section 4 Page 13 of 31 I

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Vcrm:ct Ycckee Nucl:cr P:wcr Stati:n Inservica Testing Prcgram ,

RELIEF REOUEST Number: RR-P02, Revision 0 (Sheet 2 of 2)

ALTERNATE METHOD:

Differential pressure and flow rate parameters will be measured across both HPCI pumps as an integral unit. Vibration monitoring will be performed for each pump individually. Both pumps will be inspected and repaired as necessary if any abnormal conditions in differential pressure or flow rate occur.

USNRC EVALUATION STATUS:

Relief was granted in the September 1993 SER [ Reference (s)) for Relief Request RR-P02, Revision 0.

Revision 19 Section 4 Page 14 of 31

Verm:nt Ycnkea Nucl:er P wer Stati:n Ins:rvics Testing Program .

RELIEF REOUEST l

Number: RR-P03, Revision 1 (Sheet 1 of 2)

SYSTEM: High Pressure Coolant Injection l

COMPONENTS:

Pump Number Safety Class Drawing Number Dwg. Coord.

P44-1A 2 G-191169 Sh 2 G-11 P44-1B 2 G-191169 Sh 2 G-10 l P44-1A and P44-1B are the High Pressure Coolant Injection (HPCI) main (high pressure) and .

booster (Iow pressure) pumps, respectively. 'Ihey have the safety functions to operate in series to I provide 1) adequate core cooling and reactor vessel depressurization following a small break  !

loss of coolant accident, and 2) reactor pressure control during reactor shutdown and isolation.

l EXAM OR TEST CATEGORY:

Differential Pressure (dP).

CODE REOUIREME T: Part 6 Para. 4.6.1.2(a) " Range" "The full-scale range of each analog instrument shall not be greater than three times the reference value."

Para. 4.6.2.2 " Differential Pressure" "When determining differential pressure across a pump, a differential pressure gauge or transmitter that provides direct measurement of pressure difference'or the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe, may be used."

l REOUEST FOR RELIEF _1 -

Reliefis requested on the basis that the proposed alternatives would provide an acceptable level ofquality and safety.

i Revision 19 Section 4 Page 15 of 31 l

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- Wrmont Yankee Nucle:r Pcwer St:tica Inservics Testing Program BELIEF REOUEST l

Number: RR-P03, Revistor.1 (Sheet 2 of 2) l REOUEST FOR RELIEF (cont.):

- Differential pressure across the HPCI pumps is determined by the difference between pressure l measurements taken at a point in the inlet pipe and at a point in the discharge pipe as allowed by Paragraph 4.6.2.2 of Part 6 of the Code. The installed HPCI pump inlet pressure indicators are

! designed to provide adequate inlet pressure indication during all expected operating and post accident conditions. The full scale range,85 psig, is sufficient for a post accident condition when the suppression chamber is at the maximum pressure. This, however, exceeds the full-scale range l limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 26 psig, Limit = 78 psig).

l The suction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure. The installed gauges are calibrated to within +/- 1.17%

L _ accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be +/- 0.99 psi. This is considered to be suitable for determining that adequate NPSH is available for HPCI pump operation.

l Pump discharge pressure during testing is approximately 1170 psig, which results in a calculated differential pressure of approximately 1144 psig. The resulting inlet pressure inaccuracy of +/-

0.99 psi represents an error in differential pressure measurement of +/- 0.08% (0.99 psi /1144

- psid = 0.00086). This is consistent with Table 1 of Part 6 of the Code, which requires that

instrument accuracy for differential pressure be better than 2% of full-scale.

ALTERNATE METHOD:

! Differential pressure will be measured using the existing station system installed inlet pressure

( indicators.

! USNRC EVALUATION STATUS:

Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-P03, Revision 1. ,

6 Revision 19 Section 4 Page 16 of 31

Verm:nt Yenk:e Nucl=r P wer St:tien Inservic Testing Prrgrcm RELIEF REOUEST Number: RR-PO4, Revision 0 (Sheet 1 of 3)

SYSTEM: High Pressure Coolant Injection COMPONENTS: I Pump Number Safety Class Drawing Number Dwg. Coord.

P44-1A 2 G-191169 Sh 2 G-11 P44-1 A is the High Pressure Coolant Injection (HPCI) main (high pressure) pump. The main pump has the safety function to operate in series with the booster pump, P44-1B, to provide 1)  :

adequate core cooling and reactor vessel depressurization following a small break loss of coolant l accident, and 2) reactor pressure control during reactor shutdown and isolation.

j EXAM OR TEST CATEGORY:

Vibration Velocity (Vv).

CODE REOUIREMENT: Part 6 Para. 5.2(d) " Test Procedure"

" Pressure, flow rate, and vibration (displacement or velocity) shall be determined and compared with corresponding reference values. All deviations from the reference values shall be compared with the limits given in Table 3 and corrective action taken as specified in para. 6.1."

REOUEST FOR RELIEF:

Reliefis requested on the basis that the proposed alternatives would provide an acceptable level of quality and safety.

Past testing and analysis performed on the HPCI System by Vermont Yankee, the pump manufacturer, and by independent vibration consultants has revealed characteristic pump vibration levels which exceed the acceptance criteria stated in Table 3 of Part 6 of the Code. This testing and analysis meets the intent of Paragraph 4.3 and footnote 1 of Part 6 of the Code.

Revision 19 Section 4 Page 17 of 31

Vcrment Ycnkea Nuclear Pcwer Stati:n Ins 2rvica Testing Program RELIEF REOUEST Number: RR-P04, Revision 0 (Sheet 2 of 3)'

REOUEST FOR RELIEF (cont.h 1

i ne root causes of the higher vibration levels have been determined to be:

a) ' An acoustical resonance in the piping connecting the low pressure (LP) and high pressure (HP) pumps, and _ ,

' b) The presence of a structural resonance in the horizontal direction on the HP pump.

These resonance conditions are design related and have existed since initial pump installation.

They have been documented over a number of years of operating experience. j i

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' An additional past contributor to the higher vibration levels was the excitation resulting from the J blade pass frequency from the previously installed four vane impeller in the low pressure (LP) pump. In an effort to reduce / eliminate this effect, the four vane impeller was replaced with a five vane impeller during the 1989 refueling outage. This replacement significantly_ reduced vibration levels in both the LP and HP pumps. However, due to the resonance effects referenced above, the j HP pump vibration levefs remain higher than the acceptance criteria stated in Table 3 of Part 6 of I the Code. j Although existing vibration levels in the HP pump are higher than standard acceptance criteria, I they are acceptable and reflect the unique operating characteristics of the HPCI pump. It has been concluded that there are no major vibrational concems that would prevent the HPCI pump from i performing its intended function.

1 ALTERNATE METHOD: i To allow for practicable vibration monitoring of the HPCI HP pump, altemate vibration acceptance criteria are required. Full spectrum vibrational monitoring will be performed during

each quarterly test and the following criteria will be used for the HP pump

Test Parameter Accentable Ranne Alert Ranne Reauired Action Ranne  ;

V, s 2.5 Vr > 2.5 Vr to and > 6 Vr but not including 6 Vr or

> 0.675 in/sec, but not > 0.70 in/sec.

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> 0.70 in/sec.

In addition, the resonance peaks will be evaluated during each test and will have an Acceptable Range upper limit of 1.05 Vr and an Alert Range upper limit of 1.3 Vr.

He standard acceptance criteria of Table 3 of Part 6 will be applied to the LP pump.

Revision 19 Section 4 Page 18 of 31

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. Vcrm
nt Yc kee Nuclear P w:r St:ti:a Inservice Testing Prcgram I

1 RELIEF REOUEST ,

i Number: RR-PO4, Revision 0 (Sheet 3 of 3)

USNRC EVALUATION STATUS
)

Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-P04,

! Revision 0.

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Verm:nt Yenkee Nuclear Power Station Inservice Testing Program i

RELIEF REOUEST Number: RR-P05, Revision 1 (Sheet 1 of 2)

SYSTEM: Core Spray COMPONENTS:

Pump Number Safety Class Drawing Number Dwg. Coord.

P46-1A 2 G-191168 J-l1 P46-1B 2 G-191168 J-14 P46-1 A & B are the low pressure Core Spray pumps. They have the safety function to operate to provide adequate core cooling following a loss of coolant accident and reactor depressurization.

EXAM OR TEST CATEGORY:

DifTerential Pressure (dP).

CODE REOUIREMENT: Part 6 Para. 4.6.1.2(a) " Range" "The full-scale range of each analog instrument shall not be greater than three times the reference value."

l Para. 4.6.2.2 " Differential Pressure" l "When determining differential pressure across a pump, a differential pressure gauge or transmitter that provides direct measurement of pressure difference or the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe, may br/used."

REOUEST FOR RELIEF:

Reliefis requested on the basis that the proposed altematives would provide an acceptable level l of quality and safety.

i Differential pressure across the Core Spray pumps is determined by the difference between i pressure measurements taken at a point in the inlet pipe and at a point in the discharge pipe as allowed by Paragraph 4.6.2.2 of Part 6 of the Code. The installed Core Spray pump inlet pressure indicators are designed to provide adequate inlet pressure indication during all expected operating and post accident conditions. The full scale range,60 psig, is sufficient for a post accident condition when the suppression chamber is at the maximum pressure. This, however, exceeds the full-scale range limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 7.5 psig, Limit = 22 psig).

l Revision 19 Section 4 Page20 of 31 l

l

Verment Yankee Nuclezr Pcwer St: tion Ins:rvice Testing Program

. RELIEF REOUEST Number: RR-P05, Revision 1 (Sheet 2 of 2)

REOUEST FOR RELIEF:

The suction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure. The installed gauges are calibrated to within +/- 1.6%

accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be +/- 0.96 psi. This is considered to be suitable for determining that adequate NPSH is available for Core Spray pump operation.

Pump discharge pressure during testing is approximately 240 psig, which results in a calculated differential pressure of approximately 232.5 psig. The resulting inlet pressure inaccuracy of +/-

0.96 psi represents an error in differential pressure measurement of +/- 0.41% (0.96 psi /232.5 psid = 0.0041). This is consistent with Table 1 of Part 6 of the Code, which requires that instrument accuracy for differential pressure be better than 2% of full-scale.

ALTERNATE METHOD:

Differential pressure will be measured using the existing station system installed inlet pressure indicators.

USNRC EVALUATION STATUS:

Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-P05, Revision 1.

Revision 19 Section 4 Page 21 of 31

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Verment Yankee Nuclecr Power Stction Inservice Testing Program RELIEF REOUEST Number: RR-P06, Revision 1(Sheet 1 of 2)

SYSTEM: Reactor Core Isolation Cooling COMPONENTS:

Pump Number Safety Class Drawing Number Dwg. Coord.

P47-1A 2 G-191174 Sh 2 F-08 P47-1 A is the Reactor Core Isolation Cooling (RCIC) pump. It has the safety function to operate to provide makeup water to the reactor vessel during shutdown and isolation in order to prevent the release ofradioactive materials to the environs as a result ofinadequate core cooling.

EXAM OR TEST CATEGORY:

I Differential Pressure (dP).

CODE REOUIREMENT: Part 6 4

Para. 4.6.1.2(a) " Range" "The full-scale range of each analog instrument shall not be greater than three times the reference value."

'i Para. 4.6.2.2 " Differential Pressure" "When determining differential pressure across a pump, a differential pressure gauge or transmitter that provides direct measurement of pressure difference or the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe, may be used."

REOUEST FOR RELIEF:

Reliefis requested on the basis that the proposed alternatives would provide an acceptable level ofquality and safety.

- Differential pressure across the RCIC pump is determined by the difference between pressure measurements taken at a point in the inlet pipe and at a point in the discharge pipe as allowed by Paragraph 4.6.2.2 of Part 6 of the Code. The installed RCIC pump inlet pressure indicators are designed to provide adequate inlet pressure indication during all expected operating and post accident conditions. The full scale range, 85 psig, is sufficient for a post accident condition when the suppression chamber is at the maximum pressure. This, however, exceeds the full-scale range

- limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 20 psig, Limit = 60 psig).

- Revision 19 Section 4 Page 22 of 31

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Vcrm:nt Ycnkee Nucl:cr Paw:r St.:ti:n Ins:rvics Tcsting Prcgram RELIEF REOUEST Number: RR-P06, Revision 1(Sheet 2 of 2)

REOUEST FOR RELIEF:

The suction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure. The installed gauges are calibrated to within +/- 1.17%

accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be +/- 0.99 psi. This is considered to be suitable for determining that adequate NPSH is available for RCIC pump operation.

Pump discharge pressure during testing is approximately 1130 psig, which results in a calculated differential pressure of approximately 1110 psig. The resulting inlet pressure inaccuracy of +/-

0.99 psi represents an error in differential pressure measurement of +/- 0.09% (0.99 psi /1110 psid = 0.00089). This is consistent with Table 1 of Part 6 of the Code, which requires that instrument accuracy for differential pressure be better than 2% of full-scale.

ALTERNATE METHOD:

Differential pressure wil,1 be measured using the existing station system installed inlet pressure indicators.

USNRC EVALUATION STATUS:

Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-P06, Revision 1.

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Revision 19 Section 4 Page 23 of 31 A

Vcrm::t Ycnkee Nucirr Pawar St:tica Inservice Testing Program RELIEF REOUEST ,

Number: RR-P07, Revision 0 (Sheet 1 of 1)

THIS RELIEF REQUEST WAS DELETED IN REVISION 15 OF THE IST PROGRAM.

i This RR number is being maintained for traceability to the Third Interval IST Program Submittal  !

SER's.  :

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i Revision 19 Section 4 Page 24 of 31

Verment Yenk:e Nucler Pswer Stati::n Inservice Testing Program l

RELIEF REOUEST Number: RR-P08, Revision 0 (Sheet 1 of 2) l l

SYSTEM: Reactor Building Closed Cooling Water i COMPONENTS:

[ PumpNumber Safety Class Drawing Number Dwg. Coord.

P59-1 A 3 G-191159 Sh 3 A-07 P59-1B 3 0-191159 Sh 3 B-07 l- These pumps are the Reactor Building Clol sed Cooling Water (RBCCW) pumps. They have a safety function to provide cooling water to the safety related cooling loads served by the RBCCW system.

EXAM OR TEST CATEGORY:

Differential Pressure (dP).

CODE REOUIREMENT: Part 6 Para. 4.6.1.2(a) " Range" "The full-scale range of each analog instrument shall not be greater than three times the reference value."

i Para. 4.6.2.2 " Differential Pressure" "When determining differential pressure across a pump, a differential pressure gauge or transmitter that provides direct measurement of pressure difference or the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe, may be used."

REOUEST FOR RELIEF:

Reliefis requested on the basis that the proposed alternatives would provide an acceptable level  ;

ofquality and safety.  !

Differential pressure across the RBCCW pumps is determined by the difference between pressure measurements taken at a point in the inlet pipe and at a point in the discharge pipe as allowed by Paragraph 4.6.2.2 of Part 6 of the Code. The installed RBCCW pump inlet pressure indicators, with a full scale range of 30 psig, are designed to provide adequate inlet pressure indication during all expected operating and post accident conditions. This, however, exceeds the full-scale range limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 6.5 psig, Limit = 19 psig).

Revision 19 Section 4 Page 25 of 31

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I Verm::t Ycnkee Nuclear Pcwer St:ti:n Inservice Testing Program RELIEF REOUEST Number: RR-P08, Revision 0 (Sheet 2 of 2)

BEQUEST FOR RELIEF (cont.):

The saction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure. The installed gauges are calibrated to within +/- 0.4%

accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be +/ .12 psi. This is considered to be suitable for determining that adequate NPSH is available for RBCCW pump operation.

Pump discharge pressure during testing is approximately 80 psig, which results in a calculated differential pressure of approximately 73.5 psig. The resulting inlet pressure inaccuracy of +/ .12 psi represents an error in differential pressure measurement of +/- 0.16% (.12 psin3.5 psid =

0.0016). This is consistent with Table 1 of Part 6 of the Code, which requires that instrument accuracy for differential pressure be better Gian 2% of full-scale.

ALTERNATE METHOD:

Differential pressure wil,1 be measured using the existing station system installed inlet pressure indicators.

USNRC EVALUATION STATUS:

Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-P08, Revision 0.

I Revision 19 Section 4 Page 26 of 31

Vcrment Ycnkee Nuclear Power Station Inservice Testing Program RELIEF REOUEST ,

Number: RR-P09, Revision 0 (Sheet 1 of 4)

SYSTEM: Diesel Fuel Oil-COMPONENTS:

i PumpNumber Safety Class - Dawing Number Dwg. Coord.

P92 1A 3 G-191162 Sh 3 E-05 l

P92-1B 3 G-191162 Sh 3 D-05 i

These pumps are the Diesel Fuel Oil Transfer pumps. They have a safety function to provide

. diesel fuel oil to the diesel oil day cank during Emergency Diesel Generator operations.

EXAM OR TEST CATEGORY:

Flow Rate (Q).

CODE REOUIREMENT
Part 6 Para. 4.6.5 " Flow Rate Measurement" "When measuring flow rate, use a rate or quantity meter installed in the pump test circuit. If a meter does not indicate the flow rate directly, the record shall i include the method used to reduce the data."

Para. 5.1 " Frequency ofInservice Tests" "An inservice test shall be run on each pump, nominally every 3 months,

except as provided in paras. 5.3, 5.4, and 5.5."

l l REOUEST FOR RELIEF:

1 t

l Relief is requested on the basis that compliance with the Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety and that the proposed alternatives would provide an acceptable level of quality and safety.

During quarterly inservice testing, pump flow rate cannot be directly measured.  !

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Revision 19 Section 4 Page 27 of 31 3 m m .oc - . - - . . . - - . , - - - , - - - . ~ . ,

i Vermant Yankee Nucleir Power Statisn Inservice Testing Prcgram RELIEF REOUEST j Number: RR-P09, Revision 0 (Sheet 2 of 4) l i

REOUEST FOR RELIEF (cont.h

! 'Ihe Emergency Diesel Generator fuel oil supply system consists of two parallel trains, one for each diesel. Fuel oil is supplied directly to th' diesel fuel block from the 800-gallon day tank.  !

Makeup to each diesel day tank is accompl'.,ned automatically from the 75,000-gallon storage tank by operation of the respective Diesel Fuel Oil Transfer pump. The diesel day tank is sized

for three (3) hours of continuous full load operation, based on a diesel fuel oil consumption rate l of approximately 3.4 gpm. The Diesel Fuel Oil Transfer pumps are positive displacement pumps l l with a design capacity of approximately 8.7 gpm. I p It is considered impracticable to directly measure pump flow rate on a quarterly basis. There is j no flow rate instrumentation installed in the Fuel Oil Transfer system. Sufficient straight sections L of piping are required to properly measure flow rate, through the use of either permanently or E temporarily installed instrumentation, such as non-intrusive flow measurement devices. The only

[ sufficient straight sections of piping exist in the buried sections of the supply headers.

Installation of flow rate instrumentation or a pump test loop would require significant system  !

1 redesign and modification, which would be costly and burdensome to Vermont Yankee.

I 4

Diesel Fuel Oil Transfer pump flow rate can be determined indirectly by measuring the level change in the diesel day tank versus the pump operating time required to make that change.

} However, in order to allow for evaluation of the test results against the acceptance criteria of j Table 3 of Part 6 of the Code, the test must be performed with the respective Emergency Diesel Generator secured. This eliminates the unknown variability of the diesel fuel oil consumption rate.

In addition, in order to provide measurement accuracy comparable with Table 1 of Part 6 of the l Code, the automatic pump start feature on low diesel day tank level must be disabled and the diesel day tank volume reduced prior to the test through operation of the respective Emergency l Diesel Generator.

Disabling the automatic start feature of the Diesel Fuel Oil Transfer pump on low diesel day tank level lessens the ability of the Emergency Diesel Generator to operate automatically without  ;

operator assistance, reduces the availability of an engineered safety system, and requires entry ,

~ into a Vermont Yankee Technical Specifications Limiting Condition of Operation, with the required alternate testing requirements.

i Revision 19 Section 4 Page 28 of 31

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Vcrment Yenkee Nucle:r Pcwer Statica Inservice Testing Program l

RELIEF REQUEST i

l Number: RR-P09, Revision 0 (Sheet 3 of 4)

ALTERNATE METHOD:

During quarterly inservice testing of each Diesel Fuel Oil Transfer pump, it will be verified that the pump is capable of supplying fuel oil to the respective diesel day tank at a flow rate greater than that required by the operating Emergency Diesel Generator. This is verified by an increase in diesel day tank level during the diesel surveillance testing. In addition, full spectrum vibrational monitoring and measurement of pump discharge pressure will be performed with the results evaluated against the acceptance criteria of Table 3 of Part 6 of the Code.

Once each operating cycle the flow rate of each Diesel Fuel Oil Transfer pump will be determined indirectly by measuring the level change in the diesel day tank versus the pump operating time required to make that change. This will be performed with the respective Emergency Diesel Generator secured, the automatic pump start feature on low diesel day tank level disabled, and the diesel day tank volume reduced prior to the test through operation of the respective Emergency Diesel Generator. This testing will provide measurement accuracy comparable with Table 1 of Part 6 of the Code and the results will be evaluated against the acceptance criteria of Table 3 of Part 6 of the Code. As with the quarterly testing, full spectrum vibrational monitoring a"nd measurement of pump discharge pressure will be performed with the results evaluated against the acceptance criteria ofTable 3 of Part 6 of the Code.

Such testing is considered commensurate with the pump type and service and provides an acceptable level of quality and safety, based on the following:

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l Revision 19 Section 4 Page29 of 31

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Vermant Yenkes Nuclerr Power St2tien Inservice Testing Program RELIEF REOUEST Number: RR-P09, Revision 0 (Sheet 4 of 4) l l ALTERNATE METHOD (cont.h a) A review of the pump design flow rate versus the diesel fuel oil consumption rate indicates

! an excess capacity of approximately 60 percent. As such, operational readiness of the l pumps is still assured with up to 60 percent degradation, provided that pump bearing l vibration is not excessive. Assurance of acceptable pump bearing vibration levels is l provided through the full spectrum vibrational monitoring.

i b) A review of Vermont Yankee maintenance records and industry experience, as documented in NPRDS, indicates that the pumps are highly reliable and that the above testing methods are acceptable for assessing pump operational readiness and detent' ag potential degradation.

At Vennont Yankee, four (4) failures have occurred in twenty (20) years of plant operations. Of these failures, three (3) were related to electrical components and one (1) was related to high bearing vibrations. In addition, minor shaft seal leakage has been noted  :

and corrected.

  • i i

l The industry experience is consistent with Vermont Yankee. For similar pumps in similar I applications, fifteen (15) failures have been reported via NPRDS. Of these failures, nine (9) were related to excessive seal leakage, four (4) were related to electrical components and two (2) were related to high bearing vibrations.

Each of the above failure modes is adequately monitored during the quarterly inservice testing through visual inspection of the pump seals, proper starting and operation of the l pump upon low diesel day tank level, and full spectrum vibrational monitoring.

f USNRC EVALUATION STATUS: -

Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-P09, Revision 0.

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I Revision 19 Section 4 Page 30 of 31

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Vcrm::t Yc;kee N clear Pow r St:ti:n Inservice Testing Program RELIEF REOUEST Number: RR-PIO, Revision 1 (Sheet 1 of 1)

THIS RELIEF REQUEST WAS DELETED IN REVISION 18 OF THE IST PROGRAM.

This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

e Revision 19 Section 4 Page31 of 31

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Vcrmat Ycakee Nuclear Pcwer Stati::n Ins:rvica Tcsting Prcgrcm i

5.0 Valve' Inservice Testing Program 5.1 Scope The Third-Interval Valve Inservice Testing (IST) Program establishes testing requirements -

to assess the operational r**dinaa of certain Safety Class 1,2, and 3 valves and pressure

- reliefdevices, including their actuating and position indicating systems The active or passive Safety Class 1,2, and 3 valves included are those which are required  !

to perform a specific functionin:

a) Shutting down the reactor to the cold shutdown condition, b) Maintaining the reactor in the cold shutdown' condition, or c) ' Mitigating the consequences of an accident.

l The Safety Class 1,2, and'3 pressure relief devices included are those for protecting systems or portion of systems which perform a required function in:

a) Shutting down the reactor to the cold shutdown condition, L b) Maintaining the reactor in the cold shutdown condition, or

- c) Mitigating the consequences of an accident.

The following are excluded fmm the above, provided that they are not required to perform a specific function as specified above:

'a) Valves used only for operating convenience such as vent, drain, instrument, and test valves; i b) Valves used only for system control, such as pressure regulating valves; l

-)c ' Valves used only for system or component maintenance.

!  : Extemal control and protection systems responsible for sensing plaht conditions and providing signals for valve operation are also excluded from the above.

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Revision 19 Section 5 Page 1 of 179 l.

Vcrmrt Ycnkee Nucirr Pr.wer Strti:a Inservice Testing Prcgrrm 5.2 Valve Program Listing Table 5-1, " Valve Listing" lists all valves and pressure relief devices included in the Third-Interval ValveIST Program.

This Table identifies all valves and pressure relief devices subject to inservice testing, the inservice test requirements, testing frequency, and any applicable relief requests and/or  !

remarks. Table 5-1 is sorted by Drawing. The column headings in Table 5-1 are listed and  ;

explained below:  ;

1 Drawing The Flow Diagram which depicts the valve or pressure relief device. If the valve or pressure relief device appears on multiple Flow Diagrams, then the primary Flow Diagram identifieris listed.

Drawing Title l

The title of the Flow Diagram.

4 Valve Number The unique number that identifies the valve or pressure relief device. The valve number corresponds to the MPAC Database utilized at Vermont Yankee.

Nomenclature The common name for the valve or pressure relief device.

Dwg Coor The coordinate location (e.g., D-05) on the Flow Diagram where the valve or pressure relief devic.e appears.

Safety Class The safety class of the valve or pressure relief device as it appears on the Flow Diagram.

The safety classification of the valve or pressure relief device shown on the Flow Diagrams were determined in accordance with the Vermont Yankee Safety Classification Manual.

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Revision 19 Section 5 Page 2 of 179

Verm:nt Ycnkea Nucle r Pawar St:ti:n Ins:rvics Testing Prcgram 5.2 Valve Program Listing (cont.)

OM Cat The valve category as defined by Paragraph 1.4 of Part 10 of the Code. All categories are identified for those valves which have more than one applicable category (i.e. A/C for category C valves that also have leakage requirements).

A: Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required function (s).

B: Valves for which seat leakage in the closed position is inconsequential for fulfillment of their required function (s).

C: Valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves) for fulfillment of their required function (s).

D: Valves which we actuated by an energy source capable of only one operation, such as rupture disks or explosively actuated valves. ,

Active / Passive The valve classification as defined by Paragraph 1.1 of Part 10 of the Code.

Act Those valves which are required to change obturator position to accomplish their required function.

Pass Those valves which maintain obturator position and are not required to change obturator position to accomplish their required function.

Size (Inch)

The nominal pipe size of the valve, in inches.

Revision 19 Section 5 Page 3 of 179

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

f-a i .' Verm=t Ye:kee Nucle:r Pcwsr StIti::n -Ins:rvica Testing Program I Body L 'Ihe valve body style designator where: ,

, WAY - for 3-Way Valves L BL for BallValves ,

f BTF. for Butterfly Valves CK? . for simple CheckValves EFC for Excess Flow CheckValves GA for Gate Valves

! GL for Globe Valves GSC - for Globe Stop Check Valves .

RD- for Rupture Discs .

RV for ReliefValves.

SQUIB - for explosively W-3 valves i SRV for Safety /ReliefValves .

L l Actuator-The type of actuator provided with the valve body where:

AO -

for Air Operated EXP for Explosive Charge .

HO for Hydraulically Operated  ;

MAN for Manually Operated j I

. MO-AC for Motor Operated, AC powered motor MO-DC for Motor Operated,DC powered motor SA for Self Actuated (i.e. Relief Valves, etc.)

SO- for Solenoid Operated NormalPosition This field details the valve's position during normal plant operation (if the subject system is L required to be in a standby condition during normal power operation, the valve's normal 4

+ position is the position of the valve when the system is in it's standby condition), where:

C for Closed LC for Locked Closed O. for Open LO for Locked Open

- O/KLfor Open, Key Locked L O/C for Open or Closed (dependent on system demand) l T- for Throttled i1 Revision 19 - Section 5 Page 4 of 179 i-

Vcrm::t Yc:::kso Nucirr Pcwer Stati:n Inservice Testing Pr: gram Safety Position The position a valve or pressure-relief device is required to function in shutting down the reactor to the' cold shutdown condition, maintaining the reactor in the cold shutdown y condition, or mitigating the consequences of an accident.

i C for Closed function O for Open function O/C for both Open or Closed functions l Test Type (and Stroke Direction) l- The test type is an abbreviation of the type of test required to be performed and the stroke l

direction in which the test is performed.

l LJ OM Category A Valves, which are containment isolation valves tested in accordance with the requirements of OM-10 subsection 4.2.2.2 and 10 CFR 50 Appendix J on a fixed frequency. Analysis ofleakage rate and corrective j action is in accordance with OM-10 subsection 4.2.2.3 (e) and (f).

l LJB OM Category A Valves, which are containment isolation valves tested in accordance with the requirements of OM-10 subsection 4.2.2.2 and 10 CFR

50 Appendix J using Option B performance criteria to establish variable test frequencies. Analysis ofleakage rate and corrective action is in accordance with OM-10 subsection 4.2.2.3 (e) and (f).

LT OM Category A Valves, which perform a function to limit leakage to a

! specific amount and are tested in accordance with the requirements of OM-10 subsection 4.2.2.3.

LEF . Category A Excess Flow Check Valves, which perform a function to limit leakage to a specific amount and are tested in accordance with the requirements of OM-10 subsection 4.2.2.3. Satisfactory completion of excess flow check valve leakage testing also satisfies both the open and close valve L exercise requirements of OM-10 subsection 4.3.2.2.

L STC Active Category A and B Power-Operated Valves, whiefi are full-stroked tested in the closed direction and the stroke times are measured and evaluated in accordance with Paragraph 4.2.1 of Part 10 of the Code.

L STO Active Category A and B Power-Operated Valves, which are full-stroked tested in the open direction and the stroke times are measured and evaluated in accordance with Paragraph 4.2.1 of Part 10 of the Code.

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Revision 19 Section 5 Page 5 of 179 i,

l~ Vermcnt Ycnkea Nuclear Pawar St:tirn Inservice Testing Prsgr:m Test Type (cont.)

SC Active Category A and B Non-Power-Operated Valves and Category C Check Valves, which are full-stroked tested in the closed direction in accordance with Paragraphs 4.2.1 and 4.3.2 of Part 10 of the Code.

SO Active Category A and B Non-Power-Operated Valves and Category C Check Valves, which are full-stroked tested in the open direction in accordance with Paragraphs 4.2.1 and 4.3.2 of Part 10 of the Code.

PSC Active Category A and B Valves and Category C Check Valves, which are partial-stroked tested in the closed direction in accordance with Paragraphs 4.2.1 and 4.3.2 of Part 10 of the Code.

PSO Active Category A and B Valves and Category C Check Valves, which are partial-stroked tested in the open direction in accordance with Paragraphs 4.2.1 and 4.3.2 of Part 10 of the Code.

PIT Valves with remote position indicators are verified in accordance with Paragraph 4.1 ofPart 10 of the Code.

FST Active Category A and B Valves with fail-safe actuators, tested in accordance with Paragraph 4.2.1.6 of Part 10 of the Code.

ET OM Category D Explosively Actuated Valves, which are tested in accordance with Paragraph 4.4.1 of Part 10 of the Code.

RD OM Category D Rupture Discs, which are replaced in accordance with Paragraph 4.4.2 of Part 10 of the Code.

CD OM Category C Check Valves, which are disassembled in accordance with paragraph 4.3.2.4(c) of Part 10 of the Code.

SP OM Category C Relief and Safety Relief Valves are tested in accordance with Paragraph 4.3.1 of Part 10 of the Code.

SKIDActive Category A, B and C skid-mounted components or component subassemblies in which testing of the major component is an acceptable means for verifying the operational readiness of the skid-mounted and component subassemblies in accordance with NUREG 1482, Paragraph 3.4.

N/A For passive valves with no testing required.

i Revision 19 Section 5 Page 6 of 179

Vcrm:nt Ycekee Ncci:cr Pcwsr Sthtim . Inservics Testing Prcgram l

l.

l Test Frequency L >

L The test performance frequency associated with each test type will be specified where:

1-1 IM for every 1 Month l 6M for every 6 Months' 1Y for every 1 Year 2Y for every 2 Years 5Y for every 5 Years 10Y for every 10 Years CS for Cold Shutdown .

L OC' for Once Per Operating Cycle D

'Q for Quarterly RO forReactor Refueling Outage

. N/A for Not Applicable Var for Variable IAW Appendix J Option B performance criteria l

CSJ/ROJ/RR The Cold Shutdown Justification / Refuel Outage Justification or Relief Request number ,

associated with the subject valve or pressure relief device and test type or test frequency, .

. where applicable.

Remarks .

When appropriate, clarifying comments or other remarks will be included for the affected valve, pressure relief device, test type or test frequency.

Revision 19 - Section 5 Page 7 of 179

,Eq Vcrm:nt Ycnkee Nrclear Psw:i:r Statio2 Eservice Testi g Program Table 5-1 Valve Listing '

- Drawing: 5920-271 DrawingTitle: NeutronMonitoring System '

Dwg Safety OM Act / Slee my Act Nona Safety FaEl TestTest CSJ/ROJ h6 Valve Number Nomienclature Coor Class Cat Pass (inch) Pos Pos Posl Type Freg RR BY-7-1 Neutron Monitoring C 2 A Act .375 BL SO C C FC FST- Q n/a Note 6 Systan11P hbe Ball U 2Y n/a '

Valve PE 2Y Wa S7C Q n/a BY-7-2 Neutron Monitoring C-07 2 A Act .375 BL SO C C FC FST Q n/a Note 6 SystanTIP hbe Ball U 2Y n/a i

~

Valve PE 2Y Wa S1C Q n/a BV-7-3 Neutron Morutonng C-07 2 A Act .375 BL SO C C FC FST' Q. n/a Note 6 SystenTip TubeBall LJ 2Y n/a Valve - PIT 2Y Wa  :

STC Q n/a ,

S-7-1 Neutron Moniering C-07 2 D Act .375 SQUIB EXP O C n/a - ET RO n/a -

SystanTiphbe Shear Valve S-7-2 Neutron Monitoring C-07 2 D Act .375 SQUIB EXP O C n/a ET- RO n/a i SystemTip Tube Shear ,

Valve i n/a . ET.. RO I s-7-3 Neutron Monitoring C-07 2 D Act .375 SQU1B EXP O. C n/a Systan 71p'ITibe Shear l Valve .

I f

Revision 19 Drawig : 5920-271 Section 5 Page 8 of 179  !

i

- Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191159 Sh 1 Drawing *Iltle: Senice WaterSystem Dwg Safety OM Act / Size Body Act Nonn Safety Fail Test Test CSJ/ROJ hah Valve Number Nomenclatner Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR FCV-104-17A , SW Supply to Screen D-04 3 B Act 4 GA HO C C FC FST Q n/a Note 8 Wash Flow ControlValve STC Q n/a FCV-104-17B SW Supply to Screen E-04 3 B Act 4 GA HO C C FC FST Q n/a Note 8 Wash Flow ControlValve . S1C Q n/a PCV-104-17C SW Supply to Screen F-04 3 B Act 4 GA HO C C FC FST Q n/a Note 8 Wash FlowControlValve STC Q n/a FCV-104-17D SW Supply to Screen F-04 3 B Act 3 GA HO C C FC FST Q n/a Note 8 Wash Flow ContmlValve STC Q n/a FCV-104-17E SW Supply to Screen G-04 3 B Act 3 GA HO C C FC FST Q n/a Note 8 ,

Wash FlowControlValve STC Q n/a PCV-104-69A RHRSW PCV for SW to J-13 3 B Act 8 GL AO C O FO FST Q n/a Note 8 A-EDG and RRUs 5,7 S1D Q n/a PCV-104-69B RHR PCV for SW to B- B-13 3 B Act 8 GL AO C O FO FST Q n/a Note 8 EDG AND RRUs 6,8 S1D Q n/a SE-70-4A RHRSW Pump Motor K-10 3 B Act 1 GA SO C O FO FST Q n/a .

Cooling coilSupply S10 Q n/a Valve SE-70-4B RHRSW Pump Motor K-10 3 B Act 1 GA SO C O FO FST Q n/a Cooling CoilSupply STO Q n/a Valve SE-70-4C RHRSW Pump Motor K-10 3 B Act 1 GA SO C O FO FST Q n/a Cooling Coi! Supply SiO Q n/a Valve SE-70-4D RHRSW Pump hlotor K-10 3 B Act 1 GA SO C O FO FST Q n/a i

Cooling coil Supply STO Q n/a Valve SP-70-3A A Service WaterStrainer H-05 3 B Act 2 BL AO C C FC FST Q n/a Note 8 Backwash Valve STC Q n/a Revision 19 Drawing : G-191159 Sh 1 Section 5 Page 9 of 179

t P

Vcrmont Yankee Nuclear Power Station Inservice Testing Program

- Table 5-1 Valve Listing Drawing : G-191159 Sh 1 - Drawing Tkle: Semcc Water System Dwg Safety OM Act / Size wy . Act Norma Safety Fa8 Test Test CSJ/ROJ hah Valve Museber Noemenclature Coor Class Cat Pass (isnk) Pos Pos Pos Type Friq RR ,

SP-43B B SanceWaterStramer C-05 3 B Act 2 BL' AO C C FC FST Q n/a Note 8 ,

BackwashValve S7C Q n/a SR-%13A RHRSW Pump Motor L-09 3 C Act .75 RV SA C O/C n/a SP 10Y n/a i Cooling Relief Valve .

SR-78-13B RHRSW Panp Motor L-09 3 C Act .75 RV SA C O/C n/a SP 10Y n/a Cooling ReliefValve .!

SR-%I3C RHRSW Panp Motor L-09 3 C Act .75 RV SA C O/C n/a SP 10Y n/a Cooling ReliefValve SR-%13D RHRSW Pump Motor L 09 3 C Act .75 RV SA C O/C n/a SP 10Y n/a Cooling ReliefValve SR-42A SWReliefValve I-08 3 C Act 1 RV SA C O/C . n/a SP 10Y n/a [

SR-79-25 SW ReniefValve C-08 3 C Act 1 RV SA C O/C n/a SP 10Y ' n/a [

! V78-130A CW Pump Cooling SW C-05 3 B Act 3 GA MAN O C n/a SC Q n/a Note 8 l Supply ,

t V78-130B CW Pump Cooling SW I-05 3 B Act 3 GA MAN O C n/a SC_ Q _ n/a Note 8 Supply j V70-13A SW Supply to the A J-07 3 B Act 24 GA MAN O O/C n/a SC RO ROI-V16 Note 8 HenderIsoldion V70-13B SW Supply to the B B-07 3 B Act 24 GA MAN O OC n/a SC RO ROJ-V16 Note 8 HenderIsolation V79-15A SW Supply to the A J-08 3 B Act 12 GA MAN O C n/a SC RO ROJ-V17 Note 8 RBCCW Heat Exchanger j V70-15B SW Supply to tiie B B-08 3 B Act 12 GA MAN O C n/a SC RO ROJ-V17 Note 8 RBCCW Heat Exchanger l

V70-16B Altanate Cooling to SW C-09 3 B Act 24 GA MAN C O/C n/a SO RO ROJ-V21 Note 8 ,

Supply Revision 19 Drawing : G-191159 Sh 1 Section 5 Page 10 of 179

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a l

Vcrmont Yankee Nuclear Power Station Insenvice Testing Program  !

1 Table 5-1 Valve Listing j Drawing: 0-191159 Sh 1 Drawing 11tle: Semce Water System :

Dwg Sa % OM Act / h Body Act Nonn Safety fab Test Test CSJ/ROJ hah 'I Valve Nunnber Nommenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR V79-184 AltCooling WaterLine C-09 ~3 B Act 1 GA MAN C O/C n/a SC RO ROJ-V21 Note 8 Vent SO RO ROJ-V21 f V79-187A Gland SealSupply to SW J-06 3 B Act 1.25 GA MAN O C n/a SC RO ROJ-VI8 Note 8 - ~

Panps A and B .

V79-187B Gland SealSupply to SW B-06 3 B Act 1.25 GA MAN O C . n/a SC RO ROJ-VI8 Note 8 l Pumps C and D V79-19A SW Supply Hcnder H-09 3 B Act 24- GA MO-AC O O/C FAI PIT 2Y n/a 1 C.+++ - t Valve SE Q n/a i i SM Q n/a V7519B SW Supply Hender C-09 3 B Act 24 GA MO-AC ' O O/C FAI PIT ~ 2Y n/a CrossconnectValve sm - Q n/a N Q

  • V79-1A Savice Water Peng C-02 3 C Act 14 CK SA O/C O/C n/a PSO Q ROJ-V14 Note 10 Discharge Check Valve SC RO ROJ-V14 SO RO ROJ-V14 V70-1B Service WaterPanp B-02 3 C Act 14 CK SA O/C O/C n/a PSO Q ROJ-V14 - Note 10 i Discharge Check Valve SC RO ROJ-V14 SO RO ROJ-V14 ,

t V79-IC Service Water Pump K-02 3 C Act 14 CK SA O/C O/C n/a PSO Q ROJ-V14 Note 10 Discharge Check Valve SC RO ROJ-V14 SO RO ROJ-V14 V70-1D ServiceWaterPump J42 3 C Act 14 CK SA O/C O/C r/a PSO Q ROJ-V14 Note 10 Discharge Check Valve SC RO ROJ-V14 SO RO ROJ-V14 V70-20 SWSupply Valve to H-11 3 B Act 20 GA MO-AC O C FAI PIT 2Y n/a Turbine Building Cooling SE Q n/a i Loads Revision 19 Drawing : G-191159 Sh 1 Section 5 Page 11 of 179 i

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing .j Drawing: G-191159 Sh 1 Drawleg

Title:

Service WaterSystem Dwg Safety OM Act ! Size Body Act None Safety fab Test Test CSJ/ROJ h& t Valve Number Nomenclature Coor Class Cat P.e:s (inch) Pos Pos Pos Type Freg RR V7424B Alternate Cooling Supply C-12 3 B Act 2.5 GA MAN C O n/a SO Q n/a Note 22 to RBCCW Valve also appears on G-191159 Sh3 V7&27 SW to Firewater D-02 3 B Act 1.5 GL -MAN LO C n/a SC Q n/a Note 8 m ___ ,..g Line V70-281A 18B SW Sydan Vacuurn J-09 3 C Act 2 .CK SA C OC n/a SC RO ROJ-V28 BreakerCheck Valve SO RO ROJ-V28 I WS-281B 18B SW Sydan Vacuum B-09 3 C Act . 2 CK SA C OC n/a SC RO RGJ-V28 BreakerCheckValve SO RO ROJ-V28 ,

1

- V70 281C isB SW System Vacuum J-09 3 C Act 2 CK SA C OC n/a SC- RO ROJ-V28  ;

BreakerCheck Valve SO RO ROJ-V28 V70-281D 18B SWSystem Vacuum C-09 3 C Act 2 CK SA C OC n/a SC RO ROJ-V28 BreakerCheck Valve SO RO ROJ-V28 .

V70-29 Alternate Cooling to SW D-13 3 B Act 3 GA MAN C O n/a SO Q n/a Note 22 Supply Valve also appears on G-191159 Sh 3 V79-29A Alternate Cooling to SW D-13 3 B Act 3 GA MAN C O n/a SO Q n/a Note 22 ,

Supply Valve also appears on G-191159 Sh 3 V70-2A SWPump Discharge C-03 3 B Act 14 GA MAN O- OC n/a SC RO ROJ-V16 Note 8 Isolation Valve  ;

i V70-2B SW PumpDischarge B-03 3 B Act 14 GA MAN O OC ' n/a SC RO ROJ-V16 - Note 8 i Isolation Valve, i V70-2C SW Pump Discharge J-03 3 B Act 14 GA MAN O OC n/a SC RO ROJ-V16 Note 8 IsolationValve V70-2D SW Pump Discharge J-03 3 B Act 14 GA MAN O OC n/a SC RO ROJ-V16 Note 8 Isolation Valve  ;

I Revision 19 Drawing : G-191159 Sh 1 Section 5 Page 12 of 179

m Vcrmrt Yc;kee Nrclear Pcwcr St: tion Inservice Testing Program Table 5-1 Valve Listing Erawing: G-191159 Sh l DrawingTitle: Service WaterSystem Nomenclature Dwg Safety OM Act / Size My Act Norm Safety Fail Test Test CSJ/ROJ hah Valve Number Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR V7042B Attemate Cooling Supply C-12 3 B Act 2.5 GA MAN C O n/a SO Q n/a Note 22 to RDCCW Valve also appears on G-191159 Sh 3 V70 36A Altemate Cooling Supply C-13 3 B Act 3 GA . MAN C O n/a SO Q n/a Note 22 to RBCCW Valve also appears on G-191159 Sh 3 V70,36B Alternate Cooling Supply C-13 3 B Act 3 GA MAN C O n/a SO Q n/a Note 22 to RBCCW Valve also appears on G-191159 Sh 3 V7048A RIIRSW Pump Discharge K-12 3 C Act 12 CK SA C O/C n/a SC Q n/a Check Valve SO Q n/a V70,38B RIIRSW Pump Discharge B-12 3 C Act 12 CK SA C O!C n/a SC Q n/a CheckValve SO Q n/a V70-40A RIIRSW Pump Discharge K-12 3 C Act 12 CK SA C O/C n/a SC Q n/a CheckValve SO Q n/a V70-40B RIIRSW Pump Discharge A-12 3 C Act 12 CK SA C O/C n/a SC Q n/a CheckValve SO Q n/a V70-42A RIIRSWAltanate K-13 3 B Act 8 GA MAN C O n/a SO Q n/a Notc 8 Cooling to SW Supply V70-42B RHRSW Altemate B-13 3 B Act 8 GA MAN C O n/a SO Q n/a Note 8 Cooling to SW Supply V70-43A IBA SW Discharge Loop J-12 3 C Act 8 CK SA O O/C n/a PSO Q n/a IIender Check Valve SC RO ROJ-V32 SO RO ROJ-V32 V70 43B 18A SW Discharge Loop B-12 3 C Act 8 CK SA O O/C n/a PSO Q n/a IIca&r Check Valve SC RO ROJ-V32 SO RO ROJ-V32 Revision 19 Drawing : G-191159 Sh 1 Section 5 Page 13 of 179

Vcrmont Yankee Nuclear Power Station - Inservice Testing Program Table 5-1 Valve Listing Drawing: 'G-191159 Sh 1 Drawing

Title:

' Service Water System -

Dwg Safety OM Act / Size My Act Nona Safety fab Test Test CSJ/ROJ hah Valve Namber Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR V70-504 Alternate Cooling to SW D-12 3 B Pass 2 GA MAN C C n/a n/a n/a- n/a Supply V70,511B IRB SW System Vacuum H-12 3 C Act 2 CK SA C O/C n/a SC RO ROJ-V28 Breaker CheckValve . SO RO ROJ-V28 V70-5 1C ISB SW System Vacuum H-12 3 C Act 2 CK SA C O/C n/a SC RO ROJ-V28 i BreakerCheck Valve SO RO ROJ-V28 V705A SW X-connection to Fire J-03 3 B Pass 20 GA MAN O O n/a n/a n/a n/a Systan V70-5B SW X-connection to Fire C-03 3 B Pass 20 GA MAN O O n/a n/a n/a n/a Systan V704 SW ScreenWash F-03 3 B Act 8 GA MAN O C n/a SC Q n/a Note 8 Alternate Cooling / Isolation Valve Revision 19 Drawing : G-191159 Sh 1 Section 5 Page 14 of 179

__ _ __._m. _.___- . _ _ _ . _ _ _ _ _ _ ____._-.._______.____..____._-___m_ . . _ _ _ _ _ . _ . _ _ . - __...______.__..__.________m __._____.___._____;_._.____-_

Vermont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing ,

Drawing : G-191159 Sh 2 Drawing

Title:

Service WaterSystem Dwg Safety OM Act / Sire Body Act Nona Safety Fail Test Test CSJ/ROJ RemW Valve Nuunber NomencInture Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR FCV-104-28A Diesel Generator A H-05 3 B Act 8 GL AO C O FO SKID Q n/a Note 12 Cooling WaterInlet

(

FCV-104-28B . DieselGenerator B D45 3 B- Act 8 GL AO C O FO SKID - Q n/a Note l2 r CoolingWaterInlet . +

i PCV-104-73A 18B DieselGeneratorA J-04 3 B Act 8 GL HO O O FO SKID Q n/a Note l2 ServiceWaterPump  ;

i PCV-194-73B 18B DieselGenerator B B-04 3 B Ac: 8 GL HO O. O FO SKID Q n/a - Note 12 Service Water Pump ,

Disclurge  ;

SB-70-1 SW To Main C*~ D-09 NNS B Act 24 BW MAN O/C OC n/a SC CS CSJ-V16 Note 8 ,

Ducharge Block Valve SO CS CSJ-V16  ;

t SR-78-16A DieselGeneratorJacket I-06 3 C Act 1 RV SA C OC ' n/a SP 10Y n/a WtrCoolerSafety Relief Valve SR-76-16B Diesel Generator Jacket C-05 3 C Act 1 RV SA C O/C n/a SP 10Y n/a i WtrCoolerSafety Rehef l f

Valve RHRHX ServiceWater * * * * * * * * * * *

  • V10-89A = H-01
  • See G-191172 for valve .

Outlet Valve info and test i%-.~a. l V16 89B a RHR HX Scrvice Water E-01

  • See G-191172 forvalve OutletValve info and test requirements f SWDucherge to Cooling D-07 GA MAN OC OC n/a SC CS CSJ V16 Note 8 V79-11 3 B Act 14 .

TowerBasinIsolation SO. CS CSJ-V16 r Valve =

i v70-16A Alt. Cing Deep Basin to D-07 3 B Act 24 GA MAN C OC n/a - SO RO ROJ-V21 Note 8  ?

RHRSW Pump Suct. Iso. [

Valve -

MAN OC CS CSJ-V16 Note 8 V70-17 Alternate Cooling to SW D-06 3 B Act 20 GA O n/a SO Supply

. Revision 19 Drawing : G-191159 Sh 2 Section 5 Page 15 of 179  ;

I I

Vermont Yankee Nuclear P;wer Statior Inservice Testi;g Prograin Table 5-1 Valve Listing  ;

Drawing: ' G-191159 Sh 2 Drawing'lltle: Semce WaterSystem Dwg Safety OM Act / Size My Act Nons Safety fab Test Test CSJ/ROJ h6 Valve Nussber I Mommsclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR V7s-17A #1 West Cing Tower SW D47 3 B Pass 6 GL MAN T O' n/a SC RO~ n/a Note 9 DistributionTray Valve SO . RO ' n/a Note 22 V7s-173 #1 West Cing TowwSW D-07 3 B Pass 6 GL -

MAN T O . n/a SC RO n/a Note 9 - i

~ DistributionTrayValve so, RO n/a Note 22 6- MAN T n/a SC RO

, V70-17C #1 West Cing Towa SW D-07 3 .B Pass GL O n/a Note 9  !

DistributionTray Valve SO RO n/a Note 22 -

V70-17D #1 West Cing Tower SW D-07 3 B Pass 6 GL. MAN T- O n/a SC 'RO n/a Note 9 DistributionTray Valve .SO RO n/a Note 22 i

V76-Is SW Discharge Hender E47 3 B Act 20 GA MAN O O/C n/a ' SC CS CSJ-V16 Note 8 .!

IsolationValve V70-283 SW Supply to RRU-9 B-03 3 B Act 1.25 GA MAN O- C n/a SC Q n/a . Note 8 Isolation Valve V70-206 SW to RRITs 17A and J-03 3 B Act 2 GA MAN O- C n/a SC Q n/a Note 8

! 17B, Isolation Valve i s

V76-252B ~ 18B SW System vacuum G-05 3 C Act 2 CK SA C O/C n/a SC RO ROJ-V28 ,

Bienker CheckValve SO RO ROJ-V28  !

V76252C isB SW System Vacuum . G-05 3 C Act 2 CK SA C O/C n/a - SC RO ROJ-V28

Breaker CheckValve SO RO ROJ-V28 .

V76 414 SW to Red Monitor from D-08 NNS B Act .75 GA MAN O/C C. .n/a 3C Q n/a - Note 8 SW Discharge to Deep  ;

Basin Revision 19 Drawing : G-191159 Sh 2 Section 5 - Page 16 of 179 2

___._.m- . _ . _ . ._.m._.____.__.________.______.______._____m _ _ _ _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ . _ _

Inservice Testing Program Vermont Yankee Nuclear Power Station -

Table 5-1 Valve Listing Drawing: G-191159 Sh 3 Drawing'I1tle: RCW Cooling Water System Dwg Safety OM Act / Size My Act Norm Safety fab Test Test CSJ/ROJ RemW Valve Number Nonneoclatuit Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR RV-70-117A RBCCW Drywell Piping M-10 2 C Act .75 RV SA LC OC n/a SP 10Y n/a TherinalReliefValve SR-70-1A SW ReliefValve B-04 3 C Act 1 RV SA C OC n/a .SP 10Y n/a SR-70-1B SW ReliefValve C-04 3 C Act 1 RV 'SA C OC n/a SP 10Y n/a '

SR-79-6A SW ReliefValve J-05 3 C Act 1 RV. ~ SA C OC n/a SP 10Y n/a SR-78-6B SW ReliefValve I-05 3 C Act 1 RV SA C OC n/a SP 10Y n/a V70-106 Rad Waste Building Inlet P-02 3 B Act 2 GA MAN O C n/a SC Q n/a Note 8 V70-107 RadWaste Building P-05 3 B Act 2 GL MAN O C n/a SC Q n/a Note 8 Outlet t V7o-113 iss Prunary contanunent K-08 2 AC Act 8 CK SA O C n/a LJB Var nha RCWSupplyIsolation SC RO ROJ-V24 Valve V76-113D Test Connection for L-08 2 B Pass .75 GA MAN LC C n/a n/a n/a n/a

, Penetration X-23 V79-117 18B Prunary Contauunent L-12 2 A Act 8 GA MO-AC O C FAI LJB Var n/a

> RBCCW Return Valve PIT 2Y n/a S'IC CS CSJ-Vol V19-117D Test Connection for M-12 2 B Pass .75 GA MAN LC C n/a n/a n/a n/a j Penetration X-24 V70-24A RBCCWcooling to CRD N-02 3 B Act 2.5 GA MAN O O/C n/a SC Q n/a Note 8 and B/D RHRPumps Alternate Cooling Supply O-03 * * * * * * * * * * * *

  • See G-191159 Sh I for V70-24B =

to RBCCW valve info and est i requirennents V70-28 RBCCWcooling to CRD O-10 3 B Pass 3 GA MAN C C n/a n/a n/a n/a Note 8 end RHRPurnps .

Revision 19 Drawing : G-101159 Sh 3 Section 5 Page 17 of 179 t

Vermont Yankee Nuclear Power Station . Inservice Testing Program ~

Table 5-1 Valve Listing ,

Erawhag: G-191159 Sh 3 - DrawingTitle: RCW Cooling WaterSystem Dwg Safety OM Act / Size My Act None Safety fab Test Test CSJ/ROJ h6 Valve Number Nomienclature Coor Class Cat Pass (inch) Pos Pos' Pos Type Freg RR V79-28A RBCCW cooling to CRD O-10 3' B Act 3 GA MAN O~ OC n/a SC Q' n/a . Note 8 and RHRPiunps Alternate Cooling Rettun Q-10 * * * * * * * * *- * *

  • V79-29 * -
  • See G-191159 Sh I for  ;

fanRBCCW . valveinfo and test requu==en -

, V73 29A

  • AlternateCooling Return P-10 * -* * * * * * * * * *- *
  • See G-191159 Sh I for i  !

fanRBCCW valveinfo and est W i I

V7930A 18B C"'i Pump 1A Cooler 1,4 3 B Act I ~ GA MAN O C N/A SC Q n/a Note 23 Ira iss CRD Pump 1B Cooler Act GA MAN O C N/A SC.  :

V7saeB M-4 3 B 1 Q n/a - Note 23 V79J1A isB CRD Pump 1A Cooler M-4 3 B Act 1 GL- MAN O C' N/A SC Q n/a Note 23 outlet t V7041B Is'B CRD Pump IB Cooler N-4 3 B Act 1 GL MAN O C N/A SC Q n/a Note 23  !

Outlet i V7042A RBCCWcooling to P-02 3 B Act 2.5 GA MAN O O/C n/a SC. Q n/a Note 8  ;

Radweste and AE RHR  ;

Pumps i Attemate Cooling Supply P-03 * * * * * * * * * * *- *

  • See G-191159 Sh I for V7sJ2B =

to RBCCW valve info and test .

requirements  !

Altemate Cooling Supply O-02 * * * * * * * * * * * *

  • See G-191159 Sh I for V7646A* l to RBCCW valve info and test requirements Attemate Cooling Supply P-02 * * * * * * * * * * * *
  • See G-191159 Sh I for V7046B =

! to RBCCW valve info and test t requirements -

2 i

Revision 19 Drawing : G-191159 Sh 3 Section 5 Page 18 of 179 i

Vcrmont Yankee Nuclear Power Station ' Inservice Testing Program - '

i Table 5-1 Valve Listing I Drawing: ' G-191159 Sh 3 ' Drawing 'I1tle: RCW Cooling Water System Dwg Safety OM Act/ Size My None Safety Fail Test Test CSJ/ROJ h4 Valve Number Nemeenclatore ' Act Coor Class Cat Pass (inch) Pos 'Pos- Pos Type Freg RR

. V70-95A RBCCW Pump Discharte A-07 3 C Act 12 CK- SA O/C OC . n/a - SC Q . n/a -

CheckValve SO Q afa V7s 95B RBCCWPump Discharte B-07 3 C Act ' 12 OC SA O/C OC n/a SC 'Q_ n/a  :

Check Valve . SO Q n/a i

i 1

f T

i i

3 L

t Rivision 19 Drawing : G-191159 Sh 3 Section 5 Page 19 of 179 ;

V;rmont Yankee Nuclear Power Station LInservice Testing Program Table 5-1 Valve Listing Drawing: - G-191159 Sh 5 Unning

Title:

Recuculation Pmnp Cooling Water ,

Valve Number Dwg Safety OM Act / Size Norus Safety Fall Test Test CSJ/ROJ Nomenclature Coor Class Cat Pass (inch) M . Act Pos Pos Pos Type Freq RR hah .

SI,2-2-7A Recirculation PumpInst G-02 2 I A/C Act EFC SA O OC n/a LEF RO ROJ-VOI Excess FlowCheck Valve SI,2-2-7B Recirculation PumpInst G 02 2 A/C Act 1 EFC SA O OC n/a LEF RO ROJ-Vol Excess FlowCheckValve St,2-24A Recirculation PumpInst A/C Act G-02 2 1 EFC SA O O/C n/a LEF RO ROJ-Vol Excess FlowCheckValve 51,2-24B A/C Act Recirculation Pump 1nst G-02 2 1 EFC SA O O/C n/a LEF RO ROJ-Vol Excess Flow CheckValve l

Revision 19 Drawing : G-191159 Sh 5 Section 5 Page 20 of 179

- _ _ _ _ _ _ _ _ = . .__ - _ _ _ _ _ _ _ _ - . _ _ _ _ - _ _ - _ - . ._ _ _______ - __-__ __. _ _---- _____- __. - _ _ _ _ - - _ _ _ _ _ - - _ _ _ _ -

Vcrmont Yankee Nuclear Power Station Inservice Testing Program -

Table 5-1 Valve Listing Drawing : G-191160 Sh 3 DrawingTitle: Instrument AirSystem Dwg Safety OM Act / Size My Act Norm Safety Fall Test Test CSJ/ROJ Remarks Valve Number Nomenclatuit Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR SR-72-5 isa CAC Air /N2 Receiver E-14 3 C Act IXI.5 RV SA C O N/A SP 10Y- n/a ReliefValve Mt-151 Compressor Suction Test E-17 2 B Pass 1 GL MAN LC C n/a n/a n/a n/a Connection V72-152 Dnun/ rest Connection L-13 2 B Pass .75 GA MAN LC C n/a n/a n/a n/a ,

V72-152C Dram /restConnection L-18 2 B Pass .75 GA MAN LC C n/a n/a ' n/a n/a V72-153A Check ValveTest L-15 2 B Pass .75 GA MAN LC C n/a n/a n/a n/a .

Connection V72-28A Isolation to Outboard L-15 NNS B Act 1 GL MAN O C n/a SC CS CSJ-V17  !

MSIVs V72-28B Isolation to Outboard L-16 NNS B Act i GL MAN O C n/a SC CS CSJ-V17 MSIVs V72-28D 19 Isolation to Outboard K-16 NNS B Act 1 GL MAN C O n/a SO CS CSJ-V17

  • MSIVs V72-28E 19 Isolationto Outboard K-16 NNS B Act 1 GL MAN C O n/a SO CS CSJ-V17 MSIVs V72-38A 18B PCAC CompressorInlet E-17 2 A Act 2 GL AO O C FC FST Q n/a ContammentIsolation LJB Var n/a Valve PE 2Y da S1T' Q n/a V72aB 18B PCAC CompressorInlet F-17 2 A Act 2 GL AO O C FC FST Q n/a  !

ContainmentIsolation LIB Var n/a Valve PE 2Y da S71' Q n/a V72-89B DrywellInstnnnent Air K-14 2 A/C Act 2 CK SA O C n/a LJ 2Y n/a '

Supply CheckValve SC RO ROJ-V22 V72-89C Drywellinstrument Air K-15 2 A/C Act 2 CK SA O C n/a LJ 2Y n/a Supply Check Valve SC RO ROJ-V22 Revision 19 Drawing : G-191160 Sh 3 Section 5 Page 21 of 179  ;

Vermont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191160 Sh 5 DrawingTitle: Senice AirSystem Dwg Safety OM Act / Size My 'Act Norm Safety Fail Test Test CSJ/ROJ hah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Fng RR SR-724A ISB SA/IA Air Receiver G-9 3 C Act 2X3 RV SA C O N/A SP 10Y n/a ReliefValve SR-724B ISB SA/IAAirReceiver J-9 3 C Act 2x3 RV SA C O N/A SP 10Y n/a ReliefValve t

Revision 19 Drawing : G-191160 Sh 5 Section 5 Page 22 of 179

Vcrmont Yc kee N clear Pcwcr St; tion Inservice Testi g Program Table 5-1 Valve Listing Drawing: G-191160 Sh 7 Drawing

Title:

DiesciGenerator Staning Air System Valve Number Dwg Safety OM Act / Size Norm Safety Fail Test Test CSJ/ROJ Nomenclature Body Ad h6 Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR

. AS-24-1A DG Startmg Air Engme B-16 3 B Act 1.5 GL SO C O FC PSO 6M RR-V03 InletValve PSO IM RR-V03 S'IO OC RR-V03 AS-24-1B DG Starting Air Engine B-03 3 B Act 1.5 GL . SO C O FC PSO 6M RR-V03 InletWve PSO 1M RR-V03 STD OC RR-V03 AS-24-2A DG Starting AirEngine B-17 3 B Act 1.5 GL SO C O FC PSO 6M RR-V03 InletValve PSO IM RR-V03 STO OC RR-V03 AS-24-2B DG Startmg Air Engine B-03 3 B Act 1.5 GL SO C O FC PSO 6M RR-V03 Inlet Valve PSO IM RR-V03 STO OC RR-V03 AV-24-1A DG Starting Air Engine B-17 3 B Act .1875 GA SO O C FO SC 1M RR-V03 Inlet Vent Valve STC 6M RR-V03 AV-24-1B DG Starting Air Engine B-03 3 B Act .1875 GA SO O C FO SC IM RR-V03 Inlet Vent Valve STC 6M RR-V03 SR-72-6A DG Starting Air Receiver E-15 3 C Act .75 RV SA C O/C n/a SP 10Y n/a ReliefValve SR-724B DG Startmg Air Receiver E-13 3 C Act .75 RV SA C O/C n/a SP 10Y n/a ReliefValve I SR-724C DG Starting Air Reciew E-07 3 C Act .75 RV SA C O/C n/a SP 10Y n/a ReliefValve I

SR-724D DG Starting Air Reciever E 05 3 C Act .75 RV SA C O/C n/a SP 10Y n/a ReliefValve .

V72-1018A 18B DG Startmg Air Receiver G-11 3 C Act .75 CK SA O/C C N/A SC Q n/a Inlet Check Valve V72-1918D 18B DG Starting AirReceiver F-8 3 C Act .75 CK SA O/C C N/A SC Q n/a InletCheck Valve Revision 19 Drawing : G-191160 Sh 7 Section S Page 23 of 179

_ . . ___ J

Vcrmont Yankee Nuclear Power Station ' Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191160 Sh 7 DrawingTitle: Diesel Generator Starting Air System Dwg Safety 0M Act / Size Body Monm Safety fab Test Test CSJ/ROJ g,g i Valve Number Nomenclature Act Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR V7242AX Service Airto DG D-14 3 B Pass 2 GA MAN LC. C n/a da Wa n/a Starting Air Cross ConnectValve V7242BX Sernce Airto DG D-06 '3 B Pass 2 GA MAN LC C n/a n/a n/a n/a Starting Air Cross ConnectValve ,

t i

R:: vision 19 Drawing : G-191160 Sh 7 Section 5 Page 24 of 179 -

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

Vcrm:nt Ycckee Nzclear Pcw;r Station Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191160 Sh 8 Drawing

Title:

Instrument AirSystem Dwg Safety OM Act / Size Body Act Norm Safety Fail Test Test CSJ/ROJ hah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR SE-105-2A N2 Supply 3-Way Vent C-06 3 B Pass .75 3-WAY SO O O FO n/a n/a n/a Valve ,

SE-105-2B N2 Supply 3-Way Vent C-12 .3 D Pass .75 3-WAY SO O O FO n/a n/a n/a Valve SR-72-10A N2 Supply ReliefValve C-05 3 C Act .75 - RV ~ SA C O/C n/a SP 10Y n/a SR-72-10B N2 Supply ReliefValve C-04 3 C Act .75 RV SA C O/C n/a SP 10Y n/a SR-72-9A N2 Supply ReliefValve F-05 3 C Act .75 RV SA C O/C n/a SP 10Y n/a SR-72-9B N2 Supply ReliefValve F-04 3 C Act .75 RV SA C O/C n/a SP 10Y n/a V72409 InewAir to Reactor Fe04 3 A/C Act .375 CK SA O C n/a LT 2Y n/a Building Railroad Airlock SC Q n/a V72410 Instrument Airto Reactor Fe04 3 A/C Act .375 CK SA O C n/a LT 2Y n/a Building Ralread Airlock SC Q n/a t

Revision 19 Drawing : G-191160 Sh 8 Section 5 Page 25 of 179

Vcrmont Ycnkee Nrclear Pcwcr Stntion I: service Testi g Program Table 5-1 Valve Listing Drawing: G-191162 Sh 2 Drawing

Title:

Fuel Oil-Miscellaneous Systems Dwg Safety OM Act / Size Body Act Norm Safety fab Test Test CSJ/ROJ hah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR LCV-198-2A 19 DieselOilDay Tank E 08 3 B Act 1.5 GA AO C O/C FC FST Q n/a LevelControlValve SO Q n/a STE Q n/a STO Q n/a LCV-198-2B 19 DieselOilDay Tank C-08 3 B Act 1.5 GA AO .C O/C FC FST Q n/a LevelControlValve SO Q n/a SIC Q n/a STO Q n/a SR-78-3A DieselFuelOilTransfer E 06 - 3 C Act .75 RV SA C O/C n/a SP 10Y n/a Pump Discharge Relief Valve SR-78,3B DieselFuelOilTransfa D-06 3 C Act .75 RV SA C O/C n/a SP 10Y n/a Pump Discharge Relief Valve V78-10A LCV-3 Inlet FO Storage E-07 3 B Pass 1.5 GA MAN LC C n'a n/a n/a n/a Building FO Pump Room V78-11 LCV-3 Bypass FO F-07 3 B Pass 1.5 GA MAN C .C n/a n/a n/a n/a Storage Buikling FO Pump Room V78-2 FuelOilStorageTank E 02 3 C Act 4 CK SA C C n/a CD RO rJa FillLine Check Valve V78-28A 19 DieselFuelOilTransfer E-06 3 C Act 1.25 CK- SA C O n/a SO Q n/a Pump Discharge Check Valve V78-28B 19 Diesel FuelOilTransfer D-06 3 C Act 1.25 CK SA C O n/a SO Q n/a Pump Discharge Check Valve -

V78-41A DK)lland Pnmmg Pump G-11 3 C Act CK SA C C n/a SKID 1M n/a Note 12 Discharge Check V78-41B DK)IIand Pnmmg Pump E-11 3 C Act CK SA C C n/a SKID 1M n/a Note 12 Discharge Check Revision 19 Drawing : G-191162 Sh 2 Section 5 Page 26 of 179

Vermont Yankee Nuclear Power Station Inservice Testing Program:

Table 5-1 Valve Listing Drawing: G-191162 Sh 2 DrawingTitle: Fuel Oil-Miscellaneous Systems Dwg Safety OM Act / Size My Act Norm Safety fab Test Test CSJ/ROJ hah -

VaheNumber Nomendature RR Coor Class Cat Pass (inch) Pos Pos Pos Type Freq

. V78-42A DK) Engme DrivenFuel G-12 3 C Act CK SA C O/C Wa SKID IM n/a Note 12 Pump Discharge Check V78-42B DK) Engine DrivenFuel D-12 3 C Act CK SA C O/C n/a SKID IM n/a - Note 12 PanpDischarge Check ,

V7s-9 FuelOilTransfer Pump E-06 3 B Pass 2 GA MAN LC C n/a n/a n/a n/a Recuc.

r l

1 Revision 19 Drawing : G-191162 Sh 2 Section 5 Page 27 of 179

_____..____.______.______.____._.____.___________.____._.__....___.__.____.m _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ , _ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _

Vermont Yankee Nuclear Power Station Inservice Testing Programa Table 5-1 Valve Listing- -

~ Drawing: . G 191165 Drawing 11tle: Sampling System DWE Safety OM Act / Sine Norne Safety fab Test Test CSJ/ROJ g ,,,,,g, Valve Meanber Neuseectature Coor Class Cat Pass (inch)

M Act Pos Pos Pos Type Freg RR

' FCV-IS-160

  • RHRReturn Line Ptocess G-16 ' * *
  • See G-191172 forvalve Sampling Valve info and test reque--se 750199-75A-1
  • CAD SampleTorus D-17 *- * * * * * * * * * * *
  • See W-E-75-002 for -

InboardIsolationValve . . valve info and test requiresnents

  • * * * * * * * * * * *
  • See W-E-75-002 for F50-199-75A-2
  • CAD SampleTorus D-17 OutboardIsointionValve valveinfo and test requis--ee 750199-75A-3
  • CAD SampleTorus D-17 * * * * * * * *

.* See W-E-75-002 for Inboard 1solationValve valveinfo and test requirements CAD SampleTorus D-17 * * * * * * * * * * -* *

  • See W-E-75 402 for Pso.to9-75A-4 a OutboardIsolationValve valveinfo and test requiresnents CAD Sample Lower D-16 * * *' * * * * * * * * *
  • See W-E-75 402 for FSO-199-75B-1
  • DrywellinboardIsolation . valve info and test Valve - requiresnents
  • See W-E-75-002 for FSO 199-75B-2 = CAD SampleLower D-16 DrywellOutboard valveinfo and test IsolationValve requirements psO.199-75C-1 a CAD Sample Mid C-15 * * * * * * * * * * * *
  • See W-E-75-002 for .

DrywellInboardIsolsiion . valve info and test Valve requiresnents FSO-199-75C-2 a CAD Sample Mid C-15 * * *

  • See W-E-75-002 for :

DrywellOutbosid valve info and test IsolationValve requirements FSO-199-75D-1

  • CAD Sample Upper B-15 * * * * *' * * * * *- -* *
  • See W-E-75-002 for DrywellInboardIsolation valve info and test -

Valve requiresnents Revision 19 Drawing : G-191165 Section 5 Page 28 of 179 '

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191165 DrawingTitle: SamplingSystem Dwg Safety OM Act / Size Body Act Norm Safety Fail Test Test CSJ/ROJ hah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR FSO-199-75D-2

  • CAD Sample Upper B-15 * * * * * * * * * * * *
  • See VY-E-75-002 for DrywellOutboard valve info and test Isolation Valve requirements CAD CAM Return * * * * * * * * * * *
  • FSO-109-76A
  • F-19 .
  • See VY-E-75 002 for ContammentIsolation valve info and test Valve requirements CAD CAM Return * ~* * * * * * * * * *
  • FSO-107-76B
  • G-19
  • See VY-E-75-002 for ContainmentIsolation valveinfo and test Valve requiremerds PAS-101 Post Accident Samping K-14 2 A Pass .375 GL AO C C FC U 2Y n/a Note 13 System Jet Pump Sample Valve PAS-102 Post Accident Sampling K-16 2 A Pass .375 GL AO C C FC U 2Y n/a Note 13 System Jet Pump Sample Valve PAS-103 PostAcci* ntSampling L-14 2 A Pass .375 GL AO C C FC U 2Y n/a Note 13 System Jet Pump Sample Valve PAS-104 PostAccidentSampling K-16 2 A Pass .375 GL AO C C FC U 2Y n/a Note 13 System Jet Pump Sample Valve PAS-106 Post Accident Sampling L-16 2 A Pass .375 GL AO C C FC LT 2Y n/a Note 13 System Pmge Valve Valve also appears on G-191169 Sh 1 PAS-108C Post Accidat Sampling K-15 2 A/C Pass .375 CK SA C C FC U 2Y n/a Note 13 Systcm Jet Pump Sample Check Viv PAS-199C Post Accident Sampling L-15 2 A/C Pass .375 CK SA C C FC U 2Y n/a Note 13 System Jet Pump Sample Check Viv PAS-114 Drain ValveIsolation L-15 2 B Pass .375 GL MAN LC C n/a rva n/a n/a Revision 19 Drawing : G-191165 Section 5 Page 29 of 179

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191165 Drawing Thie: Sampling System Dwg Safety OM Act / Size Body Act Nonn Safety Fail Test Test CSJiROJ g,g Valve Number Nomenclature RR Coor Class Cat Pass (inch) Pos Pos Pos Type Freg PAS-115 Drain LineIsolation L-15 2 B Pass .375 GL MAN LC C n/a n/a n/a n/a PAS-117 Jet Pump 1 Sample Line I-13 2 B Pass .375 GL MAN LC C n/a n/a n/a n/a Test Connection PAS-118 Jet Pump 1 Sample Line I-13 2 B Pass .375 GL . MAN LC C n/a n/a n/a n/a TestConnection PAS-120 JetPump 2 Sample Line I-12 2 B Pass .375 GL MAN LC C n/a n/a n/a n/a Test Connection PAS-121 Jet Pump 2 Sample Line I-12 2 B Pass .375 GL MAN LC C n/a n/a n/a n/a Testconnection SL-2-3-21B Nuclear BoilerVessel C-13 1 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 InstExcess FlowCheck Valve SI,2-3-21D NuclearBoilerVessel C-13 1 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-Vol Inst Excess FlowCheck Valve

  • See VY-E-75-002 for VG-23
  • CAD Rad Monitor G-16 Supply Contamment valve info and test Isolation Valve 4m VG-26 = CAD Rad Monitor G-15 * * * * * * * * * * * *
  • See VY-E-75-002 for Supply Contamment valve info and test Isolation Valve 4m Revision 19 Drawing: G-191165 Section 5 Page 30 of 179

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191167 Drawing

Title:

NuclearBoiler Dwg Safety OM Act / Size Body Act Nonn Safety Fail Test Test CSJ/ROJ Remah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR FCV-2-17 RxVesselHem!Steen B-06 2 B Pass 1 GL AO C C FC PIT 2Y n/a Note 14 Space Vent Flow Control Valve FCV-2-18 Rx VesselHead Steen B-05 1 B Pass 1 GL

  • AO C C FC PIT 2Y n/a Note 14 Space Vent FlowControl ,

Valve FCV-2-20 Rx VesselHemiSeal C-06 1 B Pass 1 GL AO O O FO PIT 2Y n/a Note l4 LeakageFlowControl Valve FCV-2-21 RxVesselHemiscal C-05 2 B Pass 1 GL AO C C FC PIT 2Y n/a Note 14 LeakageFlowControl Valve FCV-2-39 18B RxRecue SarnpleLine L-04 2 A Act .75 GL AO C C FC FST Q n/a Note 20 Flow Control / Isolation LJB Var n/a Valve PIT 2Y n/a STE Q N/A FCV-2-40 18B Rx Recire SampleLine L-03 2 A Act .75 GL AO C C FC FST Q n/a Note 20 FlowControl/ Isolation LJB Var n/a valve pg.g. 2Y da STC Q N/A-RV-2-71A Nuclear Boiler D-08 1 C Act 6X10 SRV SA C O/C n/a SP SY ROJ-V02 Note 7 Safety /ReliefValve ,

RV-2-71B Nuclear Boile G-03 1 C Act 6X10 SRV SA C O/C n/a SP SY ROJ-VD2 Note 7 Safety /ReliefValve RV-2-71C Nuclear Boiler - G-08 1 C Act 6X10 SRV SA C O/C n/a SP SY ROJ-V02 Note 7 Safety /ReliefValve RV-2-71D Nuclear Boiler 11-0 8 1 C Act 6X10 SRV SA C O/C n/a SP SY ROJ-V02 Note 7 Safety /ReliefValve sir 2-23 NB FlowLimiting Valve C-03 2 C Pass 1 EFC SA O O n/a n/a n/a n/a Revision 19 Drawing : G-191167 Section 5 Page 31 of 179

- Vcrmont Yankee Nuclear Power Station Inservice Testing Program .

Table 5-1 Valve Listing Drawing: G-191167 _ DrawingTitle: . Nuclear Boiler Vdve Neuaber Nomenclature Dwg Safety OM Act / Size my Act Nem Safety fab Test Test CSJ/ROJ hm Coer Class Cat Pass (inch) Pos Pos Pos Type Freg RR Sb2-381A NB FlowLinutmg Valve E-04 2 C Pass ' 1 EFC .SA O O n/a n/a n/a ' n/a ,

Ste2-3clB NB Flowtimitmg Valve D-04 2 C Pass 1 EFC SA O O n/a n/a n/a n/a .j Str2 301E NB FlowLimitmg Valve E44 2 C Pass 1 EFC SA O O n/a n/a n/a n/a l

~

SL2-381F NB FlowLimitag Valve D-04 2 C Pass 1 EFC SA O O n/a n/a n/a n/a Sb2-385A NuclearBoilerVessel M-02 2 NC Act 1 EFC SA O (#C n/a LEF RO ROJ-V01 ,

Ind Excess FlowCheck Valve i 51,2-345B Nuclear BoilerVessel M-02 2 A/C Act 1 EFC SA O OC n/a LEF RO ROJ-V01 Ind Excess FlowCheck  ;

, Valve sir 242A Nuclear Boiler Vessel I-13 2 A/C Act 1 EFC SA O C n/a LEF RO ROJ-Vol i Ind Excess FlowCheck Valve .

SI,242B NuclearBoilerVessel I-13 2 A/C Act 1 EFC SA O C n/a LEF RO ROJ-V01  !

Ind Excess FlowCheck Valve Ste242C NuclearBoilerVessel J-13 2 A/C Act 1 EFC SA O C n/a LEF RO ROJ-VD1 IndExcess FlowCheck ,

Valve  !

Ste242D NuclearBoilerVessel J-13 2 NC Act 1 EFC SA O C ' n/a LEF RO ROJ-Vol  ;

l Ind Excess FlowCheck Valve ,

sir 244A Nuclear BoilerVessel K-13 2 A/C Act 1 EFC SA O OC n/a LEF RO ROJ-VD1 Ind Excess FlowCheck Valve l Ste244B Nuclear Boiler Vessel K-13 2 NC Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 Ind Excess FlowCheck I

Valve Str244c Nuclear Boilcr Vessel K-13 2 NC Act 1 EFC SA O O/C n/a LEF RO ROJ-V01  !

I IndExcess FlowCheck Valve Revision 19 Drawing : G-191167 Section 5 Page.32 of 179 ,

t f

4 Vcrmont Yankee Nuclear Power Station Inservice Testing Program -

Table 5-1 Valve Listing

' Crawing: G-191167 Drawing

Title:

NuclearBoiler Dwg Safety OM Act / Sire Body Act Norm Safety Fail Test Test CSJ/ROJ hah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Fral RR

- - SL2-64D NuclearBoilerVesel L-13 2 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-Vol Ind Excess FlowCheck Valve SU2-73A NuclearBoiler Vesel F-12 2 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-VO1 Ind Excess Flow Check Valve  ;

Sb2-73B NuclearBoiler Vesel F-12 2 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-VO1  :

Ind Excess FlowCheck Valve .

I SU2-73C Nuclear Boiler Vessel G-12 2 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 Ind Excess Flow Check Valve SL2-73D NuclearBoilerVessel G-12 2 A/C Act 1 EFC SA O O/C da LEF RO ROJ-V01 Inst Excess FlowCheck ,

Valve sb2-73E Nucicar Boiler Vessel G-12 2 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 IndExcess FlowCheck Valve SL2-73F NuclearBoilcr Vessel G-12 2 A/C Act 1 EFC SA O O/C LEF RO ROJ-Vol Inst Excess FlowCheck Valve SL2 73G Nuclear Boiler Vessel H-12 2 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 Inst Excess FlowCheck Valve SL2-73H Nuclear BoilerVessel H-12 2 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 Inst Excess FlowCheck l Valve .

SR-2-14A SRV Exhaust Line M-12 NNS C Act 3 CK SA C C n/a SC RO ROJ-V27 Vacuum Breaker SR-2-14B SRV ExhaustLine M-12 NNS C Act 3 CK SA C C n/a SC RO ROJ-V27 Vacuum Breakcr Revision 19 Drawing : G-191167 Section 5 Page 33 of 179

-Inservice Testing Program Vermont Yankee Nuclear Power Station'-

Table 5-1 Valve Listing -

Erawing: G-191167 Drawing

Title:

NucicarBoiler  ;

F- afdy OM Acd Size Body Nonn Sddy fab M M NW Rennarks -

Valve Naasber Nomenclature Act RR G*. j Class Cat Pass (nich) Pos. Pos ' Pos Type Freg ,

SR-2-14C SRVExhaustLine M-12 NNS C Act 3  % SA C O n/a SC RO ROJ-V27 .' '

Vacuum Breaker I

SR-2-14D SRV Exhaust Line M-12 NNS - C Act 3 m SA C C n/a SC. RO ROJ-V27 VacuumBreaker '

SR-2-14E SRV Dishage Line . L-12 3 C 'Act -10 N~ SA C OC n/a SP . 10Y n/a j Vacuum Relief Valve SR-2-14F SRVDischarge Line . L-12 3 C Act . 10 m SA C O/C n/a SP 10Y n/a Vacuum ReliefValve SR-2-14G SRVDischarBe Line L-12 3 C Act 10 N SA C ~ OC n/a SP 10Y n/a t

Vacuum ReliefValve i SR-2-14H SRV Discharge Line L-12 3 C Act 10 m SA C OC n/a SP 10Y n/a Vacuum ReliefValve SR-2-141 SRV Discharge Line L-12 3 C Act 10 m SA C OC n/a SP 10Y n/a Vacuum ReliefValve t SR-2-14J SRV DischargeLine L-12 3 C Act 10 N SA .C OC n/a SP 10Y n/a ~;

Vacuum ReliefValve SR-2-14K SRVDischarge Line L-12 3 C Act 10 m SA C- OC n/a SP 10Y n/a Vacuum R,wrValve L-12 3 C Act 10 N SA C OC n/a SP 10Y n/a SR-2-14L SRV Discharte Line Vacuum ReliefValve NuclearBoiler D-08 1 C Act 6X8 SRV SA C OC n/a SP 5Y n/a -

SV-2-7eA i Safety /ReliefValve H-08 C Act 6X8 SRV SA C OC n/a SP SY n/a l SV-2-70B NuclearBoiler 1 Safety /ReliefValve V2-27A Reactor Feedwater F-03 1 AC Act 16 m SA O OC n/a LJ 2Y n/a l InjectionLine Check SC RO _. ROJ-VD3 (

I Valve SO Q ROJ-V03 V2-27B Reactor Feedwater H-02 2 C Act 16 & SA O C n/a SC RO ROJ-VU3  :

InjectionLine Check Valve j

. Drawing : G-191167 Section 5 Page 34 of 179 Revision 19

. . _ _ _ _ _ _ _ _ _ _ _ ______________ _ _ _ _ _ _ _ _ _ _ _ _ ___ __ _ _ __ ___ _ ________________t

Vermont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191167 Drawing Tide: Nuclear Boiler Dwg Safety OM Act / Size My Act Norm Safety Fail Test Test CSJ/ROJ %g Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR V2-28A - Reactor Feedwater F-05 i NC Act 16 CK SA O O/C n/a LJ 2Y n/a Injection Line Check SC RO ROJ-V03

. Valve SO Q ROJ-V03 V2-2sB Reactor Fcedwater H-05 1 A/C Act 16 CK , SA O O/C n/a IJ 2Y n/a Injection Line Chak SC RO ROJ-V03 Valve SO Q ROJ-V03 V2400G . NBS Globe Valve F 04 2 B Pass 1.00 GL MAN C C n/a n/a n/a n/a V2400H NBS Globe Valve E-04 2 B Pass 1.00 GL MAN C C n/a n/a n/a n/a  !

V247A MSRV ActuatorNitrogen B-08 2 A/C Act 1 CK SA O/C C n/a LT 2Y n/a Supply CheckValve SC RO ROJ-V04 V2 37B MSRVActuatorNitrogen G-09 2 NC Act 1 CK SA O/C C n/a LT 2Y n/a '

Supply Check Valve SC RO ROJ-V04 V2,37C MSRVActuatorNitrogm G-09 2 A/C Act 1 CK SA O/C C n/a LT 2Y n/a Supply Check Valve SC RO ROJ-V04 V2 37D MSRV Actuator Nitrogen H-09 2 NC Act 1 CK SA O/C C n/a LT 2Y. n/a supply Check Valve SC RO ROJ-V04 V2 39AA 188 Penetration X-41 le04 2 NC Act .5 CK SA C O/C n/a LJB Var n/a ThermalReliefValve SC RO ROJ-V29 SO RO ROJ-V29 V2 41 Recire SampleTest Line M-03 2 B Pass 75 GL MAN LC C n/a n/a n/a n/a TestConnection V2-53A Rx Recirculation Pump 1,09 1 B Act 28 GA MO-AC O C FAI PIT 2Y n/a DischargeIsolation Valve SE CS CSJ-V04 V2-53B Rx Recirculation Pump L-09 1 B Act 28 GA MO-AC O C FAI PIT 2Y n/a i Discharge Isolation Valve STC CS CSJ-V04 V2-54A Rx Recirculation Pump L-09 1 B Act 4 GA MO-AC O C FAI PIT 2Y n/a Discharge Bypam Valve STC CS CSJ-V04 Revision 19 Drawing : G-191167 Section 5 Page 35 of 179

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191167 DrawingTitle: NuclearBoiler

'Dwg Safety OM Act / Size y~, gc, Nonn Safety Fail Test Test CSJ/ROJ ' hah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR

. V2-54B Rx Recirculation Pump L 09 1 B Act 4 GA MO AC O C FAI PIT 2Y n/a Ducharge BypassValve SE CS CSJ-V04 V2-74 Main Steam Line Drain E-10 1 A Act 3 GA MO-AC C C FAI U 2Y n/a contanunentIsolatim . PIT 2Y n/a valve STC n/a Q

V2-74A Penetration X-8 Hermal D-10 2 A/C Act .5 CK SA C O/C n/a W 2Y n/a ReliefValve SC RO ROJ-V29 SO RO ROJ-V29 Y2-75 TestConnection Between F-12 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Valves V2-74 and 77 V2-77 Main Steam Line Drain E-13 1 A Act 3 GA MO-DC C C FAI U 2Y n/a Contammentlsolation PIT 2Y n/a Valve STC Wa Q

V240A Main SteamIsolation D-10 1 A Act 18 GL AO O C FC FST Q n/a Note 1 valve u 2Y n/a PIT 2Y n/a STC Q n/a V240B Main SteamIsolation G-12 1 A Act 18 GL AO O C FC FST Q n/a Note 1 Valve U 2Y n/a PIT 2Y n/a STC Q n/a V240c Main SteamIsolation G-12 1 A Act 18 GL AO O C FC FST Q n/a Note 1 Valve U 2Y n/a

- PIT 2Y n/a STC Q n/a V240D Main SteamIsolation H-12 1 A Act 18 GL AO O C FC FST Q n/a Note 1 Valve u 2Y n/a PIT 2Y n/a STC Q n/a Revision 19 Drawing : G-191167 Section 5 Page 36 of 179

Inservice Testing Program Vermont Yankee Nuclear Power Station Table 5-1 Valve Listing Drawing: G-191167 Drawing T tle: NuclearBoiler Norsa Safety fab Test Test CSJ/RO Nomenclatur, Dwg Safety OM' Act / Size Body Act Renearts Valve Numher Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR V242A MSIVActuatorNitrogen B-10 2 A/C Act 1 CK SA O/C C n/a LT- 2Y n/a Supply CheckValve SC RO ROJ-V05 -

V242B MSIVActuatorNitros;en B-lO 2 A/C Act 1 CK SA O/C C n/a ,LT 2Y n/a Supply Check Valve . SC RO ROJ-V05 V242C MSIVActuatorNitrogen B-lO 2 A/C Act 1 CK SA O/C C n/a LT 2Y n/a Supply Chak Valve SC RO ROJ-V05 V242D MSIV Actuator Nitrogen B-10 2 A/C Act 1 CK SA O/C C- n/a LT 2Y n/a Supply CheckValve SC RO ROJ-VOS V243A Steam Line A Test D-12 2 B Pass 35 GL MAN LC C n/a n/a n/a n/a Connection V243B SteamLine B Test G-12 2 B Pass 35 GL MAN LC C n/a n/a n/a n/a Connectior V243C Steam LinekTest H-12 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Connection V243D Steam Lir.:D Test I-12 2 B Pass 35 GL MAN LC C n/a n/a n/a n/a Connection  ;

Main Steamisolation D-13 A Act 18 GL AO O C FC rsr Q n/a Note 1 V246A 1 Valve LJ 2Y n/a i PIT 2Y n/a S'It Q n/a V246B Main SteamIsolation G-12 1 A Act 18 GL AO O C FC FST Q n/a Note 1 i

valve LJ 2Y n/a PIT 2Y n/a  !

. STC Q n/a  ;

v246C MainSteamIsolation G-12 1 A Act 18 GL AO O C FC FST Q n/a Note 1 l Valve LJ 2Y n/a PIT 2Y n/a STC Q n/a i

Drawing : G-191167 Section 5 Page 37 of 179 Revision 19

Vermont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listir>g ,

Drawing: G-191167 Drawing

Title:

Nuclear Boiler Valve Namber Nomenclature Dwg Safety OM Act / Size Body Act Norn Safety Fail Test Tes: CSJ/ROJ hah Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR V246D MainStearnIsolation - H-12 1 A Act - 18 .GL AO O C FC FST Q n/a Note 1 Valve U 2Y n/a PIT 2Y n/a STC Q n/a V247A MSIVActuatorAir B-13 2 A/C Act 1 CK SA O/C C n/a LT 2Y n/a Supply CheckValve SC RO ROJ-V05 V247B MSIVActuatorAir B-13 2 A/C Act 1 CK SA O/C C n/a LT 2Y n/a Supply CheckValve SC RO ROJ-V05 V247C MSIVActuatorAir B-13 2 A/C Act 1 CK SA O/C C n/a LT 2Y n/a Supply Check Valve SC RO ROJ-V05 V247D MSIVActuatorAir B-13 2 A/C Act 1 -CK SA O/C C n/a LT 2Y n/a Supply CheckValve SC RO ROJ-V05 V2-94A FeedWater Line ATest F44 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Connection ,

V2-74B FeedWater B Test H-04 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Connection V2-96A ReactorFeedwater H-03 1 A/C Act 16 CK SA O O/C n/a LJ 2Y n/a InjectionLine Check SC RO ROJ-V03 Valve SO Q ROJ-V03 v2-96B Reactor Feedwater F-03 2 C Act 16 CK SA O C n/a SC RO ROJ-V03 Injection Line Check Valve

~

V2-98A NBS Globe Valve N-03 2 B Pass 1.00 GL MAN C C n/a n/a n/a n/a V2-988 NBS GlobeVal e N-12 2 B Pass 1.00 GL MAN C C n/a n/a n/a n/a ,

Revision 19 Drawing : G-191167 Section 5 Page 38 of 179

Vcrmont Yankee Nuclear Power Station Inservice Testing Program

' Table 5-1 Valve Listing Crawing : G-191168 Drawir.g

Title:

Core Spray System Valve Number Nomenclature Dwg Safety OM Act / Size Body Act Nonn Safety Fail Test Test CSJ/ROJ g,g Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR

- SI,14-31 A . CoreSprayInst Excess F-07 2 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-VO1 FlowCheck Valve S1,14-31B Core sprayInstExcess E-07 2 A/C Act i EFC SA O O/C n/a LEF RO ROJ-V01 Flow CheckValve SR-14-20A Cor- Spray Pump F-11 2 C Act 1.5 RV SA C O/C n/a SP 10Y n/a DiscLvge ReliefValve SR-14-20B Core Spm Pump D-12 2 C Act 1.5 RV SA C O/C n/a SP 10Y n/a DischargeIWiefValve V14-10A Core Spray Pump I-Il 2 C Act to CK SA C O/C n/a SC Q n/a Discharge Check Valve SO Q n/a V14-10B Core Spray Pump I-14 2 C Act 10 CK SA C O/C n/a SC Q n/a Discharge Check Valve

V14-11A Core Spray Injection G-09 2 B Act 8 GA MO-AC O O FAI PIT 2Y n/a.

Valve STO n/a Q

V14-11B Core Spray Injection C-09 2 B Act 8 GA MO-AC O O FAI PIT 2Y n/a Valve STO n/a Q

V14-12A Core Spray Injection G-08 1 A Act 8 GA MO-AC C O/C FAI IJ 2Y n/a Note 21 IsolationValve LT 2Y n/a PIT 2Y n/a STE Q n/a STO Q n/a V14-12B Core Spray Injection C-08 1 A Act 8 GA MO-AC C O/C FAI LJ 2Y n/a Note 21 Isolation Valve LT 2Y n/a

- PIT 2Y n/a STC Q n/a STO Q n/a V14-13A 19 Core Spray Injection F-06 i A/C Act 8 CK SA C O/C n/a CD RO ROJ-V34 Note 21 Check Valve LT 2Y n/a SC Q n/a Revision 19 Drawing : G-191168 Section 5 Page 39 of 179

' Vcrmont Yankee Nuclear Power Station Inservice Testing Program -

Table 5-1 Valve Listing Drawing : G-191168 DrawingTitle: Core Spray System Dwg Safety OM Act / Size Body Act Nonn Safety Fall Test Test CSJ/ROJ hah Valve Number Nomenclature Pos Pos Pos Type Fng RR Coor Class Cat Pass (inch)

V14-13n 19 Core Spray Inicction D-06 1 A/C Act 8 CK SA C O/C c/a CD RO ROJ-V34 Note 21  ;

Check Valve LT 2Y n/a SC Q n/a Core Sprayinjection Line F-05 1 B Pass 8 GA . MAN LO O n/a PIT 2Y n/a Note 14

.V14-14A Valve Core SprayInjectionLine E-05 B Pass 8 GA MAN LO O n/a PIT 2Y n/a Note 14 V14-14B 1 Valve V14-16A Core Spray to RIIR L-11 2 B Pass 4 GA MAN C C n/a n/a n/a n/a System Isolation Valve V14-16B Core spray to RIIR M-11 2 B Pass 4 GA MAN C C n/a afa n/a n/a SystemIsolationValve V14-22A 18A Condensate Transfer I-09 2 C Act 2 CK SA C C n/a SC OC RR-V14 Note 11 itsh Check Valve V14-22B 18A Condensate Transfer B-10 2 C Act 2 CK SA C C n/a SC OC RR-V14 Note 11 FlushCheck Valve V14-23A isA Condensate Transfer 1-09 2 C Act 2 CK SA C C n/a SC OC RR-V14 Note ll Flush Check Valve V14-23B 18A CondensateTransfer B 09 2 C Act 2 CK SA C C n/a SC OC RR-V14 Note 11 FlushCheckValve V14-26A 19 CoreSpray PumpTest F-10 2 B Act 8 GL MO-AC C O/C FAI PIT 2Y n/a LineIsolation Valve STC Q n/a STO Q n/a 19 Core Spray PumpTest E-10 2 B Act 8 GL MO-AC C O/C FAI PIT 2Y n/a V14-26B LineIsolation Valve STC Q n/a S1D Q n/a V1440A Core Spray Injection F-07 2 A Pass .75 GA MAN C C n/a LT 2Y n/a Note 21 Check Valve Bypass Valve Drawing : G-191168 Section 5 Page 40 of' 179 R; vision 19

' ' " - -- -- s . - _ __ _ _ , , _ , _ _ , _ _ , _ , , _ , _ _ _ _ _ _

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191168 DrawingTitle: Core Spray System Dwg Safety OM Act / Size My Act Norm Safety Fail Test Test CSJ/ROJ hah -

Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR

- V14,30B Core Spray Injection D-07 2 A Pass .75 GA MAN C C n/a LT 2Y n/a Note 21 Check Valve Bypass Valve V14,33A 18A Core Spray Discharge H-11 2 C Act 1 CK SA O/C C n/a SC OC RR-V13 Note 11 Pressuization Line CheckValve V14,33B isA Core Spray Docharge H-15 2 C Act 1 CK SA O/C C n/a SC OC RR-V13 Note ll L imtionLine CheckValve V14-5A Core Spray Pump H-12 2 B Act 3 GA MO-AC O O/C FAI PIT 2Y n/a Mmunum Flow Valve STC Q n/a STO Q n/a V14-5B Core Spray Pump H-13 2 B Act 3 GA MO-AC O O/C FAI PIT 2Y n/a Minimum Flow Valve STC Q n/a STD Q n/a V144A Test Connection K-04 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a V144B Test Connection 1,04 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a ,

V14-7A Core Spray Pump Suction K-11 2 B Act 12 GA MO-AC O/KL O/C FAI PIT 2Y n/a Valve STE Q n/a V14-7B Core Spray Pump Suction L-11 2 B Act 12 GA MO-AC O/KL O/C FAI PIT 2Y n/a Valve STC Q n/a V14443A Test Connection H-07 2 B Pass .75 GA MAN LC C n/a n/a n/a n/a V14443B TestConnection C-07 2 B Pass .73 GL MAN LC C n/a n/a n/a n/a V14-8A Core Spray Supply From K-12 2 B Pass 12 GA MAN LC C n/a n/a n/a n/a CSTIsolation Valve V14-8B Core Spray Supply From L-14 2 B Pass 12 GA MAN LC C n/a n/a n/a n/a CSTIsolation Valve Revision 19 Drawing : G-191168 Section 5 Page 41 of 179

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191169 Sh 1 DrawingTitle: High Pressure Coolant Injecten System Dwg Safety OM Act / Size Norm Safety Fail Test Test CSJ/ROJ Valve Number Nomenclature My Act hah Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR FCV-23-42 IIPCISteam Line Drain K-13 NNS B Act 1 GL AO O O/C FC FST -Q n/a PotIsolationvalve PIT 2Y n/a STE Q n/a STO Q n/a FCV-23-43 HPCI Steam Line Drain K-14 NNS B Act 1 GL AO O OC FC FST Q n/a PotIsolationvalve PIT 2Y n/a STC Q n/a STO Q n/a LCV-23-53 MnStm DminTrap H-14 2 B Act 1 GL AO C O FC FST Q n/a

  • Bypass & Stramer PIT 2Y n/a Blowo!TTrap Bypass da STC Q STO Q n/a i PAS-106* Post Accident Sampling J-05 * * * * * * * * * * * *
  • See G-191165 forvalve System Purge Valve info and test requirements S-23-6 HPCITurbme Exhaust I-06 2 D Act 16 RD SA C O/C n/a RD SY n/a Line Rupture Dise S-23-7 HPCITurbine Exhaust H-06 NNS D Act 16 RD SA C O/C n/a RD SY n/a t Line Rupture Disc SL23-37A Nuclear BoilerVessel F-05 2 A/C Act .75 EFC SA O O/C n/a LEF RO ROJ-Vol Inst Excess FlowCheck .

valve SL2347B Nuclear BoilerVessel F-05 2 A/C Act .75 EFC SA O O/C FC LEF RO ROJ-V01 InstExcess FlowCheck i Valve sb2347C Nuclear BoilerVessel F-05 2 A/C Act .75 EFC SA O O/C FC LEF RO ROJ-VOI

  • Inst Excess FlowCheck Valve ,

Sb2347D Nuclear Boiler Vessel F-05 2 A/C Act .75 EFC SA O O/C FC LEF RO ROJ-VO1 Inst Excess Flow Check j Valve 1

Revision 19 Drawing : G-191169 Sh 1 Section 5 - Page 42 of 179

Vcrmont Yankee Nuclear Power Station - Inservice Testing Program ,

Table 5-1 Valve Listing Drawing: G-191169 St.1 Drawing

Title:

High Pressure Coolant Injection System Dwg Safety OM Act / Size Body Act Norm Safety Fail Test Test CSJ/ROJ he Valve Number Nomenclature l Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR SSC-23-12 IsB IIPCITmbme Exhaust I-03 2. A/C Act 20 GSC SA C O/C n/a LJ 2Y n/a Stop CheckValve SC RO ROJ-V25 SO Q n/a SSC-23-13 IIPCI TurbmeExhaust J-04 2 C Act 2 GSC .SA C O n/a CD RO n/a Drain Stop Check Valve PSO Q n/a V23-14 IIPCISteamSupply Valve F-13 2 B Act 10 GA MO-DC C O FAI PIT 2Y n/a STO Q n/a V23-15 IIPCI Steam Supply D-04 1 A Act 10 GA MO-AC O O/C FAI LJ 2Y n/a inboard containment PIT 2Y n/a Isolation Valve STC Q n/a S10 Q n/a V23-153A HPCITorus Supply Line L-03 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Drain Valve V23-16 18B IIPCI Steam Supply D-05 1 A Act 10 GA MO-DC O O/C FAI LJB Var n/a Inboanicontainment PIT 2Y n/a Isolation Valve STC n/a Q

STO Q n/a V23-160A 18B IIPCI Steam Supply E-05 2 A Pass 1.75 GL MAN LC C n/a LJB Var n/a Drain Valve V23-17 HPCI Pump Suetion D-Il 2 B Act 14 GA MO-DC O O/C FAI PIT 2Y n/a Valve from Condensate STC Q n/a StorageTank STO Q n/a V23-18 IIPCI Pump Discharge to G-05 2 C Act 14 CK SA C O/C n/a SC CS CSJ-V06 Feedwater Check Valve SO CS CSJ-V06 V23-19 HPCI Discharge to G-06 2 B Act 14 GA MO-DC C O FAI PIT 2Y n/a Feedwaterlsolation Valve STO Q n/a V23-20 IIPCI Pump Discharge G-08 2 B Act 14 GA MO-DC O O FAI PIT 2Y n/a Valve STO Q n/a Revision 19 Drawing : G-191169 Sh 1 Section 5 Page 43 of 179

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Erawing: G-191169 Sh 1 DrawingTitle: High Pressure Coolant Injection System Valve Number Nomenclature Dwg Safety OM Act / Size My Act Norm Safety Fail Test Test CSJ/ROJ Remarks Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR V23-20B IRA Pressunzing and Vent G.07 2 C Act 1 CK SA C C n/a SC OC RR-V13 Note 11 Valves HPCIto RX Keep Fill V23-21 HPCI PumpTest Return Fe07 2 B Act 10 GL MO-DC C C FAI PIT 2Y n/a Valve to Condensate STE n/a Q

StorageTank V23-25 HPCI Pump Mmunum F-09 2 B Act 4 GL MO-DC C O/C FAI PIT 2Y n/a Recire Valve STC Q n/a STO Q n/a V23-26B HPCI Exhaust Dmin to J-04 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a TorusTest Connection Valve V23-27A HPCI Test Connection E-04 2 B Pass .75 GL MAN- LC C n/a n/a n/a n/a V23,32 isA IIPCI Pump Suction E-11 2 C Act 14 CK SA O/C O/C n/a SC OC RR-VIS Note 11 CheckValve from Cond. SO Q n/a StorageTank V23-56 HPCI'nnbine Exhaust J-05 2 C Act 2 CK SA O/C C n/a CD RO n/a Drain CheckValve LT 2Y n/a PSO Q n/a SC RO ROJ-V25 V23-57 IIPCITorus Suction F-10 2 B Act 16 GA MO-DC C O/C FAI PIT 2Y n/a ContainmentIsot Valve- STC Q n/a Outbd STD n/a Q

V23-58 HPCI Torus Suction L 04 2 B Act 16 GA - MO-DC C O/C FAI PIT 2Y n/a ContainmentIsolation STC Q n/a Valve STO n/a Q

V23-59A HPCI Torus Supply Test I OS 2 B Pass .75 GL MAN C C n/a n/a n/a n/a Connection Valve V23-61 HPCI Torus Suction Ie06 2 C Act 16 CK SA C O n/a CD RO n/a Check Valve Revision 19 Drawing : G-191169 Sh 1 Section 5 Page 44 of 179

A- .

i Vcrmont Yankee Nuclear Power Station - Inservice Testing Program Table 5-1 Valve Listing

- Drawing: G-191169 Sh 1 DrawingTitle: High Pressure Coolant Injection System Dwg Safety OM ' Act / Slae My None Safety fab Test Test CSJ/ROJ - hah Valve Number Nomenclature Ad RR Coor Class Cat Pass Onch) Pos Pos Pos Type Freq V2342 IIPCIPumpMuumum J-10 2 C Act 4 m- SA C O/C n/a ' CD . RO n/a Recire CheckValve PSO Q da V2343A IIPCITestCormection en I-03 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Toms Exhaust .

V2345 19 IIPCIhExhaust I-03 2 NC Act 20 m SA C O/C n/a LJ 2Y n/a CheckValve SC RO ROJ-V25 '

SO Q n/a V23445 tan 11PCITurbine Exhaust I-2 2 A/C Act 3 m SA C O/C N/A LT 2Y n/a Hisis nozzle checkvalve VacuumBreaka PSO Q n/a design. '

SC RO ROJ-V33 SO RO ROJ-V33 V23446 isB IIPCITurbmeExhaust I-2 2 A/C Act 3 m . SA C O/C N/A LT 2Y n/a Disisnozzle checkvalve '

Vacuum Breake PSG Q n/a design.

SC RO ROJ-V33 SO RO ROJ-V33 a

Drawing : G-191169 Sh 1 Section 5 - Page 45 of 179 Revision 19

t Vcrmont Yankee Nuclear Power Stalion Inservice Testing Program -

Table 5-1 Valve Listing Drawing: G-191169 Sh 2 Drawing

Title:

High Pressure Coolant Injection System Nomenclature Dwg Safety OM Act / Size My Act Nonn Safety Fail Test Test CSJ/ROJ gg Valve Number Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR HPCI-CONTROL HPCISteam Supply F-13 2 B Act 10 GL HO O O FC PIT 2Y n/a Note 12 Turtune Controlvalve SKID Q n/a HPCI-STOP HPCITurbine Stop Valve F-15 2 B Act 10 GA HO C O/C FC PIT 2Y n/a Note 12 SKID Q n/a LCV-23-39 IIPCI Gland SealReturn M-11 3 B Act 1 GL AO C O/C FC FST . Q u/a Level contDmValveto PIT 2Y n/a Radwade STC Q n/a STO Q n/a LCV-23-40 HPCI Gland SealReturn M-11 3 B Act 1 GL AO C O/C FC . FST Q n/a LevelCont Dm Valve to PIT 2Y n/a Radwade STC Q- n/a S'IO Q n/a LCV-23-54 HPCI Drain to Gland I-12 2 B Act 1 GL AO C O FC FST -Q n/a Seal C1=d-"" PIT 2Y n/a STC Q n/a S'IO Q n/a PCV-23 50 IsB Pressure ControlValve J-12 2 B Act 2 GL HO O O FO SKID Q n/a CoolingWaterto Lube Oil Cooler SR-23-34 HPCI Safety Valve D-09 2 C Act 1.5 RV SA C O/C n/a SP 10Y n/a SR-23-66 HPCI Booster Pump J-12 2 C Act 1.5 RV SA C O/C n/a SP 10Y n/a Gland SealCond. Line ReliefValve V23-130 HPCI Gland SealTube L-11 2 C Act 2 CK SA C O n/a SKID Q n/a Note 12 Side Return Check Valve V23-131 HPCI Gland Seal Cond. L-11 2 C Act 2 CK SA C O!C n/a SKID Q n/a Note 12 Shell Side Return Check Valve i

Rtvision 19 Drawing : G-191169 Sh 2 Section 5 Page 46 of 179

. Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191169 Sh 2 Drawing

Title:

High Pressme Coolant Injection System Dwg Safety OM Act / Size My Act None Safety Fail Test Test CSJ/ROJ y ,,g-Valve Number Nomenclature Coor Class Cat Pass (mach) Pos Pos Pos Type Freq RR V23-148A HPCI Steam Rmg/ Chest G-14 3 C Act 1- CK SA O/C O n/a SKID Q n/a Note 12 Drain Check Valve V2314sB IIPCISteam Rmg/ Chest G-14 3 C Act 1 CK SA 'O/C O n/a SKID Q n/a Note 12 .

Drain Check Valve .

V23-50A IIPCI Gland SealCond. J-10 2 B Act 2 GA AO C O FO PIT 2Y n/a Note 12 Supply Valve SKID Q n/a I

s b

Revision 19 Drawing : G-191169 Sh 2 Section 5 Page 47 of 179 ;

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191170 Drawing

Title:

Control Rod Drive Ilydraulic System Dwg Safety OM Act / Size My Act Nonn Safety Fail Test Test CSJ/ROJ Remah Valve Number Nomenclature

, Ct,or Class Cat Pass (inch) Pos Pos Pos Type Freq RR CV4-126 CentrolRod Drive Scram C-16 2 B Act 1 GL AO C O FO FST RO ROJ-V06 Note 16 Valve (Typicalof 89) PIT 2Y n/a i S1D RO ROJ-V06 CVa-127 ControlRod Drive Scram C-18 2 B Act .75 GL AO C O FO FST RO - ROJ-V06 Note 16 Valve (Typicalof 89) PIT 2Y n/a STO RO ROJ-V06 LCV-3-33A 18B Scram Discharge Volume D4)7 2 A Act 2 BL AO O C FC FST Q n/a DrainLevelControlValve LT 2Y n/a PIT 2Y n/a STU Q n/a LCV-3-33B 18B ScramDischarge Volume D-03 2 A Act 2 BL AO O C FC FST Q n/a Drain Level ControlValve LT 2Y n/a PIT 2Y n/a STE Q n/a LCV 3-33C 18B f,crumDischarge volume D-08 2 A Act 2 BL AO O C FC FST Q n/a DrainLevelControlValve LT 2Y n/a PIT 2Y n/a STC Q n/a LCV 3-33D 18B ScramDisclunge Volume D-03 2 A Act 2 BL AO O C FC FST Q n/a Draini.evel control Valve LT 2Y n/a PIT 2Y n/a STC Q n/a PCV-3-32A isa Scram DL%e Volume A-09 2 A Act 1 BL AO O C FC FST Q n/a VentPressureC9ntrol LT 2Y n/a Valve PIT 2Y Wa SIC Q n/a Revision 19 Drawing : G-191170 Section 5 Page 48 of 179

a Vcrmont Yankee Nuclear Power Station ' Inservice Testing Progrann .

Table 5-1 Valve Listing .

Drawing: G-191170 DrawingTitle: Control Rod Drive Hydraulic System ~

Valve Numiber Neuneoclature Dwg Way OM Act / h Body Act Nenn W M h h WM g,,,,,g, .

Coor Class Cat Pass (inch) Pos Pos - Pee Type Freq RR e PCY442a IRB Scram DechargeVolume A-01 2 A Act 1 BL . AO O C FC FST Q n/a i VatPresnue Control LT 2Y n/a i Valve PIT 2Y Wa S'It Q n/a -

50,1-12e CRD ManualControl D-17 2 B Act .5 GA SO .C C FC' FST RO ROJ-V06 Note 17 ExhaustValvegypical STC RO ROJ-V06 of89) .

5 0,3-121 CRD ManualControl D-18 2 B Act .5 GA SO C C FC FST RO ROJ-V06 . Note 17 ExhaustValve Fypical STC RO ROJ-V06 ,

of89)

S 4 3-122 CRD ManuelControl C-18 2 B Act .5 GA SO C C FC FST RO ROJ-V06 Note 17 WithdrawalValve 31C RO ROJ-V06 Gypicalof 89)

SO3-123 CRD ManualControl C-17 2 B Act .5 GA SO C C FC FST RO ROJ-V06 Note 17 Insertion Valve Fypical - STC RO ROJ-V06 I' of89)

. V3-114 Scram ExhaustTo C-18 2 C Act .75 CK SA C OC n/a SC RO ROJ-V06 Note 18 i Discharge Volume Check SO' RO - ROJ-V06 i (Typicalof 89)

V3-115 CRD Charging WaterTo B-16 2 AC Act .5 CK SA O/C C n/a LT RO ROJ-V06 Note 19 i Accumulator Check SC RO ROJ V06 UYPi calof 89) ,

V3-13e Drive WaterInsert High B-14 2 B Pass .75 GL MAN C C n/a n/a n/a ria ' ~f Point VentUypical of 89)

V3-132 Drive WaterWithdrawal A-14 2 B Pass .75 GL MAN C C n'a n/a n/a n/a IIigh Point Vent,(Typical j of89)

V3-137 Drive Water Supply B-17 2 C Act .5 CK SA 'OC C n/a SC RO ROJ-V06 CheckValve(Typicalof 89)

Revision 19 Drawing : G-191170 Section 5 Page 49 of 179

- Vcrmont Yankee Nuclear Power Station I: service Testing Prograna ' ,

Table 5-1 Valve Listing Drawing: G-191170 DrawingTkle: ControlRod Drive Hydraulic System Dwg Safety OM Act / Sise Neran Safety fab Test Test CSJ/ROJ ValveNussber Neunenclature -

Coor Class Cat Pass (inch)

% Act Pos Pos Pos Type Freg RR h6 v3-13e CRD Cooling Water B-16 2 C Act .5 & SA O/C lC n/a SC Q n/a Note 3 supply Check valve  :

(rypicalof 89) l V3-162A Scrum Ducharge Volume A-09 2 A/C Act 1 CK SA O C n/a LT 2Y n/a VaitCheck Valve RO ROJ-V12 SC V3-162B ScramDischarge Volume A-01 2 A/C Act 1 CK SA O C n/a LT 2Y n/a Ventcheck Valve SC RO - ROJ-V12 V34e8A Recire Pump SealPurge F-12 2 B Pass .75 GL 1(AN C C n/a n/a n/a n/a ,

Valves ,

B Pass M Ai!' C  !

v3-4ess Recirc Pump SealPurge F-12 2 .75 GL C n/a n/a . n/a n/a Valve v3-4 tea Recirc Pump SealPurge F-13 2 B Pass .75 GL MAN C .C n/a n/a n/a n/a Valve .

i V3-4 ten Recirc Pump ScalPurge F-13 2 B Pass .75 GL MAN C C n/a n/a n/a n/a ,

Valve V3-412A 18B Recirculshon Pump Seal E-12 2 A/C Act .75 CK SA O/C C n/a IJB Var n/a

Purge Supply Check SC RO ROJ-V07

. Valve v3 412B ISB Recirculshon Pump Seal E-12 2 A/C Act .75 CK SA O/C C n/a LJB Var n/a

., Purge Supply Check SC RO ROJ-V07

Valve V3-413A 18B Recirculshon Pump Seal E-12 2 A/C Act .75 CK SA O/C C n/a LJB Var n/a Purge Supply Check SC RO ROJ-V07 Valve V3-413B 18B Recirculation Pump Seal E-12 2 A/C Act .75 CK SA O/C _C n/a LJB Var n/a Purge Supply Check SC RO ROJ-V07 Valve  ;

t i

Revision 19 Drawing : G-191170 Section S Page 50 of 179  !

l

Vermont Yankee Nuclear Power Station Inservice Testing Program '

Table 5-1 Valve Listing

. Drawing: G-191171 Drawing'I1tle: Stanchy Liquid Control System .

Dwg Safety OM Act / Size My Act None Safety fab Test Test CSJ/ROJ g ,,, g Valve Nuanber ' Nesmenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR S-11-14A SLCInyctan(Squib) G-03 '2 D Act - ' l.5 SQUIB EXP C O. . n/a Er- 2Y - n/a - Note 4 -

Vdve 3

-S-11-14B SLCInpctan(Squib) H-03 2 D Act 1.5 SQUIB 'EXP C O n/a- ET 2Y n/a Note 4 Valve . . .

SR-1139A SLC Discharge Relief G-08 2 C Act 1 RV SA C O/C n/a SP OC RR-VD8 Valve SR-1139B SLC Dacharge Relief K-08 '2 C. Act 1- RV SA C O/C n/a SP OC RR-VD$ -

, Valve V11-16 SLCInjecten Pqnng H-03 1 C Act 1.5 CK SA C O/C n/a SC RO ROJ-V08 j CheckValve SO RO ROJ-VD8 V11-17 SLCInjecten Piping I-02 1 C Act 1.5 CK SA C O/C n/a SC RO ROJ-V08 CheckValve SO RO ' ROJ-V08 ,

VII-Is SLCInjecten Valve I-02 1 P Pass 1.5 ' GA MAN LO O n/a PIT '- 2Y n/a - Note 14 V1136 SLCTest Connection I-03 2 B Pass .75 GL MAN . LC C n/a - n/a n/a n/a V11-43A SLC Pump Ducherge H-07 2 C Act 1.5 CK SA. C~ O/C n/a SC Q n/a CheckValve SO Q n/a V11-43B SLC Pump Dacharge J-07 2 C Act 1.5 CK SA C O/C n/a SC Q n/a ^

CheckValve -SO 'Q n/a i

D Revision 19 Drawing : G-191171 Section 5 Page 51 of' 179 i

m Vermont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191172 Drawing

Title:

Resminal Heat Renovat System 1

Dwg Safdy N Act / h None Safety Fall Test Test CSJ/ROJ '

Valve Number Nomenclature Body Act Read Coor Class Cat Pass (inch) Pos Pos Pos Type Fng RR  !

. MV-10-16e RHRReturnLine Process F-15 2 B Act .75 GL AO C C FC FST Q n/a Valve also appears on G- f SanPling Valve PIT 2Y n/a 191165 [

STC Q n/a -

j RV-19-210A Rdief Valve - E-12 1 A/C Pass .5 ' RV . SA C C n/a U 2Y n/a  !

RV-18-210B ReliefValve E-06 1 A/C Pass .5 RV SA -C C n/a U 2Y n/a SR-10-35A RHRPump Ducharge D-02 2 C Act 1 RV SA C OC da- SP 10Y n/a ,

ReliefValve SR-10,35B RHRPump Ducharge D-15 2 C Act 1 RV SA C OC n/a SP 10Y . n/a ,

RdiefValve  !

GR-10 40 RHRShutdownCooling G-07 2 C Act 1 RV SA C O/C n/a SP 10Y n/a l Suction Line ReliefValve  ;

SR-19-72A RHR ReliefValve L-07 2 C Act 1 RV SA C OC n/a SP 10Y n/a ,

SR-19-72B RHR Rdief Valve ' L-11 2 C Act 1 RV SA C OC n/a SP 10Y n/a  ;

SR-19-72C RHR ReliefValve J-07 2 C Act 1 RV SA C O/C n/a SP 10Y n/a i SR-19-72D RHR ReliefValve J-10 2 C Act 1 RV SA C OC n/a . SP 10Y n/a .

SR-1940A RIR Heat Exchanger L-03 2 C Act 4 RV SA C OC n/a SP 10Y n/a "Ihbe Side Relief Valve SR-19-80B RHR HeatExchanger L-14 2 C Act 4 RV SA C OC n/a SP 10Y n/a Tube Side ReliefValve SR-16-86A RHRIIest Exchanger L-03 2 C Act 1 RV SA C OC n/a SP 10Y n/a

  • ShellSideReliefValve -!i SR-19-86B RHR HeatExchanger L-14 2 C Act 1 RV SA C O/C n/a SP 10Y n/a i ShellSide ReliefValve V10-13A Suppression PoolRHR L-08 2 B Act 20 GA CK O/KL OC FAI PIT 2Y n/a Purnp Suction Valve STC Q n/a  !

STO Q n/a Revision 19 Drawing : G-191172 Section 5 Page 52 of 179

Vcrmont Yankee Nuclear Power Station Inscryice Testing Program Table 5-1 Valve Listing Krawing : G-191172 Drawing

Title:

Residual Heat Removal System Valve Number Nomenclature Dwg Safety OM Act / Size My Act Nona Safety Fail Test Test CSJ/ROJ hah Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR

. V10-133 Suppression PoolRIIR I,09 2 B Act 20 GA MO-AC O/KL OE FAI PIT 2Y n/a Pump Suction Valve STC Q n/a STD Q n/a V16-13c Suppression PoolRHR J-08 2 B Act 20 GA MO-AC O/KL O/C FAI PIT 2Y n/a Pump Suction Valve STC Q n/a STO Q n/a V16-13D Suppression PoolRIIR J-09 2 B Act 20 GA MO-AC O/IG, O/C FAI PIT 2Y n/a Pump Suction Valve STC Q n/a ,

STO Q n/a V19-15A Recirculation Loop K-07 2 B Act 20 GA MO-AC C O/C FAI PIT 2Y n/a Supply Valve to RHR STC Q n/a Pump suction STO da Q

V16-15B Recirculation Loop K-10 2 B Act 20 GA MO-AC C O/C FAI PIT 2Y n/a Supply Valve to R11R STC Q n/a Pump Suction S1D Q Wa V10-15c Rairculation Loop J-07 2 B Act 20 GA MO-AC C O/C FAI PIT 2Y n/a Supply Valve to RIIR STC Q n/a Pump Suction STO n/a Q

I V10-15D Recirculation Loop J-10 2 B Act 20 GA MO-AC C O/C FAI PIT 2Y n/a Supply Valveto RIIR STC Q n/a Pump Suction da STO Q V19-16A RHRPump Discharge I-05 2 B Act 4 GA MO-AC O O/C FAI PIT 2Y n/a i MiniFlow Retum to STC Q n/a Suppression Pool STO n/a Q

V16-16B RHR Pump Discharge I-12 2 B Act 4 GA MO-AC O O/C FAI PIT 2Y n/a MiniFlowReturn to STC Q n/a Suppression Pool STO Wa Q

I Revision 19 Drawing : G-191172 Section 5 Page 53 of 179

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

Vermont Yankee Nuclear Power Station - Inservice Testing Program Table 5-1 Valve Listing Erawing : G-191172 Drawing

Title:

- Residual Heat Removal System Nomenclature Dwg Safety OM Act / Size my ge, Norma Safety Fail Test Test CSJ/ROJ hah i Valve Number -

Coor Class Cat Pass (inch) Pos Pos Pos Type Fng RR V10-17 1sB Recarc Supply to RHR G 08 1 A Act 20 GA MO-DC C O/C . FAI LJB Var n/a Note 21 Pump Suct. Outbd. .

LT 2Y n/a Isolation Valve PE 2Y Wa >

~

STC CS CSJ-V08 STO CS CSJ-V08 V19-17Al V10-17 Bonnet Vent G-08 2 B Act .5 GL MAN C O/C n/a SC CS CSI-V18 Valve V18-18 IsB Recire Supply to RHR F-08 1 A Act 20 GA MO-AC C O/C FAI LJB Var n/a Note 21 '

Pump SuctionInbd LT 2Y n/a IsolationValve PE 2Y- da STC CS CSJ-V08 STO CS CSJ-V08

  • V10-182 RHRSW to RHR I-02 2 C Pass 10 CK SA C n/a n/a n/a n/a n/a -

Emergency FillCheck Valve V10-183 RHRSW to RHR J-02 2 B Pass 10 GA MO-AC C C FAI PIT 2Y n/a -

Emergency FillIsolation [

Valve V10-184 RIIRSW to RIIR J-02 2 B Pass 10 GA MO-AC C C FAI PIT 2Y n/a Emergency FillIsolation Valve V10-18A 18B Penetration X-12 F-08 2 A/C Act .50 CK SA C O/C n/a LJB Var n/a Note 21 "Ihennal ReliefValve LT 2Y n/a SC RO ROJ-V29 SO RO ROJ-V29 ,

V10-18A5 18B V10-18 Bonnet Relief F-08 2 A/C Act .50 CK SA C O/C n/a LJB Var n/a Note 21 Valve LT 2Y n/a SC RO ' ROJ-V29 SO RO ROJ-V29 V10-198B 18B Process Sampling Valve E-14 2 A Pass .75 GL MAN LC C n/a LJB Var n/a e

Revision 19 Drawing : G-191172 Section 5 Page 54 of 179

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Crawing: G-191172 DrawingTitic: Residual Heat Removal System Dwg Safety OM Act / Size hdy Act Nonn Safety Fail Test Test CSJ/ROJ Remah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR V10-19A RHRMuumumFlow 1,05 2 C Act 3 CK SA O/C O/C n/a CD RO n/a CheckValve PSO Q n/a V10-19B RIRMmunum Flow L-12 2 C Act 3 CK SA O/C O/C n/a CD RO n/a CheckValve . PSO Q n/a V10-19C RIIR Minimum Flow J-05 2 C Act 3 CK SA O/C O/C n/a CD RO n/a CheckValve PSO Q n/a V10-19D RIIR MaumumI' iw J-12 2 C Act 3 CK SA O/C O/C n/a CD RO n/a Check Valve PSO Q n/a V10-20 RIIRLoop Crossconnect H-05 2 B Pass 20 GA MO-AC C C FAI PIT 2Y n/a Valve V10-206A RIIR Suppression Pool I-08 2 B Pass .75 GA MAN C C n/a n/a n/a n/a Suction Dmin V10-206B RIRSuppression Pool I-09 2 B Pass .75 GA MAN C C n/a n/a n/a n/a Suction Line Drain V10-25A RIIRto Recirc Loop E-06 1 B Act 24 GA MO-AC O O FAI PIT 2Y n/a Isolation Valve STO Q n/a V10-25B RHRto Recirc Loop E-12 1 B Act 24 GA MO-AC O O FAI PIT 2Y n/a Isolation Valve STO Q n/a V10-26A ISB RHRTo Containment C-07 2 A Act 12 GA MO-AC C O/C FAI LJB Var n/a Spray Isolation Valve PIT 2Y n/a STC Q n/a STO Q n/a i V10-26B 18B RIIRTo Contamment C-10 2 A Act 12 GA MO-AC C O/C FAI LJB Var n/a sprayIsolation talve PIT 2Y n/a STC Q n/a STO Q n/a R:. vision 19 Drawing : G-191172 Section 5 Page 55 of 179

w Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191172 DrawingTitle: ResidualHeatRemovalSystem Dwg Safety OM Act / Size My Act Nonn Safety Fail Test Test CSJ/ROJ hah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR

- V10-27A RHR to Recire Loop D46 1 A Act ' 24 GL MO-AC C O/C FAI U 2Y n/a Note 21 Isolation Valve LT 2Y n/a PIT 2Y n/a STC Q n/a STO Q n/a V10-27B RHR to Recire Loop D-12 1 A Act 24 GL MO-AC C O/C FAI U 2Y n/a Note 21 Isolation Valve LT 2Y n/a PIT 2Y n/a STC Q n/a i

STO Q n/a V10,31A Isa RIIRTo Contamment C-08 2 A Act 12 GA MO-AC C O/C FAI LJB Var n/a Spray Isolation Valve PIT 2Y n/a STC Q n/a STD Q n!a V10 31B 18B RHRTo Contamment C-10 2 A Act 12 GA MO-AC C O/C FAI LJB Var n/a spray Isolation Val ~ PIT 2Y n/a STC Q n/a STO Q n/a V10-34A 18B RHR SuppressionPool E-03 2 A Act 10 GL MO-AC C O/C FAI UB Var n/a cooling Supply Valve PIT 2Y n/a STC Q n/a ,

STO Q n/a V10-34B 18B RIIR SuppressionPool E-14 2 A Act 10 GL MO-AC C O/C FAI UB Var n/a

., Cooling Supply Valve PIT 2Y n/a STE Q n/a STO Q n/a V10-36A 18A RHRPump Discharge J43 2 C Act 1 CK SA O/C C n/a SC OC RR-V13 Note 1I Ihking Line Check Valve Revision 19 Drawing : G-191172 Section 5 Page 56 of 179

Vcrmont Yankee Nrclear Paw:r Station Inservice Testing Program Table 5-1 Valve Listing Crawing: G-191172 Drawing

Title:

ResidualHeat Removal System Dwg Safety OM Act / Size Body Act Nona Safety fab Test Test CSJ/ROJ hah Valve Nuanber Mouncociature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR VisJ6B IsA RHRPump Ducharge J-14 2 C Act 1 & SA O/C C- . n/a SC- OC RR-V13 Note ll P. a; LineCheck t

Valve VitJ8A 18B Suppresmon Chamber E-04 2 A Act 4 GL MO-AC C O/C FAI UB Var - n/a RHRSpray Ring Supply PIT 2Y n/a 4

Valve g q g, -

STO Q n/a +

V16J8B IsB Suppresnon Chamber F-13 2 A Act 4 GL MO-AC C OC FAI UB Var n/a >

RHRSpray Ring Supply PE 2Y Wa i Valve g q g,  ;

S10 Q n/a VISJ9A 18B RHRCont D-04 2 A Act 12 GA MO-AC C O/C FAI LJB Var n/a Spray /Suppresson Pool - PIT 2Y n/a .

t Cooling Supply Valve - g q g, S10 Q n/a ,

V1009B IsB RHRCont D-13 2 A Act 12 GA MO-AC C OC FAI LJB Var n/a ,

Spray /Suppresson Pool PR 2Y n/a Cooling Supply Valve g q g, STO Q n/a V16 46A RHRto RecireInjection Fe07 1 AC Act 24 & SA C OC n/a LT 2Y n/a Note 21 Check Valve SC Q n/a  !

SO CS CSJ-V14 V16 46B RHRto RecireInjection E-10 1 AC Act 24 & SA C OC n/a LT -2Y n/a Note 21 Check Valve SC Q n/a SO CS CSJ-V14 _

V10-48A RHRPump Discharse L-05 2 C Act 16 & SA OC OC n/a PSO Q CSJ-VIS CheckValve SC Q n/a '[ '

SO CS CSJ-VIS Revision 19 Drawing : G-191172 Section 5 Page 57 of 179

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

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191172 a. wing

Title:

Residual Heat Removal System swg Safety OM Act / Sire Body Act Nonn Safdy Faa Ted h N OJ Remarks Valve Number Nomenclature lCoor Class Cat Pass (inch) Pos Pos Pos Type Freg RR V10-48B RIIRPump Discharge L-13 2 C Act 16 CK SA O/C O/C n/a PSO Q CSJ-V15 Check Valve SC Q n/a SO CS CSJ-VIS V10-48C RHRPump Discharge J-05 2 C Act 16 CK . SA O/C O/C n/a PSO Q CSJ-V15 Chcck Valve SC Q n/a SO CS CSJ-V15 V10-48D RIIRPump Discharge J-13 2 C Act 16 CK SA O/C O/C n/a PSO Q CSJ-VIS Check Valve SC Q r/a SO CS CSJ-V15 V10-52A RHRContainment Spray C-08 2 B Pass .75 GL MAN C C n/a n/a n/a n/a Loop A Test Connection V10-52B RHRContainment Spray C-10 2 B Pass .75 GL MAN C C n/a n/a n/a n/a Loop B TestConnection V10-57 I8B RHR Loop Crossconnect H-13 2 B Act 4 GA MO-DC C C FAI PIT 2Y n/a To RadWasteIsolation STE Q n/a Valve V10-65A RIIRIIX Bypass Valve J-03 2 B Act 20 GL MO-AC O O/C FAI PIT 2Y n/a STC Q n/a STO Q n/a V1M5B RIIR HX Bypass Valve K-15 2 B Act 20 GL MO-AC O O/C FAI PIT 2Y n/a -

STC Q n/a STO Q n/a V10-66 18B RIIRLoop Crossconnect H-13 2 B Act 4 GA MO-AC C C FAI PIT 2Y n/a To RadWaste Isolation STC Q n/a Valve V10-78A RIIR "A" Injection Line F-06 2 B Pass .75 GL MAN C C n/a n/a n/a n/a Test Connection V10-78B RIIR"B"lajection Line F-12 2 B Pass .75 GL MAN C C n/a n/a n/a n/a Test Connection Revision 19 Drawing : G-191172 Section 5 Page 58 of 179

L S

Vcrinont Yankee Nuclear Pcwcr Station I service Testi;g Program Tabic 5-1 Valve Listing Drawing: G-191172 DrawingTitle: ResulualHeatRemovalSystem Dwg Safety OM Act / Sise Noma Safety Fall Test Test CSJ/ROJ Resad l Valve Number Noamenclature.

Coor Class Cat Pass (inch)

M Act Pos Pos- Pos Type Fatg RR V1081A RHRto Recire Loop E-07 2 B Pass 24 GA- MAN LO O n/a PIT 2Y n/a - Note 14

InjectionValve r V1681B RHRto Recire Loop E-10 2~ B Pass 24 GA MAN !O- O n/a PIT 2Y- n/a Note 14 InjectionValve ,

~

V1684- Test Connection Between G-09 2 B Pass .75 ' GL MAN C' C n/a n/a n/a n/a V10-17 and 18 V1689A RHRHX Savice Water M-01 3 B Act 12 GL MO-AC -C O/C FAI PIT 2Y_ n/a Valve also appears on G- '!

OutletValve . STC Q n/a 191159 Sh 2 -[

S10 Q n/a i V1649B RHRHX Service Water M-17 3 B Act 12 GL - MO-AC C O/C FAI PIT 2Y n/a Valve also appears on G- -

OutletValve SIC Q n/a 191159 Sh 2 STO - Q^ n/a ' l Vio-91A . Test Connection E-07 2 B Pass .75 GA MAN LC C. n/a n/a n/a n/a Vio-91B Test Connection E-11 2 B Pass 35' GA MAN LC 'C n/a n/a n/a - n/a Vie-95A Test Connection -D-04 2 B Pass 35 GA MAN LC ~C . n/a . n/a n/a n/a V10-95B Test connection D-14 2 B Pass .75 GA . MAN LC C- n/a n/a n/a n/a I a VIS-96A Test *- C-08 2 B Pass .75 GA MAN LC C . n/a n/a . n/a n/a j Vio.968 Test connection C-10 2 B Pass .75 GA MAN LC C n/a ~ n/a n/a n/a ~

I Revision 19 Drawing : G-191172 Section 5 Page 59 of 179 .

i

f Vcrmont Yankee Nuclear Power Station Inservice Testing Pmgram.

~

~ Table 5-1 Valve Listing 'i Drawien: G-191173 Sh 1 Drawing Tkle: ' Fuel Pool Cooling & Cleanup System Valve Namnber ' Nomenclature Dwg W OM ActI h Body ~ Act None W M M M WM .

g,,,,,g,-

Coer Class Cat Pass (inch) Pos Pos Pos Type Fng RR

- - V19-18 FuelPoolDenunerahmer - I-13 3' C' Act 6 CK SA O .C n/a SC ~ .Q n/a -

Return CheckValve V19-21A ' FuelPoolCooling Return A-07 2 .C Act 6 CK SA O .O' n/a SO Q n/a ~

to FuelPool Check Valve .

V19-21B FuelPoolCooling Retum A-07. 2 C Act 6 CK 'SA O '- O n/a .SO Q .. n/a to FuelPoolCheck Valve i V19-220 NoonalFuelPool G.07 3 B . Act 8 GA MO-AC O C FAI PIT 2Y n/a .

Coohng Subsystem Isolation Valve 3It - Q- n/a 3

V19-221 Nonnal FuelPool - G-08 3 B' Act 8 GA MO-AC O C FAI PIT 2Y n/a Cooling Subsystem STC . Q .- n/a

' Isolation Valve V19-224 FuelPool C-- =r-" I-12 3 C ' Act 6 CK- 'SA O C n/a SC RO ROJ-V23 Retum CheckValve V19-45 U Gate Valve F/D Bypass K-0i 3 B Pass 4 GA M A'4 C C n/a n/a - n/a n/a t

.V19-53 UGate Valve RX WellL H-05 3 B Pass 6~ GA MAN C. C n/a n/a - n/a n/a f

Recirc Valve -

'i I

i t

I

-l Revision 19 Drawing : .G-191173 Sh 1 Section 5 ' Page 60 of 179  ;

_--_ _ __ - _ - _ _ _ - _ _ _. --- - __ -____-___J

Vcrmont Yankee Nuclear Power Station Inservice Testing Program -

Table 5-1 Valve Listing Drawing: G-191173 Sh 2 Drawing

Title:

FuelPoolCooling& Cleanup System Dwg Safety OM Act / Size Body Act Nonn Safety Fail Test Test CSJ/ROJ Rema h Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR f.V19-232A Standby FuelPoolHeat C-07 3 C Act 1 RV SA C O/C. n/a SP 10Y Wa ExchangerFPC Side ReliefValve RV19-232B Standby FuelPoolHeat F-07 3 C Act 1 RV.

  • SA C O/C n/a SP 10Y n/a ExchangerFPC Side ReliefValve RV70-260A Service Water Relief D-08 3 C Act .75 RV SA C O/C n/a SP 10Y n/a Valve RV70-260B ServiceWaterRelief F-08 3 C Act .75 RV SA C O/C n/a SP 10Y n/a Valve V11226 Standby FPCS Manual C-13 3 B Pass 6 GA MAbi C C n/a n/a n/a n/a Isolation- ESS Pump .

Cross-tie i V19-230A Standby FuelPool G-10 3 C Act 6 CK SA C O/C n/a SC Q n/a Cooling Pump Discharge SO Q n/a CheckValve i V19-230B Standby FuelPool H-10 3 C Act 6 CK SA C O/C n/a SC Q n/a Cooling Pump Discharge SO Q n/a Check Valve ,

V70-244A 1sn SW System Vacuum B-10 3 C Act 2 CK SA C O/C n/a SC RO ROJ-V28 BreakerCheckValve SO RO ROJ-V28 V70-244B 18B SW System Vacuum B-10 3 C Act 2 CK SA C O/C SC RO ROJ-V28 Breaker CheckValve SO RO ROJ-V28 V70-257A SFPC Hx ScrviceWater C-10 3 B Act 4 GL MO-AC C O FAI PIT 2Y n/a outlet STC Q n/a Hrottling/IsolationValve g g g V70-257B SFPC IIx ServiceWater F-10 3 B Act 4 GL MO-AC C O FAI PIT 2Y n/a Outlet STC Q n/a nrottling/ Isolation Valve g q g, Revision 19 Drawing : G-191173 Sh 2 Section 5 Page 61 of 179

Vermont Yankee Nuclear-Power Station Inservice Testing Program Table 5-1 Valve Listing Crawing: G-191174 Sh 1 Drawing

Title:

Reactor Core Isolation Cooling System Valve Number Nomenclature Dwg Safety OM Act / Size My Act Nonn Safety Fall Test Test CSJ/ROJ h6 Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR -

. FCV-13-34 RCIC Main Steam Drain K-17 NNS B Act 1 GL AO O O/C FC FST Q n/a to Condenser Valve PIT 2Y n/a .

STC Q n/a S10 Q n/a FCV-13435 RCIC Main Steam Drain L-17 NNS B Act 1 GL AO O O/C FC FST Q n/a .

to Condenser Valve PIT 2Y n/a STC Q n/a S'ID Q n/a LCV-13,32 RCIC Steam DrainTrap H-17 2 B Act .75 GL AO C O/C FC FST Q n/a Bypass Valve PIT 2Y n/a STC Q n/a STO Q n/a -

Sb13-55A RCIC Instrumentation B-08 2 NC Act .75 EFC SA O O/C n/a LEF RO ROJ-Vol Excess FlowCheck Valve SL13-55B RCIC Instrumentation C-08 2 NC Act .75 EFC SA O O/C n/a LEF RO ROJ-V01 Excess FlowCheck Valve Sb13-55C RCIC Instrumentation B-08 2 NC Act .75 EFC SA O O/C n/a LEF RO ROJ-V01 Excess FlowCheck Valve SL13-55D RCIC Instrumentdion C-08 2 NC Act .75 EFC~ SA O O/C n/a LEF RO ROJ-V01 Exces FlowCheck Valve SSC-13-10 RCIC Barometric Cond K-09 2 C Act 2 GSC SA C O n/a SO Q n/a Vacuum Pump Disch ,

Stop Check Valve SSC-13-9 18B RCIC Steam Exhaust K-03 2 A/C Act S GSC SA C O/C n/a LJ 2Y n/a stop Check Valve SC RO ROJ-V26 SO Q n/a i V13-143A RCIC Pump SuctionTed N-09 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Connection Revision 19 Drawing : G-191174 Sh 1 Section 5 Page 62 of 179 x__ - - - _ - _ -.--,a-,-----u-- - - - - - - . _ -_ _ - - - - - _ - - - - - - ._--_---,__.----,-.u--- - - _ _ , - _ - - - - - - _ _ - - - - - - - - - - _ - - - - _ _ _ . . , - - -

Vermont Yankee Nuclear Power Station Inservice Testing Program 7 i Table 5-1 Valve Listing Drawing: G-191174 Sh 1 Drawing flete: Reactor Core Isolation Cooling System _

D ' Safety OM Act / Sise Norm Safety fab Test Test CSJ/ROJ Valve Nussber Nonsenclature la' a r Class Cat Pass (inch)

M Act Pos Pos Pos Type Freg RR h6 V13-15 RCIC Steam Supply E47 1 A Act 3 GA MO-AC O OC FAI IJ 2Y n/a  !

Inbo.ra Contamment PIT 2Y- n/a  !

Isolation Valve Wa STC Q .[

STO Q n/a  !

V13-15eA - 188 SteamLine Drain Root Fe09 2 A Pass 1 GL. MAN LC C n/a IJB Var n/a i Valve r V13-16 18B RCIC Steam Supply F,09 1 A Act 3 GA MO-DC O O/C FAI IJB Var n/a Outboard Contamment PIT 2Y n/a 5 IsolationValve g q g, t STD Q n/a l

.V13-1s Cond nsate Supply to E-14 2 B Act 6 GA MO-DC O OC FAI PIT 2Y n/a l RCIC Pump Suction SIC Q Wa I Valve 3.gg q g, [

v13-19 18A Condensate supply to E-14 2 C Act 6 CK' SA OC OC n/a - SC OC RR-VIS Note 11 RCIC Pump Suction SO Q n/a Check Valve

V13-29 RCIC Pump Discharge G-10 2 B Act 4 GA MO-DC O O FAI PIT 2Y n/a Isolationvalve STO Q n/a i' v13-2eB 18A n- -- .:.- Valve Keep G-11 2 C Act 1 CK SA C C n/a SC OC RR-V13 Note 1I f FillSystem [

V13-21 RCIC InjectionIsolation G-09 2 B Act 4 GA MO-DC C O FAI PIT 2Y n/a i Valve STO Q n/a ,

V13-22 RCIC Injection Check G-09 2 C Act 4 CK SA C OC n/a SC CS CSJ-V10 Valve . SO CS CSJ-VIO

V13-27 RCIC Pump Discharge I-I1 2 B Act 2 GL MO-DC C OC FAI PIT 2Y n/a Minimum FlowValve STC 'Q n/a f STO Q n/a

[

Revision 19 Drawing : G-191174 Sh 1 Section 5 Page 63 of 179

~

Vcrmont Yankee Nuclear Power Station JInservice Testing Program Table 5-1 Valve Listing

' Erawing: G-191174 Sh 1 DrawingTitle: Reactor Core Isolation Cochng System Dwg Safety OM Act / Size Body Norun Safety fab Test Test CSJ/ROJ '

Valve Number Nomenclature Coor Class Cat Pass (inch)

Act Pos Pos Pos Type Freg RR

' hh VI3-29 RCIC Panp Discharge J-10 2 C Act 2 CK SA C OC n/a CD RO n/a -

Mmunum FlowCheck PSO n/a Valve Q

V13,30 RCIC PumpDischarge E-10 2 B. Act 4 GL' MO-DC C C FAI PIT 2Y . n/a '

Retun to Con &nute SE Wa Storage Tank Q

V13 38 RCIC Vacuum Pump K-11 2 C Act 2 ' CK - SA C OC n/a SC~ RO ROJ-V26 DischarEe Check Valve SO Q n/a

. ' V13,39 Supp PoolSupply to F-13 2 B Act 6 GA MO-DC C OC FAI PIT 2Y n/a ,

I RCIC Pump SuctInbd SK n/a IsolValve Q

gm q g, *

, V1340 Suppression Pool Supply N-11 2 C Act 6 CK SA C O n/a CD RO n/a to RCIC PumpSuction l CheckViv. ,

V13-41 Supp PoolSupply to N-10 2 B Act 6 GA MO-DC C OC FAI PIT 2Y n/a RCIC Pump SuetInbd STC n/a Isol Valve Q

g q g, V13-43A RCIC Pump SuctionTest N-11 2 B Pass .75 GL MAN C C . n/a n/a n/a n/a . 1 Connection V13-46A RCIC Main Steam Line E-08 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Test Connection  !

2 V13-Se 19 RCIC Tube Exhaust K-08 2 AC Act 8 CK SA C OC n/a LJ 2Y n/a CheckValve SC RO ROJ-V26 SO Q n/a V13-52B RCIC Pump Ditharge K-09 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a -

Test Connection l t

V13-53A RCIC TurbmeExhaust K-08 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Tedconnection l I

i Revision 19 Drawing : G-191174 Sh 1 Section 5 Page 64 of 179  :

i I

. Vcrmont Yankee Nuclear Power Station Inservice Testing Program ,

Table 5-1 Valve Listing Drawing : . G-191174 Sh I Drawing'Iltle: Reactor Core Isolation Cooling System Valve Number Nomenclature Dwg Safety OM Act / Size My Act Norna Safety Fan Test Test CSJ/ROJ Remah Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR V13420 18B ' RCIC 'Ibrtune Exhaust K-8 2 A/C Act 2 CK SA C O/C N/A LT 2Y n/a Disisnozzle checkvalve Vacuum Brmker PSO n/a design.

Q SC RO ROJ-V33 SO RO ROJ-V33 V13421 isB RCIC Turbine Exhaust K-8 .2 A/C Act 2 CK SA C O/C N/A LT 2Y n/a Thisisnozzle checkvahe VacuumBreaker PSO n/a design.

Q SC RO ROJ-V33 SO RO ROJ-V33 i

L

^

r Drawing : G-191174 Sh 1 Section 5 Page 65 of 179 I Revision 19 ,

Vcrmont Yankee Nuclear Power Station inservice Testing Program Table 5-1 Valve Listing Drawing : G-191174 Sh 2 Drawing 11tle: Reactor Core Isolation Cooling System i

Dwg Safety OM Act / She My Norma Safety Fall Test Test . CSJ/ROJ Valve Number Nomenclature Ad hah Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR LCV-13-12 RCIC Baro Cond .

L-10 3 B Act 1 GA AO C O/C FC FST Q n/a condensate Pump Disch PIT 2Y n/a Dmin LCV g q g, SIO Q n/a LCV-13-13 RCIC Baro Cond L-10 3 B Act 1 GA AO C O/C FC FST Q n/a Condensate Pump Disch PIT 2Y n/a Drain LCV da S'PC Q STO Q n'e PCV-13-23 Cooling Wcier to H-06 2 B Act 2 GL AO O O FO SKID Q n/a Note 12 Barometric Condenser RCIC-CONTROL RCIC Turbine Govenung D-12 2 B Act 2 GL HO O O/C FAI PIT 2Y n/a Note 12 Valve SKID Q n/a S-13-3 RCIC Tu:bine Steam E-11 2 D Act 8 RD SA C O/C n/a RD SY n/a Exhaust Rupture Disc S-13-4 RCIC Turbine Steam E 09 NNS D Act 8 RD SA C O/C n/a RD SY n/a Exhaust Rupture Disc SR-13-25 RCIC Pump Suction C-07 2 C Act 1 RV SA C O/C n/a SP 10Y n/a ReliefValve SR-13-26 RCIC Pump Discharge I-07 2 C Act 1 RV SA C O/C n/a SP 10Y n/a Line to Bammetric Cond ReliefViv SR-13-27 RCIC Bammetric J-14 3 C Act 1.5 RV SA C O/C n/a SP .10Y n/a CondenserReliefValve V13-1 RCIC TurbineTrip & D-14 2 B Act 2 GL MO-DC O O/C FAI PIT 2Y n/a Note 12 Throttle Valve RE Q Wa V13-131 RCIC Steam Supply Valve E-15 2 B Act 3 GL MO-DC C O/C FAI PIT 2Y n/a S'IC Q n/a S~IO Q n/a Revision 19 Drawing : G-191174 Sh 2 Section 5 Page 66 of 179 j

Vcrmont Yankee Nuclear Power Station . Inservice Testing Program  ;

Table 5-1 Valve Listing Drawing: G-191174 Sh 2 DrawingTitle: Reactor Core Isolation Cooling System Nomenclature Dwg Safety OM Act / Sire Body Act Nonn Safety Fall Test Test CSJ/ROJ h2 Valve Number Coor Class Cat Pass (inch) Pos Pos Pos Type Freg

_ RR V13-132 RCIC Ptunp Discharge G-06 2 B- Act 2 GL MO-DC C O/C FAI PIT 2Y da ,

Valve to Baronutric ,c iC Q n/a '

  • STO -Q' n/a V13-133 RCIC T wornetric Cond K-10 2 C Act 2 CK .SA ~C O/C n/a SKID Q n/a Note 12 Conderde Purnp Disch CheckValve V13-70 RCIC Baro Cond K-13 3 C Act 1.25 CK SA C O n/a SKID Q n/a Note 12 Condensate PumpDisch .

CheckValve 1

i 4

i Revision 19 Drawing : G-191174 Sh 2 Section S Page 67 of 179 l

__________________________________j

Vcrmont Yankee Nuclear Power Station Inservice Testing Program'

~

Table 5-1 Valve Listing Drawing: G-191175 Sh 1 Drawing

Title:

Primary Containmem & Atmosphere Control Valve Namber Dwg Safety OM Act / Size Norum Safety Fail Test Test CSJ/ROJ NoacacIntare My Act g,g Coor Class Cat Pass (lack) Pos Pos Pos Type Freg RR SB-16-19-10 PCAC Supp Chamber J-13 2 A Act 18 BTF AO C C FC FST Page Supply ContIsol Q n/a valve U 2Y n/a PE 2Y Wa STC Q n/a SB-16-19-11A PCACVacuum Relief K-15 2 A/C Act 20 BTF AO C O/C FO FST Q n/a Note 15 From Secondary U 2Y n/a ContammentIso Valve PE 2Y Wa SP 6M n/a STC Q n/a STO Q n/a SB-16-19-11B PCAC Vacuum Relief M-15 2 A/C Act 20 BTF AO C OC FO FST Froen Secondary Q n/a Note 15 CoatammentIso Valve U 2Y n/a pg gy g, SP 6M n/a STC Q n/a STO Q n/a SB-16-19-23 PCAC Contamment H-15 2 A Act 6 BTF AO C C FC FST Purge Supply Q n/a ContammentIso Valve U 2Y n/a pg gy g, STC Q n/a SB-16-194 PCAC to SBGT D-01 2 A Act 8 BTF AO O C FC FST Q n/a Valve also appears on G-ContammentIsolation Valve U 2Y n/a 191238 PE 2Y da STC Q n/a SB-16-194A PCAC Drywellburge & F-02 2 A Act 3 BTF AO C C FC FST Q n/a Vent Outlet Bypass Cont Iso 1 Valve U 2Y n/a PE 2Y da  ;

j STC Q n/a Revision 19 Drawing : G-191175 Sin 1 Section 5 Page 68 of 179

. _ _ _ . - 1

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Crawing: G-191175 Sh 1 DrawingTide: Primary Containment & Atmosphere Control Dwg Safety OM Ad/ Sk Body Act Norm Safety Fait Test Test CSJ/ROJ h6 Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR 58-16-1945 PCAC Supp Chb Prg A L 03 2 A Act 3 B'IF AO O C FC FST Q n/a VentLine BypassInbd W 2Y n/a ContIsol Viv pg 2y ga S'IC Q n/a SB-16-19-7 PCAC Purge & Vent D-01 2 A Act 18 BTF AO C C FC FST Q n/a ExhaustContamment U 2Y n/a IsolationValve PE 2Y da STC Q n/a SB-16-19-7A PCAC DrywellPurge & Fe02 2 A Act 18 BTF AO C C FC FST Q n/a Vent Outlet ContIsol U 2Y n/a Valve PIT ' 2Y n/a S'IU Q n/a SB-16-19-7B PCAC Supp Chb Purge & K-03 2 A Act 18 BTF AO C C FC FST. Q n/a VentOutletInbd Cont U 2Y n/a IsolValve PIT 2Y n/a STC Q n/a SB-16-19-8 PCAC Drywell Air Purge I-12 2 A Act 18 B'IF AO C C FC FST Q n/a Inlet ContammentIsol U 2Y n/a Valve PIT 2Y n/a STC Q n/a SB 16-19-9 PCAC AirPurge Supply I-16 2 A Act 18 BTF AO C C FC FST Q n/a From Rx Bldg ContIsol U 2Y n/a Valve PIT 2Y n/a STC Q n/a V16-19-12A PCAC Vacuum Relief K-16 2 A/C Act 20 CK SA C O/C n/a U 2Y n/a From Secondary SC Q n/a ContaimnentCheckViv SO n/a Q

SP 6M n/a Revision 19 Drawing : G-191175 Sh 1 Section 5 Page 69 of 179 i

' Vcrmont Yankee Nuclear Power Station Inservice Testing Program ~  :

Table 5-1 Valve Listing Drawing: G-191175 Sh I DrawingTitle: Primary Containment & Atmosphere Control -

Dwg SafetyI OM Act / Slee My Norum Safety Fall Test Test CSJ/ROJ '

Valve Number Nomenclature Act h6 Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR

. V16-19-12B PCAC Vacuum Relief M-16 2 A/C Act 20 m SA C- O/C - n/a LJ 2Y n/a From Secondary n/a SC- Q ContammentCheck Viv da SO' Q

  • SP 6M . n/a ,

V16-19-13A DrywellAirLock H-06 2 A Pass 1.5 BL MAN LC C n/a LJ 2Y n/a Equalizing Vent  !

V16-19-13B Drywell Airlock Vent H-06 2 A Pass 1.5 BL MAN LC C n/a - LJ 2Y n/a I V16-19-19B PCAC Globe Valve M-16 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a i i i i V16-19-20A PCAC Globe Valve K-16 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a -)

V16-19-21A PCACTest Connection K-01 2 B Pass .75 GL MAN LC C n/a ' n/a n/a n/a .

V16-19-22B PCACTestconnechon I-13 2 B Pass .75 GL MAN LC C n/a . n/a n/a n/a V16-19-56 Drywell Air Lock I-06 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Preammzabon Valve  !

V16-19-5A DrywellTo Suppresnon J 08 2 A/C Act 18 m SA C OC n/a LT 2Y n/a  ;

Chamber Downcorner SC n/a Vacuum Breaker Q i SO' Q da  !

SP 6M n/a V16-19-5B DrywellTo Suppresnon J-08 2 A/C Act 18 m- SA C O/C n/a - LT 2Y n/a ,

Chamber Downcomer SC Q n/a +

Vacuum Brunkcr SO Q Wa SP 6M n/a

- V16-19-5c DrywellTo Suppression J-08 2 A/C Act 18 m SA C O/C n/a LT 2Y n/a Chamber Downcomer SC n/a Q.

Vacuum Breaker t SO Q Wa SP. 6M n/a f l i Revi:sion 19 Drawing : G-191175 Sh 1 Section 5 Page 70 of 179

=

Vcrmont Yankee Nuclear Power Station Inservice Testing Prograin i

Table 5-1 Valve Listing '

~ Drawing: G-191175 Sh I Drawing

Title:

Pnmary Containment & Atmosphere Control ,

Neuneoclatute Dwg Safety OM Act / Sise g 3,g Nerna Safety fab Test Test CSJ/ROJ hd Valve Nussber Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR ,

^

, V16-19-5D DryweRTo Suppresson K-08 2 A/C ' Act - -18 CK SA C OC n/a LT 2Y- n/a ChamberDowncomer SC Q. n/a VacmanBreaker i SO -Q Wa

SP 6M n/a  !

. ' V16-19-5E DryweRTo Suppreamon J-08 2 A/C Act 18 CK ' SA C OC n/a LT 2Y n/a  !

ChamberDownmmer SC Q n/a , [

. VacumnBreaker go q g, j SP- 6M - n/a  !

V16-19-5F DryweRTo suppreamon J-08 2 A/C Act 18 - CK SA - C O/C n/a LT 2Y n/a .  !

ChamberDownmmer SC Q Wa-  !

Vacuum Breaker SO Q Wa SP 6M n/a j

. V16-19-5G DrywellTo Suppresnon J-08 2 A/C Act 18 CK SA C O/C n/a LT 2Y n/a ;i Chamber Downmmer SC n/a Q

Vacuum Breaker SO- Q da  !

SP 6M n/a  ;

V16-19-5H DrywellTo Suppresson J-08 2 A/C Act 18 CK SA C O/C n/a . LT 2Y n/a ChamberDowncomer SC Q n/a VacuumBreaker SO Q Wa  !

SP - 6M n/a l

., V16-19-51 DrywenTo Suppresson K-08 2 A/C Act 18 CK SA C OC n/a LT 2Y n/a -[

Chamber Downmmer SC n/a i

VacuumBreaker Q [

da i

SO Q. [

SP 6M n/a V16-19-5J DryweRTo Suppresson J-08 2 A/C Act 18 CK SA C OC n/a . LT 2Y n/a ChamberDowncomer SC Q. n/a  !

Vacuum Breaker go q. g,- l SP 6M - n/a i

Drawing : G-191175 Sh 1 Section 5 - Page 71 of 179 Revision 19 I

_ _ - _ _ _ _ - . _ _ - _ _ _ - - _ _ _ _ _ _ _ _ _ _ - _ - _ - _ - _ _ _ - - _ _ - _ - - _ _ _ . - - -t

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191175 Sh 1 Drawing

Title:

Primary Containment & Atmosphere Control Valve Number Noamenclature Dwg Safety OM Act / Size Body Act Nonn Safety Fail Test Test CSJ/ROJ hah Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR

, V16-20-20 PCAC Contammatt H-12 2 A Act 1 GA SO O C FC FST Q n/a Page Makeup Outbd U 2Y n/a ContIsol Valve PR 2Y da STC Q n/a V16-20-22A PCAC Contamment H-11 2 A Act 1 GL SO C C FC FST Q n/a Purge Makeup ContIsol U 2Y n/a

  • Valve PIT 2Y n/a STC Q n/a V16-20-22B PCAC Contamment H-12 2 A Act 1 GL SO O C FC FST Q n/a PurgeMakeup ContIsol U 2Y n/a  ;

Valve PE 2Y Wa S'IU Q n/a V16-20-28 Torus MakeupTest I-11 2 B Pass 35 GA MAN C C n/a n/a n/a n/a Connection V16-20-30 Drywell MakeupTest I-12 2 B Pass 35 GL MAN LC C n/a n/a n/a n/a  ;

Connection l j V20-400A Torus Drain Valve N-09 2 B Pass 2 GL' MAN LC C n/a n/a n/a n/a V20 40eB Toms DrainValve N-07 2 B Pass 2 GL MAN LC C n/a n/a n/a n/a Revision 19 1)rawing : G-191175 Sh 1 Section S Page 72 of 179  ;

i

- Vcrm:ntYcrkeeN clearPow rStation Inservice Testing Program Table 5-1 Valve Listing

' Drawing
G-191175 Sh 2 Drawing'Iltle: Pnmary Containment & Atmosphere Control Valve Number Nomienclatum Dwg W OM Act / h Body 'Act Norum Safety fab Test Test CSJ/ROJ Pos Type Freg RR g,,g ,

Coor Class Cat Pass (inch) Pos Pos  ;

. SOV-7-107 ' 188 NeutonMonstonng C-10 '3- A Act 1" -GL SO' O. C FC FST Q n/a . New Valve confonns with  !

SysteinTip Purge IJ . 2Y- n/a . RG 1.97, s

, IsolationValve pg.g.. 2Y Wa STC Q ' n/a  !

SR-16-19-77 18B Nitrogen Supply Safety A-11 3 C Act IXI.5 RV ' SA - C. O- N/A SP 10Y .N/A RdiefValve V7-1 ISB Neutron Monitoring D-08 2 A/C Act .5 CK SA OC C n/a IJ 2Y n/a ~

SystemTe PurgeIm. SC R O R O J- V I1 CheckValve t

I i

i t

4 i

Revision 19 Drawing : G-191175 Sh 2 Section 5 Page 73 of 179  !

i

[

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

5 Vcrmont Yankee Nuclear Power Station Inservice Testing Progrant Table 5-1 Valve Listing y Krawing: G-191177 Sh 1 Drawing 11tle: RadwasteSystems

  • Dwg Safety OM Act / She My Act Norm Safety fab Test Test CSJ/ROJ  %

Valve Number _ Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR

. RV-2682A Pen.X-18"IhennalRelief A-03 2 C Act 35 RV SA C OC n/a SP 10Y ' n/a Valve RV-20-94A Pen.X-19'IhennalRelief F-03 2 C Act 35 RV- SA C OC n/a .SP 10Y . n/a i Valve V2S319A Rx Bldg MoorDrain - D-06 2 B Pass 1.5 GA

  • MAN LC C n/a n/a n/a n/a PumpTo Suppression  ;

PoolIso Valve

- V2S319B Rx Bldg MoorDrain D-06 2 B Pass 1.5 GA MAN LC C n/a n/a n/a n/a '

PanpTo Suppresnon PoolIso Valve Rx Bldg Floor Drain GA MAN LC C n/a n/a n/a n/a '!

V20,319C C-08 2 B Pass 1.5 PumpTo Suppression PoolIso Valve V20J19D Rx Bldg FloorDrain C 08 2 B Pass 1.5 GA MAN LC C n/a n/a n/a n/a Pump To Suppression PoolIso Valve V20-75A Test Connection B44 2 B Pass 35 GA MAN C C n/a n/a n/a n/a V20-79A Test Connection B-04 2 B Pass .75 GA MAN C C n/a n/a n/a n/a i V2S82 DrywellFloorDrain B-04 2 . A Act 3 BL AO O C FC FST Q n/a Sump Contaime.ent LJ 2Y n/a IsolationValve PE 2Y Wa .

S'It Q n/a V20-83 Drywen FloorDmin B-05 2 A Act 3 BL AO O C FC FST Q n/a Sump Contamment LJ 2Y n/a -

Isolation Valve pg .2y g, STC Q n/a V20-92A Test Connection G-04 2 B Pass .75 GA MAN C C n/a n/a n/a n/a .

V20-93A Test Connection G-04 2 B Pass 35 GA MAN C C n/a n/a n/a - n/a Revision 19 Drawing : G-191177 Sh 1 Section 5 Page 74 of 179 i

m Vcrmr.t Yc2kee Nrclear Pdwer Statio1 Inservice Testing Program -

Table 5-1 Valve Listing Drawing:- G-191177 Sh 1 - DrawingTitle: Radwaste Systems .

Dwg Safdy OM Act / Size My Nerna Safety fab Test Test CSJ/ROJ hd Valve Number Nonnenclature Act Coor Class Cat l Pass (inch) Pos Pos Pos Type Frest .RR V2694 DrywellE;We Drain G-04 2_ A Act 3 BL' AO. O. C- FC FST Q n/a Sump Contma""' W 2Y n/a I883"'i** M' PIT 2Y n/a STC Q n/a ,

v20-95 Drywell E r ;--- =^ Drain G-05 2 A Act 3- BL AO O C FC FST Q n/a Sump contammet U 2Y n/a - 4 I8838'i'" M' PIT 2Y n/a ,

STC Q n/a s

P L

k t

t i

s Revision 19 Drawing : G-191177 Sh 1 Section 5 Page 75 of 179 i

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191178 Sh 1 Drawing 11tle: Reactor Water Cleanup System Nomenclature Dwg Safety OM Act / Size Body Act .

Norma Safety fab Test Test CSJ/ROJ hah Valve Number Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR

. V12-15 IBB ReactorWaterCleanup D-02 1- A Act 4 GA MO-AC O C FAI IJB Var n/a ContammentIsolation PIT 2Y n/a .

Valve da

- 3.TC Q.

V12-16 RWCU Dram / rest D-03 1 B Pass 75 GL . MAN C C n/a n/a n/a n/a Cw tini V12-18 isB ReactorWater Cleanup D-03 1 A Act 4 GA MO-DC O C _ FAI UB . Var ~ n/a ContammentIsolation PIT 2Y n/a Valve STC Wa Q

V12-28A RWCU Pump Discharge D-08 3 C Act 3 m SA OC C n/a CD RO n/a  :

CheckValve V12-28B RWCU Pump Discharge G-08 3 C Act 3 m SA O/C C n/a CD RO n/a ,

CheckValve V1242 RWCU Flowto B-05 2 C Act 4 m SA O/C C n/a CD RO n/a '

Feedwater System Isolation Check Valve V1242A RWCU Flow to B45 3- C Act 4 & SA O/C C ri/a CD RO n/a '

FeedwaterSystem Isolation Check Valve k

Revision 19 Drawing: G-191178 Sh 1 Section 5 Page 76 of 179 m______..--_-_______a__m ____w. __-_.__-m.m_---___m.a._____1m_______.-_______.____o-______..-_____-____mm.

e.w-_-_u

Vcrmont Yankee Nuclear Power Station Inservice Testi:g Program Table 5-1 Valve Listing Drawing: G-191237 Sh 2 Drawing'I1tle: HVAC 'nubine, Service & Cortrol Room Building Dwg Safety OM Act / Size My Act Norm Safety fab Test Test CSJ/ROJ hah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR

. SACC-1A- Cent Room HVAC I-03 3 C Act 1375 N SA O/C O Wa SKID : Q Wa CHECK Chiller Refriguant  !

Piping Check Valve SACC-1B. Cont RoomHVAC I-04 3 C Act 1375 CK SA O/C O da SKID Q Wa I

' CHECK ChilkrRefrigerant -

Piping Check Valve SCW-46A SAC-1 Temperature B-6 3 B Act 2 3-WAY AO O O FO FST Q Wa ControlValve Heating m q g, and Vmt Room SCW-65A HVAC ExpansionTank D-04 3 B Act .75 GL MAN C C Wa SC Q Wa IsolationValve .

SCW-8A ControlRoomHVAC E-05 3 C Act 3 CK SA 'O O Wa SO Q Wa Chilled WaterPump Disch CheckValve SR-SACC-1A-1 Cont Room HVAC H-03 3 C Act .75 RV SA C O/C Wa SP 10Y Wa Chiller Refrigerant Pipmg ReliefValve SR-SACC-1A-2 Cont Room HVAC H-03 3 C Act .75 RV SA C O/C da SP 10Y Wa Chiller Refrigerant Pipmg ReliefValve SR-SACC-1B Cont Room HVAC H-04 3 C Act 1.25 RV SA C O/C da SP 10Y Wa Chiller Refrigerant '

Pipmg ReliefValve Revision 19 Drawing : G-191237 Sh 2 Section S Page 77 of 179 i

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

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: G-191238 DrawingTitle: HVAC - Reactor Building Dwg Safety OM Act / Size Norm Safety Fail Test Test CSJ/ROJ Valve Number Nomenclature My Act hah Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR SB-1-125-1A Standby GasTreatment G-08 2 B Act 12 BTF AO C O FO FST Q n/a TrainInlet Valve PIT 2Y n/a STD Q n/a SB-1-125-1B Standby GasTreatment G-07 2 B Act 12 BTF AO C O FO FST Q n/a TrainInlet Valve - PIT 2Y Wa STO Q n/a SB-1-125-2A Standby Gas T'entment HM 2 B Act 12 BTF AO O O/C FO FST Q n/a TrainInlet Valve PIT 2Y n/a STC Q n/a STD Q Wa SB-1-125-2B Standby GasTreatment HM 2 B Act 12 BTF AO C O/C FO FST Q n/a TrainInlet Valve PIT 2Y n/a STC Q n/a STO Q n/a SB-1-1254A Standby GasTreatmmt G4 2 B Act 12 BTF AO O O FO FST Q n/a Train Discharge Valve PIT 2Y n/a STO Q n/a SB-1-1254B Standby Gas Treatment G4 2 B Act 12 BTF AO C O FO FST Q n/a Train Discharge Valve PIT 2Y n/a STO Q n/a SB-1-125-4A Standby Gas Treatment H-07 2 B Act 12 BTF AO C O/C FC FST Q n/a Train Dilution Valve PIT 2Y n/a STC Q n/a

. STO Q n/a SB-1-125-4 B Standby Gas Treatment }{ 4 2 B Act 12 BTF AO C O/C FC FST Q n/a Train Dilution Valve PIT 2Y n/a STC Q n/a STO Q n/a Revision 19 Drawing : G-191238 Section 5 Page 78 of 179

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing : G-191238 Drawing 11tle: HVAC-Reactor Building Dwg Safety OM Act / Size Body Act Norm Safety fab Test Test CSJ/ROJ hah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR SB-t-125-5 Standby Gas Treatmmt G-06 2 B Act 4 BTF AO C O/C FC FST Q n/a Train Xconn Valve PIT 2Y n/a STC Q n/a STO Q n/a 1 SB-10 RX Building Supply H 08 2 B Act 54 BTF AO O C FC FST Q n/a Isolation Valve PIT 2Y n/a STC Q n/a SB-11 RxBldg Exhaustto Stack G-08 2 B Act 54 BTF AO O C FC FST Q n/a See Cond IsolationValve PIT 2Y n/a STC Q n/a 5 8-12 Rx Bldg Exhaustto Stack G-09 2 B Act 54 BTF AO O C FC FST Q n/a Sec cond IsolationValve PIT 2Y n/a ,

STC Q n/a 58-16-194

  • See G-191175 forvalve ContammentIsolation info and test requirements Valve SB 9 RX Building Supply H-09 2 B Act 5A BTF AO O C FC FST Q n/a Isolation Valve PIT 2Y n/a ,

STE Q n/a SGT-7A Standby Gas Treatmmt F-07 2 C Act 12 CK SA C O/C n/a SC Q n/a Train Discharge Check SO Q n/a Valve SGT-7B Standby GasTreatment F-06 2 C Act 12 CK SA C O/C n/a SC Q n/a Train Discharge Check SO Q n/a Valve Revision 19 Drawing : G-191238 Section 5 Page 79 of 179 ,

Vcrmont Yankee Nuclear Power Statio a Inservice Testing Program Table 5-1 Valve Listing

' Drawing : G-191267 Sh 1 Drawing

Title:

Nuclear Boiler Vessel Instrumeni2ation Dwg Safety OM Act / Size Body Act Norm Safety FaR! Test Test CSJ/ROJ hah Valve Number . Nomenclature Coor Class Cat Pass (inch) Pos Pos Posl Type Freq RR SL2-3-11 Nuclear Boiler Vesel C-06 2 AC Act 1 EFC SA O O/C n/a LEF RO ROJ-VO1 Ind Excess FlowCheck Valve Sb2-3-13A Nuclear BoilerVessel D-06 2 AA: Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 Ind Excess FlowCheck Valve SL2-3-13B Nuclear Boiler Vessel C-12 2 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 Ind Excess FlowCheck Valve sb2-3-15A Nuclear BoilerVessel D-06 2 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-Vol Inst Excess Flow Check Valve s b2-3-15B Nuclear Boiler Vessel D-12 2 AC Act 1 EFC SA O OC n/a LEF RO ROJ-V01 Inst Excess FlowCheck Valve sb2-3-17A Nuclear Boiler Vessel E-06 2 A/C Act 1 EFC SA O OC n/a LEF RO ROJ-VO1 InstExcess Flow Check Valve s b 2-3-17B Nuclear Boiler Vessel E-12 2 AC Act 1 EFC SL O O/C n/a LEF RO ROJ-VO1 Inst Excess FlowCheck Valve SL2-3-19A Nuclear BoilerVessel F-06 2 A/C Act 1 EFC SA O OC n/a LEF RO ROJ-VO1 Inst Excess FlowC;eck Valve ,

sb2-3-19B Nuclear BoilerVessel F-12 2 AC Act 1 EFC SA O OC n/a LEF RO ROJ-VO1 Inst Excess FlowCheck Valve .

SL2-3-21 A Nuclear Boiler Vessel H-06 1 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-VO1 Inst Excess FlowCheck Valve s b 2-3-21B

  • Nuclear Boiler Vessel H-06
  • See G-191165 for valve Inst Excess Flow Check info and test requirements Valve Revision 19 Drawing : G-191267 Sh 1 Section 5 Page 80 of 179

'h

- Vcrmont Yankee Nuclear Power Station Inservice Testing Pargram-Table 5-1 Valve Listing

?

Drawing: G-191267 Sh 1 Drawing'I1tle: . NuclearBoilerVesselInstannensation yg y,g y g,, Dwg Safety OM Act / Sise wy .- Act Nenn Safety fab Test Test CSJ/ROJ h6 Coer Class Cat Pass (inch) Pos Pos Pos Type Freg RR' E2-3-21C NuclearBoila Vessel H-12 1 A/C Act 1 EPC -SA O. OE n/a LEF RO ROJ-Vol Inst Excess FlowCheck ,

- Valve

  • *- * * * * *
  • See G-191165 forvalve sb2,3-21D = - Nuclear Boiler Vessel H-12 -*- ~* *..

IndExcess FlowCheck ido W M sequim I Valve ,

sb2-3-23A NuclearBoiler Vessel G-06 1 AE Act 1- EFC SA O OC n/a LEF RO ROJ-V01 IndExcess FlowCheck Valve i 51,2-3-23 8 Nuclear Boiler Vessel G-06 1 AC Act 1 -EFC SA O OE n/a LEF RO ROJ-V01 IndExcess FlowCheck 3 Valve SI,2-3-23C NuclearBoila Vessel G-12 1 AC Act 1 EFC SA O OE n/a LEF -RO ROJ-Vol -

IndExcess FlowCheck  ;

Valve sb2-3-23D . NuclearBoilaVessel G-12 1 AC Act 1 EFC ' SA O OE n/a LEF RO ROJ-V01 Ind Excess FlowCheck Vdu SI,2-3-25 NuclearBoilerVessel 14 2 AE Act .1 EPC SA O OE n/a LEF RO ROJ-V01 ,

Ind Excess FlowCheck .;

Vd e 51,2-3-27 Nuclear Boiler Vessel 14 2 AC Act .I EFC SA O OC n/a ' LEF RO ROJ-Vol IndExcess Flow Check .

Valve 51,2-3-31A NuclearBoiler Vessel F4 1 AE Act 1 EFC SA O O/C - n/a LEF RO ROJ-Vol IndExcess Flow Check Valve . _,

51,2-3-31B Nuclear Boiler Vessel FM 1 AC Act 1 EFC SA O OE n/a LEF RO ROJ-Vol Ind Excess FlowCheck Valve ,

51,2-3-31C Nuclear Boila Vessel FM 1 NC Act 1 EFC SA O OE n/a LEF RO ROJ-VD1 Inst Excess FlowCheck Valve .

Revision 19 Drawing : G-191267 Sh 1 Section 5 Page 81 of 179 ,

I Vcrm=t Ycckee NzcIrr Paw;r Statin I: service Testing Program Table 5-1 Valve Listing Drawing: G-191267 Sh 1 DrawingTitle: Nuclear Boiler Vessel Instrumentation Dwg Safety OM Act / Sire My Act Norm Safety Fail Test Test CSJ/ROJ hah Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR

- Si,2-3-31D Nuclear Boiler Vessel F4 1 NC Act 1 EFC SA O O/C n/a EF RO ROJ-VO1 Ind ExcessFlowCheck Valve SI,2-3-31E Nuclear BoilerVessel FM 1 NC Act 1 EFC SA O O/C n/a EF RO ROJ-Vol Inst ExcessFlowCheck Valve SI,2-3-31F NuclearBoiler Vessel F4 1 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-VO1 Ind Excess FlowCheck Valve ST,2-341G NuclearBoiler Vessel FM 1 NC Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 -

Inst Excess Flow Check Valve SI,2-3-31H Nuclear Boiler Vessel F4 1 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 Inst Excess FlowCheck Valve SI 2-341I Nuclear Boiler Vessel F-12 1 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 Inst Excess FlowCheck '

Valve SI,2-3-31J NuclearBoiler Vessel F-12 1 NC Act 1 EFC SA O O/C n/a LEF RO ROJ-VO1 Ind Excess Flow Check Valve L SI,2-3-31K NuclearBoilcr Vessel F-12 1 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-VO1 Inst Excess FlowCheck Valve SI 2-3-31L NuclearBoiler Vessel F-12 1 NC Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 Inst Execa Flow Check Valve .

S1,2-3-31M Nuclear Boiler Vessel F-12 1 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-V01 InstExcess FlowCheck Valve 51,2-3-31N Nuclear Boiler Vessel F-12 1 NC Act i EFC SA O O/C n/a LEF RO ROJ-VO1 Inst Excess Flow Check Valve Revision 19 Drawing : G-191267 Sh 1 Section 5 Page 82 of 179

>e Vcrmont Yankee Nuclear Power Station - Inservice Testi:g Program Table 5-1 Valve Listing Drawing : G-191267 Sh 1 Drawing

Title:

Nuclear Boiler Vessel Instmmentation Dwg Safety OM Act / Size My Act Nona Safety Fall Test Test CSJ/ROJ hW Valve Numaber - Nomenclatum <

Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR sir 2-3-31P . Nuclear BoilerVessel F-12 1 A/C Act 1 EFC SA O O/C n/a LEF RO ROJ-VO1 InstExcess FlowCheck Valve Ste2-3-31Q NuclearBoiler Vessel F-12 1 A/C Act 1 EFC SA O. O/C n/a LEF RO ROJ-V01 InstExcessFlowCheck Valve SI ,2-3-33 Nuclear Boiler Vessel I-12 2 A/C Act i EFC SA' O O/C n/a LEF RO ROJ-V01 Inst Excess FlowCheck Valve SI 2-3-35 Nuclear Boiler Vessel J46 2 A/C Act 1 EFC SA O C n/a LEF RO ROI-VO1 I InstExcess Flow Check Valve V2 3-28A NBVI Globe Valve F-06 2 B Pass 1.00 GL MAN C C n'a n/a n/a n/a v2 3-2sB NBVIGlobe Valve F-11 2 B Pass 1.00 GL MAN C C n/a n/a n/a n/a r

r i

I F

i Revision 19 Drawing : G-191267 Sh 1 Section 5 Page 83 of 179 t

_ _ _ _ _ _ . __.m_.m . _ _ _ . . _ .m __ _ _ _ _ . _ m_ _ _._.._.m..m._. _ . _ . - .___._.._.____._._-.._._m_ _ _ . . _ _ . _ _ . _ _ _ .

Vcrmont Yankee Nuclear Power Station Inservice Testing Program -

Table 5-1 Valve Listing Drawing: G-191267 Sh2 ' Drawing

Title:

Nuclear Boiler Vessel Instnamentation Valve Number Nomenclature Dwg Safety OM Act / Size Body Act Nonn Safety Fall Test Test CSJ/ROJ hah Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR V2-3-430A Reference Leg Backfill C-09 2 NC Act .375 CK SA C C n/a U 2Y n/a Inlet Check Valve SC RO ROJ-V15 V2 3-430B Reference Leg Back Fill E-09 2 NC Act .375 CK SA C C- n/a U 2Y n/a Inlet Check Valve . SC RO ROJ-VIS -

V2,3-432A Reference Leg Back Fill C-10 2 NC Act .375 CK SA C C n/a U 2Y n/a CheckValve SC RO ROJ-V15 V2,3-432B Reference Leg Back Fill E-10 2 NC Act .375 CK SA C C n/a U 2Y n/a CheckValve SC RO ROJ-V15 V2 3-433A Reference Leg Back Fill F-09 2 NC Act .375 CK -SA C C n/a U 2Y. n/a Inletcheck Valve SC RO ROJ-V15 V2,3-433B ReferenceLeg Back Fill H-09 2 NC Act .375 CK SA C C n/a U 2Y n/a Inlet Check Valve SC RO ROJ-V15 V2-3-435A Referenceleg Back Fill F-10 2 NC Act .375 CK SA C C n/a U 2Y n/a InletCheck Valve SC RO ROJ-V15 V2 3-435B Reference Leg Back Fill H-10 2 NC Act .375 CK SA C C n/a U 2Y n/a InletCheck Valve SC RO ROJ-VIS -

V2 3-444A Penetraten X-28A Test C-10 2 B Pass .375 GL MAN C C n/a n/a n/a n/a Connection V2-3-444B Penetration X-28D Test E-10 2 B Pass .375 GL MAN C C n/a n/a n/a n/a Connection V2,3-447A PenetrationX-29A Test F-10 2 B Pass .375 GL MAN C C n/a n/a n/a n/a Connection V2-3-447B Penetration X-29D Test H-10 2 B Pass .375 GL MAN C C n/a n/a n/a n/a Connectic,n V2 3-448A Penetration X-28A Test C-10 2 B Pass .375 GL MAN C C n/a n/a n/a n/a Connection V2 3-448B Penetration X-28D Test E-10 2 B Pass .375 GL MAN C C n/a n/a n/a n/a Connection Revision 19 Drawing : G-191267 Sh 2 Section 5 Page 84 of 179

y Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing : . G-191267 Sh 2 Drawing

Title:

Nuclear Boiler Vessel Instrumentation Dwg Safety OM Act / Size My Norma Safety fab Test Test CSJ/ROJ hah Valve Number Nomenclature Act Coor Class Cat Pass (inch) Pos Pos Pos Type Freq RR

- V2 M 51A P setration X-29A Test F-10 2 B Pass .375 GL MAN C C n/a n/a n/a n/a Connection V2 M 51B Men X-29D Test H-10 2 B Pass .375 GL MAN C C n/a n/a n/a n/a Connection A

Revision 19 Drawing : G-191267 Sh 2 Section 5 Page 85 of 179

Vcrmont Yankee Nuclear Power Station Inservice Testi g Program Table 5-1 Valve Listing Crawing : VY-E-75-002 Drawing 11tle: Containmerit Ats.,.y:a Dilution System Dwg Safety OM Act / Size My Act Norma Safety Fall Test Test CSJ/ROJ hah Valve Naumber Nonnenclatum Coor Class Cat Pass (inch) Pos Pos Pos Type Ferg RR PSO *-475A-1 CAD SampleTorus J 2 B Act 1 GA SO C OC FC ' FST Q. 'n/a Note 5 InboardIsolationValve PIT 2Y n/a Valve also appears on G-STC Q n/a - -191165 ,

STD .Q n/a '

FSO 199-75A-2 CAD SampleTorus J-14 2 B Act 1 GA SO C O/C FC - FST Q n/a- Note 5 OutboardIsolationValve PIT 2Y n/a Valve also appears on G-STC Q n/a 191165 -

STO ' Q n/a FSO-199-75A-3 CAD Supply Torus J-14 2 B Act 1 GL SO C O/C FC FST Q n/a Note 5 Inboard Isolation Valve PIT 2Y n/a Valve also appears on G-STC Q .n/a 191165 >

STD Q n/a FSO-199-75A-4 CAD SupplyTorus J-14 2 B Act 1 GL SO C O/C FC FST Q n/a Note 5 OutboardIsolationValve PIT 2Y n/a Valve also appears on G- :i STC Q n/a 191165.

S1D Q n/a  ;

FSO-199-758-1 CAD Sample Lower I-12 2 B Act 1 GA SO O O/C - FC FST Q n/a Note 5 DrywellInboardIsolation PIT 2Y n/a Valve also appears on G-Y"I n/a STC Q 191165 ,

~

STO Q n/a FSO 109-75B-2 CAD Sample Lower I-12 2 B Act 1 GA SO O~ O/C FC FST Q n/a Note 5 DrywellOutboard PIT 2Y n/a Valve also appears on G- (

Isolation Valve STC n/a 191165 Q  ;

S1D Q n/a FSO 109-75C-1 CAD Sample Mid G-12 2 B Act 1 GA SO .O O/C FC FST Q n/a Note 5 DrywellInboaniIsolation PIT 2Y n/a Valve also appears on G- 1 Valve STC n/a 191165 Q  ; ~

STO Q n/a r

Revision 19 Drawing : VY-E-75-002 Section 5 Page 86 of 179 -  :

Vcrmont Yankee Nuclear Power Station ' Inservice Testing Program - .

Table 51 Valve Listing Irawing: - VY-E-75402 Drawing litle: 1 Containment Atmosphere Dilution System Dwg Safety OM Act / Size My Act Norm Safety fab Test Test CSJ/ROJ hs i Valve Number Nomenclature _

Coor Class Cat Pass (inch) Pos Pos Pos Type Freat RR F50-199-75C-2 CAD SampleMid G-12 2 B Act 1 GA SO O. 'OC FC FST. Q n/a - Note 5 - f DaywellOuttmard PIT 2Y n/a Valve also appears on G-  !

Isolation Valve SK Q n/a 191165

, SIO Q n/a FSO 199-75D-1 CAD Sample Upper G-12 2 B Act 1 GA- SO O OC FC FST Q n/a Note 5  ;

DrywellInboardIsolation PIT 2Y n/a Valve also appears on G-Valve STC Q n/a . 191165 STO Q n/a ,

FSO-199-75D-2 CADhieUpper G-12 2 B Act 1 GA SO- O O/C FC FST Q n/a . Note 5  ;

DrywellOutboard PIT 2Y n/a ' Valve also appears on G-  ;

IwlationValve STC n/a Q 191165

. S'ID Q n/a F50-199-76A isB CAD CAM Return L-13 2 A Act 1 GA SO. -O OC FC FST Q n/a Valve also appears on G-ContammentIsolation IJB Var n/a 191165 '

Valve PE 2Y da STC Q n/a STD Q n/a F50-199-76B IsB CAD CAM Reten L-13 2 A Act 1 GA SO O OC FC FST Q n/a Valve also appears on G- ,

ContammentIsolation LJB Var n/a 191165  !

Valve PE 2Y' Wa STC Q' n/a STD - Q n/a '

NG-11A CAD N2 Supply H-09 2 A Act 1 GL SO C OC FC FST Q n/a i ContammentIsolation IJ . 2Y n/a

~

Valve PE 2Y Wa S'It Q n/a ,

STO Q n/a j l

i Revision 19 Drawing : VY-E-75-002 Section 5 Page 87 of 179  !

Vcrmont Yankee Nuclear Power Station Inservice Testizg Program

- Table 5-1 Valve Listing Drawing: VY-E-75-002 Drawing

Title:

Containment Atmosphere Dilution System Dwg Safety OM Act / Size Body Act Nonn Safety Fail Test Test CSJ/ROJ g,g Valve Number Nomenclature Coor Class Cat Pass (inch) Pos Pos Pos Type,Freq RR

- NG-11B CAD N2 Supply H-08 2 A Act 1 GL SO C O/C FC FST Q n/a contammentIsolation U 2Y n/a Valve PU 2Y da STC Q n/a SID Q n/a NG-12A CADN2 Supply J-09 2 A Act 1 GL SO C O/C FC FST Q n/a ContammentIsolation U 2Y n/a Vdve PIT 2Y n/a STE Q n/a STD Q n/a NG-12B CADN2 Supply J-08 2 A Act 1 GL SO C O/C FC FST Q n/a ContammentIsolation U 2Y n/a Valve PIT 2Y n/a STC Q n/a STD Q n/a NG-13A CADN2 Supply 1-09 2 A Act 1 GL SO C O/C FC FST Q n/a C au. ntIsolation U 2Y n/a Valve PIT 2Y n/a STC Q n/a STD Q n/a NG-13B CADN2 Supply H 09 2 A Act 1 GL SO C O/C FL FST Q n/a ContammentIsolation U 2Y n/a Valve PE 2Y n/a STC Q n/a

. STO Q n/a NG-19 ManualValve H-10 2 B Pass 1 GL MAN LC C n/a n/a n/a n/a NG-20 Manual Valve J-08 2 B Pass 1 GL MAN LC C n/a n/a n/a n/a PSV-NG-34A Pressure Relief Valve B-03 2 C Act .5 RV SA C O/C n/a SP 10Y n/a ,

PSV-NG-34B Pressure Relief Valve G-03 2 C Act .5 RV SA C O/C n/a SP 10Y n/a Revision 19 Drawing : VY-E-75-002 Section 5 Page 88 of 179

Vcrmont_ Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing: VY-E-75-002 Drawing

Title:

Containment Atmosphere Dilution Systen Dwg Safety OM Act / Size Norm Safety Fail Test Test CSJ/ROJ '

Vdve Number - Nomenclature Coor Class Cat Pass (inch)

M Act Pos Pos Pos Type Freq RR

%,g SS-75A IsolationValve L-14 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a VC-12A VG-8A Test Connection H-12 2 B Pass 1 GL MAN LC C. n/a n/a n/a n/a VG-12B VG-8B Test Connection I-14 2 B Pass 1 GL MAN C C n/a n/a n/a n/a . l VG-13 Torus RootIsolation J-13 2 B Pass 1 GL ' MAN LC C n/a n/a n/a n/a Supply to ID102 Monitor VG-17A Test Connection C-14 2 B Pass 1 GL MAN LC C n/a n/a n/a n/a VG-17B Torus CAD Vent Line F-14 2 B Pass 1 GL MAN C C n/a n/a n/a n/a '

Test Connection VG-19 TorusCam/ID102 J-14 2 B Pass 1 GL MAN LC C n/a n/a n/a n/a AnalyzerTest Connection VG-21 CAM sampleLine From G-18 2 B Pass 1 GL MAN C C n/a n/a n/a n/a Drywell/rosusAtmos VG-22A CADTo SBGTSystem B-16 2 A Act 1 GL MO-AC - C O/C FAI LJ 2Y n/a contammentisolation PIT 2Y n/a Valve STC Wa Q

STD Q n/a VG-22B CADTo SBGT System E-16 2 A Act 1 GL MO-AC C O/C FAI LJ 2Y n/a ContammentIsolation PIT 2Y n/a Valve STC n/a Q

STO Q n/a VG-23 IsB CAD Rad Monitor J-19 2 A Act 1 GL SO O O/C FC FST Q n/a Valve also appears on G-Supply Contamment LJB Var n/a 191165 IsolationValve Prr 2Y da STC Q n/a STO Q n/a VG-24 CAD 11202 Analyzer L-11 2 B Act 1 GL SO O O/C FC FST Q n/a Note 5 ReturnIsolation Valve PIT 2Y n/a STC Q n/a STO Q n/a Revision 19 Drawing : VY-E-75-002 Section 5 Page 89 of 179 i

__._____.________.__.__._______________m_ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . ____. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,

Vcrmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing Drawing : VY-E-75-002 Drawing

Title:

Containment Atmosphere Dilution System Valve Number Nomenclature Dwg Safety OM Act / Size Body Act Nonn Safety Fail Tes; Test CSJ/ROJ hah Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR

. VG-25 CAD H202 Analyzer L-11 2 B Act 1 GL SO O O/C FC FST Q n/a Note 5 ReturnIsolation Valve PIT 2Y n/a i STC Q n/a STO Q n/a VG-26 IsB CAD Rad Monitor J-19 2 A Act 1 GL SO O O/C - FC FST Q n/a Valve also appears on G-Supply Containment LJB Var n/a . 191165 IsolationValve PIT 2Y n/a I STC Q n/a STO Q n/a VGJ2 CheckValve M-15 2 C Pass .75 CK SA C C n/a n/a n/a n/a VG-33 CADII202 Analyzer L-11 2 B Act 1 GL SO O O/C FC FST Q t./a Note 5 i RetumIsolationValve PIT 2Y n/a STC Q n/a STD Q n/a VG 34 CADII2O2 Analyzer L-11 2 B Act 1 GL SO O O/C FC FST Q n/a Note 5 RetumIsolation Valve PIT 2Y n/a STC Q n/a STD Q n/a '

VG 35 VG-18 Test Connection K-12 2 B Pass 1 GL MAN LC C n/a n/a r./a n/a VG 37 Sample StationInlet K-17 2 B Pass .375 GL MAN C C n/a n/a n/a n/a Isolation.

VG 38 Sample Station Outlet L-17 2 B Pass .375 GL MAN C C n/a n/a n/a n/a Isolation VG3) Outletlsolation* L-18 2 B Pass .375 GL MAN C C n/a n/a n/a n/a VG-41 H2/02 MonitorRetumto L-16 2 B Pass 1 GL MAN LC C n/a n/a n/a n/a RB Ventilation System VG-82 112/02 MonitorRetum to K-16 NNS B Pass 1 GL MAN LC C n/a n/a n/a n/a RB Ventilation System VG-78 TestConnection G-17 2 B Pass .75 GL MAN LC C n/a n/a n/a n/a Revision 19 Drawing : VY-E-75-002 Section 5 Page 90 of 179 -

V:rmont Yankee Nuclear Power Station Inservice Testing Program Table 5-1 Valve Listing

' Drawing: VY-E-75-002 Drawing

Title:

Containment Atmosphere Dilution System Nomenclature Dwg Safety OM Act / Size My Act Norm Safety fab Test Test CSJ/ROJ Researks Valve Number Coor Class Cat Pass (inch) Pos Pos Pos Type Freg RR

. VG-79 H2K)2 Mon. Return Line H-15 2 B Pass .75 GL MAN LC C n/a n/a n/a n'a to Torus /RB Vent.Sys.

Test Conn VG.80 K-17 2 B Pass .75 GL MAN LC C n/a n/a n/a 'n/a VG-9A CADTo SBGTSystem H-12 2 A Act 1 GL " SO C ' O/C FC FST Q n/a .

ContammentIsolation LJ 2Y n/a Valve PE 2Y da ,

STE Q n/a STO Q n/a VG CADTo SBGT System I-14 2 A Act 1 GL SO C O/C FC FST Q n/a ContainmentIsolation Ly '2Y n/a valve PE 2Y da STC Q n/a <

STO Q n/a Revision 19 Drawing : VY-E-75-002 Section 5 Page 91 of 179

, m . _ _ . -___ . _ _ _ _ _ . _ _ _ . . . _ _ _ . _ _ _

l i

' Vernent Ycnkee Nuclear Power Station - Inservice Testing Program  !

L

- 53 Valve Notes 1

.l. Full stroke ' exercising and timing tests of the MSIVs are accomplished quarterly when reactor power is decreased to less than 75 percem. At least twice a week, the L . MSIVs are also exercised by partial closure and subsequent reopening. I 1

2. This Note was deleted in Revision 19 of the IST Program.

l

3. Testing of CRD Cooling Water Supply Check valve, V3-138, is not required when  !

the corresponding control rod has been declared inoperable and its directional control  !

l valves disarmed in accordance with the provisions of Technical Specifications l L 3.3.A.2. -l

[

l 4. At least once during each operating cycle, the Standby Liquid Control system shall .l l be verified operable by: a) Initiating one of the SLC loops, excluding the primer ,

l chamber and inlet fitting, and verifying a flow path from the pump to the reactor i vessel. Both loops shall be tested over the course of two operating cycles. (T.S.  !

4.4.A.2) b) Testing of both trigger assemblies removed from the system (each l refueling outage) by installing in the test block to verify operability. c) Testing of l >

the replacement trigger assemblies by installing one of the assemblies in the test L block and firing it using the installed circuitry. Replacement triggers shall be from the sanic batch as the test assembly. The unfired replacement triggers, taken from the same batch shall be installed into the explosive valves. (T.S. 4.4.A.3 and 4.6.E)

5. Only one valve in each CAD sample line or H202 analyzer line is required to be operable in accordance with Technical Specifications Table 4.7.2.b.

i

6. Positive verification of full opening of the Transversing In-Core (TIP) Ball Valves, l BV-7-1 through 3 is shown by successful insertion of the TIP Probe through the  ;

L valve. Positive verification of full closing of the valve is shown during each 1 Refueling Outage by successful leak testing (LJ). This testing is in compliance with Paragraph 4.1 of Part 10 of the Code which states "Where local observation is not possible, other indications shall be used for verification." Local observation of valve position would require disassembly of the valve enclosures as the limit switches are contained within the enclosures.

7. ' The Nuclear Boiler Safety / Relief Valves, SV-2-70A & B and RV-2-71 A through D will be tested in accordance with the requirements of OM-1 only.

i 8. These valves form the Alternate Cooling System boundary alignment and are

' otherwise included in the IST Program per based on a commitment to NRC.

Reference:

OP-2181; NRC Inspection Report 94-03, dated 3/4/94.

I L

L Revision 19 Section 5 Page 92 of179

Wrm=t Ycnkoa Nucirir Power Ststian Ins:rvica Testing Prcgram

-5.3 Valve Notes (Con't)

9. The Cooling Tower SW Distribution Tray valves, V70-17A through V70-17D shall be cycled once each refueling as part of augmented testing to the 1994 Service Water System Self Assessment Report. These valves are not required to be exercised in accordance with the requirements of 10 CFR 50.55a.
10. The Service Water Pump Discharge Check Valves, V70-1A through ID, are part-stroke exercised open on a quarterly basis during plant operation during the regularly scheduled quarterly service water pumps tests. These valves are full stroke exercised open during refueling outages.

I1. The RHR and Core Spray Keep-Fill Check Valves (V10-36A, V10-36B, V14-33A, and V14-33B) are verified closed on an operating cycle basis utilizing a non-intrusive technique.

The Core Spray Discharge Flushing Line Check Valves (V14-22A, V14-22B, V14-23A and V14-23B) are verified closed on an operating cycle basis utilizing a non-intrusive technique.

The HPCI and RCIC Keep-Fill Check Valves (V23-20B and V13-20B) are verified closed dn an operating cycle basis utilizing a non-intrusive technique.

The HPCI and RCIC Pump Suction Valves (V23-32 and V13-19) are verified closed on an operating cycle basis utilizing a non-intrusive technique,

12. These valves are skid-mounted. NUREG 1482, Section 3.4 states that the testing of l the major component is an acceptable means for verifying the operational readiness of the skid-mounted component and component subassemblies if the licensee documents this approach in the IST program. The scope of skid-mounted components additionally includes components that are not mounted on the skid, but which function much the same as skid mounted components.
13. These valves are post-accident sampling (PASS) valves. NUREG 1482, Section 4.4.2 states that PASS valves that perform a containment isolation ftmetion are l required to be included in the IST Program. ,

I

14. These valves are Category B passive valves. NUREG 1482, Section 4.2.6 states that the code does not restrict the verification cf remote position indication to only active L valves. OM-10, Table 1, indicates that the licensee mu::t also verify the position for

. Category B passive valves.

i Revision 19 Section 5 Page 93 of179 i

I Vermtat Ycnkee Nuclear Pcwer St tian Ins:rvice Testing Program' l

l 5.3 : Valve Notes (Con't) 1 L

15. The performance of pressure sensing instrumentation testing for PCAC Vacuum Relief from Secondary Containment Iso Valves, SB-16-19-11A and 11B, is i performed (OP 4376) as required by OM-1 subsection 3.3.2.3 and Technical Specification 4.7.A.5.a. '
16. The Control Rod Drive Scram Inlet and Outlet Valves, CV-3-126 and CV-3-127, will be tested in accordance with the requirements of Tech. Spec Surveillance 4.3.C.1  !

after refueling outages and prior to operation above 30% power,

17. The CRD Manual Control Insertion, Withdrawal and Exhaust Valves, SO-3-120, 121,122 and 123 are verified operable in accordance with the weekly rod testing  ;

, performed in accordance Tech. Spec. Surveillance 4.3.A.2 during power operations.

'Ihe closure operation of these valves and the control rod drives are verified after refueling outages and prior to operation above 30% power per Tech. Spec.

Surveillance 4.3.C.1.

18. The Scram Exhaust To Discharge Volume Check Valves, V3-114, will be tested in accordance with the requirements of Tech. Spec Surveillance 4.3.C.1 after refueling outages and prior to operation above 30% power.
19. The CRD Charging Water to Accumulator Check Valves, V3-115, closure verification will be performed by the accumulator pressure decay test (OP 4111) during refueling outages.

l 20. The Reactor Recirculation Sample Line Flow Control / Isolation valves, FCV-2-39 l and FCV-2-40, had direct position indication installed to meet R.G.1.97 and OM-10.

l (EDCR 97-406/RFO-20,1998).

l

21. These valves are PIV's, they are subject to leak testing commensurate with i nominal operating reactor vessel pressure.

I

22. These manually operated valves are required to open for the Alternate Cooling l Mode (ACS) of the Service Water System.
23. These manually operated valves are required to close for the Alter'nate Cooling Mode (ACS) of the Service Water System. Valves were added per commitment to BMO 97-61.

l

. Revision 19 Section 5 Page 94 of179 l _

Verm:st Yckee Nucle:r Pcwer St:ti:n Ins;rvico Testing Prcgram COLD SHUTDOWN JUSTIFICATION Number: CSJ-V01, Revision 2 (Sheet 1 of 1)

SYSTEM: Reactor Building Closed Cooling Water COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V70-117 A 2 G-191159 Sh 3 L-12 Valve V70-117 is the reactor building closed cooling water retum containment isolation valve. This valve has a safety function in the closed position to provide primary containment isolation.

JUSTIFICATION:

This valve cannot be full-stroke exercised closed during nonnal (power) operation since shutting this valve would stop cooling water flow to vital primary containment equipment, including the primary containment air coolers and the reactor recirculation pumps.

This valve will be stroke timed closed during Cold Shutdowns in accordance with Paragraphs 4.2.1.2(c), (f), (g) and (h) of the code.

t f

l t

Revision 19 Section 5 Page 95 of179

Vcrm=t Yc kee N: clear Pcwer St tin Itservica Testing Prcgram COLD SHUTDOWN JUSTIFICATION Number: CSJ-V02, Revision 1 (Sheet 1 of1)

THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 18 OF THE IST PROGRAM.

This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

Revision 19 Section 5 Page 96 of179

1 Vsrm:nt Yenkee Nucle:r Pcwer St:ti:n Ins:rvice Tcsting Prcgram i

COLD SHUTDOWN JUSTIFICATION j Number: CSJ-V03, Revision 1 (Sheet 1 of 1) 1 THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 15 OF THE IST I PROGRAM. l 1

This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

Revision 19 Section 5 Page 97 of179 4

l l Vcrm:nt Yenkee Nrcle:r Pcwcr St: tic Inservice Testing Prcgrcm COLD SHUTDOWN JUSTIFICATION l- Number: CSJ-V04, Revision 2 (Sheet l of1) l SYSTEM: Nuclear Boiler COMPONENTS:

l Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V2-53A B 1 G-191167 L-09 V2-53B B 1 G-191167 L-09 V2-54A B 1 G-191167 L-09

[ V2-54B B 1 G-191167 L-09 These valves are the reactor recirculation pump discharge isolation and bypass valves. They have a safety function in the closed position to limit primary system coolant loss following a LOCA and to ensure low pressure coolant injection flow is properly directed to the reactor.

1 JUSTIFICATION:  !

l These valves cannot be , exercised closed during reactor power operation since cycling these valves l

~

l - would result in a reactor recirculation pump trip.

l These valves will be stroke timed closed during Cold Shutdowns in accordance with Paragraphs 4.2.1.2(c), (f), (g) and (h) of Part 10 of the Code.

l l

l l

1 t

L 6

l Revision 19 Section 5 Page 98 of179

Vcrm:st Yeckee Nucle r Pcwer St:ti:n Inservice Testing Pmgram COLD SHUTDOWN JUSTIFICATION Number: CSJ-V05, Revision 2 (Sheet 1 of1)

SYSTEMI Co:e Spray COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V14-13A A/C 1 G-191168 F-06 V14-13B A/C 1 G-191168 D-06 These valves are the Core Spray injection check valves. They have a safety function in the open position to pass core spray injection flow to the reactor, and in the closed position for primary containment and pressure isolation.

THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 19 OF THE IST PROGRAM.

This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's. .

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l Vcrment Ycnkes Nuclear Pswer St ti:n Inservice Testing Pr: gram I COLD SHUTDOWN JUSTIFICATION Number: CSJ-V06, Revision 1(Sheet 1 of1)

SYSTEM: High Pressure Coolant Injection

. COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V23-18 C 2 G-191169 Sh 1 G-05 This valve is the High Pressure Coolant Injection (HPCI) discharge to Feedwater Line "A" check valve.

The valve has a safety function in the open position to pass HPCI flow to the reactor and in the closed l position to prevent backflow feedwater into HPCI piping.

JUSTIFICATION:

This valve cannot be exercised open during normal (power) operation since flow through this valve must be injected into the reactor coolant system. This would thermally shock the reactor nozzles and cause a positive reactivity excursion. Manual operation of the valve is not possible since the valve is located in the steam tunnel which is inaccessible during power operations.

This valve will be manually exercised open and closed during Cold Shutdowns when the steam tunnel is accessible in accordance with 4.3.2.2(c), (f), (g) and (h) of Part 10 of the Code.

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l Vcrm:nt Ycakee Nucl=r Pswer St tica Ins:rvice Testing Program COLD SHUTDOWNJUSTIFICATION Number: CSJ-V07, Revision 0 (Sheet 1 of 1) l THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 18 OF THE IST

, PROGRAM.

. This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal . j SER's.

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Verm:nt Ycnke3 Nucle:r Pswer St:ti:n Inservice Testing Prcgrcm COLD SHUTDOWN JUSTIFICATION Number: CSJ-V08, Revision 2 (Sheet 1 of1)

SYSTEM: Residual Heat Removal COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V10-17 A 2 0-191172 G-08 V10-18 A 2 G-191172 F-08 i

These valves are the Residual Heat Removal (RHR) shutdown cooling supply isolation valves. They have a safety function in the closed position to provide primary containment and pressure isolation, and in the open position to provide RHR pump suction during shutdown cooling operation.

JUSTIFICATION:

These valves cannot be stroke timed open during reactor power operation since there is a 100 psig l interlock that prevents opening these valves during power operation. This interlock is required to prevent overpressurization of the lower pressure rated RHR shutdown cooling subsystem.

These valves will be stroke timed open and stroke timed closed during Cold Shutdowns in accordance with Paragraphs 4.2.1.2(c), (f), (g) and (h) of Part 10 of the Code.

9 Revision 19 Section 5 Page 102 of179

L Verment Ycnkee Nucle r Power St: tion Inservics Testing Progr::m i

I i

COLD SHUTDOWN JUSTIFICATION '

i Number: CSJ-V09, Revision 1 (Sheet 1 of 1)

THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 15 OF THE IST PROGRAM.

' This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

Revision 19 Section 5 Page 103 of179 l'

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Vcrmr.t Yerkee Nucle:r P:wcr Stati::n Inservica Testing Pr: gram COLD SHUTDOWN JUSTIFICATION Number: CSJ-V10, Revision 2 (Sheet 1 of 1)

SYSTEM: Reactor Core Isolation Cooling COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V13-22 C 2 0-191174 Sh 1 G-09 This valve is the Reactor Core Isolation Cooling (RCIC) discharge to Feedwater Line "B" check valve.

,'Ihe valve has a safety function in the open position to pass RCIC flow to the reactor and in the closed position to prevent backflow into the RCIC system.

JUSTIFICATION:

This valve cannot be exercised open during normal (power) operation since flow through this valve must be injected into the reactor coolant system. This would thermally shock the reactor nezzles and cause a positive reactivity excu;sion.

This valve is located in the steam tunnel which is inaccessible during power operations. Additionally, there is no means to manually exercise this valve.

'Ihis valve will be exercised open and closed during Cold Shutdowns in accordance with Paragraphs 4.3.2.2(c), (f), (g) and (h) of Part 10 of the Code.

Revision 19 Section 5 Page 104 of179 l

i Vcrm:nt Ycnkee Nuclear P wcr St:ti:n Inservica Testing Prcgram COLD SHUTDOWNJUSTIFICATION Number: CSJ-Vil, Revision 1 (Sheet 1 of1) j i

THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 18 OF THE IST PROGRAM.

l This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

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Revision 19 Section 5 Page 105 of179

l-Vcrm::t Ycnkes Nuclz:r Power St: tina Inservice Tcsting Pr: gram COLD SHUTDOWNJUSTIFICATION Number: CSJ-V12, Revision 1 (Sheet 1 of 1)

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l THIS COLD SHUTDOWN JUSTIFICATION DELETED IN REVISION 18 OF THE IST PROGRAM.

This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal i SER's.

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I Revision 19 Section 5 Page 106 of179

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Verm:2t Yer;kee Ntcizr Psw:r Stiti:2 Ins:rvics Testing Program l COLD SHUTDOWN JUSTIFICATION Number: CSJ-V13, Revision 1 (Sheet 1 of1)

THIS COLD SHUTDOWN JUSTIFICATION DELETED IN REVISION 18 OF THE IST PROGRAM.

This CSJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

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i Revision 19 Section 5 Page 107 of179 4

Vcrm=t Yenkee Nuclesr P:wer Stati::s Inservic Tcsting Progr:m COLD SHUTDOWN JUSTIFICATION Number: CSJ-V14 Revision 1 (Sheet 1 of 1)

SYSTEM: Residual Heat Removal COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V10-46A NC 1 0-191172 E-07 V10-46B NC 1 G-191172 E-10 These valves are the Low Pressure Coolant Injection (LPCI) injection check valves. They have a safety function in the open position to pass LPCI flow to the reactor, and in the closed position for primary containment and pressure isolation.

JUSTIFICATION:

These valves cannot be exercised open during normal (power) operation since the Residual Heat Removal (RHR) pump discharge cannot overcome reactor pressure. Manual exercising is not possible during plant operation be,cause the valves are located inside the inerted drywell and are not accessible during plant operation.

These valves will be exercised open with flow during Cold Shutdown in accordance with Paragraphs 4.3.2.2(c), (f), (g) and (h) of Part 10 of the Code.

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I Vcrmest Ycnkee Nuclerr Pcwer Statian Inservica Testing Pr: gram i

'i l COLD SHUTDOWN JUSTIFICATION Number: CSJ-V15 Revision 1 (Sheet 1 of 1)  ;

i SYSTEM: Residual Heat Removal 1 l

COMPONENTS:

. Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

- V10-48A C 2 G-191172 L-05 V10-48B C 2 G-191172 L-13 V10-48C - C 2 G-191172 J-05 V10-48D . C 2 G-191172 J-13 These valves are the RHR pump discharge check valves. These valves have a safety function to open to pass RHR pump' discharge flow for all modes of RHR/LPCI system operation. These valves also

~ have a safety function to close to prevent the backflow of water through an idle RHR pump ~.

Justification:

It is not practical to perfonn a full-stroke open exercise of these valves on a quarterly basis during plant operation. These valves are exercised during the performance of the quarterly RHR pump surveillance.  !

During plant operation, the only practical flow path for these pumps is in the torus to torus flow path.

The RHR pumps do not have sufficient head to flow to the recirculation loops with the reactor coolant .

system at normal operating pressure. Typical RHR pump flowrates in the. torus to torus flow {

. configuration are approximately 6,500 gpm for the RHR pump test. The required design accident condition flow rate to perform a full-stroke exercise is 7,300 gpm which can only be achieved when the  !

RHR system is in the vessel to vessel flow configuration.

These valves will be part-stroke open exercised quarterly during plant operation and will be full-stroke

open exercised during cold shutdowns in accordance with Paragraphs 4.3.2.2(b), (f), (g) and (h) of Part 10 of the Code. -

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- Revision 19 - Section 5 Page 109 of179

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Vcrmant Ycnkee Nucher Pcwcr Ststica Insarvice Testing Prcgram l

COLD SHUTDOWN JUSTIFICATION l

Number: CSJ-V16, Revision 0 (Sheet'l of 2) l SYSTEM: Service Water l COMPONENTS:

l Valve Number - OM Cat. Safety Class - Drawing Number Dwg. Coord.

V70-11 B 3 G-191159 Sh 2 D-07 V70-17 B 3 G-191159 Sh 2 D-06 SB-70-1 B NNS- G-191159 Sh 2 D-09

. V70-18 B -3 G-191159 Sh 2 E-07 Valve V70-11 is the SW Discharge to Cooling Tower Basin Isolation Valve. The safety function of this valve is to open to provide water to the Cooling Tower Basin to prevent the development of ice in the basin.

Valve V70-17 is the Altemate Cooling to SW Supply valve. The safety function of this valve is to open to provide flow to the Cooling Tower spray header to provide an attemate cooling path for the Service Water System. ,

Valve SB-70-1 is the SW Discharge to Main Condenser Discharge Block Valve. The safety function of this valve is to open to provide a flow path to the river. These valves have an active function to change position in order to provide a path for flow to the Cooling Tower when the Service Water System is

- required to be in the Altemate Cooling mode of operation.

Valve V70-18 is the Service Water Header Discharge Isolation Valve. The safety function of this valve is to close to maintain inventory of vital cooling water when the Service Water System is in the Altemate Cooling mode ofoperation.

JUSTIFICATION:

It is no' practicable to full or part stroke exercise these valves quarterly during normal (power) operation for the following reasons.

The Service Water system is designed with two discharge flow paths - main condenser discharge block and cooling tower. The discharge flow path is selected based on environmental conditions.

l, Service Water is discharged to the cooling tower deep basin when Connecticut River temperature is less than 45*F to keep the deep basin from freezing. The deep basin cannot be allowed to freeze, l

because it contains water inventory necessary for alternate cooling mode operation of Service Water

! system. Service Water is discharged to the condenser discharge block when Connecticut River temperature is greater than or equal to 45*F. This discharge path causes less back pressure in the

[ discharge line and increases flow through the Emergency Diesel Generator Jacket Water Coolers.

i  : The flow increase is necessary to compensate for higher river water temperature.

- Revision 19 Section 5 Page 110 of179 i-

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! Verm:nt Ycnkee Nuclear P wer St::ti:n Inservic: Testing Pr: gram COLD SHUTDOWN JUSTIFICATION Number: CSJ-V16, Revision 0 (Sheet 2 of 2)

V70-11, V70-17, SB-70-1 and V70-18 are large (20" and 24") manual valves and must be operated as a set because their positions are interdependent. For example, allowing V70-11 and SB-70-1 to be open at the same time, except for the minimum time required for system lineup changes, could drain the deep basin inventory. Closing V70-18 with Service Water discharge lined-up to the main condenser discharge block will isolate Service Water from the safety-related cooling loads and closing V70-18 with Service Water discharge lined-up to the cooling tower will isolate turbine

- building cooling loads.

These valves will be full stroked open and close during cold shutdown in accordance with Paragraph j

' 4.212(c) (f) and (g) when Service Water cooling loads are more managable 1

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Verm:nt Yankee Nucle:r Pswer St:ti:n Insarvice Testing Program COLD SHUTDOWN JUSTIFICATION Number: CSJ-V17 Revision 0 (Sheet 1 of 1)

SYSTEM: Instrument Air COMPONENTS:

l l Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V72-28A B NNS G-191160 Sh 3 L-15 L

V72-28B - B NNS G-191160 Sh 3 L-16 l V72-28D - B NNS G-191160 Sh 3 K-16 V72-28E B NNS. G-191160 Sh 3 K-16 V72-28A and V72-28B have a safety function to close to isolate the Instrument Air (IA) system from

l. the outboard MSIVs. Following an Appendix R fire event in the control room and cable spreading .

I room, V72-28A and V72-28B are closed to isolate the air supply and V72-28D and V72-28E are opened to vent the residual air contained in the piping from the air supply isolation valves to the MSIV accumulators. This action prevents the MSIVs from inadvertently re-opening if a hot short were to occur in the MSIV solenoid circuitry.

Reference:

Minor Modification 96-34.

V72-28D and V72-28E l$ ave a' safety function to open to vent the residual air contained in the IA ,

system supply to the outboard MSIVs (V2-86A, V2-86B, V2-86C and V2-86D). Following an 1

Appendix R. fire event in the control room and cable spreading room, V72-28A and V72-28B are i i

closed to isolate the air supply and V72-28D and V72-28E are opened to vent the residual air contained l in the piping from air supply isolation valves to the MSIV accumulators. This action prevents the

MSIVs from inadvertently re-opening if a hot short were to occur in the MSIV solenoid circuitry.

Reference:

Minor Modification 96-34.

l Justification:

l V72-28A and V72-28B cannot be exercised closed and cannot be exercised open during power l operation on a quarterly basis exercising these valves would isolate / vent instrument air to the MSIV accumulators. Instrument Air pressure is required to maintain the MSIVs in the open position. The loss ofinstmment air pressure would cause the MSIVs to go to the closed position and result in a reactor power transient. .

V72-28A and V72-28B will be full-stroke closed ar.d V72-28D and V72-28E will be full-stroke opened during Cold Shutdowns in accordance with Paragraphs 4.2.1.2(f) & (g) of Part 10 of the Code, i

Revision 19 - Section 5 Page 112 of179 l

Verm=t Yerkes Nucle:r P wer St:tien Ins:rvice Testing Prcgram j i

i COLD SHUTDOWN JUSTIFICATION l

l Number: CSJ-V18, Revision 0 (Sheet 1 of 1)

SYSTEM: ResidualHeatRemoval COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord. I V10-17Al B 2 G-191172 G-08  ;

l Valve V10-17Al is the V10-17 outboard containment isolation valve bonnet pressure locking relief I

device. This is a manual globe type valve. The safety function of this valve is to open to alleviate bonnet pressure locking of V10-17 in an Appendix R scenario.

JUSTIFICATION:

l It is not practical to full or part-stroke open V10-17Al dtr ing power operation. Opening V10-17Al is a '

potential personnel / contamination hazard due to the release of high pressure (1000 psig) contaminated fluid. During cold shutdown, V10-17 bonnet pressure will equalize with reactor pressure and opening V10-17Al is not a personnel hazard.

V10-17Al will be full-stroke opened during Cold Shutdowns in accordance with Paragraphs 4.2.1.2(f)

& (g) ofPart 10 of the Code.

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L Revision 19 Section 5 Page 113 of179

Vcrm:nt Yankee Nucirr Power Statinn Ins;rvice Testing Pr: gram REFUELING OUTAGE JUSTIFICATION l

Number: ROJ-V01, Revision 2 (Sheet 1 of 3)

SYSTEM: Nuclear Boiler High Pressure CoolantInjection Reactor CoreIsolation Cooling Recirculation Pump Cooling Water COMPONENTS:-

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord. I SL-13-55A NC 2 0-191174 Sh 1 B-08 SL-13-55B NC 2 G-191174 Sh 1 C-08 SL-13-55C NC 2 G-191174 Sh 1 B-08 SL-13-55D NC 2 G-191174 Sh 1. C-08 SL-14-31 A NC 2- G-191168 F-07 SL-14-31B NC 2 G-191168 E-07  !

SL-2-62A A/C 2 G-191167 I-13 SL-2-62B NC 2 G-191167 I-13 SL-2-62C A/C - 2 G-191167 J-13 SL-2-62D A/C 2 G-191167 J-13 SL-2-64A NC 2 G-191167 K-13 j SL-2-64B NC 2- G-191167 K-13 SL-2-64C A/C 2 G-191167 K-13 SL-2-64D NC 2 G-191167 L-13 SL-2-73A A/C 2 G-191167 F-12 j SL-2-73B A/C 2 G-191167 F-12 SL-2-73C A/C 2 G-191167 G-12 SL-2-73D NC 2 G-191167 G-12 SL-2-73E A/C 2 G-191167 G-12 SL-2-73F A/C 2 G-191167 G-12 SL-2-73G A/C 2 G-191167 H-12 i SL-2-73H A/C 2 G-191167 H-12 SL-2-2-7A NC 2 G-191159 Sh 5 - G-02 SL-2-2-7B A/C 2 G-1911.!9 Sh 5 G-02 SL-2-2-8A NC 2 G-191159 Sh 5 G-02 SL-2-2-8B - A/C 2 G-191159 Sh 5 G-02 SL-2-3-11 A/C 2 G-191267 Sh 1 C-06 SL-2-3-13A A/C 2 G-191267 Sh 1 D-06 l SL-2-3-13B A/C 2 G-191267 Sh 1 C-12

SL-2-3-15A NC 2 G-191267 Sh 1 D-06

- Revision 19 Section 5 Page 114 of179

4

' Vermcat Yankee Nuclerr Pawsr Stitisn Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V01, Revision 2 (Sheet 3 of 3)

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

SL-2-305A A/C -- 2 G-191167 M-02 SL-2-305B - A/C 2 G-191167 M-02 SL-23-37A A/C 2 G-191169 Sh 1 F-05 SL-23-37B A/C 2 G-191169 Sh 1 F-05 SL-23-37C A/C 2 G-191169 Sh 1 F-05~

. SL-23-37D A/C 2 G-191169 Sh 1 F-05 f

l These valves are instrumentation line excess flow check valves. They are required to be verified operable in accordance with Vermont Yankee Technical Specification 3.7.D.1.

JUSTIFICATION:

These valves cannot be exercised closed during normal (power) operation since closing these valves would isolate instrumentation required for power operation. These valves can only be verified to closed by leak testing performed during the primary system inservice pressure test performed each refueling outage. This teg cannot be repeated during each Cold Shutdown since the reactor vessel is not pressurized during Cold Shutdowns.

These valves will be exercised open and closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.3 and 4.3.2.2(e) (h) of Part 10 of the Code.

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[ i Revision 19 Section 5 Page 116 of179

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4 L Verm:nt Ycnk 3 Nucle r Pawsr St:tias Ins:rvics Testing Pr: gram -

REFUELING OUTAGE JUSTIFICATION T mber: ROJ-V02, Revision 1(Sheet 1 of1) l SYSTEM: Nucle 6 . .x r i  ;

COMPONENTS:

L Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

RV-2-71A C -1 G-191167 D-08  ;

RV-2-71B C 1-

~

G-191167 G-08 i RV-2-71C - C 1 G-191167 G-08 l RV-2-71D C 1 0-191167 H-08 Valves RV-2-71 A through D are the nuclear boiler main steam safety / relief valves. ney have a safety )

.. function in the open position for. Automatic Depressurization System (ADS) operation and for l overpressure protection, and in the closed position to maintain reactor coolant inventory.  !

l JUSTIFICATION:

Stroke testing of these valyes quarterly during power operation is not recommended. As recommended i I

. by NUREG-0737 and the corresponding study by the BWR Owners Group (BWR Owners Group Evaluation of NUREG-0737, Item II.K.3.16, " Reduction of Challenges and Failures of Relief Valves"), j

- the exercising of these valves should be minimized to reduce the number of challenges to safety / relief  ;

valves.

1 ne failure of any relief valve to close during stroking at power operation would cause an uncontrolled rapid depressurization of the primary system (stuck open relief valve transient) along with an undesired positive reactivity excursion.

' These valves can only be tested with primary system pressure greater than 100 psig, therefore, they cannot be exercised during cold shutdowns or during refueling outages. Exercising these valves at each start-up from cold shutdown (or quarterly) would produce additional stress cycles on the nuclear boiler system which could lead to a low cycle fatigue failure. These valves will be exercised during plant startup after each refueling outage in accordance with Paragraph 4.2.1.2(h) of Part 10 of the Code and 1 Paragraph 3.4.1.l(d) of Part 1 of the Code. ,

his Refueling Outage Justification is for clarification purposes only.

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! Vermsnt Yankee Nucleer Pcwsr Ststi::n Inservics Testing Prcgram L

j- REFUELING OUTAGE JUSTIFICATION t

c .. . . .

Number: ROJ-V03, Revision 2 (Sheet 1 of 2) t;

SYSTEM
NuclearBoiler COMPONENTS:

i - Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V2-27A - A/C- 2 G-191167 F-03 V2-27B C. 2 G-191167 H V2-28A - NC 2 G-191167 F-05 9 . V2-28B NC .2 G-191167 H-05 V2-%A NC 2 G-191167. H-03  !

V2-%B - C 2 0-191167 F-03 i

' Valves V2-27A and V2-28A are the outboard and inboard containment isolation check valves for the "A" Feedwater Line, respectively. They have a safety function in'the closed position to provide j primary containment isolation, and in the open position to pass High Pressure Coolant Injection flow to i the reactor.

. Valves V2-96A and V2-28B are the outboard and inboard containment isolation check valves for the l

"B" Feedwater Line, respectively. 'Ihey have a safety function in the closed position to provide primary containment isolation, and in the open position to pass Reactor Core Isolation Cooling flow to  !

the reactor.

Valve V2-96B is the second outboard check valve in the "A" Feedwater Line. The valve has a safety function in the closed position to prevent diversion of High Pressure Coolant Injection flow in the "A"  ;

Feedwater Line.- l Valve V2-27B is the second outboard check valve in the "B" Feedwater Line. The valve has a safety

~ function in the closed position to prevent diversion of Reactor Core Isolation Cooling flow in the "B" Feedwater Line.

'- Section 5 Page 118 of179 Revision 19

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Verment Ycnkee Nucle r Pswer Statisn Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V03, Revision 2 (Sheet 2 of 2) l JUSTIFICATION: l 1

i

' dese valves cannot be exercised closed during normal (power) operation because the feedwater system is required to maintain reactor vessel water level. Interruption of feedwater to perform the I

, exercise test of these valves would result in a reactor scram.

These valves can only be stroke close tested via a leak type or non-intrusive test. Testing during Cold  ;

Shutdowns is impracticable due to the significant system and test equipment configurations required.  !

Additionally, valves V2-27B, V2-28B and V2-96A cannot be exercised during Cold Shutdowns since this would require removing the only mechanism of reactor vessel level control (via the Reactor Water l Cleanup System).

l V2-27A, V2-28A, V2-28B and V2-96A will be stroke close tested each Refueling Outage during i leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of  !

the Code.

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V2-27B and V2-96B will be stroke close tested each Refueling Outage using non-intrusive testing or

. disassembly in accordance with Paragraphs 4.3.2.2(e), (h) and 4.3.2.4(a) or (c) of Part 10 of the Code.

l V2-27B and V2-96B were replaced during the 1996 Refueling Outage. Valve disassembly was used l instead of a non-intrusive test for this refuel outage because:

  • These valves were disassembled to facilitate installation.

. These valves were manually stroked after installation to verify freedom of movement and blue

, checked. These action satisfy the OM-10 stroke close requirement intent.

Revision 19 Section 5 Page 119 of179

Verm:nt Ycnkee Nucle:r Pcwzr Stati:n Ins:rvice Testing Prcgram

' REFUELING OUTAGE JUSTIFICATION Number: ROJ-V04, Revision 1 (Sheet 1 of 1)

SYSTEM: NuclearBoiler COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V2-37A NC 2 0-191167 B-08 V2-37B A/C 2 G-191167 G-09 V2-37C NC 2 G-191167 G-09 V2-37D NC 2 G-191167 .H-09 These valves are the Main Steam Relief Valve (MSRV) actuator air supply check valves. They have a safety function in the closed position to ensure automatic depressurization system (ADS) capability is maintained via the MSRV accumulators on a loss of the instrument nitrogen supply.

JUSTIFICATION:

These valves are located,in the drywell and thus cannot be stroke close exercised during normal power operations or Cold Shutdowns when the drywell is inerted. 'Ihese valves can only be stroke close tested via a leak type or non-intrusive test which would reqse isolating the instrument nitrogen supply to the MSRVs. Testing during Cold Shutdowns is impracticable due to the significant system and test equipment configurations required.

These valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.3 and 4.3.2.2(e), (h) of Part 10 of the Code.

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L l Verm st Ycnkes Nucle:r P:wer St:tian I servico Testing Prcgram 1

REFUELING OUTAGE JUSTIFICATION l l i l Number: ROJ-V05, Revision 1 (Sheet 1 of 1) l lx SYSTEM: Nuclear Boiler - l l' COMPONENTS: )

l Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V2-82A NC 2 G-191167- B-10 V2-82B A/C 2 0-191167 B-10

[ V2-82C A/C 2 G-191167 B-10 V2-82D NC 2. G-191167 B .

V2-87A A/C 2 G-191167 B-13

. V2-87B A/C 2 G-191167 B-13 V2-87C - A/C 2- G-191167 B-13 V2-87D A/C 2 G-191167 B-13

[

These valves are the Main Steam Isolation Valve (MSIV) actuator air supply check valves. They have a safety function in the closed position ~ to ensure MSIV capability is maintained via the MSIV accumulators on a loss o(instrument air or nitrogen supply.

JUSTIFICATION:

p Valves V2-82A thmugh D are located in the drywell and thus cannot be stroke close tested during I l nonnal power operations or Cold Shutdowns when the drywell is inerted.

% ves V2-87A through D are located in the main steam tunnel which is inaccessible during power )

operadons, thus, these valves cannot be stroke close tested during normal power operations.

i These valves can only be stroke close tested via a leak type or non-intrusive test which would require isolating the instrument air or nitrogen to the MSIVs. Testing during Cold Shutdowns is impracticable due to the significant system and test equipment configurations required. j These valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.3 and 4.3.2.2(e), (h) of Part 10 of the Code. ,

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- Verac:t Yenkea Nucle:r Power St tion Inssrvics Testing Program L

REFUELING OUTAGE JUSTIFICATION L Number: ROJ-V06, Revision 3 (Sheet 1 of 2)

L SYSTEM: ControlRod Drive Hydraulic -

L ..

l- COMPONENTS: (Typicalof 89 each)

Valve Number .. . OM Cat. Safety Class Drawing Nurnber Dwg. Coord.

l . CV-3-126 B 2 0-191170 C CV-3-127 B 2 G-191170 C-18 SO-3-120 B 2 G-191170 D-17 SO-3-121 B 2 0-191170 D SO-3-122 B 2 G-191170 C-18 SO-3-123 B 2 G-191170 C-17 V3-114 C. 2 G-191170 C-18 V3-115 A/C- 2 G-191170 B-16 V3-137 - C 2 G-191170 B-17 i

Valves CV-3-126 & 127 are the Control Rod Drive (CRD) scram valves. These valves have a safety l

function in the open position to pass scram accumulator discharge to the control rod drives for a reactor scram.

Valves S0-3-120 & 123 are the manual control exhaust and insertion valves, respectively, for the CRD under piston area. They have a safety function in the closed position to prevent diversion of scram accumulator discliarge into the exhaust water header or the drive water header.

Valves S0-3-121 & 122 are the manual control exhaust and withdrawal valves, respectively, for the l CRD over piston area. These valves have a safety function in the closed position to ensure that scram 1 exhaust flow is properly directed to the discharge volume.

Valves V3-114 are the scram exhaust to the discharge volume check valves. These valves have a safety function in the open position to pass scram exhaust flow to the discharge volume. These valves have a safety function in the closed position to prevent the scram discharge volume from operating the drive in l

1 the event that the scram discharge volume pressure should exceed reactor pressure following a scram.

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i: Valves V3-115 are the charging water to the CRD accumulator check valves. These valves have a j ' safety function in the closed position to prevent diversion of scram accumulator discharge into the l- charging header.

L i- Valves V3-137 are the Drive Water Supply Check Valves. These valves have a safety function in the

. closed position to prevent a loss ofinventory to the drive water riser L

1 Revision 19 Section 5 Page 122 of179

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l Verment Yenks Nuclesr Power Statica Inservice Testing Program I

l BEFUELING OUTAGE JUSTIFICATION i-Number: ROJ-V06, Revision 3 (Sheet 2 of 2) l JUSTIFICATION:

l Exercising valves CV-3-126, CV-3-127, V3-114 and V3-137 during power operation would require ,

scramming the plant solely for testing purposes. Since scram insertion times are representative of valve i operability and stroke times, testing will be performed in accordance with Technical Specifications 4.3.C.1 and 2. These sections require that all control rods be subjected to scram-time measurements on L a refueling outage basis and that 50% of the control rods be measured for scram times every 16 to 32 L weeks. An evaluation is required that provides reasonable assurance that proper control rod drive perfonnance is being maintained. These tests will adequately verify valve operability and stroke times.  !

' . Valves SO-3-120 through 123 are verified operable at least once a week in accordance with Technical Specifications 4.3.A.2 for each partially or fully withdrawn operable control rod. For a control rod that is fully inserted, the safety function of these valves is fulfilled. Stroke testing these valves while the l control rod is fully inserted will not result in an increase in safety or quality. All control rods drives are verified operable in accordance with Technical Specifications 4.3.B.1 each Refueling Outage, thus i stroke testing of these valves for control rods that remained fully inserted throughout the operating l

[ cycle will occur each Refueling Outage. This alternate test frequency is consistent with NUREG 1482, )

l Appendix A, NRC Staff Position 7 " Testing Individual Scram Valves For Control Rods in Boiling i Water Reactors."  !

l Closure testing of V3-115 requires that the CRD pumps be stopped to depressurize the charging water i

. header. 'Iherefore the accumulator pressure decay test (OP 4111) will be performed during refueling

outages. 'Ihis altemate test frequency is consistent with NUREG 1482, Appendix A, NRC Staff l ' Position 7 " Testing Individual Scram Valves For Control Rods in Boiling Water Reactors."

Closure testing of V3-114 requires a scram signal to be in and the scram discharge volume to be l pressurized. This condition is beyond operating parameters as specified in Technical Specification 3.3.,

therefore testing can only be performed during a refueling outage when test conditions can be met.

These valves will be exercised as a minimum each Refueling Outage in accordance with Paragraphs  !

l 4.2.1.2(e), (h) and 4.3.2.2(e), (h) of Part 10 of the Code.

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Verm:nt Ycnke3 Nucl22r Pswer Statica Inservice Testing Pr: gram REFUELING OUTAGE JUSTIFICATION Number: ROJ-V07, Revision 2 (Sheet 1 of1)

SYSTEM: ControlRod Drive Hydraulic I

COMPONENTS: ,

l Valve Number OM Cat. . Safety Class Drawing Number Dwg. Coord.

V3-412A NC 2 G-191170 E-12  ;

V3-412B NC 2 0-191170 E-12 V3-413A NC 2 G-191170 E-12 .

V3-413B A/C 2 G-191170 E-12  !

l These valves are the r: circulation pump seal purge supply check valves. They have a safety function in i the closed position to provide primary containment isolation.

JUSTIFICATION:

These valves can only be exercised closed via a leak type or non-intmsive test which would require 1 isolating the seal purge,to the recirculation pumps. To preclude adverse affects on seal life, the l recirculation pumps would have to be secured. Testing during Cold Shutdowns is impracticable due to j the significant system and test equipment configurations required. l These valves will be exercised closed each Refueling Outage during leakage rate testing performed in l accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of the Code.

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Revision 19 Section 5 Page 124 of179

l Vcrmest Ycskee Nuct:cr P wer Stati::n Inservice Testing Program i

l REFUELING OUTAGE JUSTIFICATION

[' Number: ROJ-V08, Revision 2 (Sheet 1 of1)

SL9 TEM: StandbyLiquidControl COMPONFEIE;:.

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V11-16 C 1 G-191171 H-03 Vll-17 C 1 G-191171 I-02 These valves are the Standby Liquid Control (SLC) injection line check valves. ney have a safety function in the open position to pass borated water into the reactor, and in the closed position to provide primary containment isolation.-

JUSTIFICATION:

Exercising these valves open during power operation would require injecting borated water into the reactor coolant system. This would create a reactivity excursion and potential for reactor trip. Injection of demineralized water would require removing the SLC system from service to clean the borated solution from the piping and replacing the explosive actuated valves.

Full-stroke closed testing requires the removal of at least one explosive actuated valve.

i nese valves will be full-stroke exercised open during refueling outages when the SLC system can be '

tested without creating a reactivity excursion.

These valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.3.2.2(e), (h) of Part 10 of the Code.

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Revision 19 Section 5 Page 125 of179

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Verm::t Ycnkee Nuclear Pcwer Stati n Inservies Testing Pragram REFUELING OUTAGE JUSTIFICATION L Number: ROJ-V09, Revision 0 (Sheet 1 of 1) t L

i THIS REFUELING OUTAGE JUSTIFICATION WAS WITHDRAWN IN REVISION 18 OF THE IST PROGRAM. ,

This ROJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

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Revision 19 Section 5 Page 126 of179

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-i Term::t Ycnkee Nuclear P wer St-tin'- Inservice Test +ng i Program REFUELING OUTAGE JUSTIFICATION j Number: ROJ-V10, Revision 1(Sheet 1 of 1)  !

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THIS REFUELING OUTAGE JUSTIFICATION WNi WITHDRAWN IN REVISION 16 OF THEIST PROGRAM.  !

This ROJ nmnber is being maintained for traceability to the Third Interval IST Program Submittal SER's.

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l Verm:nt Ycnkee Nuclear Pcwer St: tion Inservice Testing Program I

I REFUELING OUTAGE JUSTIFICATION l

l Number: ROJ-Vil, Revision 3 (Sheet 1 of1) l SYSTEM: Neutron Monitoring System COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V7-1 A/C 2 G-191175 Sh 2 D-08 This valve is one of two Neutron Monitoring System (NMS) Tip Purge primary containment isolation valves. This valve, in conjunction with SOV-7-107, has a safety function in the closed position to provide primary containment isolation.

JUSTIFICATION:

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This valve can only be tested via a leak type or non-intrusive test that requires securing of the nitrogen purge to the NMS Tip system. The nitrogen purge is required during operation and Cold Shutdown to prevent condensation and corrosion in the NMS Tip system.

This valve will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of the Code.

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I Revision 19 Section 5 Page 128 of179 e

l Vcrmont Yankee Nuclear Power Station Inservice Testing Program l

l REFUELING OUTAGE JUSTIFICATION l Number: ROJ-V12, Revision 1 (Sheet 1 of 1)

SYSTEM: Control Rod Drive Hydraulic COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

l V3-162A NC 2 G-191170 A-09 V3-162B NC 2 0-191170 A-01 1

These valves are the Control Rod Drive (CRD) scram discharge volume vent check valves. They have i a safety function in the closed position to isolate the scram discharge volume during a scram condition, thereby preventing reactor coolant inventory loss.

JUSTIFICATION:

These valves can only be exercised closed via a leak type or non-intrusive test which would require removing the CRD system from service. Testing during Cold Shutdowns is impracticable due to the significant system and test equipment configurations required.

These valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.3 and 4.3.2.2(e), (h) of Part 10 of the Cod e. )

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l Revision 19 Section 5 Page 129 of179

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Vcrm::t Yenice Nucirr Pcw:r St: tina Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V13, Revision 1 (Sheet 1 of1)

THIS REFUELING OUTAGE JUSTIFICATION WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.

This ROJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

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Revision 19 Section 5 Page 130 of179

l Vermont Yankee Nuclear Power Station - Inservice Testing Program

' REFUELING OUTAGE JUSTIFICATION Number: ROJ-V14, Revision 2 (Sheet 1 of 2)

SYSTEM: Service Water i

COMPONENTS: l

. Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord. ,

V70-1A C- 3 G-191159 Sh 1 C I V70-1B C 3 G-191159 Sh 1 B-02 V70-lC C -3 G-191159 Sh 1 - K-02 V70-1D - C 3 G-191159 Sh 1 J-02 These valves are the station setvice water pump discharge check valves. They have a safety function m the open position to provide cooling water to systems and equipment required to operate under accident conditions and to provide an inexhaustible supply of water for standby coolant system operation. They have a function in the closed position to pmvent the diversion of cooling water through an idle station Service Water pump.

JUSTIFICATION: ,

The maximum required accident condition flow of 6,149 gpm, (Calc. VYC-1279, Rev,0; Case 8,

" Discharge to condenser discharge block with low system resistance and LNP"), is not achievable with the current service water system configuration. The maximum required accident condition flow is based on a single pump operating near run-out conditions due to a postulated mpture of non-seismic, non-isolated portions of the service water system concurrent with an accident. The station service water pumps do not have installed instrumentation that permits determination ofindividual flow rates for these check valves. It is not practical or possible, using maximum required accident condition flow, to verify the open position of these valves during normal operation, cold shutdown, or refueling outages. The check valves can be verified to be full open during these refueling outage tests using nonintrusive techniques. These check valves have, on a one-time basis, been verified to 4

be in their fu!! open position during normal operation using one .non-intrusive technique (radiography). The calculated flows recorded during this verification ranged between approximately 1,800 - 3,000 gpm. Thus there is reasonable assurance that these check valves are in a full open position at flows much less than the maximum required accident flow of 6,149 gpm. -

Revision 19 Section 5 Page 131 of179

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Vermant Yankee Nuclear Power St2 tion Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V14, Revision 2 (Sheet 2 of 2)

JUSTIFICATION (Continuedh It is impractical to verify these valves in the open position on a quarterly basis or during cold shutdown due to equipment setup, potential RT contractot coordination, and, depending on the NIT technique, equipment exposure / access considerations. The NRC has indicated in a public workshop response that "Section 4.1.4 of NUREG-1482 states that the need to set up test equipment is adequate justification to defer backflow testing of check valves to a refueling outage frequency.

Although not stated in NUREG-1482, this guidance could be applied to the use of NIT for forward flow testing of check valves as well." These valves will be verified to be in their full open position during refuel outages using nonintrusive technology.

- It is not possible to reverse flow test these check valves on a quarterly basis or during cold shutdown 1

due to the need to secure service water pumps. Depending on seasonal cooling load requirements, all four service water pumps may be operating during power operation, and in some cases, during cold shutdown. The reverse flow test currently involves running one pump at a reference condition during refuel outages and taking credit for the adjacent idle pump check valve closure based on the running pump being capable of- meeting the reference condition and acceptance criteria.

Nonintrusive techniques niay also be used to verify valve closure in lieu of pump performance test credit.

These valves will be verified to be in the full open position using nonintrusive techniques. Full stroke exercising closed will be verified by using reverse flow during curve performance testing or nonintrusive techniques in accordance with OMa-1988, Part 10, Paragraph 4.3.2.2(e) during each refueling outage. Partial forward flow credit will continue to be taken during the quarterly pump surveillance test in accordance with OMa-1988, Part 10, Paragraph 4.3.2.2(b).

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Vermrst Yc kee Nccle:r Pcwer St:tia Itservica Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V15, Revision 1 (Sheet 1 of1)

SYSTEM: Nuclear Boiler Vessel Instrumentation

.G. OMPONENTS:

~

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V-2-3-430A NC 2 G-191267 Sh 2 C-09 V-2-3-430B A/C 2 G-191267 Sh 2 E-09 V-2-3-432A NC 2 G-191267 Sh 2 C-10 V-2-3-432B A/C 2 G-191267 Sh 2 E-10 V-2-3-433A A/C 2 G-191267 Sh 2 F-09 V-2-3-433B A/C 2 G-191267 Sh 2 H-09 V-2-3-435A NC 2 G-191267 Sh 2 F-10 V-2-3-435B A/C 2 G-191267 Sh 2 H-10 These valves are the reactor vessel instrumentation reference leg back fill inlet check valves. These valves are required to close in order to prevent the reference legs from emptying in the event of a break in the non-safety related portion of the back-fill system and perform a containment isolation function.

JUSTIFICATION:

These valves cannot be exercised during power operations or during cold shutdowns since shutting these valves would isolate filling water to the reference leg lines for reactor vessel pressure and level instrumentation. The function of the reference leg backfill system is to ensure that the reactor water level reference leg fluid does not become saturated with non-condensable gases. Full closure of these valves is verified during local leakage rate tests when the test boundary is drained and vented which could introduce non-condensable gases to the reference legs.

'Ihese valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of the Code.

Revision 19 Section 5 Eage 133 of179 a ----- -

Vcrm
st Yankse Nucl:ar P wsr Station Inservice Testing Program i

REFUELING OUTAGE JUSTIFICATION

!' Number: ns V16, Revision 1(Sheet 1 of1)

SYSTEM: Service Water COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V70-13A B 3 G-191159 Sh 1 J-07 V70-13B B 3- G-191159 Sh 1 B-07

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V70-2A B 3 G-191159 Sh 1 C-03

, ' 70-2B B 3 G-191159 Sh 1 B-03 70-2C B 3 G-191159 Sh 1 J-03

' '70-2D B 3 G-191159 Sh 1 J-03 These valves are the Service Water System Header Supply Isolation Valves. The safety functon of these valves is to close in order to isolate the upstream portions of the Service Water System when transferring to the Altemate Cooling mode of operation.

l E!STIFICATION: ,

l It is impracticable to full or part-stroke close exercise these valves on a quarterly basis or during cold l shutdowns. Closure of these valves could interrupt cooling flow to their respective trains of the Reactor Building Closed Cooling Water system heat exchangers (E-8-1A or E-8-1B), the RHR heat exchangers (E14-1 A or E14-1B) and the emergency diesel generator lube oil and jacket w~ater coolers.

! Interruption of flow to these components could cause damage to equipment. These valves will be full-l stroke exercised closed during refueling outages in accordance with Paragraphs 4.2.1.2 (e) and (h) of I

l' art 10 of the Code when cooling flow to these components can be isolated.

Revision 19 Section 5 Page 134 of179

i Vcrm=t Ycekee N=lrr P wer Station Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V17, Revision 1 (Sheet 1 of1)

SYSTEM: Service Water COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V70-15A B 3 G-191159 Sh 1 J-08 V70-15B B 3 G-191159 Sh 1 B-08 These valves are the Service Water System Header Supply Isolation Valves. The safety function of these valves is to close to eliminate Alternate Cooling Flow from bypassing the cooling tower while the Service Water System is in the Altemate Cooling mode of operation.

JUSTIFICATION:

It is impracticable to full or part-stroke exercise these valves on a quarterly basis or during cold shutdowns. Closure of either of these valves could interrupt cooling flow in their respective trains to the Reactor Building Closed Cooling Water system heat exchangers (E-8-1A or E-8-1B). The RBCCW systems provide cooling flow to components such as the RHR pump coolers, the CRD pump coolers, and the spent fuel pool heat exchangers (E9-1 A and E9-1B) which are required for the safe operation of the plant at power and cold shutdown periods. These valves shall be full-stroke exercised during refueling outages These valves will be full-stroke exercised closed in accordance with Paragraph 4.2.1.2(e), (h) of Part 10 of the Code during each refueling outage when these cooling loads can be safely isolated.

4 Revision 19 Section 5 Page 135 of179

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Verment Ycakee N cirr Pswer Station Inservice Testing Program  ;

1  !

REFUELING OUTAGE JUSTIFICATION

. Number
ROJ-V18, Revision 1 (Sheet 1 of 1)

SYSTEM: Service Water COMPONENTS:

ValveNumber OM Cat. Safety Class . Drawing Number Dwg. Coord.

V70-187A B 3 G-191159 Sh 1 J-06 V70-187B B 3- G-191159 Sh 1 B-06

' These valves are the Service Water Pump Gland Seal Supply Isolation Valves. The safety function of these valves is to close in order to provide a backup leakage barrier for the Service Water Supply Header Isolation Valves (V70-13A and V70-13B) while the Service Water System is in the Altemate Cooling mode ofoperation.

JUSTIFICATION:

. It is impracticable to full or part-stroke exercise these valves on a quarterly basis or during cold

' shutdowns. The closure of either one of these valves will interrupt cooling flow to two of the Service Water Pump gland seals. Operation of the service water pumps without gland seal flow is not recommended. The Service Water Pumps are required to be operable during power operation and cold shutdowns for cooling to other loads.

These valves will be full-stroke exercised closed in accordance with Paragraph 4.2.1.2(e), (h) of Part 10 of the Code during each refueling outage when one loop of service water (two service water pumps) can be secured.

I Revision 19 Seetion 5 Page 136 of179

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Vermont Yankee Nuclear Power Station Inservice Testing Program REFUELING OUTAGE JUSTIFICATION I l

Number: ROJ-V19, Revision 0 (Sheet 1 of 1)

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THIS REFUELING OUTAGE JUSTIFICATION WAS WITHDRAWN FROM THE IST PROGRAM.

This ROJ number is being maintained for traceability to the Third Interval IST Program Submittal

. SER's.  ;

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Revision 19 Section 5 Page 137 of179

Verm:nt Yankee Nuclear Power Station Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V20, Revision 0 (Sheet 1 of 1) l THIS REFUELING OUTAGE JUSTIFICATION WAS WITHDRAWN FROM THE IST PROGRAM. -

This ROJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

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Revision 19 Section 5 Page 138 of179

L Verm=t Yerksa Nuclear Pcwsr Station Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V21, Revision 2 (Sheet 1 of1)

SYSTEM: Service Water I

COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V70-16A B 3 G-191159 Sh 2 D-07 i V70-16B B 3 G-191159 Sh I C-09 V70-184 B 3 G-191159 Sh 1 C-09 V70-16A and V70-16B are in the RHRSW pump suction line from the cooling tower. The safety function of these is to open to supply a suction source to the RHRSW pumps from the cooling tower when the service water system is aligned for the altemate cooling mode of operation. V70-184 is used to vent piping between V70-16A and V70-16B when altemate cooling is placed in service.

JUSTIFICATION:

It is impracticable to ful,1 or part-stroke exercise these valves on a quarterly basis or during cold i shutdowns. The suction line from the cooling towers to valve V70-16B is chemically treated to control the growth of microbiologically influenced corrosion (MIC). The opening of these valves could dilute '

the chemical mixture in this line. Dilution of the chemical mixture in this line would reduce its effectiveness.

These valves will be full-stroke exercised closed in accordance with Paragraph 4.2.1.2(e), (b) of Part 10 of the Code during each refueling basis when the line can be retreated with chemicals.

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! Revision 19 Section 5 Page 139 of179 4

Vcrmont Yankee Nuclear Power Station Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V22, Revision 1 (Sheet 1 of1)  ;

i SYSTEM: Instrument Air System COMPONENTS:

1 Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V72-89B NC 2 G-191160 Sh 3 K-14  ;

V72-89C NC 2 G-191160 Sh 3 K-15 l These valves are the Instrument Air to the Drywell Containment Isolation Valves. These valves have a i

safety function to close to prevent the release of fission products from the drywell to the reactor I building in the event of an accident. I JUSTIFICATION:

It is not practical to verify the closure function of these valves on a quarterly or cold shutdown basis.

The only means to verify closure of these valves is to perform a leakage type test or to utilize a non-l intrusive testing method. ,  !

In order to assure closure of these valves to perform a leakage rate test or non-intmsive test, it would be necessary to isolate instrument air to the main steam isolation valves inside containment. Additionally, in order to perform a leakage type test, it would be necessary to open system drains and vents. l Isolation of this line could result in closure of the air operated main steam isolation valves and subsequent reactor scram. l These valves will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of the Code.

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v Vermont Yankee Nuclear Power Station Inservice Testing Program REFUELING OUTAGE JUSTIFICATION  ;

Number: ROJ-V23, Revision 1 (Sheet 1 of 1) i i

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SYSTEM: Standby Fuel Pool Cooling i COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord. ,

Vl9-224 C 3 G-191173 Sh 1 1-12 i

Vl9-224 is normally open during plant operation to allow cooling flow to pass to the fuel storage pool.

The safety function of this valve is to close to provide isolation capability of the non-seismic nonnal fuel pool cooling system from the standby fuel pool cooling system.

JUSTIFICATION: l It is not practical to full-stroke exercise this valve to the closed position on a quarterly basis or during cold shutdowns. This valve is normally open to allow cooling flow from the normal fuel pool cooling pumps to the fuel storage pool. Additionally this valve is located directly upstream of check valve l Vl9-18. The only practical means to verify the closure of this valve is to pressurize the volume between Vl9-223, Vl9-53 and Vl9-46 and V19-224 utilizing a differential pressure or leakage type test or by performing a non-intrusive test when nonnal fuel pool cooling system flow through the demineralizer is isolated. The use of non-intrusive techniques to verify closure on a quarterly basis or ,

during cold shutdowns is not practical. These valves are not located in an easily accessible location and i scaffolding is required to setup the necessary equipment.

I NUREG 1482, subsection 4.1.4, states "The NRC has determined that the need to setup test equipment l

is adequatejustification to defer backflow testing of a check valve until a refueling outage". l The closure function of this valve will be verified during refueling outages by utilizing a differential pressure or leakage type test or by performing a non-intrusive test in accordance with Paragraph 4.3.2.2(e), (h) of Part 10 of the Code, f

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Vcrm: t Yc:kee Nucle r Pcwer Stati:2 Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V24, Revision 2 (Page 1 of 1)

SYSTEM: Instrument Air System COMPONENTS:

I Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord. j V70-113 A/C 2 G-191159 Sh 3 K-08 l l

This valve is the RBCCW system drywell supply line containment isolation valve. This valve has a i safety function to close to prevent the release of fission products from the drywell to the reactor i building in the event of an accident.

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JUSTIFICATION:

It is not practical to verify the closure function of this valve on a quarterly or cold shutdown basis. The only means to verify closure of this valve is to perform a leakage type test or to utilize a non-intrusive l testing method.

In order to assure closure 'of this valve, it is necessary to perform a leakage rate test or non-intrusive test. Leakage type testing would require isolation of the RBCCW system supply to the drywell and opening of system drains and vents. Isolation of this line would result in a loss of cooling flow to 1 important plant equipment such as the recirculation pumps, possibly resulting in their failure.

l This valve will be exercised closed each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.3.2.2(e), (h) of Part 10 of the Code.

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L Revision 19 Section 5 Page 142 of179

L Verm::nt Ycnkee Nuclear Pcwer Station Inservice Testing Program I

REFUELING OUTAGE JUSTIFICATION Number: ROJ-V25, Revision 2 (Sheet 1 of1)

SYSTEM: High Pressure Coolant Injection l COMPONENTS:

Valve Number - OM Cat. Safety Class Drawing Number Dwg. Coord.

V23-56 C 2 G-191169 Sh 1 J-05 V23-65 A/C 2 G-191169 Sh 1 1-03 SSC-23-12 A/C 2 0-191169 Sh 1 I-03 V23-56 is the HPCI Turbine Drain Condensate Exhaust Line Containment Isolation Valve. This valve is normally closed during plant operation. This valve has a safety function to open to pass turbine exhaust condensate to the torus. Additionally, this valve has a safety function to close for containment isolation. The Appendix J Program exempts this valve from leak rate testing.

V23-65 and SSC-23-12 are the HPCI Turbine Steam Exhaust Line Containment Isolation Valves.

These valves are normally closed during plant operation. These valves have a safety function to open to pass turbine exhaust stqam to the torus. Additionally, these valves have a safety function to close for containment isolation and are included in the Appendix J Program for leak rate testing. EDCR 98-402 ,

modified the vacuum breaker arrangement to the extent that these valves are now exposed to the torus I airspace, thus requiring testing per Appendix J. l JUSTIFICATION:

1 It is not practical to verify the closure function of these valves on a quarterly or cold shutdown basis.

During normal operation the HPCI steam and condensate exhaust lines are required to be available to j support operation of the HPCI turbine. The only practical means to verify the closure of V23-56 is to i pressurize the volume between SSC-23-13 and V23-56 utilizing a differential pressure or leakage type test or by performing a non-intrusive test. The only practical means to verify the closure of V23-65 is to pressurize the volume between SSC-23-12 and V23-65 utilizing a leakage type test during Appendix J l testing. The only practical means to verify the closure of SSC-23-12 is to pressurize the volume between SSC-23-12 and the torus utilizing a leakage type test during Appendix J testing. Additionally, the use of non-intrusive techniques or leak rate testing to verify closure on a quarterly basis or during cold shutdowns is not practical. These valves are not located in an easily accessible location and scaffolding is required to setup the necessary equipment.

NUREG 1482, subsection 4.1.4, states "The NRC has determined that the neel to setup test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage".

The closure function of these valves will be verified during refueling outages by utilizing a differential pressure or leakage type test or, for V23-56, by performing a non-intrusive test in accordance with l Paragraph 4.3.2.2(e), (h) of Part 10 of the Code.

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Verm:nt Ycnkee Nuclear Pcwer St ti:n Inservice Testing Program REITTELING OUTAGE JUSTIFICATION Number: ROJ-V26, Revision 2 (Sheet 1 of 1)

SYSTEM: Reactor Core Isolation Cooling COMPONENTS:

Valve Number OM Cat. Safety Clast. Drawing Number Dwg. Coord.

V13-38 C 2 0-191174 Sh 1 K-11 V13-50 A/C 2 G-191174 Sh 1 K-08 SSC-13-9 A/C 2 G-191174 Sh 1 K-08 V13-38 is the RCIC Turbine Vacuum Pump Exhaust Line Containment Isolation Valve. This valve is normally closed during plant operation. This valve has a safety function to open to pass vacuum pump discharge to the torus. Additionally, this valve has a safety function to clo< ; for containment isolation.

The Appendix J Program exempts this valve from leak rate testing.

V13-50 and SSC-13-9 are the RCIC Turbine Steam Exhaust Line Containment Isolation Valves.

These valves are normally closed during plant operation. 'Ihese valves have a safety function to open to pass turbine exhaust steam to the torus. Additionally, these valves have a safety function to close for containment isolation and are included in the Appendix J Program for leak rate testing. EDCR 98-402 modified the vacuum breaker arrangement to the extent that these valves are now exposed to the torus airspace, thus requiring testing per Appendix J.

JUSTIFICATION:

It is not practical to verify the closure function of these valves on a quarterly or cold shutdown basis.

During normal operation the RCIC steam and vacuum pump exhaust lines are required to be available to support operation of the RCIC turbine. The only practical means to verify the closure of V13-38 is to pressurize the volume between SSC-13-10 and V13-38 utilizing a differential pressure or leakage type test or by performing a non-intrusive test. The only practical means to verify the closure of V13-50 is to pressurize the volume between SSC-13-9 and V13-50 utilizing a leakage type test during Appendix J testing. The only practical means to verify the closure of SSC-13-9 is to pressurize the volume between SSC-13-9 and the torus utilizing a leakage type test during Appendix J testing. Additionally, the use of non-intrusive techniques' or leak rate testing to verify closure on a quarterly basis or during cold shutdowns is not practical. These valves are not located in an easily accessible location and scaffolding is required to setup the necessary equipment.

l NUREG 1482, subsection 4.1.4, states, "The NRC has determined that the need to setup test equipment is adequatejustification to defer backflow testing of a check valve until a refueling outage".

The closure function of these valves will be verified during refueling outages by utilizing a differential pressure or leakage type test or, for V13-38, by performing a non-intrusive test in accordance with Paragraph 4.3.2.2(e), (h) of Part 10 of the Code.

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Vcrm::t Yorkee N clarr Pcwer Stati:n Inservice Testing Pr: gram REFUELING OUTAGE JUSTIFICATION Number: ROJ-V27, Revision 0 (Sheet 1 of 1)

SYSTEM: Nuclear Boiler COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

SR-2-14A C NNS G-191167 M-12 SR-2-14B C NNS G-191167 M-12 SR-2-14C C NNS G-191167 M-12 i SR-2-14D C NNS G-191167 M-12 SR-2-14A through 14D are 3 inch Main Steam Relief Valve (MSRV) exhaust line vacuum breakers. '

These valves are normally closed during plant operation. These valves have a safety function to close to direct MSRV discharge flow to the suppression pool in the event of a MSRV actuation.  !

l JUSTIFICATION:  !

It is not practical to verify the closure function of these valves on a quarterly or cold shutdown basis.

These valves are located in the drywell and are not accessible during normal power operations or Cold Shutdowns when the drywell is inerted. These valves can only be tested when the drywell is accessible and the reactor vessel is depressurized.

.These valves will be manually exercised closed each refuel outage in accordance with Paragraph 4.3.2.2(e), (h) of Part 10 of the Code.

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Revision 19 Section 5 Page 145 of179

Verme:t Yankee Nucl:cr Pcwcr St:tien Inservice Testing Program REFUELING OUTAGE JUSTIFICATION t

Number: ROJ-V28, Revision 1 (Sheet 1 of 2)

'~

SYSTEM: Fuel Pool Cooling & Cleanup' .

Service Water J COMPONENTS:

Valve Number . OM Cat. Safety Class Drawing Number Dwg. Coord.

V70-244A C 3 G-191173 Sh 2 B-10 V70-244B C 3 . G-191173 Sh 2 B-10 V70-281A C 3 G-191159 Sh 1 J-09 :

V70-281B C 3 G-191159 Sh 1 B-09 V70-281C ~ C 3 G-191159 Sh 1 J-09 V70-281D C 3 G-191159 Sh 1 C-09 V70-51IB C 3 G-191159 Sh 1 H-12 V70-511C C 3 G-191159 Sh 1 H-12 V70-252B - C 3 G-191159 Sh 2 G  ;

V70-252C - -C 3 G-191159 Sh 2 0-05

'Ihese 2" swing check valves are the Service Water System vacuum breaker check valves.

These valves have a safety function in the open direction to eliminate vacuum in the service water system that is postulated to occur following a station electrical blackout or an Appendix R postulated fire. Eliminating the vacuum minimizes the potential for system water hammer upon service water i Pump restart.  !

These vacuum breaker check valves have a safety function in the closed direction to maintain the  !

service water system pressure boundary.

JUSTIFICATION:

Thisjustification concerns both the open and the closed position.

Open Position - The valves cannot be full flow tested in the open position based on thc current system configuration, lack of instrumentation and the absence of flow calculations establishing design flow

, , requirements. A mechanical exerciser cannot be used to measure required full stroke opening force p' based on interference resulting from the series pair spatial relationship. Disassembly to verify forward

!~ flow exercising is possible during refueling outages when the associated service water subsystem is made available for maintenance as part of a scheduled LCO. It is impractical to disassemble these valves on a quarterly basis or during cold shutdowns. These valves are located in the overhead and

~ require installation' of scaffolding to perform disassembly and inspection.

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Vermont Ycnkee Nuclear Power Station Inservice Testing Program l

REFUELBG OUTAGE JUSTIFICATION Number: ROJ-V28, Revision 1 (Sheet 2 of 2)

J'USTIFICATION (Continuedh Closed Position - During normal operation these valves are closed and form the necessary service water system pressure boundary. Based on the series pair configuration, any leakage past both valves l would be readily evident by noticing water flowing past the seat of the outboard check valve which is open to atmosphere. Stroke close testing of the individual check valves is possible however; installation of scaffolding is required to gain access to the test connections. The use of jumper hoses is also required to perform testing on the outboard valve. Drain hoses are required to test the inboard valves.

In addition, the test involves a hardship such that manual operator actions would be necessary to restore l the system if the postulated events occurred while the test was in progress. It is impractical to test these valves on a quarterly basis or during cold shutdowns. Per NUREG 1482, Section 4.1.4, the NRC has determined that the need to set up test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Alternate Testing Disassembly and inspection will be used to satisfy forward and reverse flow testing. Based on the large grouping of valve pairs and the alternating refueling outage basis for scheduling individual service water subsystem LCO maintenance actions, disassemblies will be performed using a sampling program l during refueling outages. Specifically, three pairs of valves (6 valves total) will be disassembled, inspected, and full stroke exercised during one refueling outage with the other two pairs (4 valves total) j being disassembled, inspected, and full stroke exercised the following refueling outage. During the .

disassembly, the disk will be manually exercised and the intemals of the valve will be verified to be  !

structurally sound (no loose or corroded parts). If a disassembled valve is not capable of being full stroke exercised or there is binding or failure of a valve's intemals, all other vacuum breaker check valves in both groups will be disassembled, inspected, and manually full stroke exercised during the I l same refueling outage. Use of non-intrusive techniques was considered for this application and determined impractical given the valve design and system application. Partial valve stroking with flow l is not practical following reassembly. Quality disassembly, reassembly and inspection techniques provide sufficient confidence that the valves will perform their intended function when challenged.

Oma-1998, Part 10, Paragraph 4.3.2.4(c) permits disassembly every refueling , outage to verify operability of check valves. NUREG 1482 and Generic Letter 89-04, Position 2 permit the use of a sample disassembly and inspection plan when the licensee determines it is burdensome to disassemble and inspect all applicable valves each refueling outage.

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Verm=t Yc kee Nucl:cr Pcwer Station Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V29, Revision 0 (Sheet 1 of1)

SYSTEM: Residual Heat Removal Nuclear Boiler COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V10-18A A/C 2 G-191172 F-08 V10-18A5 A/C 2 G-191172 F-08 V2-39A A/C 2 G-191167 L-04 V2-74A A/C 2 0-191167 D-10 V10-18A has a safety function to open to provide overpressure protection for Penetration X-12. V10-18A and associated piping are configured like an typical equalizing line across V10-18. V10-18A also has a safety function to close as one of the inboard containment isolation valves for Penetration X-12.

(Ref. EDCR# 96-416).

V10-18A5 has a safety function to open to provide V10-18 bonnet pressure locking protection. V10-18A5 also has a safety function to close as one of the inboard containment isolation valves for Penetration X-12. (Ref. EDCR# 96-416, ECN-1).

V2-39A has a safety function to open to provide overpressure protection for Penetration X-41. V2-39A and associated piping are configured like an typical equalizing line across FCV-2-39. V2-39A is oriented to open anytime pressure on the penetration side of FCV-2-39 is greater than reactor side of FCV-2-39. V2-39A also has a safety function to close for primary containment isolation of penetration X-41. (Ref. EDCR# 96-416).

V2-74A has a safety function to open to provide overpressure protection for Penetration X-8. V2-74A and associated piping are configured like an typical equalizing line across V2-74. V2-74A is oriented to open anytime pressure on the penetration side of V2-74 is greater than reactor side of V2-74. V2-74A also has a safety function to close for primary containment isolation of penetration X-8. (Ref. EDCR#

96-416).

JUSTIFICATION:

It is not practical to full or part-stroke exercise these valves on a quarterly basis or during cold shutdowns. These valves are located inside the drywell and are not accessible during power operation.

The stroke open and close function of these valves will be verified each refueling outage in accordance with Paragraph 4.3.2.2(e), (h) of Part 10 of the Code.

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Vermont Yankee Nuclear Power Station Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V30, Revision 1 (Sheet 1 of 1)

THIS REFUELING OUTAGE JUSTIFICATION WAS WITHDRAWN IN REVISION 18B OF THEIST PROGRAM.

This ROJ number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

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i Verm=t Yerkee Nuclear P wer St:ti:n Icservice Tcsting Prcgram REFUELING OUTAGE JUSTIFICATION Number: ROJ-V31, Revision 0 (Sheet 1 of 2)

SYSTEM: Resdinal Heat Removal, Reactor Water Cleanup, Reactor Core Isolation Cooling and High Pressure CoolantInjection COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V10-19A C 2 G-191172 L-05 V10-19B C 2 G-191172 L-12 V10-19C C 2 G-191172 J-05 V10-19D C 2 G-191172 J-12 V12-28A C 3 G-191178 Sh 1 D-08 V12-28B C 3 G-191178 Sh 1 G-08 V12-62 C 2 G-191178 Sh 1 B-05 i V12-62A C 3 G-191178 Sh 1 B-05 V13-29 C 2 G-191174 Sh 1 J-10 V13-40 C 2. G-191174 Sh 1 N-11 V13-817 C 2 G-191174 Sh 1 K-07 V13-818 C 2 G-191174 Sh 1 K-07 l SSC-23-13 C 2 G-191169 Sh 1 J-04 V23-56 C 2 G-191169 Sh 1 J-05 V23-61 C 2 G-191169 Sh 1 L-06 I V23-62 C 2 G-191169 Sh 1 J-10 V23-842 C 2 G-191169 Sh 1 I-02 V23-843 C 2 G-191169 Sh 1 I-03 V78-2 C 3 G-191162 Sh 2 E-02 Valves V10-19A through D are RHR pump. They have a safety function in the open position to pass i RHR flow to the suppression pool for pump protection. They have a safety function in the close position to prevent backflow through an idle RHR pump.

Valves V12-28A and V12-28B are RWCU pump discharge check valves. They havp a safety function in the closed position to prevent reverse flow in the event of a HELB upstream of the RWCU pumps.

Valves V12-62 and V12-62A are RWCU flow to Feedwater system isolation check valves. They have a safety function in the closed position to prevent gross diversion of RCIC flow and prevent reverse

flowin the event of a HELB upstream.

i Valve V13-29 is RCIC pump miminum flow recin:ulation line check valve. It has a safety function in the closed position to provide primary containment isolation and a safety function in the open position t

to pass RCIC flow to the suppression pool for pump protection.

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i Vcrmat Yenkee Nuclesr Powcr St:tinn Inservice Testing Program 4

REFUFLING OUTAGE JUSTIFICATION Number: ROJ-V31, Revision 0 (Sheet 2 of 2)

' Valve V13-40 is RCIC pump suction valve from the suppression pool. It has a safety function in the open position to pass flow from the suppression pool to the RCIC pump suction. This flow path is

requied aAer the CST supply has been exh==W.

~ Valves V13-817 and V13-818 are RCIC turbine exhaust line vacuum breakers.'They have a ' safety function in the closed position to provide primary containment isolation and a safety function in the i

. open position to prevent water hammet on RCIC turbine exhaust line check SSC-13-9.

. Valves SSC-23-13 and V23-56 are HPCI turbine exhaust drain check valves. They have a safety function in the closed position to provide primary containment isolation and a safety function in the open position to pass condensate in the HPCI turbine exhaust line drain pot to the suppression pool.

Valve V23-61 is HPCI pump suction valve from the suppression pool. It has a ' safety function in the open position to pass flow from the suppression pool to the HPCI pump suction. This flow path is .

. requied aAer the CST supply has been exhausted.

Valve V23-62 is HPCI pump miminum flow recirculation line check valve. It has the closed position to provide primary containment isolation and a safety function in the open position to pass HPCI flow to .

the suppression pool for pump protection.

LValves V23-842 and V23-843 are HPCI turbine exhaust line vacuum breakers. They have a' safety i function in the closed position to provide primary containment isolation and a safety function in the j L open position to prevent water hammer on HPCI turbine exhaust line check SSC-23-12. j l Valve V78-2 is the Diesel Fuel Oil Storage Tank fill line check valve. It has a safety function in the close position to prevent loss of Diesel Fuel Oil Storage Tank contents int he event of failure of the NNS fillline.

JUSTIFICATION: I Valves V10-19A, V10-19B, V10-19C, V10-19D, V13-29, V13-40 SSC-23-13, V23-56, V23-61 and V23-62 cannot be verified to exercise full open during normal (power) operation due to the lack of i instrumentation for positive test results.

Valves V12-62,V12-62A,-V13-817, V13-818, V23-842, V23-843 and V78-2 cannot be individually exercised closed during nonnal (power) operation because there are two check valves in series without I

test connections.

Valves V12-28A and V12-28B cannot be verified to exercise closed during normal (power) operation

{ due to the lack ofinstrumentation for positive test results.

e

Each of these valve will be disassembled and irspected each refueling outage in accordance with Paragraph 4.3.2.4(c) of the Par t10 of the Code.

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Vermnt Ycnkee Nuclear Power Station Inservice Testing Program  !

I REFUELING OUTAGE JUSTIFICATION I l

Number: ROJ-V32, Revision 0 (Sheet 1 of 2)

SYSTEM: Service Water COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V70-43A C 3 G-191159 Sh 1 J-12 V70-43B C 3 G-191159 Sh 1 B-12 These 8" swing check valves are the Service Water System loop header discharge check valves.

l These check valves have a safety function in the open direction to provide cooling water to various ECCS room area coolers during nonnal plant operation and to the standby emergency diesel generator 1 jacket water, lube oil and after coolers when the diesel generator is inservice.

These valves have a safety function in the closed direction to prevent reverse flow during the service water alternate cooling rnode of operation. When the service water system is operating in the alternate i cooling mode, these check valves close to ensure Residual Heat Removal Service Water (RHRSW) pump flow is directed to the RHR heat exchangers, ECCS area coolers and the standby emergency diesel generatorjacket water, lube oil and after coolers.

JUSTIFICATION:

Thisjustification concems both the open and closed position.

Open Position - The design required flow through these check valves is between 900 and 1050 gpm.

when the ECCS room coolers are inservice and the diesel generator is in operation. The maximum required accident condition flow, for example, assumes higher flows through the ECCS coolers with a postulated line break to NNS number 17 room cooler. This condition brings the required accident condition flow to approximately 1900 gpm. for the "A" SW loop. The "B" SW loop is similar however a lower flow is required since a break at the NNS number 9 room cooler has not been postulated. This information was obtained from calculation VYC-1279, " Service Water Hydraulic Analysis". The design flow inputs are listed in section 4.0 of the calculation. Case #6 was used to arrive at the maximum required accident flow for these check valves. Instrumentation is not installed to measure

total flow through these valves. The diesel generator branch (one of up to five branches) is the only l - parallel path instrumented with a flow element (reads in percent of flow). It is not practicable to i

simulate or obtain line break conditions to pass the maximum required accident condition flow through room cooler or diesel generator branches. It is impractical to forward flow exercise these valves with j flow on a quarterly, cold shutdown or refueling frequency.

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Verment Yankee Nuclear Power Station Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V32, Revision 0 (Sheet 2 of 2)

. Closed Position - During normal plant operation these valves continuously pass flow to supply various ECCS room area coolers and to the standby emergency diesel generatorjacket water, lube oil and after coolers when the diesel generator is inservice. It is impractical to reverse flow exercise these valves on a quarterly or cold shutdown frequency due to the extent of components that must be declared inoperable to accomplish testing. Closure testing of these valves would require shutdown of the service water pumps in their individual trains or by isolating the required flow to various ECCS room area coolers and to the standby emergency diesel generator jacket water, lube oil and after coolers.

Additionally, although impractical, with no specific frequency being established, closure testing could be performed whenever the service water system is operated in the attemate cooling mode (ACS).

l Isolation of flow to the room coolers and the diesel generator permits the disk to travel to its seat by gravity. Disassembly and inspection or non-intrusive techniques would then be required to confirm that the valves are in the closed position.

Alternate Testing Partial flow testing of these valves is satisfied quarterly. Disassembly and inspection or use of non-intrusive techniques will be used to satisfy forward and reverse flow testing. Use of either method will be' performed using a sainpling program during refueling outages. Periodic disassembly is also required for verification of internal coating integrity and system cleaning per LER-89-017, corrective l action #2. A sampling program is justified due to the extent of system isolation and drain down

]

required to perform check valve disassembly combined with the need to keep certain ECCS systems i and the diesel generators available during refueling outages. Regarding non-intrusive testing, NUREG i 1482 specifies that the extensive effort to set up test equipment and the adverse impact on system  !

operation provides sufficientjustification to defer the test to a refueling outage. Specifically, one check I valve is disassembled and inspected or non-intrusively tested every refuel outage with the other check  !

l valve being disassembled and inspected or non-intrusively tested the following outage. During the l disassembly, the internals of the valve will be verified to be structurally sound (no loose or corroded parts.) If the disassembled valve is not capable of being full stroke exercised or there is binding or L failure of the valve intemals, the other valve will also be disassembled, inspected and manually L exercised during the same refuel outage. Regarding non-intrusive testing, if problems are found with l the sample valve that are determined to affect the operational readiness of the valve, the other valve l must be tested using non-intrusive techniques during the same outage. Oma-1988, Pwt 10, Paragraph 4.3.2.4(c) permits disassembly every refueling outage to verify operability of check valus. NUREG 1482 and Generic Letter 89-04, Position 2 permit the use of a sample disassembly and m ' spection plan I when the licensee determines it is burdensome to disassemble and inspect all applicable valves each refueling outage. NUREG 1482,4.1.2 permits the use of non-intrusive techniques using a sampling

program.

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f Revision 19 Section 5 Page 153 of179 l

Vcrm:nt Ycnkee Nucb:r Pcwer Strti:n Inservice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V33, Revision 0 (Sheet 1 of 2)

SYSTEM: Reactor Core Isolation Cooling (RCIC) and High Pressure Coolant Injection (HPCI)

COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V13-820 A/C 2 G-191174 Sh 1 K-8 i V13-821 A/C 2 G-191174 Sh 1 K-8 V23-845 A/C 2 G-191169 Sh 1 I-3 V23-846 A/C 2 G-191169 Sh 1 I-3 I

These nozzle type check valves are utilized as the RCIC/HPCI turbine exhaust line vacuum breakers to  ;

prevent water hammer. l

- The water hammer phenomenon can result when steam in the exhaust piping condenses (collapses) and causes a rapid drop in pressure in the exhaust piping. As the pressure in the exhaust piping drops  !

below the pressure in the torus, water quickly is drawn up the exhaust piping and results in the water I hammer event. The vacuum breakers are designed to introduce air into the exhaust piping when the exhaust piping pressure decreases below the suction side pressure of the vacuum breaker. The air

. prevents a significant vacuum from developing and thus eliminates the conditions required to initiate a water hammer event.

l l

JUSTIFICATION:

l Thisjustification concems both the open and closed position.

Open Position - Per calculation VYC-1790, accident air-flow through the vacuum breaker line is 3909 SCFH for RCIC and 18,817 SCFH for HPCI. Verifying the maximum accident condition required flow through these valves is not possible due to the large gas volume required and extremely high flow velocities through the 3/4" test connections. Providing an adequate downstream vent to pass accident l

condition flow also presents the potential for contaminating test personnel and the surrounding area. A reduced flow air test can demonstrate that the disk exercised to the full open position at less than accident flow as detected by non-intrusive acoustic technology. It is impractical to verify these valves l

in the open position on a quarterly basis or during cold shutdown due to the need to gain component access and to set-up non-intrusive test equipment. Performance of this test requires access to overhead areas,- routing of air hoses, and set-up of several non-intrusive signal-conditioning devices.

Additionally, the specific system must be removed from service to accomplish this testing. Section 4.1.2 of NUREG-1482 permits the use of non-intrusive testing and acknowledges that relief is not l required except as would be necessary for the testing frequency if the test interval extends beyond each refueling outage as allowed by OM-10. Partial stroke open credit can be verified quarterly by observing that the turbine exhaust pressure enters the vacuum range and retums to approximately

zero after the turbine is shutdown.

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l Verment Ycnkee Nuclear Pcwer Station Inservice Testing Program l REFUELING OUTAGE JUSTIFICATION Number: ROJ-V33, Revision 0 (Sheet 2 of 2)

Closed Position - During normal plant operation, with the RCIC/HPCI pumps in standby, these nozzle type vacuum breaker check valves are installed in series and maintained in the closed position by means of an intemal spnng. In the event one vacuum breaker is stuck open, exhaust steam will not discharge directly into the torus air space as a result of the series design concept. Additional closing force is provided by steam when the e.pplicable turbine is in operation. A seat leakage limit has been established such that the toms environment will not be adversely affected during turbine operation. It is impractical to verify these valves in the closed position on a quarterly basis or during cold shutdown due to the need to gain component access, set-up air hoses and install test equipment. Additionally, the applicable system must be removed from service to accomplish this testing. During refueling, RCIC and HPCI are not capable of being operated without a steam supply available, presenting the ideal opportunity for leak-rate / closed position testing. Section 4.1.4 of NUREG-1482 permits extension of the test interval to a refueling outage for check valves verified closed by leak testing.

Alternate Testing Partial open stroke testing of these valves is verified quarterly following shutdown of the associated turbine. RCIC Turbine Steam Discharge Line Series Vacuum Breakers V13-820/821 and HPCI l Turbine Steam Discharg'e Line Series Vacuum Breakers V23-845/846 shall be tested with air to demonstrate stroke open and stroke close capability during refueling outages. Leak tightness is demonstrated by allowing no greater than 14.3 SCFH at a test pressure of 5 psid. The open stroke verification is performed at less than accident flow using non-intrusive techniques, specifically MOVATS UDS acoustic technology. The refueling outage test frequency is allowed by OM-10.

Additionally, NUREG 1482 permits the use of acoustic technology for open stroke testing and extension of the closed exercise test interval to a refueling outage for check valves verified closed by leak testing.

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Revision 19 Section 5 Page 155 of179 I

i Vermant Ycnkee Nuclesr Pcwer Stetica Inssrvice Testing Program REFUELING OUTAGE JUSTIFICATION Number: ROJ-V34, Revision 0 (Sheet 1 of 1)

SYSTEM: Core Spray COMPONENTS:

Valve Number - OM Cat. Safety Class Drawing Number Dwg. Coord. ,

V14-13A - A/C 1 G-191168 F-06 I

V14-13B A/C 1 G-191168 D-06 These valves are the Core Spray injection check valves. They have a safety function in the open position to pass core spray injection flow to'the mactor, and in the closed position for primary containment and pressure isolation.

i JUSTIFICATION: '

l Open position - These valves cannot be' exercised open during normal (power) operation since core spray pump discharge cannot overcome reactor pressure. Manual exercising is precluded during power operation since the valves pre inside the inerted drywell. Manual exercising has been performed in the past,'during cold shutdown conditions, yielding test implementation difficulty and inconsistent test L results. Empirical data has identified that packing drag and break away torque are too. closely, related for these valves. Mechanical exerciser test methods using break-away torque criteria have the potential to INOP the valve when no degradation exists.

l 1 Disassembly and inspection will be used to satisfy forward flow testing. It is burdensome to drain

l. portions of both Core Spray trains during each refueling outage therefore, a sample disassembly and l

inspection program has been employed as permitted by GL 89-04 Position 2. Based on a 2 valve group, disassembly will be performed during refueling outages. Specifically, one valve will be disassembled,

inspected, and full stroke exercised during one refueling outage while the other valve is disassembled,
inspected, and full stroke exercised the following refueling outage. During the disassembly, the disk will be manually exercised and the intemals of the valve will be verified to be structurally sound (no loose or corroded parts). If a disassembled valve is not capable of being full stroke exercised or there is  ;

binding or failure of a valve's internals, the other check valve in the group will be disassembled,  !

' inspected, and manually full stroke exercised during the same refueling outage. Use of non-intrusive l, techniques was considered for this application and determined impractical given the valve design and E system application. Partial valve stroking with flow is also not practical following re-assembly.

. Quality disassembly, re-assembly and inspection techniques provide sufficient confidence that the .

. valves will perform their intended function when challenged.

Oma-1998, Part 10, Paragraph 4.3.2.4(c) permits disassembly every refueling outage to verify  ;

. ' operability of check valves. NUREG 1482 and Generic Letter 89-04, Position 2 permit the use of a  !

[

sample disassembly and inspection plan when the licensee determines it is burdensome to i disassemble and inspect all applicable valves each refueling outage.  !

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Section 5 Page 156 of179 L . .-. .- .-. -.

Vcrm: t Ycnk:e Nucle:r P:wer St ti:n Inservica Testing Pr: gram RELIEF REOUEST Number: RR-V01, Revision 1 (Sheet 1 of1)

SYSTEM: Service Water COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

SE-70-4A B 3 G-191159 Sh 1 K-11 SE-70-4B B 3 G-191159 Sh 1 K-11 SE-70-4C B 3 G-191159 Sh 1 K-11 SE-70-4D B 3 G-191159 Sh 1 K-11 These valves are the Residual Heat Removal Service Water (RHRSW) pump motor cooling coil supply isolation valves. They have a safety function in the open position to provide cooling for the RHRSW pump motor during operation.

EXAM OR TEST CATEGORY:

Category B. .

THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.

This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

Revision 19 Section 5 Page 157 of 179

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Vcrms:t Y:nkes Nucl::r Pcwer St:ti:n Ins rvice Testing Pr: gram RELIEF REOUEST Number: RR-V02, Revision 1 (Sheet 1 of 1)

SYSTEM: Service Water l

COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V70-1A C 3 G-191159 Sh 1 C-03 V70-1B C 3 G-191159 Sh 1 B-03 l V70-1C C 3 G-191159 Sh 1 I-03 l V70-1D C 3 G-191159 Sh 1 H-03 These valves are the station Service Water pump discharge check valves. They have a safety function in the open position to provide cooling water to systems and equipment required to operate under accident conditions and to provide an inexhaustible supply of water for standby coolant system l operation. They have a function in the closed position to prevent the diversion of cooling water through an idle station Service Water pump.

l EXAM OR TEST CATEGORY:

L l

Category C.

THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.

This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

l l

l l

Revision 19 Section 5 Page 158 of179

l Vcrm=t Ycekee Nucinr P wer St:ti:n hservics Testing Prcgram RELIEF REOUEST Number: RR-V03, Revision 1 (Sheet 1 of 2)

SYSTEM: Diesel Generator Starting Air COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

AS-24-1A B 3 G-191160 Sh 7 B-16 AS-24-1B B 3 G-191160 Sh 7 B-03 AS-24-2A B 3 G-191160 Sh 7 B-17 '~

AS-24-2B B 3 G-191160 Sh 7 B-03 AV-24-1A B 3 G-191160 Sh 7 B-17 AV-24-1B B 3 G-191160 Sh 7 B-03 These valves are the Emergency Diesel Generator (EDG) starting air inlet and vent valves. They have safety functions, as a set, to provide starting air to the EDO, to prevent EDG and/or piping damage after the EDG starts, and to prevent inadvertent EDO starts.  ;

EXAM OR TEST CATEGORY:

Category B.

CODE REOUIREMENT: Part 10 Para. 4.2.1.1 " Exercising Test Frequency"

" Active Category A and B valves shall be tested nominally every 3 months, except as provided by paras. 4.2.1.2,4.2.1.5, and 4.2.1.7."

Para. 4.2.1.3 " Valve Obturator Movement" "The necessary valve obturator movement shall be determined by exercising the valve while observing an appropriate indicator, such as indicating lights which signal the required change of obturator position, or by observing other evidence, such as changes in system pressure, flow rate, level, or temperature, which reflect change of obturator position."

i Revision 19 Section 5 Page 159 of179 l

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l Vcrm:nt Ycnke: Nucler Power Strti:n Inservica Testing Pr: gram RELIEF REOUEST Number: RR-V03, Revision 1 (Sheet 2 of 2)

REOUEST FOR RELIEF 1 l Reliefis requested on the basis that compliance with the Code requirements is impractical and that the l proposed altematives would provide an acceptable level of quality and safety.

I

- These valves do not have remote position indication. Measuring the stroke time of these valves by observing stem travel would require disassembly of the operator.

l Testing of the inlet valves individually would require the lifting of the power leads to the other valve.

Since the stroke timing of these valves is perfonned by the indirect indication of the respective EDG start time, to lift leads each quarter and perform the necessary EDG fast starts to verify each valve's stroke time would be an undue hardship. Because excessive EDO fast starts are a known contributor to decreased EDG reliability and owing to the criticality of the EDGs as part of the ECCS system, the

overall impact of testing these valves in accordance with Code requirements would be an overall decrease in plant safety. Furthermore, since the air start system is not totally redundant (e.g. they share

! common piping, components and initiating logic), testing of these valves individually on a quarterly basis would not increase the quality and safety of the system.

l ALTERNATE METHOD:

During EDG slow start testing performed each month, indirect indication that at least one of the two parallel air start inlet valves opens, and the vent valve closes, will be performed by ensuring the EDG starts. i l

During EDG fast start testing performed every six months, indirect measurement that at least one of the l I

two parallel air start inlet valves opens promptly, and the vent valve closes promptly, will be performed by ensuring the EDG starts within the Technical Specification limit of 13 seconds. Measuring the EDG )

start time gives indication of possible valve degradation (as a pair) since any significant changes in valve stroke time will be identified by longer than normal EDG ttart times.

l In addition, to further assess the operational readiness of each air start inlet valve, an independent operability test is perfonned once per operating cycle. This test will be accomplisl;ed by altemately lifting the power leads to one of the two air start valves, and then measuring the EDG fast start time with the remaining valve in operation.

USNRC EVALUATION STATUS:

Relief was granted in the March 1994 SER [ Reference (u)] for Relief Request RR-V03, Revision 1.

4 Revision 19 Section 5 Page 160 of179

Verm:ct Yetkee Nucirr Psw r St:tien Its:rvice Testing Program RELIEF REOUEST Number: RR-V04, Revision 1 (Sheet 1 of 1)

SYSTEM: FuelOilTransfer COMPONENTS:

Valve Number OM Cat. Safety Class DrawingNumber Dwg. Coord.

V78-2 C 3 0-191162 Sh 2 E-02 i Valve V78-2 is the fuel oil storage tank fill line check valve. It has a safety function in the close position to ensure fuel oil system integrity upon loss of the non-safety related fill line piping.

EXAM ORTEST CATEGORY:

Category C. l l

THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.

This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's. I l

i Revision 19 Section 5 Page 161 of179

1 l

Vermrx.t Ycnkee Nuclear Pcw;r Steti:n Ins:rvica Testing Program i i RELIEF REOUEST Number: RR-VOS, Revision 1 (Sheet 1 of1)

SYSTEM
Nuclear Boiler 1

COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

RV-2-71A B/C 1 G-19? 167 D-08 RV-2-71B B/C 1 G-19[167 G-08 RV-2-71C B/C 1 G-191167 G-08 RV-2-70A C 1 G-191167 D-08 RV-2-70B C 1 G-191167 D-08 Valves SV-2-70A and SV-2-70B are the main steam safety valves. They have a safety function to i prevent over-pressurization of the reactor coolant system.

Valves RV-2-71A through D are the main steam dual function relief valves. They have a safety function to prevent over-pressurization of the reactor coolant system and to function as part of the l

reactor coolant Automatic Depressurization System (ADS).

EXAM OR TEST CATEGORY:

! Category C THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.

l This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

l.

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l Revision 19 Section 5 Page 162 of179 l

l' Vcrm=t Ycnkee Nucirr Pewsr St:tia Inservice Testing Pr: gram RELIEF REOUEST I I Number: RR-V06, Revision 0 (Sheet 1 of 1) l l SYSTEM: High Pressure Coolant Injection l 1

COMPONENTS:

l Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.  ;

HPCI-CONTROL B 2 G-191169 Sh 2 F-13 I l

This valve is the High Pressure Coolant Injection (HPCI) turbine steam inlet Control valve. It has a i safety function to operate to provide and regulate steam to the HPCI turbine. I EXAM OR TEST CATEGORY:

Category B. l THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 18 OF THE IST PROGRAM. j This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.  !

I l

Revhion 19 Section 5 Page 163 of179

Vermrt Ycnkee Nucirr P wcr St:ti::n Inservica Testing Program RELIEF REOUEST Number: RR-V07, Revision 2 (Sheet 1 of1)

SYSTEM: Control Rod Drive Hydraulic COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.  !

V3-162A - NC 2 G-191170 A-09 l V3-162B NC 2 G-191170 A-01 These valves are the Control Rod Drive (CRD) scram discharge volume vent check valves. They have ,

a safety function in the closed position to isolate the scram discharge volume during a scram condition,  ;

thereby preventing reactor coolant inventory loss. l THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 15 OF THE IST PROGRAM.

This RR number is being maintained for traceability to the Third Interval IST Program Submittal l

SER's.

1 i

i Revision 19 Section 5 Page 164 of179

' Vermmt Ye:ekea Nuclear Power Station Inservice Testing Program RELIEF REOUEST Number: RR-V08, Revision 0 (Sheet 1 of 2)

SYSTEM: Standby Liquid Control I

COMPONENTS:

Valve Number OM Cat. - Safety Class Drawing Number Dwg. Coord.

SR-11-39A C 2 G-191171 G-08 SR-11-39B C- 2 . O-191171

. K-08 1 I

Valves SR-11-39A & B are the Standby Liquid Control (SLC) pump discharge relief valves. They have a safety function to operate to prevent overpressurization of the SLC system.

EXAM ORTEST CATEGORY:

Category C CODE REOUIREMENT: Part 1

' Para.1.3.4.l(b) " Subsequent 10 Year Periods" "All valves of each type. and manufacturer shall be tested within each subsequent 10 year period, with a minimum of 20% of the valves tested within 48 months. 'lhis 20% shall be previously untested valves, if they exist."

Para.1.3.4.1(c)(2)" Valves Not Meeting Acceptance Criteria" "Any valve exceeding its stamped set pressure by 3% or greater shall be repaired or replaced, the cause of failure shall be determined and corrected, and the valve shall successfully pass a retest before it is  !

returned to service.

REOUEST FOR RELIEF: -

' Relief is requested on the basis that the proposed alternatives would provide, an acceptable level of quality and safety. '

Revision 19 Section 5 Page 16.5 of179

,c .r- . , . .- - - - - , . . , , = . - . ,

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i E

Vermsat Yenk -3 Nucir.er Pow:r St:tian Inservice Testing Program i

! RELIEF REOUEST l-l Number: RR-V08, Revision 0 (Sheet 2 of 2) l REOUEST FOR REIJEF(CONT.):

l Vermont Yankee Technical Specifications 4.4.A requires testing of valves SR-11-39A & B at least once every operating cycle. This testing frequency represents a six-fold increase over the testing

! frequency required by Part 1 of the Code and, as such, yields more accurate valve degradation trending data. The testing is currently performed at the Vermont Yankee plant site.

The acceptable range of relief valve actuation given in Technical Specifications 4.4.A is 1400 psig to  !

1490 psig. The 1400 psig value ensures that a sufficient injection pressure can be established prior to lifting of the relief valve. The 1490 psig value ensures relief valve actuation prior to reaching the system design pressure of 1500 psig. 1490 psig translates into a maximum relief valve setpoint of 99%

of system design pressure as opposed to 110% allowable by the piping code. Applying the Part I tolerance af 3% to the current setpoint would unnecessarily reduce the acceptable range to 1400 psig to 1442 psig (1442 psig = 96% of system design pn:ssure).

The increased testing frequency and present setpoint requirements provide adequate assurance of the operational readiness of valves SR-ll-39A & B and, as such, no significant increase in the level of safety or quality can be expected if the subject Code requirements are imposed.

' ALTERNATE METHOD: i In accordance with Vermont Yankee Technical Specifications 4.4.A, valves SR-11-39A & B shall be tested at least once every operating cycle. The setting of the valves shall be between 1400 and 1490 psig.

USNRC EVALUATION STATUS:

Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-V08, Revision 0.  ;

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Revision 19 Section 5 Page 166 of179

i Vermont Yankee Nuclear Power Station Inservice Testing Program

! RELIEF REOUEST Number: RR-V09, Revision 1 (Sheet 1 of1) ~

t SYSTEM: ResidualHeat Removal COMPONENTS:

j Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

l V10-17 A 2 G-191172 D-06 V10-27A A 2 G-191172 D-06 V10-27B A 2 G-191172 D-12 Valve V10-17 is the Residual Heat Removal (RHR) shutdown cooling supply outboard primary I comainment isolation valve. The valve has a safety function in the closed position to provide primary containment and pressure isolation, and in the open position to provide RHR pump suction during shutdown cooling operation.

Valves V10-27A & B are the RHR system low pressure coolant injection primary containment isolation valves. These valves have a safety function in the closed position to provide primary containment and pressure isolation, and in the open position to pass low pressure coolar:t injection water to the reactor.

USNRC EVALUATION STATUS:

l .THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM PLAN.

This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

I d'

Revision 19 Section 5 Page 167 of179

Vcrm::nt Yenkee Nucirr Pcwer St:tirn Insarvice Testing Program RELIEF REOUEST Number: RR-V10, Revision 0 (Sheet 1 of1) ,

I SYSTEM: Residual Heat Removal Service Water '

COMPONENTS:

, Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V10-89A B 3 G-191179 Sh 2 G-01 l V10-89B B 3 G-191179 Sh 2 C-01 1 These valves are the Residual Heat Removal Service Water (RHRSW) flow control valves for the RHR heat exchangers. They have a safety function to provide and regulate cooling water to the RHR heat exchangers.

]

TIHS RELIEF REQUEST WAS WITHDRAWN IN REVISION 15 OF THE IST PROGRAM.

This RR number is being maintained for traceability to the Third Interval IST Program Submittal SER's.

l l

Revision 19 Section 5 Page 168 of179

Vcrm:;ft Ycnkee Nucle:r Pcwcr Stati:n Ins:rvica Tcsting Prcgram RELIEF REOUEST Number: RR-Vil, Revision 0 (Sheet 1 of 1) ,

1 SYSTEM: Reactor Core Isolation Cooling COMPONENTS:

l Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

RCIC-CONTROL B 2 G-191174 Sh 2 D-12 This valve is the Reactor Core Isolation Cooling (RCIC) turbine governor control valve. This valve has a safety function to operate to provide and regulate steam to the RCIC turbine.

EXAM OR TEST CATEGORY:

Category B.

THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 18 OF THE IST PROGRAM.

This RR number is bein'g maintained for traceability to the Third Interval IST Program Submittal SER's.

l Revision 19 Section 5 Page 169 of179

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Vermont Yankee Nuclear Power Station Inservice Testing Program RELIEF REOUEST Number: RR-V12, Revision 0 (Sheet 1 of1)

SYSTEM: Service Water System (SW)

COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V70-43A C 3 G-191159 Sh 1 J-12 V7043B C 3 .

G-191159 Sh 1 B-12 These valves are the Service Water System loop header discharge check valves. These valves have a safety function to close to prevent the backflow of RHRSW pump discharge to the suction of the pumps when operating in the Alternate Cooling mode of operation.

EXAM OR TEST CATEGORY:

Category C USNRC EVALUATION STATUS This Relief Request was approved for use in USNRC Generic Letter 89-04, NRC Staff Position 2.

Based on comments from the NRC, Revision 1 to this request was submitted and relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-V12, Revision 1.

Following receipt of the January 1998 SER, Vermont Yankee reexamined the reasons for the request and concluded that full Code compliance can be achieved without resorting to such relief. Vermont Yankee will meet all required testing provisions as specified by OM-10 and as amplified by the NRC guidance provided within NUREG-1482. (See ROJ-V32)

THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION ISA OF THE IST PROGRAM.

This RR ntunber is being maintained for traceability to the Third Interval IST Program Submittal SER's. -

Revision 19 Section 5 Page 170 of179

l l - Vcrm:nt Yenkee Nucirr Pcwsr Stntisn Inservics Testing Pregram l .

i RELIEF REOUEST ,

. Number: RR-V13, Revision 0 (Sheet 1 of 3) ,

1 l SYSTEM: ResidualHeat Removal (RHR)

Core Spray (CS)

Reactor Core Isolation Cooling (RCIC) '

l High Pressure Coolant Injection (HPCI)

COMPONENTS:

Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

V10-36A C 2 G-191172 J-03 V10-36B C 2 G-191172 J V14-33A - C 2 G-191168 ' H-ll V14-33B C 2 G-191168 H-15

.V23-20B C 2 G-191169 Sh 1 - G-07 l

V13-20B C 2 G-191174 Sh 1 G-11 These valves are the Residual Heat Removal, Core Spray, High Pressure Coolant Injection and Reactor Core Isolation Cooling system keep-fill check valves. These valves have a safety function to close to isolate Safety Class 2 CS, RHR, RCIC or HPCI piping from the lower pressure non-safety grade i Condensate Transfer System piping in the event of a system actuation.

EXAM OR TEST CATEGORY:

Category C L CODE REOUIREMENT: Part 10-Para. 4.3.2.1 " Exercising Test Frequency"

" Check valves shall be exercised nominally every 3 months, except as provided by paras. 4.3.2.2, 4.3.23,4.3.2.4 and 4.3.2.5."

l l REOUEST FOR RELIEF: ,

p Reliefis requested on the basis that individual full stroke exercise testing in the closed direction on a 3 month, cold shutdown or refuel outage basis in accordance with OM-10 Para. 4.3.2.1 for these valves is burdensome and does not provide a compensating increase in safety, i

I

- Revision 19 Section 5 Page 171 of179

Vermont Yankee Nuclear Power Station Inservice Testing Program RELIEF REOUEST Number: RR-V13, Revision 0 (Sheet 2 of 3)

REOUEST FOR RELIEF (CONT.h These valves are Safety Class 2 one inch lift check valves located in the keep-fill pressurization lines for the RHR, CS, HPCI and RCIC piping systems. These valves are arranged in parallel downstream of a common non-nuclear safety Condensate Transfer supply check valve. The Vermont Yankee safety analysis does not require the non-nuclear safety Condensate Transfer check valve to perform a

. safety function in support of these systems. There are no test connections between the check valves or in any of the keep-fill pressurization lines.

The use of the series pair testing method suggested in NUREG 1482, subsection 4.1.1, " Closure Verification for Series Check Valves without Intermediate Test Connections," does not provide ,

positive verification of closure of the subject check valves due to their configuration.

Individual check valve closure capability verification is presently accomplished by performing quarterly non-intrusive (radiography) testing. Indication of valve closure has been conclusive.

However, this quarterly non-intrusive testing of the subject check valves during power operations has proven to be burdensome. Among the burdens imposed by this test method and frequency of testing are:

1. Increased personnel radiation exposure -- The transport, equipment setup, exposure and equipment removal account for approximately 400 mrem / year in increased personnel radiation dose. ,

i

2. Large manpower requirements - The administration of radiological controls, control of the radiographic source and posting of exclusion areas during exposures at times requires the 4 utilization of all available plant radiation controls personnel. The completion of all the radiographs typically requires two days each quarter.
3. Extensive test equipment setup - The setup of the radiographic equipment and shielding of

' adjacent plant equipment is repeated for each valve tested.

4. Potential for unexpected challenges to plant safety systems - The use of portable radioactive sources and their movements present the potential for unexpected challenges to plant safety ,

systems due to high radiation actuations. i It is expected that the performance of radiography during cold shutdowns would present the additional burden of obtaining contract services on short notice.

4

-It is also expected that performing radiography during refuel outages will present an added risk of increased radiation exposure to personnel as more people will be subject to possible exposure during refuel outages.

Revision 19 Section 5 Page 172 of179 y w -,. . - - - w + -_ ,. - -

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l Vermant Ycnkes Nuclur Pswer Stcti::n Inservice Testing Program l RELIEF REOUEST t

l Number: RR-V13, Revision 0 (Sheet 3 of 3)

REOUEST FOR RELIEF (CONT.):

Vermont Yankee has investigated several alternate test methods with the following results:

l 1. Disassembly and Inspection of each valve on a refuel outage basis in accordance with OM-10,

! Para. 4.3.2.4(c) - NRC guidance identified in Appendix A of NUREG 1482 (question group 15) and in a previously resolved Vermont Yankee IST Program Safety Evaluation anomaly discouraged the use of the disassembly and inspection method on the basis that disassembly is I

not a true substitute for opnability testing using flow.

2. Performing sample non-inausive testing with flow as described in NUREG 1482, subsection 4.1.2, " Exercising Check Valves with Flow and Nonintrusive Techniques" - It was determined that this testing method is not appliAle for these valves since the safety function of these  !

valves is to close on cessation or reversal of flow.

3. Use of other non-intrusive testing methods (ultrasonic, magnetic or acoustic) - Due to valve size, valve type and low flow rates through these keep-fill lines it is not expected that these methods would provide conclusive indication of valve closure.  :

l l ALTERNATE TEST METHOD:

Since the subject check valves are of simple design, operate under mild service conditions and the maintenance history for these valves indicates that they have not been susceptible to service induced failures or significant wear, Vermont Yankee proposes to perform non-intrusive testing (radiography) on each check valve once each operating cycle within 2 months of the scheduled start of the next refueling outage. Testing once each operating cycle but not during refuel outages (relief request required) will reduce the risk ofincreased radiation exposure to personnel as fewer people will be subject to possible exposure.

The alternate " disassembly and inspection" methods described in Generic Letter 89-04, Position 2, do not use actual check valve response to determine check valve operability and so are provided as a compromise. The proposed use of non-intrusive testing provides a test result that uses a direct observation of actual check valve operation in response to changes in system param'eters. The use of non-intrusive testing in this manner more closely approximates the intent of the code. Although the same testing burden exists, the reduction in test frequency from 6 times per operating cycle to once per j operating cycle will greatly reduce the risk of potential unexpecteo challenges to plant safety systems.

i USNRC EVALUATION STATUS Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-V13, Revision 0.

Revision 19 Section 5 Page 173 of179

V l Vermeet Ye2kea Nucl: r Pcwe Itstian Ins:rvics Testing Program l

l RELIEF REOUEST i

! Number: RR-V14, Revision 0 (Sheet 1 of 3) l SYSTEM: Core Spray (CS)

COMPONENTS:

l Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

l  ;

V14-22A C 2 G-191168 I-09 !

V14-22B C 2 G-191168 C-10 i V14-23A C 2 G-191168 I-09 !

V14-23B C 2 G-191168 C-10 i These valves are the Condensate transfer system to Core Spray flushing line check valves. These valves have a safety function to close to isolate the high pressure Safety Class 2 CS piping from the lower  !

pressure non-safety grade Condensate Transfer System piping in the event of a CS system actuation.

EXAM OR TEST CATEGORY:

Category C . l CODE REOUIREMENT: Part 10 Para. 43.2.1 " Exercising Test Frequency"

" Check valves shall be exercised nominally every 3 months, except as provided by paras.43.2.2, 43.23,43.2.4 and 43.2.5."

REOUEST FOR RELIEF:

Reliefis requested on the basis that individual full stroke exercise testing in the closed direction on a 3 month, cold shutdown or refuel outage basis in accordance with OM-10 Para. 43.2.1 for these valves is burdensome and does not provide a compensating increase in safety.

These valves are Safety Class 2 two inch lift check valves located in the flushing. lines between the Core Spray System and the Condensate Transfer System. These valves are arranged in series-pairs in each flushing line. During normal power operation these flushing lines are isolated. There are no test

,. connections between the check valves or in either flushing line.

!- The use of the series-pair testing method suggested in NUREG 1482, subsection 4.1.1, " Closure Verification for Series Check Valves without Intermediate Test Connections," does not provide

, positive verification of closure of the subject check valves due their configuration.

L Revision 19 Section 5 Page 174 of179

l Verment Yenkee Nucleir Power Strtion Inservice Testing Program j RELIEF REOUEST Number: RR-V14, Revision 0 (Sheet 2 of 3) l REOUEST FOR RELIEF (CONT.):

i Individual check valve closure capability verification is presently accomplished by performing  ;

quarterly non-intrusive (radiography) testing. Indication of valve closure has been conclusive.

However, this quarterly non-intrusive testing of the subject check valves during power operations

. has proven to be burdensome. Among the burdens imposed by this test method and frequency of testing are:

1. Increased personnel radiation exposure - The transport, equipment setup, exposure and equipment removal account for approximately 400 mrem / year in increased personnel radiation i dose. )
2. Large manpower requirements - The administration of radiological controls, control of the i radiographic source and posting of exclusion areas during exposures at times requires the utilization of all available plant radiation controls personnel. The completion of all the l radiographs typically requires two days each quarter.
3. - Extensive test equi'p ment setup -- The setup of the radiographic equipment and shielding of .

adjacent plant equipment is repeated for each valve tested.

4. Potential for unexpected challenges to plant safety systems - The use of portable radioactive sources and their movements present the potential for unexpected challenges to plant safety systems due to high radiation actuations.

It is expected that the performance of radiography during cold shutdowns would present the additional burden of obtaining contract services on short notice.

1 It is also expected that performing radiography during refuel outages will present an added risk of increased radiation exposure to personnel as more people will be subject to possible exposure during refuel outages.

l ' Vermont Yankee has investigated several alternate test methods with the following results:

1. Disassembly and Inspection of each valve on a refuel outage basis in accordance with OM-10,,

Para. 4.3.2.4(c) - NRC guidance identified in Appendix A ofNUREG 1482 (question group 15) l and in a previously resolved Vermont Yankee IST Program Safety Evaluation anomaly

~ discouraged the use of the disassembly and inspection method on the basis that disassembly is not a true substitute for operability testing using flow.

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- Revision 19 Section 5 Page 175 of179 s e --

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Verment Yenkee Nuclear Power Statien Inservice Testing Program RELIEF REOUEST Number: RR-V14, Revision 0 (Sheet 3 of 3)

REOUEST FOR RELIEF (CONT.h

2. . Performing sample non-intrusive testing with flow as described in NUREG 1482, subsection

' 4.1.2, " Exercising Check Valves with Flow and Nonintrusive Techniques" - It was determined that this testing method is not applicable for these valves since the safety function of these

~ valves is to close on cessation or reversal of flow.

ALTERNATE TEST METHOD:

Since the subject check valves are of simple design, operate under mild service conditions and the maintenance history for these valves indicates that they have not been susceptible to service ind' ed failures or significant wear, Vermont Yankee proposes to perform non-intrusive testing (radiography) on each check valve once each operating cycle.

The alternate " disassembly and inspection" methods described in Generic Letter 89-04, Position 2, do not use actual check valve response to determine check valve operability and so are provided as a compromise. The proposed use of non-intmsive testing provides a test result that uses a direct observation of actual check valve operation in response to changes in system parameters. The use of non-intrusive testing in this manner more closely approximates the intent of the code. Vermont

. Yankee proposes to perform non-intrusive testing (radiography) on each check valve once each operating cycle within 2 months of the scheduled start of the next refueling outage. Testing once each operating cycle but not during refuel outages (relief request required) will reduce the risk of increased radiation exposure to personnel as fewer people will be subject to possible exposure.

Although the same testing burden exists, the reduction in test frequency from 6 times per operating cycle to once per operating' cycle will greatly reduce the risk of potential unexpected challenges to plant safety systems.

USNRC EVALUATION STATUS Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-V14, Revision 0.

Revision 19 Section 5 Page 176 of179 l

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, Verment Yenkes Nuclear Power Station Inservice Testing Program l

l RELIEF REOUEST  !

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Number: RR-V15, Revision 0 (Sheet 1 of 3)

SYSTEM: Reactor Core Isolstion Cooling (RCIC)

! - High Pressure Coolant Injection (HPCI) -

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COMPONENTS:
Valve Number OM Cat. Safety Class Drawing Number Dwg. Coord.

1 V13-19 C 2 0-191174 Sh 1 E-14

__ V23-32 -C 2 G-191169 Sh 1 E-11 Valve V13-19 is the Condensate Storage Tank (CST) supply to RCIC Pump suction check valve. This I

. valve has a safety function to open to supply water from the CST to the RCIC pump suction. This valve also has a safety function to close to isolate the RCIC pump suction from the CST. When RCIC pump j suction automatically transfers from the CST to the suppression pool, there is a short time when all RCIC pump suction MOVs are open at the same time. V13-19 is the only containment boundary between the suppression pool and the CST during this transfer of RCIC pump suction. l Valve V23-32 is the CST. supply to HPCI Pump suction check valve. This valve has safety function to open to supply water from CST to the HPCI pump suction. This valve also has a safety function to I close to isolate the HPCI pump suction from the CST. When HPCI pump suction automatically l transfers from the CST to the suppression pool, there is a short time when all HPCI pump suction MOVs are open at the same time. V23-32 is the only containment boundary between the suppression pool and the CST during this transfer of HPCI pump suction.

EXAM OR TEST CATEGORY:

Category C CODE REOUIREMENT: Part 10

, Para. 4.3.2.1 " Exercising Test Frequency"

". Check valves shall be exercised nominally every 3 months, except as provided.by paras.4.3.2.2, 4.3.2.3,4.3.2.4 and 4.3.2.5."

REOUEST FOR RELIEF:

Reliefis requested on the basis that individual full stroke exercise testing in the closed direction on a 3 month, cold shutdown or refuel outage basis in accordance with OM-10 Para. 4.3.2.1 for these valves is burdensome and does not provide a compensating increase in safety.

Revision 19 Section 5 Page 177 of179

s Vcrmant Yankee Nuclezr Power Statisn . Inservice Testing Program RELIEF REOUEST Number: RR-V15, Revision 0 (Sheet 2 of 3)

REOUEST FOR RELIEF (CONT.h i

Individual check valve closure capability verification is presently accomplished by performing

. quarterly non-intrusive (radiography) testing as committed to in LER 96-01, Corrective Action #3.  ;

Indication of valve closure has been conclusive. However, this quarterly non-intrusive testing of the subject check valves during power operations has proven to be burdensome. Among the burdens imposed by this test method and frequency of testing are:

1. Increased personnel radiation exposure - The transport, equipment setup, exposure and equipment removal account for approximately 400 mrem / year in increased personnel radiation

' dose.

2. Large manpower requirements -- The administration of radiological controls, control of the radiographic source and posting of. exclusion areas during exposures at times requires the utilization of all available plant radiation controls personnel. The completion of all the radiographs typice.lly requires two days each quarter.
3. Extensive test equipment setup -- The setup of the radiographic equipment and shielding of adjacent plant equipment is repeated for each valve tested.
4. Potential for unexpected challenges to plant safety systems - The use of portable radioactive sources and their movements present the potential for unexpected challenges to plant safety systems due to high radiation actuations.

It is expected that the performance of radiography during cold shutdowns would present the additional burden of obtaining contract services on short notice.

It is also expected that performing radiography during refuel outages will present an added risk of

increased radiatbn exposure to personnel as more people will be subject to possible exposure during refuel outages.

Vermont Yankee has investigated several alternate test methods with the following results )

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1. Disassembly and Inspection of each valve on a refuel outage basis in accordance with OM-10,

. Para. 4.3.2.4(c) -- NRC guidance identified in Appendix A of NUREG 1482 (question group 15) and in a previously resolved Vermont Yankee IST Program Safety Evaluation anomaly discouraged the use of the disassembly and inspection method on the basis that disassembly is not a true substitute for operability testing using flow. l l

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Verm:nt Yetkee Nucle:r Power Station Inservice Testing Program RELIEF REOUEST Number: RR-V15, Revision 0 (Sheet 3 of 3) l REOUEST FOR RELIEF (CONT.):

2. Performing sample non-intrusive testing with flow as described in NUREG 1482, subsection 4.1.2, _" Exercising Check Valves with Flow and Nonintrusive Techniques" - It was determined that this testing method is not applicable for these valves since the safety function of these valves is to close on cessation or reversal of flow.

! ALTERNATE TEST METHOD:

Since the subject check valves are of simple design, operate under mild service conditions and the

. maintenance history for these valves indicates that they have not been susceptible to service induced failures or significant wear, Vermont Yankee proposes to perform non-intrusive testing (radiography) on each check valve once each operating cycle.

The alternate " disassembly and inspection" methods described in Generic Letter 89-04, Position 2, do not use actual check valve response to determine check valve operability and so are provided as a compromise. The proposed use of non-intrusive testing provides a test result that uses a direct observation of actual check valve operation in response to changes in system parameters. The use of non-intrusive testing in this manner more closely approximates the intent of the code. Vermont Yankee proposes to perform non-intrusive testing (radiography) on each check valve once each operating cycle within 2 months of the scheduled start of the next refueling outage. Testing once each operating cycle but not during refuel outages (relief request required) will reduce the risk of increased radiation exposure to personnel as fewer people will be subject to possible exposure.

Although the same testing burden exists, the reduction in test frequency from 6 times per operating cycle to once per operating cycle will greatly reduce the risk of potential unexpected challenges to plant safety systems.

i The commitment made by Vermont Yankee in LER 96-01, corrective action #3 to verify closure operability of V13-19 and V23-32 by performing quarterly radiography will be superseded upon approval of this reliefrequest.

USNRC EVALUATION STATUS Relief was granted in the January 1998 SER [ Reference (aa)] for Relief Request RR-V15, Revision 0.

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