ML20082C707

Rev 17 to IST Program Plan

ML20082C707
Person / Time
Site:	Vermont Yankee
Issue date:	03/22/1995
From:	Connolly J, Devincentis J, Trask T VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20082C696	List: ML20082C692 ML20082C707
References
PROC-950322, NUDOCS 9504070124
Download: ML20082C707 (177)

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INSERVICE TESTING PROGRAM PLAN l Vermont Yankee Nuclear Power Station 1 Commercial Service Date: November 29, 1972 j

'l Implementation Date: March 3',, 1995

. Revision 17 Prepared By: Reviewed By:

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$ptrxw Oi brMnNle 03-0 ?- W ZL, xs <~ . Of 2 4 &

. W . Connolly Plant IST CoordiMtor d T.C.4 rask Senior Mechanical Engineer Approved By:

hpM s ,_ 3 it'1I

.T4. 'DeVincentis B.R. BUteau ME&C Manager Engineering Director

$:*! O 3 2i' Plant Operations RevieTe

& S/Ttldf R g /. Wanczyk VU-Jhs/95 Committee P Mnt Manager 0 e' J/P. Pelletier Vice President - Engineering Vermont Yankee Nuclear Power Corporation Governor Hunt Road Vernon, Vermont 05354 i

9504070124 950331' PDR ADOCK 05000271

_ P, PDR

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. Revision Summary Revision Affected

, Number Pages Summary n

13 .All Third Ten-Year Interval Update. l t

14 5-14, 5-15 Revise. valve' listing for Diesel I Generator Starting Air System l to reflect changes made under '

PDCR 92-18, DCN 1. Minor revisions.

15 Cover, 1-1, Revise to reflect Tech Spec 1-2, 2-5, 3- Amendment No. 138, EDCR 92-404,.

1, 3-2, 4-1 EDCR 93-404, PDCR 92-016,-PDCR to.4-5,~4- 92-018, CARS 93-70 and 94-06, 10, 4-12, 4- PRO 94-18, items identified 14, 4-17, 4- during revisions to implementing procedures, 19, 4-21 to 4-23, 4-25, current status of each Relief

4-29, 5-1,~ Request per.USNRC SERs 5-3 to 5-11, (References (s) and (u)], and ,'

5-13 to 5- minor revisions.

20, 5-22 to l 5-30, 5-32 to 5-34, 5- 3 36 to 5-71,  ;

5-74 to 5- "

84, 5-87, 5- I 88, 5-91 to 5-94, 5-98 to.5-98b, 5-100, 5-102, j

5-105, 5-107, 5-113, t 5-115, 5-117, 5-119, '

5-122 to 5-124, 5-126

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Revision Summary Revision Affected Number Pages Summary l

16 Cover,4-3, Revise to reflect changes made 4-7 to 4-10, due to the responses to the ,

4-30, 4-31, USNRC Safety Evaluation Report 1 5-5, 5-7 to issued on September 3, 1994, 5-11, 5-17, Alternate Cooling Water System 5-19, 5-20, additions, items identified 5-27, 5-34, during the implemenation of the 5-36, 5-38 program, current status of each to 5-41, 5- relief request and correction 43, 5-52, 5- of typographical errors.

53, 5-56 to 5-59, 5-60, 5-68, 5-77, 5-83 to 5-84, 5-89 to j 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, Revise c,0 a', low the use of the 5-129 & 5- sampling disassembly technique 130 for V70-43A and V70-43B in accordance with the guidance specified in USNRC Generic-Letter 89-04, Staff Position 2.

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b Table of Contents f Section' Pace i

1.0 . Introduction .1-1 ,

1.1 Purpose 1-1 1.2- Discussion 1-l' ,

E 2.0 Program Plan Description. 2-1 2.1 Justifications 2-l' 2.2 Relief Requests 2-2 2.3 Flow Diagrams- 2-3 0 Table 2-1:

List of Inservice Testing Flow Diagrams 2-4' 3.0 References 3-1 4.0 Pump Inservice Testing Program Plan' 4-1 ,

'4.1 Scope 4 -l' 4.2 Pump Program Listing 4-1 Table 4-1:' Pump Listing.

4 l 5 Table 4-2: Pump Quantitative Values 4-6 4.3 Pump Relief Requests 4-7 i 5.0 Valve Inservice Testing Program Plan 5-1 5.1 Scope 5 Valve Program Listing 5.2 5-2 Table 5-1: Valve Listing 5-7 5.3 Valve Notes 5-67 5.4 Valve Cold Shutdown. Justifications' 5-69 5.5 Valve Refueling Outage Justifications 5-85 5.6 Valve Relief Requests 5-113

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~ 1. 0 - Introduction

~ l 1.1- Purpose

The Third-Interval. Vermont Yankee Inservice Testing (IST).

Program' establishes l testing requirements to assess the p- , opera 91onal' readiness of certain Safety Class 1, 2, and 3'  ;

pumps and valves which are required to: j i

a). Shut down the reactor to the cold shutdown condition, l

b) Maintain the reactor in the cold shutdown condition, or I i

c).- Mitigate the consequences of design-basis accidents. ,

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

4 The Third-Interval IST Program is part of the Vermont YankeeL j

component Testing Program.  ;

Discussion 1.2

]l The Third-Interval Vermont Yankee IST Program was developed lin:

accordance with the requirements of the 1989 Edition of. i 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 provides compliance with Vermont Yankee

,y 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(b) (2) (viii), the Jnunp and valve testing requirements  !

~ were based on the ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI'OM- l 1987, " Operation and Maintenance of Nuclear Power Plants". ,

The additional requirements described in 10 CFR l

50. 55a (b) (2) (vii) 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 l to ASME/ ANSI OM-1987, with the additional' requirements, was' submitted by Vermont Yankee and approved by the USNRC- i (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-- l 1987 unless otherwise specified.

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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 j requirements.

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) .

-The USNRC. Safety Evaluations-for the Third-Interval Vermont ,

Yankee IST Program are provided in-References.(s) and (u). 1

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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 Justifications In accordance with Paragraph 4.2.1.2 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 (f), (g) and (h) of Part 10 of the Code.

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

l XXJ: CSJ for Cold Shutdown Justifications, l 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).

2: Revision Status.

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'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 TestingLProgram' Plan.

Key features common to both Program Plans are: the Pump and  ;

Valve Listings that define the scope of the Third-Interval IST- i Program,. Cold Shutdown and Refueling Outage Justifications, Relief Requests,'and applicable Notes.

Administrative and implementing procedures, reference values, ,

testLresults, and other records required to define and execute the Third-Interval IST Program are retained at Vermont. Yankee.

j 2.1 Justifications In accordance with Paragraph 4.2.1.2 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 i

.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. j Valves tested during Cold Shutdowns or Refueling Outages shall be scheduled and tested in accordance with Paragraphs 4.2.1.2~ ,

(f), (g) and (h) of Part 10 of the Code. i Cold. Shutdown and Refueling Outage Justifications are numbered  ;

in a "XXJ-VNN, Revision 5" format, where: i XXJ: C8J for cold Shutdown Justifications,  !

ROJ for Refueling Outage Justifications. j V: for valves. ]

NN: A unique sequential number, (e.g.'CSJ-V03, Rev 0, )

would be the third Cold Shutdown Justification for:  ;

Valves). i 2: Revision Status.

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' 2. 2 Relief Requests 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 been. determined to be impractical, 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 I unusual difficultyfwithout a compensating increase in the f

' level of quality and-safety, alternate testing is proposed-that would provide useful information to' assess the operational readiness.of~the component tested.

The ReliefLRequests define the component (s) and test (s)

' involved,;the basis for. relief, the proposed alternate .

testing, and the-status of the USNRC evaluation to-the Relief Request.

If testing requirements are determined to betimpractical-l during:the course'of.the interval, additional or modified.

L Relief Requests will'be' submitted in accordance with 10 CFR ll 50.55a(f) (4) (iv) .

Relief Requests are numbered in a "RR-YNN, Revision-5" format, where:

L RR: for Relief Request.

Y: . P for Pumps, Y for. Valves.

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

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2.3 Flow Diagrams i

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 i 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 procedure AP 0014,

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

"For Information Only" copies of the Flow Diagrams.shall be g provided with each USNRC Submittal. The copies shall be  ;

f 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.

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Table 2-1 [;

LIST OF INSERVICE TESTING FLOW DIAGRAMS

-(sorted by flow diagram number).  ;

Flow Diagram System .

Name Number G-191155' Piping and Instrument Symbols G-191159 Sh 1 Service Water System' G-191159 Sh 2 Service Water System G-191159 Sh 3 RCW Cooling Water System .

G-191159 Sh 5 Recirculation Pump Cooling Water G-191160 Sh 3 Instrument Air System G-191160 Sh 4 Instrument Air System G-191160 Sh 6 Service Air System G-191160 Sh 7 Diesel Generator Starting Air System ,

i G-191160 Sh 8 Instrument Air System G-191162 Sh 2 Fuel Oil - Miscellaneous Systems

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G-191165 Sampling System G-191167 Nuclear Boiler G-191168 Core Spray System G-191169 Sh 1 High Pressure Coolant Injection System  !

G-191169 Sh 2 High Pressure Coolant Injection System l G-191170 Control Rod Drive Hydraulic System G-191171 Standby Liquid Control System  ;

i G-191172 Residual Heat Removal System G-191173 Fuel Pool Cooling & Cleanup System g- Revision 13 2-4

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LIST OF INSERVICE TE8IING FLOW DIAGRAMS (sorted by flow diagram number) l l

Flow Diagram System ]

Number Name i

G-191174 Sh 1 Reactor Core Isolation. Cooling System I

G-191174 Sh 2 Reactor Core Isolation Cooling System G-191175 Sh 1 Primary Containment & Atmosphere Control -

G-191177 Sh 1 Radwaste Systems  :

G-191178 Sh 1 Reactor Water Clean Up System G-191237 HVAC - Turbine, Service & Control Room Building ,

G-191238 HVAC - Reactor Building i G-191267 Nuclear Boiler Vessel Instrumentation VY-E-75-002 Containment Atmosphere Dilution System  !

5?20-271 Neutron Monitoring System ,

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!3.e ' References a) License No. DPR-28 (Docket No. 50-271).-

i b) United. States code.of Federal Regulations,. Title 10 Chapter 1,1Part 50, Section 50.55a (57FR34666, dated' August 6, 1992).

c) ASME Boiler and Pressure Vessel Code,lSection XI,,

Division 1, " Rules for Inservice-Inspection of Nuclear Power. Plant. Components," 1989 Edition.'

d) ASME/ ANSI Standsrd OMa-1988 Addenda'to~ASME/ ANSI OM-1987,.

C " Operation and liaintenance of Nuclear' Power Plants".

e) Letter, Mr. P.M. Sears,.USNRC, .to Mr. L.A. Tremblay, VYNPC, " Vermont Yankee Nuclear Power Station,zApprovallof 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.

g) Letter, 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.LMurphy, 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 Light 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.

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.1)" Letter, Mr. ' R.W. Reid, USNRC, l to ' Mr. R.H. Groce, YAEC, "NRC Staff; Guidance.for Preparing-Pump.and Valve Testing,  !

2 Program' Descriptions and Associated-Relief Requests j i

'" L Pursuant ; to 'li0 ,CFR 50. 55a (g) , " . dated January 10,-1978.

m) Letter, . Mr. - R.W. . Reid,' USNRC, to Mr..R.H. Groce, YAEC,.

." NRC Staff-Guidance for Complying with Certain Provisions j

of'10 CFR 50.55a(g), ' Inservice Inspection Requirements',"Jdated' November 17,11976. .!

n) ' Vermont Yankee Final-Safety Analysis Report.

1 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- l Corporation Third-Interval Inservice Testing Program Plan j and Safety' Evaluation Responses," BVY 92-133, dated  ;

November 30, 1992.  !

r) Letter, Mr. D.H. Dorman, USNRC, to Mr. J.P.'Pelletier, j VYNPC, " Relief from the ASME Section XI Requirement to j!

U'p date . (On a 120-Month Interval)- the Inservice Inspection .

and Testing Programs at Vermont Yankee (TAC No. M85067) , "- ,;

NVY 93-031, dated April 6, 1993. j i

s) Letter, Mr. D.H. Dorman, USNRC, to Mr. D.A. Reid, VYNPC,

" Safety Evaluation of the Inservice Testing Program ~ j Relief Requests for Pumps and Valves, Vermont Yankee-Nuclear Power Station (TAC No. M8 5067) , " ' NVY : 93-151, ,

dated September 3, 1993. l t) Letter, Mr. D.A. Reid, VYNPC, to Document Control Desk,.  :

USNRC, " Proposed Change No. 168 to the Vermont Yankee: .i Technical Specifications - Auxiliary Electric Power l 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 . l License No.-DPR-28, Vermont Yankee Nuclear Power Station 'l (TAC No. MS7171) , " NVY 94-45, dated March 22, 1994.

v) Letter, Mr. D.H. Dorman, USNRC to Mr. D.A. Reid', Safety. ,

Evaluation of the Inservice Test Program Relief Requests  :)

for Pumps and Valves, Vermont Yankee Nuclear Power-Station (TAC No. M85067).

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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, b) Maintain the reactor in the cold shutdown condition, or c) Mitigate the consequences of design-basis accidents.

t 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-Interval Pump IST Program.

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

Pump Number The unique number that identifies the pump. The pump number corresponds to the MPAC Database utilized at Vermont Yankee. ,

Table 4-1 is sorted by Pump Number. i l

Function The common name for the pump. 1 i

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

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

H the pump appears.

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safety Class The safety classification of the pump, as' determined.in ,

accordance with. procedure AP 0014, " Safety Class Determination- l n

Instructions," and the Vermont Yankee Safety Classification E Manual.

Pump Type The pump type:

s CENT for Centrifugal pumps.

L "7ERT for Vertical line shaft pumps.

PD-RECIP- for Positive Displacement Reciprocating pumps.

PD-ROT for Positive Displacement Rotary pumps..

Test Type The Incervice Test Parameters to be determined and recorded 1 during testing performed in accordance with Paragraph 5 of Part 6 of the Code. The abbreviations correspond to those provided in Table 2 of Part 6 of the Code:

N for Speed, (if variable speed).

dP for differential Pressure, (for centrifugal and I vertical line shaft pumps).

P for discharge Pressure, (for positive displacement pumps). -

Q for Flow Rate.

Yd for Vibration, displacement, peak-to-peak.

Yv for vibration, velocity, peak.

Test Freq The test frequency associated with each test type. The abbreviations correspond to those provided in Reference (m):

t Cs for cold shutdown OC for Once Per Operating cycle i Q for Quarterly RR for Reactor Refueling Outage Relief Request l The Relief Request number associated with the subject pump and test type or test frequency, where applicable.

Remarks 7 Clarifying comments or other remarks related to the subject pump and test type or test frequency, where applicable.

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Table 4-1 Pump Listing 7 T

.Dwg Safety Pump Test Test Relief Pump Number Drawing No coor Class Type Type Freq Request Remarks .;

>- P7 1A ~ G 191159 Sh 1 C 02 3 VERT Q Q ER-P01 See Table 4 2 Q RR RR-P01 vv 'O '

dP - Q Function : Service Water Puup -

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. P71B G 191159 Sh 1 B-02 3 VERT Q Q .RR-P01 See Table 4 2 i Q RR RR-P01 Vv Q dP Q .

Function : Service Water Pump P7-1C G-191159 Sh 1 1 03 3 VERT Q Q RR-P01 See Table 4-2 +

Q RR RR-P01  ;

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dP Q Function Service Water Pump ,

P7 10 G-191159 Sh i H-03 3 VERT Q Q RR-P01 See Table 4-2 0 RR RR-P01 Vv Q dP Q function : Service Water Pump t P8 1A G-191159 Sh 1 J-12 3 VERT Q Q See Table 4-2  ;

Vv Q  !

dP Q Function RHR Service Water Pupp l P8-18 G 191159 Sh 1 1-12 3 VERT Q Q See Table 4 2  ;

Vv 0 j dP Q i

Function : RHR Service Water Pump

............................................................................................................ l P8-1C G 191159 Sh 1 B 12 3 VERT Q Q See Table 4-2 .

Vv -Q dP Q ,

Function RHR Service Water Pump _ _l P8 1D G 191159 Sh 1 A 12 3 VERT Q Q See Table 4 l

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i dP Q' i Function : RMR Service Water Pump P10 1A G-191172 L 05 2 CENT Q Q See Table 4 2 .i Vv Q- 3 dP. 0 +

Function : Residual Heat Removal Pump P10 1B G-191172 L 12 2 CENT Q Q See Table 4-2 -

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Table 4-1 Pump Listing Dwg Safety Pump Test Test Relief Pump Nunber Drawing No Coor Class Type Type Freq Request Remarks P10 1C G 191172 J 05 2 CENT Q Q See Table 4 2 Vv Q

@ Q Function : Residual Heat Removal Punp P10 1D G-191172 J-12 2 CENT Q Q See Table 4-2 vv 0 dP Q Function : Residual Heat Removal Punp P19*2A G 191173 G 11 3 CENT Q Q Yv Q dP Q Function StancR>y Fuel Pool Cooling Punp P19-2B G-191173 H-11 3 CENT Q Q VV Q dP Q Function : Standby Fuel Pool Cooling Pump P44-1A G-191169 Sh 2 G-11 2 CENT N Q See Table 4 2 Q Q RR P02 VV Q RR-PO4 dP Q RR-P02 RR P03 Function : High Pressure Coolant Injection HP Pump P44-1B G-191169 Sh 2 G 08 2 CENT N Q See Table 4 2 0 0 RR P02 Vv Q dP Q RR P02 RR-P03 function High Pressure Coolant Injection Booster Pump P45 1A G-1911T H 08 2 PD- Q Q See Table 4 2 RECIP Vv 0 P Q Function : Standby Liquid control Purp P45 1B G 191171 J-08 2 PD- Q Q See Table 4-2 RECIP Yv Q P Q Function Standby Liquid Control Punp P46-1A G 191168 J 11 2 CENT Q Q See Table 4-2 Yv Q

@ Q RR P05 Function : Core Spray Purp P46 1B G 191168 J-14 2 CENT Q Q See Table 4 2 Vv Q dP Q RR-P05 Function : Core Spray Pump

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s Table 4-1 Pump Listing Dwg Safety Pump Test Test Relief Ptap Nuuber Drawing No coor Class Type Type Freq Request Remarks

. P47 1A ' G 191174 Sh 2 F.08 2 CENT N Q See Table 4 2 0- Q VV Q dP Q RR P06 Function

• Reactor Core Isolation Cooling Pump P5941A G-191159 Sh 3 A-07 3 CENT Q Q Vv Q dP Q RR P08 Function : Reactor Building Closed Cooling Water Ptap P59 1B G-191159 Sh 3 8 07 3 CENT Q Q Vv Q dP Q RR P08 Function : Reactor Building Closed Cooling Water Putp P92 1A G 191162 Sh 2 E 05 3 PD ROT Q Q RR-P09 Q OC RR-P09 Vv 0 P Q Furetion : Diesel Fuel Oil Transfer Pump P92 1B G 191162 Sh 2 D-05 3 PD ROT Q Q RR P09 0 OC RR-P09 Vv Q P Q Function : Diesel Fuel Oil Transfer Puup SP.1 G.191237 l 11 3 CENT Q Q Vv Q '

dP Q Function Control Room HVAC Chilled Water Ptap I Revision 15 4-5

i Table 4-2 Pump Quantitative Values In addition to the reference values and allowable ranges established in accordance with Paragraphs 4.3 and 6.1, respectively, of Part 6 of the Code, the below quantitative values are established based on the Vermont Yankee Technical Specifications.

If these values cannot be met, the pump shall be declared inoperative. r Pum/ System Mininun Flow Requirements Flow Path Operability Frequency PT 1A-D SW 2700 GPM against a TDH of Normal system lineup Per Paragraph 5 of 250 feet Part 6 P8-1A-D RHRSW 2700 GPM at 70 PSIA Normal system lineup Per Paragraph 5 of i Part 6 P10 1A-D RHR 7450 e 150 GPM Vessel to Vessel Each Refuelfrg Outage P44 1A/B HPCI 4250 GPM at normal reactor Recirculate to once per operating operating pressure Condensate Storage Tant- Cycle P45 1A/B SLC 35 GPM at 1275 PSIG Recirculate to Test Tank Per Paragraph S of i using Demineralized Part 6 Water P46-1A/B CS 3000 GPM against a system Torus to Torus Each Refueling Outage head of 120 PSIG  :

P47-1A RCIC 400 GPM at normal reactor Recirculate to Per Paragraph 5 of operating pressure Condensate Storage Tank Part 6 Pressure measured at the RHR heat exchanger service water outlet when the corresponding pairs of RHR service water pumps and l station Service Water pumps are operating. .

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4 Revision 13 4-6

RELIEF REQUEST Number: RR-P01, Revision 1 (Sheet 1 of 4) ,

SYSTEM: Service Water COMPONENTS:

Safety Dwg Pump Number Class Drawing Number Coor P7-1A 3 G-191159 Sh 1 C-02 P7-1B 3 G-191159 Sh 1 B-02 P7-1C 3 G-191159 Sh 1 I-03 P7-1D 3 G-191159 Sh 1 H-03 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 provide an inexhaustible supply of water for standby coolant system operation.

EXAM OR TEST CATEGORY:

Flow Rate (Q).

CODE REOUIREMENT: Part 6 ,

Para. 5.1 " Frequency of Inservice 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."

Revision 16 4-7 1 1

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RELIEF REQUEST l

Number: RR-P01, Revision 1 (Sheet'2 of 4) j I

REQUEST FOR RELIEF:

Relief is requested on the basis that compliance with the code requirements is impractical and that:the proposed alternatives  ;

would provide an acceptable level of quality and safety.

j During normal operations, neither differential pressure nor flow ,

rate can be fixed or directly measured. Pump vibration levels i l

may also vary due to the inability to establish a repeatable ,

reference condition.

l' The four Service Water pumps are vertical, two-stage,  !

. centrifugal-type pumps which are submerged in and take suction l from the Connecticut River. They supply all the station Service i Water System requirements. The station Service Water System is a l dual header system using two parallel headers each containing two

pumps. The two parallel headers supply both the turbine and ,

i i reactor auxiliary equipment, including the Residual Heat Removal l 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- i 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 i flow control valves used to independently regulate the cooling provided to the various turbine and reactor auxiliary equipment. t Due to seasonal variations in Connecticut River water temperature ,

and level and constantly changing heat loads, the system l resistance and flow rate vary. The number of station Service Water pumps in operation is also varied dependent on system requirements. Due to these variations and the need to maintain.

proper cooling, it is considered impracticable to establish r repeatable reference values during quarterly inservice testing.

1 As a result, it is impracticable to directly measure pump flow rate on a quarterly and cold shutdown frequency. Sufficient straight sections of piping are required to properly measure flow '

rate, through the use of either permanently or temporarily installed instrumentation, such as non-intrusive flow measurement devices.

3 Revision 16 4-8 1

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RELIEF REQUEST Number: RR-P01, Revision 1 (Sheet 3 of 4)

REOUEST FOR RELIEF (con' t) :

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 I 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 l 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 i station Service Water System supplied by the pump being tested.

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 pu np 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.

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 compared to the degree possible with test data taken during the refueling outage head curve data.

Revision 16 4-9 l

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RELIEF REOUEST Number: RR-P01, Revision 1 (Sheet 4 of 4)

ALTERNATE METHOD (con't)1 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. This 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 I pump at a dead head condition where pump vibration and differential pressure can be measured for comparison in the event l

that maintenance is required to be performed between refueling outages.

1 Additionally, a head curve will be generated each refueling i outage to provide information so that the performance of the pump I can be compared to the degree possible with the an-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.

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

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

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

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

USNRC EVALUATION STATUS:

Provisional relief was granted in the September 1993 SER

[ Reference (s)] for Relief Request RR-P01, Revision O. Approval of Revision 1 of Relief Request RR-P01, is pending.

Revision 16 4-10

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

SYSTEM: High Pressure Coolant Injection COMPONENTS: ,

t Safety Dwg Pump Number Class Drawing Number Coor P44-1A 2 G-191169 Sh 2 G-11 P44-1B 2 G-191169 Sh 2 G-08 p

I P44-1A and P44-1B are the High Pressure Coolant Injection (HPCI) main (high pressure) and booster (low pressure) pumps, respectively. They have the safety functions to operate in

. series to 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 i and isolation.

EIAM OR TEST CATEGORY:

Differential Pressure (dP) .

Flow Rate (Q).

CODE REOUIREMENT: Part 6 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."

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 the method used to reduce the data."

) Revision 13 4-11

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

REQUEST FOR RELIEF:

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

i There is no means of measuring the differential pressure or the  ;

flow rate generated by each of these pumps individually.  ;

Installation of independent means of measurement for each pump is considered impracticable and would be costly and burdensome to i Vermont Yankee.

ALTERNATE METHOD:

Differential pressure and flow rate parameters will be measured across both HPCI pumps as an integral unit. Vibration monitoring

• i will be performed for each pump individually. Both pumps will be l inspected and repaired as necessary if any abnormal conditions in ,

differential pressure or flow rate occur.

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USNRC EVALUATION STATUS:.

This Relief Request is first submitted under Revision 13 to the IST Program Plan. l I

In addition, these testing techniques are consistent with those previously approved by the NRC [ Reference (s), Enclosure 1, Section 2.3].

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w' RELIEF REQUEST RNumber: RR-P03, Revision 0 (Sheet 1 of 2)

SYSTEM: High Pressure Coolant Injection i COMPONENTS:

Safety .

Dwg Pump Number Class Drawing Number Coor P44-1A 2 G-191169 Sh 2 G-11 P44-1B 2 G-191169 Sh 2 G-08 i

P44-1A and P44-1B are the High Pressure Coolant Injection (HPCI) main (high pressure) and booster (low pressure) pumps, i respectively. They have the safety functions to operate in series to 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.  :

nrkM OR TEST CATEGORY:

Differential Pressure (dP).

CODE REQUIREMENT: Part 6 Para. 4.6.1.2(a) " Range" i "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 '

i that provides direct measurement of pressure  !

difference or the difference between the pressure l at a point in the inlet pipe and the pressure at a  !

point in the discharge pipe, may be used."

9 Revision 13 4-13 l

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RELIEF REQUEST Number: RR-P03, Revision 0 (Sheet 2 of 2)

REQUEST FOR RELIEF: t Relief is requested on the basis that the proposed alternatives would provide an acceptable level of quality and safety.

Differential pressure across the HPCI 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 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 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 = 70 psig).

The suction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure.

The installed gauges are calibrated to within +/- 1.58% accuracy (FS), thus.the maximum variation in measured suction pressure due to inaccuracy would be +/- 1.34 psi. This is considered to be suitable for determining that adequate NPSH is available for HPCI pump operaticn.

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 +/- 1.34 psi represents an error in differential pressure measurement of +/- 0.11% (1.34 psi /1144 psid = 0.0012). This is consistent with Table 1 of Part 6 of the Code, which requires that instrument accuracy for differential pressure he 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 September 1993 SER [ Reference (s)) for Relief Request RR-P03, Revision O.

Revision 15 4-14 i

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RELIEF REQUEST Number RR-P04, Revision 0 (Sheet 1 of 3)  !

SYSTEM: High Pressure Coolant Injection 1

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COMPONENTS; j i

I Safety Dwg Drawing Number Coor I Pump Number Class P44-1A 2 G-191169 Sh 2 G-11

( P44-1A 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 f

small break loss of coolant accident, and 2) reactor pressure  !

j control during reactor shutdown and isolation.

EXAM OR TEST CATEGORY:

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Vibration Velocity (Vv).

CODE REQUIREMENT: Part 6

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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 1 the limits given in Table 3 and corrective action {

taken as specified in para. 6.1." ]

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Revision 13 4-15 1

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RELIEF REQUEST Number: RR-P04, Revision 0 (Sheet 2 of 3)

REOUEST FOR RELIEF:

Relief is 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.

The 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.

An additional past contributor to the higher vibration levels was the excitation resulting from the 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 HP pump vibration levels remain higher than the acceptance criteria stated in Table  :

3 of Part 6 of the Code.

Although existing vibration levels in the HP pump are higher than standard acceptance criteria, they are acceptable and reflect the unique operating characteristics of the HPCI pump. It has been concluded that there are no major vibrational concerns that would prevent the HPCI pump from performing its intended function.

Revision 13 4-16

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RELIEF REQUEST Number RR-PO4, Revision 0 (Sheet 3 of 3)

ALTERNATE METHOD:

To allow for practicable vibration monitoring of the HPCI HP pump, alternate vibration acceptance criteria are required. Full ,

spectrum vibrational monitoring will be performed during each quarterly test and the following criteria will be used fo" the HP pump:

Test Parameter Acceptable Rance Alert Rance Reauired Action Ranae ,

Vv s 2.5VI > 2.5Vr to and ) 6VI but not including 6VI or > 0.70 in/sec

> 0.675 in/sec but not

> 0.70 in/sec In addition, the resonance peaks will be evaluated during each test and will have an Acceptable Range upper lileit of 1.05 Vr and an Alert Range upper limit of 1.3 Vr.

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

USNRC EVALUATION STATUS:

l Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-PO4, Revision O.

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Revision 15 4-17 I

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t RELIEF.. REQUEST  :

Number: .RR-P05,-Revision 0 (Sheet 1 of 2)

SYSTEM Core Spray -

COMPONENTS: ,

Safety Dwg Pump Number Class Drawing Number Coor l P46-1A 2 G-191168 J-11 P46-1B 2 G-191168 J-14 P46-1A & 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:

Differential Pressure (dP).

CODE REQUIREMENT: 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 pressureLacross a i

pump, a differential pressure gauge or transmitter that provides direct measurement of pressure 4 difference or the difference between the pressure i at a point in the inlet pipe and the pressure at a j

, point in the discharge pipe, may be used."  ;

l Revision 13 4-18 ll I - . . . . _ _

RELIEF REQUEST Number: RR-POS, Revision 0 (Sheet 2 of 2)

REQUEST FOR RELIEF:

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

1 Differential pressure across the Core Spray pumps is determined j by the difference between pressure measurements taken at a point l 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 l sufficient for a post accident condition when the suppression j chamber is at the maximum pressure. This, however, exceeds the +

l' 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 j the Code (Value = approximately 7.5 psig, Limit = 22 psig).

The suction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure.

The installed gauges are calibrated to within +/- 2.0% accuracy ,

(FS), thus the maximum variation in measured suction pressure due  !

to inaccuracy would be +/- 1.2 psi. This is considered to be 1 suitable for determining that adequate NPSH is available for Core l Spray pump operation.

Pump discharge pressure during testing is approximately 240 psig,  ;

which results in a calculated differential pressure of i approximately 232.5 psig. The resulting inlet pressure  ;

inaccuracy of +/- 1.2 psi represents an error in differential l pressure measurement of +/- 0.5% (1.2 psi /232.5 psid = 0.0052). j This is consistent with Table 1 of Part 6 of the Code, which i requires that instrument accuracy for differential pressure be l better than 2% of full-scale. l l

ALTERNATE METHOD:

Differential pressure will 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-PO5, Revision O.

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y Revision 15 4-19 l 1

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J t RELIEF REQUEST Number: RR-P06, Revision 0 (Sheet 1 of 2)

SYSTEM: Reactor Core Isolation Cooling COMPONENTS:

Safety Dwg Pump Number Class Drawing Number Coor i P47-1A 2 G-191174 Sh 2 F-08

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P47-1A 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 of radioactive materials to the environs as a result of inadequate core cooling.

EXAM OR TEST CATEGORY:

Differential Pressure (dP).

CODE REQUIREMENT: 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."

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) Revision 13 4-20

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RELIEF REQUEST l l

Number: RR-P06, Revision 0 (Sheet 2 of 2)

REOUEST FOR RELIEF:

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

Differential pressure across the RCIC pump is determined by the difference between pressure measurements takan 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 oper ating 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 i the Code (Value = approximately 20 psig, Limit = 60 psig). [

The suction pressure measurement is used to verify prescribed [

NPSH requirements and to determine pump differential pressure.

The installed gauges are calibrated to within +/- 1.58% accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be +/- 1.34 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  :

i psig, which results in a calculated differential pressure of approximately 1110 psig. The resulting inlet pressure inaccuracy of +/- 1.34 psi represents an error in differential pressure measurement of +/- 0.12% (1.34 psi /1110 psid = 0.0012). This is consistent with Table 1 of Part 6 of the Code, - 'tich requires ,

that instrument accuracy for differential press are be better than 2% of full-scale.

ALTEltNATE METHOD:

' Differential pressure will 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-P06, Revision O.

Revision 15 4-21

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RELIEF REQUEST -

i Numbers RR-P07, Revision 0-(Sheet'1 of 2) r BYSTEM: Reactor Building Closed Cooling Water ,

i COMPONENTS: ,

Safety Dwg .

Pump Number Class Drawing Number Coor ,

P59-1A 3 G-191159 Sh 3 A-07 P59-1B 3 G-191159 Sh 3 B-07 i

These pumps are the Reactor Building Closed Cooling Water (RBCCW) pumps. They have a safety function to provide cooling water to ,

the safety related cooling loads served by the RBCCW system.

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

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i Revision 15 4-22 o _ . _ _

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RELIEF REQUEST Number 'RR-P07, Revision 0 (Sheet-2 of-2)

THIS RELIEF REQUEST WAS DELETED IN REVISION 15 OF THE IST -1

. PROGRAM.

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r Revision 15 4-23

t RELIEF REQUEST mumber: RR-P08, Revision 0 (Sheet 1 of 2)

SYSTEM: Reactor Building Closed Cooling Water COMPONENTS:

r Safety Dwg Pump Number Class Drawing Number Coor P59-1A '3 G-191159 Sh 3 A-07 P59-1B 3 G-191159 Sh 3 B-07 i

i These pumps are the Reactor Building Closed 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 REQUIREMENT: 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."

i Revision 13 4-24 I

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RELIEF REQUEST l i

l Number: RR-POS, Revision 0 (Sheet 2 of 2) l REOUEST FOR RELIEF:

Relief is requested on the basis that the proposed alternatives would provide an acceptable level of quality 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 l 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).

The suction pressure measurement is used to verify prescribed j NPSH requirements and to determine pump differential pressure. l The installed gauges are calibrated to within +/- 0.4% accuracy i (FS), thus the maximum variation in measured suction pressure due i

.12 psi. This is considered to be j to inaccuracy would be +/

suitable for determining that adequate NPSH is available for j" 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 pei/73.5 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 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 September 1993 SER [ Reference (s)] for Relief Request RR-P08, Revision O.

Revision 15 4-25

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

SYSTEM: Diesel Fuel Oil COMPOMENTS: 9 Safety Dwg Pump Number Class Drawing Number Coor a

P92-1A 3 G-191162 Sh 2 E-05 P92-1B 3 G-191162 Sh 2 D-05 i 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  ;

tank during Emergency Diesel Generator operations.

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EXAM OR TEST CATEGORY:

Flow Rate (Q).

i CODE REQUIREMENT: 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 include the method used to reduce the data."

Para. 5.1 " Frequency of Inservice 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."

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Revision 13 4-26 L

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RELIEF REOUEST Number: RR-P09, Revision 0 (Sheet 2 of 4)

REOUEST FOR RELIEF:

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.

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

Makeup to each diesel day tank is accomplished 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 of approximately 3.4 gpm. The Diesel Fuel Oil Transfer pumps are positive displacement pumps with a design capacity of approximately 8.7 gpm.

It is considered impracticable to directly measure pump flow rate on a quarterly basis. There is no flow rate instrumentation installed in the Fuel Oil Transfer system. Sufficient straight sections of piping are required to properly measure flow rate, through the use of either permanently or 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 redesign and modification, which would be costly and burdensome to Vermont Yankee.

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 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 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 Diesel Generator.

> Revision 13 4-27

]

RELIEF REQUEST l l

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

REOUEST FOR RELIEF fcon'tLi 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, j 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 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. ,

Such testing is considered commensurate with the pump type and ,

service and provides an acceptable level of quality and safety, based on the following:

Revision 13 4-28

l RELIEF REQUEST -I Number: RR-P09,, Revision 0 (Sheet 4 of 4) 1 ALTERNATE METHOD (con' tit j 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 pumps is still assured with up to 60 percent i degradation, provided that pump bearing vibration is not i excessive. Assurance of acceptable pump bearing vibration- .j levels is provided through the full spectrum vibrational' ,

monitoring.

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 '

determining potential degradation.

At Vermont 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.  ;

The industry experience is consistent with Vermont-Yankee.

For similar pumps in similar 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 i of the pump upon low diesel day tank level, and full '

spectrum vibrational monitoring.

USMRC EVALUATION STATUS: ,

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

l

> Revision 15 4-29

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.s s . .5 9:  !

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.;- KELIEF REQUEST Numbers- RR-P10,' Revision'O (Sheet:1 of 2)~

SYSTEM: Reactor Core-Isolation. Cooling  !

COMPONENTS: I i

Safety Dwg f Pump Number Class Drawing Number Coor  !

i R  !

l l\

P47-1A- 2 G-191174 'F-08 ,

l. +

E t

[ This pump has a function to provide makeup water to the reactor  ;

pressure vessel during shutdown and isolation in order to prevent  !

. the release of radioactive materials to the environs as a result of inadequate core cooling.  ;

EXAM OR TEST CATEGORY: j Pump Vibration (V,) f CODE REQUIREMENT:

5.2 (d) " Test Procedure" 'i

" Pressure , flow rate, and vibration (displacement or ,

velocity) shall be determined and compared with correponding [

reference values:.

All deviations from the reference values shall be compared with the limits given in Table 3 and t corrective action taken as-specified in para. 6.1."  ;

EEQUEST FOR RELIEF:  !

Relief is requested on the basis that comliance the  :

vibration limits specified in Table 3b of Part 6 of the Code  ;

for this pump is impractical and that the proposed  !

alternative would provide an acceptable level of quality and j safety.

l-t ti t

i

! Revision 16 4-30 l c --

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10 l

[ RELIEF REQUEST l Numbers iRR-P10, Revision 0 (Sheet 2 of 2) l BASIS FOR RELIEF: (con't) -j

~

Past testing and analysis performed on the RCIC pump by- l

[

Vermont Yankee, the pump manufacturer, and by independent vibration consultants has revealed characteristic pump.

L vibration levels which exceed the. acceptance criteria stated- ,

in Table 3 of Part 6 of the Code. The causes of the higher- 1 vibration levels have been determined as the following: ]

~

1. High vibration levels at the impeller vane pass  !

frequency. (4X and 5X running speed) l

2. Structural resonance.

The reference vibration values for this pump range as high f as 0.316 in/sec. The mean peak velocity value, for the ,

highest vibration point, utilizing data taken since 1990_is i

0.314 in/sec. A review of the the hydraulic and vibration test data since 1990 indicates that there has been'no degradation of the pump. Discussions with the pump manufacturer have indicated that the vibration levels for f this type of pump driven by a steam turbine are common and do not represent a mechanical problem with the pump.

~

Due to the small deviation between=the pump reference value '

and the 0.325 in/see limit specified in table 3b of Part 6 of the Code, normal fluctuations (data scatter) in vibration ,

readings cause~this pump to be unnecessarily placed in the j alert range and the fregency of testing increased.  ;

ALTERNATIVE TESTING:

In order to obtain an alert range limit for the RCIC pump that is more indicative of pump degradation, the alert range limit will be extended to greater than 2.5 V, or greater than 0.50 in/sec. The required action range specified in  !

table 3b of Part 6 of the Code will remain unchanged.

USNRC EVALUATION STATUS:

This relief request was first submitted in Revision 16 of the IST Program Plan. Approval of this relief request is pending. -

l i

3 Revision 16 4-31 L

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p 5.0 Valve Inservice Testing Program 5.1 Scope The Third-Interval Valve Inservice Testing (IST) Program

~

establishes testing requirements to assess the operational readiness.of certain Safety Class 1, 2, and 3 valves and pressure relief devices, including their actuating and

[f position indicating systems.

The active or passive Safety Class 1, 2, and 3 valves. included are'those which are required to perform a specific function in: ,

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 design-basis accidents.

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

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 design-basis accidents.

The following are excluded from 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; b) Valves used only for system control, such as pressure regulating valves; c) Valves used only for system or component maintenance.

External control and protection systems responsible for sensing plant conditions and providing signals for valve operation are also excluded from the above.

l Revision 15 5-1 l

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'l 1

_5.2 valve Program Listing i I'

Table 5-1, " Valve Listing" lists lall valves'and pressure-relief. devices _ included in the Third-Interval Valve .IST ,

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. .The column headings in Table 5-1 are listed and ,

-explained below:

' 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

, identifier is listed. Table 5-1 is sorted by Drawing.

4 Drawing Title The title of the Flow Diagram.

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.

Function 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 device appears.

Safety Class The safety classification of the valve or pressure relief

' device, as determined in accordance.with procedure AP 0014,

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

e Revision 13 5-2

g. m ~

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y OM' Cat

.The. valve' category'as. defined by1 Paragraph l.4 of Part 10 of

<- 'the code. . "All categories are identified for those valves: s d which have more-than one' applicable category (i.e. A/C for fq ,

category c valves'that also have leakage requirements)'.-

LA: ' . Valves'for.whichiseat leakageLis' limited toia:

' specific; maximum amount-in the closed position 1forf fulfillment of_their required-function (s).

u; _ '3 -

3 3: 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,Esuch-as; pressure"(relief

4

, valves) or flow' direction lcheck-valves) for fulfillment of.their requiredLfunction(s).-

p D: Valves which are actuated by an. energy' source .

o ,

capable ofJonly one; operation,.such as rupture disks or explosively actuated valves.

size (Inch) c.

The nominal pipe' size of the valve, in inches.

Body The_ valve's body style' designator where:

3-WAY for 3-Way Valves.

BL for Ball Valves-BTF for Butterfly Valves CK for simple: Check Valves ]

EFC for Excess Flow Check Valves GA for Gate Valves GL for Globe Valves GSC for Globe Stop Check Valves PLG for Plug Valves RD for Rupture Discs RV 'for Relief. Valves SQUIB for explosively actuated valves SRV for Safety / Relief Valves Actuator The. type of actuator provided with the valve body where:

for Air. Operated 1 AO EEP for Explosive Charge 50 .for Rydraulically Operated MAN for Manually-Operated ,

MO-AC Efor Motor Operated, AC powered motor  ;;

MO-DC_ for Motor Operated, DC powered motor . l SA for Self Actuated (i.e. Relief Valves, etc.) j 80 for solenoid Operated j .

. Revision 15 5-3  !

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e__-__________-_______ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ . .

Of s j

i i

Normal ~ Position' 'j l

This' field details the. valve's position during normal plant- l

" operation (if the subject system does not operate duringl. j normal power operation, the valve's' normal position is the  ;

position of the valve when the system _is not'in_ operation), -i

- where:  ;

i C- for closed' .

t c/FC. for closed, Fails closed i

- C/FO for Closed, Fails Open (

c/Lc for closed, flocked closed  ;

C/KL for Closed,~ Key Locked Closed:

O, for Open- 's O/FC for Open,' Fails closed: l O/FO for Open, Fails Open j O/LO for Open, Locked Open i O/KL for Open, Key Locked Open ,

D-V .for De-energized, Vented  !

E-P for Energized,. Pressurized i BYS for System function dependent (e.g. Check 'j Valves, etc.)  ;

Test Type (and Stroke Direction) i The test type is an abbreviation of the type of test required  !

to be performed and the stroke direction in which the test is j performed. j LJ OM Category A Valves, which are containment I isolation valves and do not provide'a reactor- l coolant system pressure isolation function. These  ;

valves are leakage rate tested, the results j analyzed, and corrective action performed in  :

accordance with the Vermont Yankee Primary i containment Leak Rate' Testing Program. The' Vermont  !

Yankee Primary Containment Leak Rate Testing Program provides compliance with Paragraphs 4.4.2.1, j a

4.4.2.2, 4. 2. 2. 3 (e) , and 4.2.2.3(f)-of Part 10 of the Code and 10' CFR 50.55a(b) (2) (vii) . j i

LT OM Category A Valves, which perform a function other  !

than containment isolation and are not Excess Flow- 1!

Check Valves. .These valves are leakage rate tested,- .I the results analyzed, and corrective. action .

performed in accordance with Paragraphs 4.4.2.1 and l 4.2.2.3 of Part 10 of the Code.

LEF OM Category A Excess Flow Check valves, which perform a function other_than containment isolation.-

These valves are leakage rate tested, the results analyzed, and corrective action performed in accordance with Paragraphs 4.4.2.1 and 4.2.2.3 of Part 10 of the Code.

Revision 15 5-4 i

i i

STC Active Category A and B Power-Operated Valves, which I 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.

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.

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 of Part 10 of the Code. The frequent- of this verification is specifie as at least once every 2 years.

FST Active Category A and B Valves with fail-safe actuators, which are 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. ,

l Revision 16 5-5 l

l

l SP OM Category C Relief and Safety Relief Valves are  !

tested in accordance with Paragraph 4.3.1 of Part'10 l of the Code. I NONE For passive valves with no testing required.

]

.]

Test Freq  ;

The test performance frequency associated with each test type I will be specified where.

i 1M for every 1 Month 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 OC for Once Per Operating Cycle Q for Quarterly t RR for Reactor Refueling Outage  !

NA for Not Applicable l Relief Request {;

The Relief Request number associat cl with the subject valve or pressure relief device and test ty o or test frequency, where i applicable. '

t Refuel Or Cold Shutdown Justification i The Refueling Outage or Cold Shutdown Justification number [

associated with the subject valve or pressure relief device  !

and test type, where applicable. {

Remarks When appropriate, clarifying _ comments or other remarks (such as " Passive") will be included for the affected valve, l pressure relief device, test type or test frequency.  ;

r i

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i l

Revision 15 5-6 i i

-+ ,

Table 5-1 I Valve Listing (Sorted by Drawing Number) 1 Drawing : G-191159 Sh 1 Drawing Title : Service Water System Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks SE-70-4A K 10 3 8 1.000 GA SO C/F0 FST Q STO Q Function : RHRSW Pump Motor Cooling Coll Supply Valve SE 70 48 K-10 3 B 1.000 GA SO C/F0 FST Q STO Q Function : RHR$W Pump Motor Cooling Coll Supply Valve SE 70 4C K-10 3 8 1.000 CA SO C/F0 FST Q STO Q Function : RHR$W Ptanp Motor Cooling coil Supply Valve SE-70-4D K 10 3 8 1.000 GA SO C/F0 FST Q STO Q Function : RHRSW Pump Motor Cooling Coll Supply Valve SR-70 13A K 09 3 C . 75 0 RV SA SYS SP 10Y Function : RHR$W Pump Motor Cooling Relief Valve SR-70-138 K 10 3 C .750 RV SA SYS SP 10Y Function : RHRSW Pump Motor Cooling Relief Valve SR 70-13C K-10 3 C .750 RV SA SYS SP 10Y ,

Function : RHRSW Pump Motor Cooling Relief Valve SR 70 130 K-10 3 C .75 0 RV SA SYS SP 10Y Function : RHRSW Punp Motor Cooling Relief Valve V70-1A C 02 3 C 14.000 CK SA SYS SC RR ROJ-V14 Note 13 SO RR ROJ V14 Function : Service Water Punp Discharge Check Valve V70 1B B-02 3 C 14.000 CK SA SYS SC RR ROJ-V14 Note 13 SO RR ROJ V14 Function : Service Water Pump Discharge Check Valve V70-1C 1 02 3 C 14.000 CK SA SYS SC RR ROJ V14 Note 13 50 RR ROJ-V14 Function : Service Water Pump Discharge Check Valve V70 10 H-02 3 C 14.000 CK SA SYS SC RR ROJ-V14 Note 13 So RR ROJ-V14 Function : Service Water Pump Discharge Check Valve 8.000 GA O SC Q Alt Cooling V70 6 F-03 3 B MAN Function : Isolation to Travelling Screen Wash  ;

Revision 16 5-7 5

I

rn Table 5-1 i Valve Listing (Sorted by Drawing Number)

Drawing : G-191159 Sh 1 Drawing Title : Service Water System 4 L

Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown . .

Valve Number Coor Class Cat (!nch) Body Act Pos Type Freq Request Justif. Remarks V70 16B C 09 3 B 24.000 GA MAN C SC- Q Alt Cooling j Function : Alternate Cooling to SW Supply }

V70 19A J-09 3 8 24.000 GA MO-AC 0 PIT RR STC Q '

STO Q Function : SW Supply Hender Crossconnect Valve V70 198 C-09 3 B 24.000 GA MO-AC 0 PIT RR ,i STC Q STO Q Function : SW Supply Header crossconnect valve V70 20 G 11 3 B 20.000 GA MO-AC 0 P!T RR STC Q Function : SW Supply Valve to Turbine Building Cooling Loads t

?

V70 24B C-12 3 B 2.500 GA MAN C SO Q Alt Cooling Function : Alternate

...................... Cooling Supply to RBCCW V70 29 D-13 3 8 3.000 GA MAN C $0 Q Alt Cooling  !

Function : Alternate Cooling to SW $@ ply V70 29A D.13 3 8 3.000 GA MAN C 50 Q Alt Cooling >

Function : Alternate Cooling to SW Supply V70 328 C 12 3 8 2.500 GA MAN C SO Q Alt Cooling Function : Alternate Cooling Supply to RBCCW j V70 36A C.13 3 8 3.000 GA MAN C SO Q Alt Cooling Function : Alternate Cooling Supply to RBCCW .;

V70 36B C 13 3 8 3.000 GA MAN C SO Q Alt Cooling  :

Function : Alternate Cooling Supply to RBCCW V70 3&A K-12 3 C 12.000 CK SA SYS SC Q  !

SO Q  :

f Fanction : RNRSW Pump Discharge Check Valve _

V70 38B B-12 3 C 12.000 CK SA SYS SC Q SO Q  ;

Function : RHR$W Ptmp Discharge Check Valve t V70 40A K 12 3 C 12.000 CK SA SYS SC Q SO Q Function RHR$W Pump Discharge Check Valve l

V70 40B A 12 3 C 12.000 CK SA SYS SC Q 50 Q Function : RHRSW Pump Discharge Check Valve I

1 Revision 16 5-8 l 1

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1 l

Table 5-1 Valve Listing (Sorted by Drawing Number) l 1

Drawing : G 191159 sh 1 Drawing Title : Service Water System Refuel or Cold Dwg Safety OM Site Norm Test Test Relief Shutdown Valve Nunber Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks V70-42A K.13 3 8 8.000 GA MAN C SO Q Alt Cooling Function : RHRSW Alternate Cooling to SW Supply V70-428 B 13 3 8 8.000 GA MAN C $0 0 Alt Cooling Function : RHR$W Alternate Cooling to SW Supply V70 43A J 12 3 C 8.000 CK SA SYS So o Alt Cooling Function SW Discharge Loop Header Check Valve NENMN V70-43B B 12 3 C 8.000 CK SA SYS SO Q Alt Cooling CE

$a w*EwwRR M RR.W ~12 Function : SW Discharge Loop Header Check Valve V70-504 D 09 3 B 2.000 GA MAN C None NA Passive Function : Alternate Cooling to SW Supply V70 130A C-05 3 8 3.000 GA MAN 0 SC Q Alt Cooling Function : Isolation to Chlorination Service Water Supply and Circ Water Pump Cooling V70-1308 I-05 3 8 3.000 GA MAN O SC Q Alt Cooling Function : Isolation to Chlorination Service Water Supply and Circ Water Pump Cooling V70 13A J 07 3 8 24.000 GA MAN O SC RR ROJ V16 Alt Cooling Function : SW Supply to the A Header Isolation V70-13B B 07 3 8 24.000 GA MAN 0 SC RR ROJ-V16 Alt Cooling Fuiction $W Supply to the B Header Isolation V70 15A J-08 3 8 12.000 GA MAN O SC RR ROJ V17 Alt Cooling Function : SW Supply to the A RBCCW Heat Exchanger B 07 3 8 12.000 GA MAN 0 SC RR ROJ-V17 Alt Cooling V70-158 Function : SW Supply to the B RBCCW Heat Exchanger PCV 104 69A J 13 3 8 8.000 GL A0 C STO Q Alt Cooling Function : RHRSV PCV FOR SW TO A EDG and RRU 5,7

..............................................'s PCV 104-698 B 13 3 8 8.000 GL A0 C STO Q Alt Cooling Function : RHR$W PCV FOR SW TO B EDG and RRU's 6,8 V70-187A J 06 3 B 1.250 GA MAN O SC RR ROJ-V18 Alt Cooling Function : Gland Seal Supply to SW Punps A and B (Non-Seismic Branch Line Valve Isolation)

VTO 187B B-06 3 B 1.250 GA MAN 0 SC Q ROJ V18 Alt Cooling I Function : Gland Seal Supply to SW Punps C and D (Non-Seismic Branch Line Valve Isolation) v70 27 D 02 3 8 1.500 GA MAN 0 SC 0 Alt Cooling Function : SW to Fire Water Pressurizing Line (Non-Seismic Branch Line Valve Isolation) 2.000 BL A0 0 STC 0 Alt Cooling SP-70-3A K-04 3 8 Function : A SW Strainer Backwash Valve (Non-Seismic Branch Line Valve) 2.000 BL A0 0 STC Q Alt Cooling SP- 70-3B C-05 3 8 Function : B SW Stralner Backwash Valve (Non-Seismic Branch Line Valve)

Revision 17 5-9

r Table 5-1 Valve Listing (Sorted by Drawing Number) l Drawing : G-191159 Sh 2 Drawing Title : Service Water System Refuel or Cold Dwg Safety OM Stre Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks SB-70 1 D-09 NC B 24.000 BTF MAN 0 SC RR ROJ-V19 Alt Cooling Function : SW To Main condensor Discharge Block Valve V70-17 D-06 3 B 20.000 GA MAN C SO RR ROJ V19 Alt Cooling i Function : Alternate Cooling from RHRSW Discharge to Cooling Tower Inlet Isolation Valve V70-16A D-07 3 8 24.000 GA MAN C 50 0 Alt Cooling Function: Alternate Cooling Deep Basin to RHR$W Pump Suction Isolation Valve V70 11 D-07 3 B 14.000 GA MAN SYS SC RR ROJ-V19 Alt Cooling Function: Service Water Discharge (Deicing) to cooling Tower Basin Isolation Valve V70 18 E 07 3 B 20.000 GA MAN O SC RR ROJ-V20 Alt Cooling Function: Service Water Discharge Header Isolation VTO-203 B-03 3 8 1.250 GA MAN 0 SC Q Alt Cooling Function: Service Water Supply to RRU-9 Isolation V70 206 J-03 3 B 2.5000 GA MAN O SC Q Alt Cooling Function: Service Water Supply to RRUs 17A,178 ! solation Valve V70 17A C.07 3 8 6.000 GL MAN SYS SC RR Passive Alt Cooling SO RR Passive Note 12 Function: #1 West Cooling Tower SV Distribution Tray Valve V70-17B C 07 3 B 6.000 GL MAN SYS SC RR Passive Alt Cooling SO RR Passive Note 12 Function: #1 West Cooling Tower SW Distribution Tray Valve v70 17C C-07 3 8 6.000 GL MAN SYS SC RR Passive Alt Cooling 50 RR Passive Note 12 Function: #1 West Cooling Tower SW Distribution Tray Valve V70-17D C-07 3 8 6.000 GL MAN SYS SC RR Passive Alt Cooling SO RR Passive Note 12 ,

Function: #1 West Cooling Tower SW Distribution Tray Valve V70-413 0-08 3 B 0.750 GA MAN SYS So Q Alt Cooling SC Q Function: Service Water Supply to Rad Monitor from SW Main Condenser Discharge Line v70-414 D 08 3 8 0.750 GA MAN SYS SO Q Alt Cooling SC Q Function: Service Water Supply to Red Monitor from SW Discharge to Deep Basin Revision 16 5-10 l

1

-- __ _ __ _ __ _ _, _. . _ _ _ .m . . - _ , _ _ . _ . _ . _

Table 5-1 Valve Listing.

(Sorted by Drawing Number)

Drawing s G-191159 Sh 3 Drawing Title : RCW Cooling Water System Refuel

. . Or Cold Dwg Safety OM Site Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks V70 95A A-07 3 C 12.000 CK SA SYS SC 0 SO Q Function : RBCCW Pump Discharge Check Valve V70 958 B-07 3 C 12.000 CK SA SYS SC Q SO Q Function : RBCCW Pump Dfscharge Check Valve V70 113 K-08 2 C 8,000 CK SA SYS SC CS CSJ-V01 Function : Pr{ mary Containment RBCCW Supply Isolation Valve v70 117 L 12 2 8 8.000 GA MO-AC 0 P!T RR STC CS CSJ V01 Function : Primary Containment RBCCW Return Valve V70-24A N2 3 8 2.50 GA MAN O SC Q Alt Cooling Funct{on RBCCW cooling to CRD and B/D RHR Ptanps V70 28 0-10 3 B 3.00 GA MAN C SO Q Alt Cooling Function: RBCCW Cooling to CRD and RHR PLanps VTO-28A 0 10 3 8 3.00 GA MAN O SC Q Alt Cooling Function: RBCCW Cooling to CRD and RHR Ptssps V70 32A P-02 3 8 2.50 GA MAN O SC Q Alt Coollng Function: RBCCW Cooling to Redweste and A/C RHR pumps V70-106 P 02 3 B 2.00 GA MAN' O SC 0 Alt Cooling Function Redwaste Building Inlet V70-107 P-05 3 8 2.00 GL MAN O SC Q Alt Cooling Function: Radweste Building outlet v70- 2A C 03 3 B 24.00 GA MAN 0 SC RR ROJ V16 Alt Cooling Function: SW Pump Discharge Isolation Valve v70 28 B 03 3 8 24.00 GA MAN O SC RR ROJ-V16 Alt Cooling Function: SW Pupp Olscharge Isolation Valve V70 2C J 03 3 8 24.00 GA MAN 0 SC RR ROJ V16 Alt Cooling Function: SW Ptsip Discharge Isolation Valve V70- 20 J 03 3 8 24.00 GA MAN 0 SC RR R0J V16 Alt Cooling i Function: $W Pump Discharge Isolation Valve  ;

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1 Revision 16 5-11 I

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w 4w.. as;s-- .e n w. w .-w,= ws ..a  %.em w p we._ . . .. . _

g, .,, )

y . ,

Tablo 5-1 i Valve Listing (Sorted by Drawing Number) f Drawing a G 191159 Sh 5 Drawing Title : Recirculation Purip Cooling Water Refuel or Cold Owg Safety OM' Site . Norm Test Test Relief Shutdown Valve Number Coor Class . Cat '(!nch) Body Act Pos Type Freq Request Justif. Remarks SL 2 2 7A G-02 2 A/C 1.000 EFC SA SYS LEF RR  :

- Function : Rectreulation Pulp Inst Excess Flow Check Valve SL 2-2 78 G 02 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Recirculation Pump Inst Excess Flow Check Valve SL 2 2 8A G 02 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 ,

r Function : Recirculation Pump Inst Excess Flow Check Valve  ;

r SL-2 2 88 G-02 2 A/C 1.000 EFC SA SYS LEF RR i SC RR ROJ-V01 i Function : Recirculation Pump Inst Excess Flow Cbeck Valve h

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Revision 16 5-12

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v-Tablo.5-1  ;

, Valve Listing  !

(Sort'ed by Drawing Number)  !

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Drawing G 191160 Sh 3- ')

Drawing Title : Instrunent Air System .j t

i Refuel -

Cr Cold  ;

Dwg Safety OM . Size Norm Test Test Relief Shutdown 4

' valve Number coor ~ Class Cat (Inch) Body 'Act Pos Type. Freq Request Justif. Romerks  !

V72 38A E 17 2 :A- 2.000' GL A0 0/FC FST Q --  !

LJ RR  !

PIT RR STC 0

[- .

1= Function : PCAC Compressor inlet containment Isolation Valve _

................................................................................................................... t V72 388 F.17 2 A 2.000 GL A0 0/FC FST - 0 .

LJ. RR ,

PIT RR

- STC 0 ,

Function PCAC Compressor Inlet Conta{nment Isolation Valve -

- V72-898 J *2 2 A/C 2.000 CK SA SYS LJ RR  ;

SC CS CSJ V02 '  ;

i Functfon : Drywelt Instrument Air Supply Check Valve V72 89C K 15 2 A/C- 2.000 CK SA SYS LJ RR SC CS CSJ-V02 Function : Drywelt Instrument Air Supply check Valve V72 103 K 11 2 A/C 2C CK SA C '.J RR Passive [

Function s'Drywelt Instrunent Air Supply Check valve  ;

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. Tablo 5-1 1 Valve Listing (Sorted by Drawing Number) orawing G 191160 sh 7

' Drawing Title : Diesel Generator Starting Air System Refuel i

or Cold I Dws Safety OM Site Norm Test Test Relief Shutdown Valve Number coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks AS-24 1A B 16 3 8 1.300 GL SO C/FC FST Q SO 1M RR-v03 As A Pair, Slow Start-I -

STO 6M RR-V03 As A Pair, Fast Start STO OC RR-V03 Individual, Fast Start Function DG Starting Air Engine Inlet Valve

[ ...................................................................................................................

AS 2418 B-03 3 8 1.500 GL SO C/FC FST Q So iM RR V03 As A Pair, Slow Start STO 6M RR-V03 As A Pair, Fast Start l> , STO OC RR V03 Individual, Fast Start Function : DG Starting Air Engine Inlet Valve AS 24-2A B 17 3 8 1.500 GL SO C/FC FST Q SO 1M RR v03 As A Pair, Slow Start STO 6M RR V03 As A Pair, Fast Start ,

STO OC RR V03 Individual, Fast Start I Function : DG Starting Air Engine Inlet Valve AS 24-28 B-03 3 8 1.500 GL So C/FC FST Q So iM RR-V03 As A Pair, Slow Start STO 6M RR V03 As A Pair, Fast Start STO OC RR V03 Individual, Fast Start Function : DG Starting Air Engine Inlet Valve AV-24 1A B 17 3 8 .125 GA SO 0/F0 FST Q SC 1M RR V03 Slow Start STC 6M RR-V03 Fast Start Function : DG Starting Air Engine !nlet Vent Valve AV-24 1B B 03 3 8 .125 GA SO 0/F0 FST Q SC 1M RR-v03 Slow Start STC 6M RR-V03 Fast Start Function : DG Starting Air Engine inlet Vent Valve RV 24 6A E-15 3 C .75 0 RV SA SYS SP

• 10Y Function : DG Starting Air Receiver Relief Valve RV-24 68 E 13 3 C .750 RV SA SYS SP 10Y Function : DG Starting Air Receiver Relief Valve RV 24-6C E-07 3 C .75 0 RV SA SYS SP 10Y Function : DG Starting Air Receiver Relief Valve RV 24-6D E 05 3 C .750 RV SA SYS SP 10Y function : DG Starting Air Receiver Relief Valve RV 24 7A H 12 3 C .750 RV SA SYS SP 10Y Function : DG Starting Air Compressor Relief Valve RV 24 78 M8 3 C .75 0 RV SA SYS SP 10Y Function : DG Starting Air Compressor Relief Valve Revision 16 5-14 i

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.. Valve Listing J (Sorted by Drawing Number)

Drawing : G 191160 sh 7 Drawing Title : Diesel Generator starting Air system i

Refuel ,

Or Cold Dwg safety CM size Norm Test Te'st Relief shutdown >

Valve Nunber coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks V72 76A H 12 3 C .750 CK SA sVS $0 o

' . Function

DG starting Air Compressor Outlet Check valve H8 .750 CK SYS so o V72 768 3 C SA

. Function : DG starting Air Compressor Outlet Check Valve i ...................................................................................................................

V72 78A E.14 3 C 2.000 CK SA SYs so o

.-- Function : DG starting Air Receiver Outlet Check Valve t

t . ..............................,.....................................................................................

I-V72 788 E.13 3 C 2.000 CK SA sys so o

. Function : DG starting Air Receiver Outlet check Valve

,~ .

V72 78C E.07 3 C 2.000 CK SA SYs $0 o Function : DG starting Air Receiver outlet Check Valve V72 780 E 05 3 C 2.000 CK SA SYs so o E Function : DG starting Air Receiver Outlet Check Valve V72 80AX G 15 3 C .750 CK SA SYS so o Function : DG starting Air Receiver Inlet Check Valve V72-808X G-13 3 C .750 CK SA sYs so 0 -

Functicn : DG starting Air Receiver Inlet Check Valve V72 80CX G-06 3 C .750 CK SA SYs 50 0 Function OG starting Air Receiver Inlet check Valve (

V72 80DX G-05 3 C .750 CK SA sYs 50 o Function : DG starting Air Receiver Inlet Check Valve V72 82AX D.14 3 8 2.000 GA MAN C None NA Passive Function : service Air to DG starting Air Crossconnect Valve V72 828X D6 3 8 2.000 GA MAN C None NA Passive  !

Function : service Air to DG starting Air Crossconnect Valve  !

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F Tablo 5-1  !

Valve Listing- r (Sorted by Drawing Number). i V

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t Drawing G-191160 Sh 8 ,

- Drawing Title.: Savics Air System 1 y

f Refuel 4

. Or Cold -l Dwg -Safety CM Size Norm Test Test Rollef Shutdown i Velve Number Coor Class Cet (Inch) Body Act Pos Type' Freq Request Justif. Romerks SE.105 2A C 06 3 5 .750 GL SO 0/FO' None N/A Passive i F metton : N2 Supply 3.Way Vent Velve , -j

- ................................................................................................................... t SE.105 28 C 12 3 8 .750 GL . S0 C/FO None N/A' Passive '

Function N2 Supply 3 Way Vent valve  ;

SR.72-9A F-05 3 C .750 RV SA SYS SP 10Y .!

Function : N2 Supply Rollef Velve i

' SR.72-95 F 04 3 C .750 RV SA .SYS SP 10Y-Function : N2 Supply Rollef Velve .

3 .750 RV SA .SYS SP 10Y j SR.72 10A . C 05 C Function N2 Supply Relief valve - '

SR 72 10s C-04 3 C .750 RV SA SYS SP 10Y 3

Function : N2 Supply Rollef Velve .

V72 609 E-04 3 A/C .375 CK SA SYS LT Q SC Q * .;

Function : Instrument Air to Reactor Building Railroad Airlock -j V72-610 E-04 3 A/C .375 CK SA SYS LT Q ,

SC Q -)

Function : Instrument Air to Reactor Building Rettroad Airlock '

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c Table 5-1 Valve Listing-(Sorted by Drawing Number) i Derwing ? G-191162 sh 2

. Drawing Title : Fuel Oil . Miscellaneous Systems Refuel

-or cold Dwg Safety OM Size Norm Test Test Relief. Shutdown Valve Nunber . Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks LCV.108 2A E 08 3 8 1.500 GA A0 C STO Q Function : Diesel Oil Day Tank Level Control Valve LCV 108-28 C 08 3 5 1.500 CA Ao C

!- STO Q Function Diesel Oil Day Tank Level Control Valve i LCV-108 3 E 07 3 8 1.500 GA A0 C/FC None None Passive per PDCR 94 022 Function : DF0 Pump Discharge to Fuel all Day Tank Valve SR-78 3A E-06 3 C .750 RV SA SYS SP 10Y Function : Diesel Fuel 011 Transfer Pump Discharge Relief Valve SR 78 38 D 06 3 C .750 RV SA SYS SP 10Y Function : Diesel Fuel Oil Transfer Pu g Discharge Relief Valve V78 2 E-02 3 C 4.000 CK SA SYS CD RR Function : Fuel Oil Storage Tank Fill Line Check Valve V78 28A E.06 3 C 1.250 CK SA SYS SC Q SO Q Function Diesel fuel all Transfer Pump Discharge Check Valve v78 288 D 06 3 C 1.250 CK SA SYS SC Q SO Q Function : Diesel Fuel Oil Transfer Punp Discharge Check Valve Revision 16 5-17

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i Tablo 5-1 Valve Listing (Sorted by Drawing Number) J l

-Drawing G 191165 Drawing Title : Sampling System f

Refuel or Cold Dwg Safety OM Size Norm Test Test Rollef Shutdown Valve Nwber coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Romerks PAS.102 K 16 2 B .750 GA Ao C/FC FST Q STC 0 1 Function : Post Accident Samplir.3 System Jet Pump Sample Valve '

PAS.104 K 16 2 's .750 GA A0 C/FC FST Q l STC 0 Function Post Accident Sampling System Jet Pump Sanple Valve

, PAS 106 L.16 2 8 .750 GA A0 C/FC FST Q STC 0 l Function : Post Accident Sampling System Purge Valve 1

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Table 5-1

. Valve Listing

. (Sorted by Drawing. Number)

Drawing G 191167 Drawing Title : Nuclear Soller Refuel Or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown

' Valve Number -Coor Class Cat 2(Inch) Body Act -Pos Type -Freq Request Justif. Remark.

FCV 2 17 B 06 2 8 1.000 .GL A0 C/FC PIT 'RR Passive Function : Rx Vessel Head Steam Space Vent Flow Control Valve FCV 2 18 B 05 1 8 1.000 GL- A0 C/FC P!T RR Passive Funct1on : Rx Vessel Head Steam Space Vent Flow Control Valve FCV 2 20 C-06 1 B 1.000 GL A0 ~0/F0 P!T RR Passive function Ex Vessel Head Seal Leakage Flow Control Valve FCV 2 21 C 05 2 8 1.000 GL A0 C/FC PIT RR Passive Function : Rx Vessel Head Seal Leakage Flow Control Valve FCV 2 39 L 04 2 A .750 GL A0 C/FC FST Q LJ RR PIT RR STC 0 Function : Rx Recirc Sample Line Flow Control / Isolation Valve FCV 2 40 L-03 2 A .750 GL A0 C/FC FST Q LJ RR PIT - RR STC Q Function : Rx Recirc Sample Line Flow Control / Isolation Valve RV 2 71A D 08 1 C 6 x 10 SRV SA SYS SP 5Y Note 9 Function : Nuclear Boller Safety / Relief Valve RV 2 71B G 08 1 C 6 x 10 SRV SA SYS SP SY Note 9

. Function : Nuclear Boller Safety / Relief Valve

. g ...............................................g........................................................... ,,,, ,

Function Nuclear Boller Safety / Relief Valve RV 2 71D H.08 1 C 6 x 10 SRV SA SYS SP SY Note 9 Function : Nuclear Boller safety / Relief Valse Revision 16 5-19

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. Table 5 .

. Valve Listing E l Sorted.by Drawing Number) I Drawing : G-191167 Drawing Title : Nuclear Bolter .;

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Refuel Or Cold e r

l; Dwg Safety OM Site .

Norm Test Test Rollef Shutdown -t

. Valve mmber. Coor - Class Cat. (Inch) Body Act Pos Type Freq Request Justif. Remarks MSRV Actuator Air Supply Solenoid Valves (Removed from the IST Program) ^l

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'SL 2-62A I-13 2 A/C 1.000 EFC' SA SYS LEF. . RR  !

SC RR R0J-V01  ;

r Function Nuclear Boller Vessel Inst Excess Flow Check Valve 1

.SL 2-628  !-13 2 A/C 1.000 EFC SA SYS LEF- RR SC RR ROJ-V01 e

Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve SL-2 62C J-13 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Funct{on : Nuclear Boller Vessel Inst Excess Flow Check Valve l 1.000 EFC SYS LEF RR 5 SL 2 62D J 13 2 A/C SA SC RR R0J-V01 Function Nuclear Botter vessel Inst Excess Flow Check Valve SL 2 64A K 13 2 A/C 1.000 EFC SA SYS LEF RR i i

SC RR ROJ V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve [

SL 2 648 K 13 2 A/C 1.000 EFC SA SYS LEF RR .

1 RR R0J V01 i SC Funct{on Nuclear Boller Vessel Inst Excess Flow Check Valve ,

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Revision 16 P

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Tablo 5-1 Valve Listing (Sorted by Drawing Number)

Drawing i G 191167 Drawing Title Nuclear Boiler Refuel or cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Nwber coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks SL 2 64C K 13 2 A/C 1.000 EFC SA SYS LEF RR

- SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve JL 2-640 L 13 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL-2 73A F 12 2 A/C 1.000 EFC~ SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 738 F-12 2 A/C 1.000 EFC SA SYS LEF RR SC RR . ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2-73C G-12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2-730 G-12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 73E G 12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Functlon : Nuclear Boller vessel Inst Excess Flow Check Valve SL 2-73F G 12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2-73G H 12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-v01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL-2-73H H-12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function Nuclear Boller Vessel Inst Excess Flow theck Valve SL 2-305A M 02 2 A/C 1.000 EFC SA SYS LEF RR ,

SC RR R0J-V01 Function Nuclear Boiler Vessel Inst Excess Flow Check Valve I

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Revision 16 5-21

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1Ealslo 5-1 )

Valve Listing l (Sorted by Drawing Number) 1 i

Drawing : G-191167 Drawing Title : Nuclear Boller Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks SL 2 3058 M-02 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ.V01 Function : Nuclear Boller vessel Inst Excess Flow Check Valve SR 2-14E L-12 3 C 10.000 RV SA SYS SP 10Y Function : SRV Discharge Line Vacuum Relief Valve SR.2 14F L 12 3 C 10.000 RV SA SYS SP 10Y Function SRV Discharge Line Vacuum Relief Valve SR 2 14G L-12 3 C 10.000 RV SA SYS SP 10Y Function : SRV Discharge Line Vacuum Relief Valve SR-2 14M L 12 3 C 10.000 RV SA SYS SP 10Y Function : SRV Discharge Line Vacuum Relief Valve SR 2 14! L 12 3 C 10.000 RV SA SYS SP 10Y Function : SRV Discharge Line Vacuum Relief Valve SR 2 14J L 12 3 C 10.000 RV SA SYS SP 10Y Function : SRV Discharge Line Vacuum Relief Valve SR-2 14K L 12 3 C 10.000 RV SA SYS SP 10Y Function : SRV Discharge Line Vacuum Relief Valve SR 2 14L L-12 3 C 10.000 RV SA SYS SP 10Y Function : SRV Discharge Line Vacuum Relief Valve SV 2 70A D.08 1 C 6x8 SRV SA SYS SP SY RR.V05 Function : Nuclear Boller Safety / Relief Valve SV 2 708 H 08 1 C 6x8 SRV SA SYS SP 5Y RR-VOS Function : Nuclear Boller Safety / Relief Valve V2-27A F-03 1 A/C 16.000 CK SA SYS LJ RR SC RR ROJ.V03 SO RR ROJ V03 Function : Reactor Feedwater Injection Line Check Valve V2 278 H-02 2 C 16.000 CK SA SYS SC RR ROJ-V03 Function : Reactor Feedwater Injection Line Check Valve Revision 16 5-22

1. - e -G- 4 t_. Jt Tablo 5-1 .,

. valve. Listing (Sorted.by Drawing Number)

Drawing G 191167 Drawing Title : Nuclear Boller Refuel l Or Cold Dwg Safety OM Size .

Norm Test Test Relief - Shutdown Valve Nunber Coor Class Cat- (!nch) Body Act. Pos . Type Freq Request Justif. Romerks

.................. .... ...... ... ...... .... ..... .... ..... .... ....... ........ ............... - b V2 28A F 05 1 A/C 16.000 CK SA SYS LJ .RR SC RR R0J-v03

$0 RR ROJ V03 Function : Reactor Feedwater injection Line Check valve v2 288 H 05 1 A/C 16.000 CK SA SYS LJ RR SC RR ROJ V03 SO . RR ROJ V03 Function : Reactor Feedwater Injection Line Check Valve V2-37A B 08 2 A/C 1.000 CK SA SYS LT RR  :

SC RR ROJ V04-Function : MSRV Actuator Nitrogen Supply Check Valve SYS LT V2-37B G 09 2 A/C 1.000 CK SA RR SC RR .ROJ V04 ,

Function : MSRV Actuator Nitrogen Supply Check Valve .

V2-37C G 09 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ.V04 Function : MSRV Actuator Nitrogen Supply Check Valve Y2 37D H 09 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ V04

'I Function : MSRV Actuator Nitrogen Supply Check Valve V2 53A L 09 1 B 28.000 GA MO AC 0 PIT- RR STC CS CSJ V04 Function : Rx Recirculation Pump Discharge Isolation Valve V2-53B L*09 1 B 28.000 GA MO*AC 0 P!T RR

. STC CS CSJ V04 .

s Function : Rx Recirculation Pump Discharge Isolation Valve V2 54A L 09 i B 4.000 GA MO-AC 0 P!T RR STC CS CSJ*V04 >

Function : Rx Recirculation Pump Ofscharge Isolation valve -

V2-548 L 09 1 B 4.000 GA MO-AC 0 PIT RR STC CS CSJ V04 Function : Rx Recirculation Pump Discharge Isolation Valve

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Revision 16 5-23 b

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Tablo 5-l'

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valve Listing

-(Sorted by Drawing Number)

Drawing G-191167 Drawing Title Nuclear Boller Refuel Or Cold  ;

Dwg ~ Safety OM Size Norm Test Test Rollef Shutdown Valve Ntaber- Coor Class Cat (!nch) Body Act Pos Type Freq Request Justif. Romerks ,

v2 74 E 10 1 A 3.000 GA MO AC C LJ RR  ;

. PIT RR i STC Q ,

Function : Maln Steam Line Drain Contafrunent Isolation Valve V2 77 E 13 1 A 3.000 GA MO-AC C LJ RR ,

PIT RR STC- Q Function : Main Steam Line Drain containment Isolation valve V2 80A D 10 1 A 18.000 GL A0 0/FC FST Q Note 1 LJ RR PIT RR STC Q . Note 1 Function : Main Steam Isolation Valve V2 808 G 12 1 A 18.000 GL A0 0/FC FST Q Note 1 LJ RR PIT RR STC 0 Note 1 Function : Maln Steam Isolation Valve V2 80C G 12 1 A 18.000 GL A0 0/FC FST Q Note 1 LJ RR PIT RR STC Q Note 1 Function : Main Steam Isolation Valve V2 800 N-12 1 A 18.000 GL A0 0/FC FST Q Note 1 LJ RR PIT RR

- STC Q Note 1 Function : Main Steam Isolation Valve 1 V2 82A B 10 2 A/C 1.000 CK SA SYS LT RR -

SC RR ROJ V05 Function : MSIV Actuator Nitrogen Supply Check Valve ,

v2-828 B 10 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ-V05 Function : MS!V Actuator Nitrogen Supply Check Valve ,

V2 82C B 10 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ-V05 Function : MSIV Instrument Nitrogen Supply Check Valve V2 82D B 10 2 A/C 1.000 CK SA SYS LT RR >

SC RR ROJ V05 Function : MS!V Instrument Nitrogen Supply Check Valve b

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Revision 16 5-24 4

Tablo.5-1 Valve Listing (Sorted by Drawing Number)

Drawing G-191167 Drawing Title : Nuclear Boiler Refuel Cr Cold Dwg safety OM Site Norm Test Test Relief Shutdown Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks Valve Number 0-13 A 18.000 GL A0 0/FC FST Q Note 1 V2 86A 1 LJ RR PIT ' RR 1 STC Q Note 1 f Function : Main Steam Isolation Valve

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Note 1 V2-868 G-12 1 A 18.000 GL A0 0/FC FST Q LJ RR PIT RR I

• STC Q Note 1 Function : Main Steam Isolation Valve G-12 A 18.000 GL A0 0/FC FST Q Note 1 v2 86C 1

. LJ RR PIT RR STC Q Note 1 i

Function : Main Steam Isolation Valve Note 1 V2 860 H.12 1 A 18.000 GL A0 0/FC FST Q LJ RR PIT RR STC Q Note 1 Function : Main Steam isolation Valve .. ..... ..... ... ..... .......................................

g g g g g g SC RR ROJ-V05 Functfon : MS!V Actuator Air Supply Check Valve

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SC RR ROJ VOS Function : MS!V Actuator Air Supply Check Valve >

V2 87C B 13 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ-VOS Function : MS!V Actuator Air Supply Check Valve

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SC RR ROJ-V05 Function : MS!V Actuator Air Supply Check Valve V2 96A H 03 1 A/C 16.000 CK SA SYS LJ RR i SC RR ROJ-V03 50 RR ROJ V03 .

Function : Reactor Feedwater Injection Line check Valve l ROJ.V03 V2 968 F.03 2 C 16.000 CK SA SYS SC RR Function : Reactor Feedwater Injection Line Check Valve Revision 16 5-25 i

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~ Tablo-5-1 valve Listing-  !

'(Sorted by Drawing Number) -lt i

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Drawing : G.191168 Orawing Title : Core Spray System  !

i Refuel l Or Cold  ;

Dug Safety DM Size Norm Test. Test Relief . Shutdown  !

Valve Nunber- Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks SL.14 31A F.07' 2 A/C '1.000 EFC SA SYS LEF RR' l SC RR ROJ.V01 z-I Function : Core Spray Inst Excess Flow Check Valve

................................................................................................................... l SL.14 31B E-07 2 A/C 1.000 EFC SA SYS LEF RR ROJ.V01  !

SC RR Function : Core Spray Inst Excess Flow Check Valve ,

SR.14 20A F.11 2 C 1.500 RV SA SYS SP 10Y ,

Function : Core Spray Pump Discharge Relief Valve  ;

SR-14 208 D 12 2 C 1.500 RV SA SYS SP 10Y  ;

Function Core Spray Pump Discharge Relief Valve l V14 5A- H.12 2 B 3.000 GA MO-AC 0 PIT RR  !

STC Q STO Q Function : Core Spray Punp Minimun Flow Valve V14 58 H.13 2 B 3.000 GA MO AC 0 PIT RR  ;

i STC Q STO Q Function : Core Spray Pump Minimum Flow Valve V14 7A K 11 2 B 12.000 GA MO-AC O/KL PIT AR Passive l Function : Core Spray Pump Suction Valve e V14 75 L 11 2 8 12.000 GA MO.AC 0/KL PIT RR Passive f Function : Core Spray Pung Suction Valve  ;

V14.BA K-12 2 B 12.000 GA MAN C/LC None NA Passive e i

Function : Core Spray Supply From CST Isolation valve

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V16 88 L.14 2 8 12.000 GA MAN C/LC None NA Passive t Function : Core Spray Supply From CST !sclation Valve .f V14 10A  !.11 2 C 10.000 CK SA SYS SC 0 .

SO Q Fumction Core Spray Punp Discharge Check Valve i V14 10s I 14 2' C 10.000 CK SA SYS SC 0-50 0 Function : Core Spray Pump Discharge Check valve E

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' Table ^5-1 Valve Listing

-(Sorted by Drawing Number)

Drawing : G 191168 Drawing Title : Core Spray System

Refuel or Cold Dwg' Safety DM . Size Norm Test Test Relief Shutdown. .

Valve Nunber Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks

' V14 11A G-09 2 A 8.000 GA MO AC 0 LJ RR PIT RR STC Q Function : Core Spray Injection valve -

v14 11B C 09 2 A 8.000 GA MO-AC 0 LJ RR PIT RR  ;

STC Q I' STO Q f.' Function : Core Spray injection Valve G 08 A 8.000 GA MO-AC C LJ RR V14 12A 1 P!T RR STC Q

h. Q STO LT RR P!V Test '

Function : Core Spray Injection Isolation Valve V14 128 C 08 1 A 8.000 GA MO-AC C LJ RR ';

PIT RR STC Q STO Q LT RR P!V Test Function : Core Spray injection Isolation Valve ,

SC CS CSJ V05 SO CS CSJ V05 Function : Core Spray injection Check Valve

;gg  ;

SC CS CSJ-VOS So CS CSJ-VOS Function : Core Spray injection Check Valve " ~ " " " " " '

g;  ;  ; i i

555 " i "'""""""i""""""""""""""'i i Function

Core Spray Injection Line Valve V14 148 E-05 1 B 8.000 GA MAN 0/LO P!T RR Passive Function : Core Spray injection Line Valve

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V14 16A L 11 2 8 4.000 GA MAN C None NA Passive i Function : Core Spray to RHR System Isolation Valve V14 168 M-11 2 8 4.000 GA MAN C None NA Passive Function : Core Spray to RHR System Isolation valve l I

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-Tablo 5 Valve Listing:

(Sorted by Drawing Number) .

Drawing G 191168- . .

-Drawing Title : Core Spray System.

Refuel or Cold Dwg Safety. CM Size Norm Test- Test Rollef Shutdown-Valve Number .Coor Class Cat (Inch) Body Act Pos Type .Freq ~ Request :Justif. Remarks'-

v14 21A H.08 2 8 2.000 GA MAN . C' None NA Passive- ,

)

Function : Cond/Deeln to Core Spray Flushing Isolation Valve V14 218- B 10 2 B 2.000 GA MAN C None NA ' Possive

. Function : Cond/Demin to Core Spray Flushing Isolation Valve .

'V14 26A F 10 2 8 8.000 GL MO-AC. C. PIT RR STC '

0

' Function : Core Spray' Pump Test Line Isolation Valve. .

V14 265 E 10 2 8 8.000 GL MO-AC C PIT RR ,i STC 0

. Function : Core Spray Pump Test Line Isolation Valve ,

V14 30A F 07 2 A 1.000. GA MAN C None NA- Passive Function : Core Spray injection Check Valve Bypass Valve V14 30s D-07 2 A. 1.000 GA MAN C None NA Passive Function : Core Spray Injection Check Valve Bypass Valve V14-33A H 11 2 C 1.000., CK SA SYS SC 0 -i' Function : Core Spray Discharge Pressurization Line Check Valve V14 338 N 15 2 C 1.000 CK SA SYS SC 0 .l' Function : Core Spray Discharge Pressurization Line Check valve h

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t Tablo 5-1 Valve Listing (Sorted by Drawing . Number)

Drawing G 191169 Sh 1 Drawing Title : High Pressure Coolant Injection System Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Nunber Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks 8 23 6  ! 06 2 C 16.000 RD SA C RD 5Y Function : HPCI Turbine Exhaust Line Rupture Disc ,

5237 H 06 NC C 16.000 RD SA C RD SY Function : HPCI Turbine Exhaust Line Rupture Disc SL 23-37A F-04 2 A/C .750 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve -

SL 23 378 F-04 2 A/C .750 EFC SA SYS LEF RR SC RR ROJ V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL 23-37C F-04 2 A/C .750 EFC SA SYS LEF RR SC oRR ROJ V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL 23 37D F 04 2 A/C . 75 0 EFC SA SYS LEF RR SC RR R0J-V01 Function Nuclear Boiler Vessel Inst Excess Flow Check Valve

$$C-23-12 1 03 2 C 20.000 GSC SA SYS SO Q Function : HPCI Turbine Exhaust Stop Check Valve SSC 23-13 J 04 2 C 2.000 GSC SA SYS 50 0 Function : HPCI Turbine Exhaust Drain Stop Check Valve V23 14 F 13 2 8 10.000 GA MO-DC C PIT RR STO Q Function : HPCI Steam Supply Valve V23 15 D 04 1 A 10.000 CA MO-AC 0 LJ RR P!T RR STC Q STO Q Function : HPCI Steam Supply Inboard Containment Isolation Valve V23 16 D 05 1 A 10.000 GA MO-DC 0 LJ RR P!T RR STC Q STO Q Function : HPCI Steam Supply Outboard Containment Isolation Valve l

4 Revision 16 5-29 1 i

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Table 5-1 valve Listing (Sorted by Drawing Number)

Drawing G 191169 Sh 1 Drawing Title : High Pressure Coolant Injection System Refuel or Cold Dwg Safety OM Site Norm Test Test Relief Shutdown Valve Number coor Class Cat (!nch) Body Act Pos Type Freq Request Justif. Remarks V23 17 D 18 2 8 14.000 GA MO-DC 0 PIT RR STC Q STO Q Function : HPCI Pump suction valve from Condensate Storage Tank V23 18 G-05 2 C 14.000 CX SA SYS SC CS CSJ V06 50 CS CSJ V06 Function HPCI Pump Discharge Check Valve to Feedwater

~

V23 19 G 06 2 B 14.000 GA MO-DC C P!T RR STO Q Function : HPCI Discharge Isolation Valve to Feedwater V23 20 G 08 2 B 14.000 CA MO-DC 0 PIT RR .

STO Q

= Function HPC! Pump Discharge Valve V23 21 E 07 2 8 10.000 GL MO-DC C PIT RR STC 0 Function : HPCI Pump Test Return Valve to Condensate Storage Tank V23 25 F.09 2 8 4.000 GL Ho-DC C PIT RR STC Q STO Q Function : HPCI Pump Minimum Recirc Valve V23 32 E 11 2 C 14.000 CK SA SYS SO Q Function : HPCI Pump suction Check Valve from Cond. Storage Tank V23-56 J 05 2 C 2.000 CK SA SYS SO Q Function : HPCI Turbine Exhaust Drain Check Valve V23-57 F-10 2 B 16.000 GA MO DC C PIT RR STC Q STO Q -

Function : HPCI Torus Suction Containme L. Valve - Outbd V23-58 L 04 2 8 10.000 GA MO-DC C PIT RR STC Q STO Q Function : HPCI Torus Suction Containment Isolation Valve Function : HPCI Torus Suction Check Valve i

1 Revision 16 5-30

l Table 5-1 i

.. valve Listing 'l (Sorted by Drawing. Number) j i

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Drawing a G 191149 sh 1

. Drawing Iftte : High Pressure Coolant Injection System [

r Refuet  !

'<' Or Cold  !

r Dwg Norm.. Test Test RC fof Shutdown l Coor Safety'QM^ Size . Body Velve Number. Class Cat (Inch) Act Pos Type Frog Ret;uest Justlf. Remarks l

. .................. .... ...... ... ...... .... ..... .... ..... .... ....... ........ ............... =

V23 62 'J.10 . 2 C 4.000 CK SA - SYS 50 0 Function : HPCI Pump Minlana Recirc Check Valve . '. j

...................................................................................................................- .i V23 65 I 03 2- C 20.000 CK SA SYS- 50 0 Note 2 -)

1 Function NPCI Turbine Exhaust Check Velve {

V23-842 I.02 . 2 C 1.000 GSC SA SYS 50 0  !

SC 0 .i

~ Function : HPCI Turbine Exh vac Skr Stop Check Valve '

V23 843 I 03 2 C 1.000 CK- SA - SYS So -Q  ;

. Function HPCI Turbine Exh Vec Bkr Check Velve '

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Tablo-5-1

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Valve Listing i (Sorted by Drawing Number)

Drawing G-191169 sh 2 Drawing Title : HighPressureCoolantInjectionSystem Refuel Or Cold Dwg Safety CM Size ' Norm Test Test Relief Shutdown valve Number coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks HPCl* CONTROL F-13 2 B 10.000 GL Ho C PIT RR STC Q RR V06 STO Q RR V06 Function : HPCI Steam Supply Turb{ne Control Valve HPCI STOP F 15 2 B 10.000 GA Ho C PIT RR STC Q STO Q Function : HPCI Turbine Stop Valve LCV 23-39 M 11 3 8 1.000 GL A0 C/FC FST Q Pli RR STC Q STO f Function : HPCI Gland Seal Return Level Cont Drn Velve to Radweste LCV 23-40 M 11 3 B 1.000 GL A0 C/FC FST Q PIT RR STC 0 STO Q Function : HPCI Gland Seal Return Level Cont Drn Valve to Radweste SR 23-66 J 12 2 B 1.500 RV SA SYS SP toy function HPCI Booster Punp Gland Seal Cond. Line Relief Valve V23 50A J 10 2 B 2.000 GA A0 C/F0 FST Q PIT RR STO Q Function : HPCI Gland Seal Cond. Supply Valve V23 130 L.11 2 C 2.000 CK SA SYS SO Q Function : HPCI Gland Seal Tube $1de Return Check Valve v23 131 L-11 2 C 2.000 Cr SA SYS SC Q SO Q Function : HPCI Gland Seal Cond. Shell $1de Return Check Valve V23 '48A G 14 3 C 1.000 CK SA SYS 50 0 Function : HPCI Steam Ring / Chest Drain Check Valve v23 1488 G.16 3 C 1.000 CK SA SYS SO Q Function : HPCI Steam Ring / Chest Drain Check Valve Revision 16 5-32

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-Tablo:5-l'  !

,' Valve Listing l (Sorted by Drawing Number) . 1 t

P

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Drawing : G 191170- .

f Drawing Title Control Rod Drive Hydraulic System .}

I l.

I Refuel'  !

Or Cold t Dwg Safety GM Sfte Norm Test Test Relief . Shutdown  !

Valve Number - Coor Class Cat (Inch) Sody Act Pos Type Freq Request Justif. Remarks

.................... .... ...... ... ...... .... ..... .... ..... .... ....... ........ ............... 'l.

CV 3 126 C 16 2 8 1.000 GL A0 C/F0 'FST -RR R0J v06 - .l PIT .RR ' ,

STO RR R0J-V06 {

, Function : Control Rod Drive Scram Inlet Valve (Typical of 89)  :

CV 3 127 C 18 2 8 .750 GL A0 C/F0 FST RR R0J V06  !

PIT RR )

STO RR ROJ V06  !

Function .: Control Rod Drive Scram outlet Valve (TypitJ5 of 89) .i, LCV 3-33A D-07 2 A 2.000 CL A0 0/FC FS1 Q i LT RR j PIT RR STC 0 .

t Function Scram Discharge Volume Drain Level Control Valve t LCV 3 338 D 03 2 A 2.000 GL A0 0/FC FST 0 i LT RR >

P!T RR j STC 0 t 1

Function : Scram Discharge Volume Drain Level Control Valve  !

LCV 3 33C D 08 2 A 2.000 GL A0 0/FC FST Q LT RR PIT RR STC 0 t Function : Scram Discharge Volume Drain Level Control Valve ('

LCV 3 333 D 03 2 A 2.000 GL A0 0/FC FST Q t LT RR  ?

PIT RR  ;

STC 0

.I' Function : Scram Discharge' Volume Drain Level control Valve t

................................................................................................................... i PCV-3 32A A 09 2 A 1.000 GL A0 0/FC FST e LT RR PIT RR 4 STC 0 f ll r Function Scram Discharge Volume Vent Pressure Control Valve t

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Table 5-1~

Valve' Listing l (Sorted by Drawing Number) i e

e Drawing : G 191170 Drawing Title : Control Rod Drive Hydraulic System i

I Refuel Or Cold i

Dwg . Safety OM Size Norm Test Test Relief Shutdown Valve Number coor Class cat (Inch) Body Act Pos Type. Freq Request Justif. Remarks I PCV 3 32B A 01 2 A 1.000 GL A0 0/FC FST Q LT RR ,

P!T RR STC Q i-Function : Scram Discharge Volune Vent Pressure Control Valve

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .l R0J-V06 6 S0-3 120 D 16 2 B- .500 GA $0 C/FC FST RR STC RR -ROJ-V06  ;

Function : CRD Manual Control Exhaust Valve (Typical of 89) ,

i ................... ,

g;;;; g  ;  ; ;gg ;g ;  ; 3 g STC RR ROJ V06-Function : CRD Manual Control Exhaust valve (Typical of 89)  !

I ...................................................................................................................

50 3-122 C 18 2 B .500 GA S0 C/FC FST RR R0J V06 STC RR ROJ-V06 Function : CRD Manual Control Withdrawal Valve (Typical of 89)

ROJ V06  !

80 3 123 C 17 2 B .500 GA SO C/FC FST RR STC RR ROJ V06 [

Function : CR0 Manual Control insertion Valve (Typical of 89)

SYS SO ROJ V06  ;

V3 114 C-18 2 C .750 CK SA - RR '

Function Scram Exhaust To Discharge Volume Check (Typical of 89)

SC RR ROJ V06 i Function CRD Charging Water To Accumulator Check (T~ na or 89)

V3 138 B 16 2 C .500 CK SA 5YS SC Q Note 3 i Function : CRD Cooling Water Supply Check Valve (Typical of 89)

V3 162A A-09 2 A/C 1.000 CK SA SYS LT RR i SC RR ROJ-V12 Function : Scram Discharge Volume Vent check valve v3 1628 A-01 2 A/C 1.000 CK SA STS LT RR SC RR R0J V12 Function Scram Discharge Volume Vent Check Valve 1

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'Tablo 5-1

,. Valve Listing (Sorted by Drawing Number) f Drawing G 191170 Drawing Title : Control' Rod Drive Hydraulle System Refuel Or Cold-Dws Safety OM Size Norm Test Test Rollef Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos- Type Freq Request Justif. Remarks

- V3 412A E 12 2 A/C .750 CK .SA SYS LJ RR SC RR R0J V07 Function : Recirculation Puup Seal Purge Supply Check Valve

! V3 412B E 12 2 A/C .750 CK SA SYS LJ RR I . SC RR R0J.V07 Function Recirculation Pump Seal Purge Supply Check Valve

. V3 413A E 12 2 A/C .750 CK SA SYS LJ RR SC RR R0J.V07 Function : Recirculation Punp Seal Purge Supply Check Valve V3 413B E 12 2 A/C .750 CK SA SYS LJ AR

. SC RR ROJ V07 Function : Recirculation Puup Seal Purge Supply Check Valve E

L Revision 16 5-35 8

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.c Table 5-1 valve Listing l (Sorted by Drawing Number) 4 I

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f Drawing G 191171 i

Drawing Title : Standby Liquid Control System  ?

'i j' Refuel or Cold. t Dwg Safety OM Site Norm Test Test Relief Shutdown l Valve Number Coor Class Cat (!nch) Body Act Pos Type Freq Request Justif. Remarks [

G 03 2 8 1.500 SOU18 EXP c ET RR Note 4 i e S.11 14A Function : SLC Injection (Squib) Valve ,

Note 4 t

, S 11 148 H-03 2 B 1.500 SOUlB EXP C ET RR Function : SLC Injection (Squib) Valve

=

................................................................................................................... l 8R 11 39A G-08 2 C 1.000 RV SA SYS SP RR RR-VOS Function : SLC Discharge Relief Valve SR-11 398 K-08 2 C 1.000 RV SA SYS SP RR RR-VOS

• Function : SLC Discharge Relief Valve }

................................................................................................................... j V11 16 H 03 1 A/C 1.500 CK SA SYS SC RR - ROJ V06 SO RR ROJ-VD8 s-  !

Function : SLC Injection Piping Check Valve

' v11 17 1 02 1 A/C 1.500 CK SA SYS SC RR ROJ VD8 .

50 RR ROJ-VD8 [

i Function : SLC Injection Piping Check Valve Passive

-i V11 18 I 02 1 8 1.500 GA MAN 0/LO PIT RR Function : SLC Injection Valve i V11 43A H-07 2 C 1.500 CK SA SYS 50 0 Function : SLC Pump Discharge Check Valve V11 438 J 07 2 C 1.500 CK SA SYS SO Q Function : SLC Pump Discharge Check Valve r

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i Tablo 5 ,

Valve Listing = ~

(Sorted' by Drawing Number) ,

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Drawing G-191172  !

Drawing Title : Restdual Heat Removal System

.{

Refuel ,

or Cold r Dwg Safety OM Site Norm Test Test Relief Shutdown Valve Number Coor Class Cat (!nch) Body Act Pos Type Freq Request Justif. Romerks  !

j FCV.10 160 F.15 2 8 .750 GL A0 C/FC FST C PIT RR .

STC 0 i Function : RHR Return Line Process Sampling Valve i

................................................................................................................... j FCV 10-185 J 02 2 8 .750 GL A0 0/F0 None NA Passive l Function : RHR Leakage To RHR Service Water Leak Detection FCV i SR-10 35A D 02 2 C 1.000 RV SA SYS SP 10Y Function : RHR Pump Discharge Relief Valve [

SR-10 35B D 15 2 C 1.000 RV SA SYS SP 10Y ~.

Function : RHR Pump Discharge Relief Valve  ;

SR 10 40 0 07 2 C 1.000 RV SA SYS SP 10Y Function : RHR Shutdown Cooling Suction Line Relief Valve  !

SR 10 80A L.03 2 C 4x6 RV SA SYS SP 10Y .

Function : RHR Heat Exchanger Tube $1de Rollef Valve l SR 10 808 L 14 2 C 4x6 RV SA SYS SP 10Y Function : RHR Heat Exchanger Tube Side Relief Valve *  !

..................................................................-................................................- l SR 10-86A L 03 2 C 1.000 RV SA SYS S> 10Y ,

function : RHR Heat Exchanger Shell Side Relief Valve l SR 10 868 L.14 2 C 1.000 - RV SA SYS SP 10Y Function : RHR Heat Exchanger Shell Side Relief Valve .

20.000 GA MO AC C/KL PIT  ;

V10 134 L 08 2 B RR STC 0 STO O ,

Function : Suppression Pool RHR Pump Suction Valve V10 138 L-09 2 B 20.000 GA MO-AC O/K'. PIT RR ,

STC 0 ,

STO O Function Suppression Pool RHR Pump suction Valve V10-13C J.08 2 7 20.000 GA MO-AC 0/KL P!T RR r STC 0 STO Q Function : Suppression Pool RHR Pump suction Valve

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9 Table 5.1 )

Valve Listing-(Sorted by Drawing Number)

Y h

Drawing G-191172 Orawing Title : Residual Heat Removal System Refuel or Cold #

Dwg Safety OM Size Norm Test Test Relief Shutdown Velve Number Coor Class Cat (Inch) Body Act. Pos Type Freq Request Justif. . Remarks V10 130 J-09 2 B 20.000 GA MO-AC O/KL PIT RR STC Q STO Q r o

Function s Suppression Pool RHR Pump Suction Valve V10 15A K 07 2 B 20.000 GA M0-AC C PIT RR STC Q STO Q ,

Function : Recirculation Loop Supply Valve to RHR Pump Suction  ;

V10 15B K-10 2 B 20.000 GA MO-AC C PIT RR-STC Q STO Q Function : Rectrculation Loop Supply Valve to RHR Pump Suction .!

V10 15C J-07 2 B 20.000 GA MO-AC C PIT RR STC Q STO Q Function : Recirculation Loop Supply Valve to RNR Pump Suction V10 150 J 10 2 8 20.000 GA MO-AC C' PIT RR .

STC Q l STO Q i s

Function : Recirculation Loop Supply Valve to RHR Pump Suction t

- V10-16A 1 05 2 B 4.000 GA MO AC 0 PIT RR ,

STC 0 STO Q Function : RHR Pump Discharge Mini Flow Return to Suppression Pool

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v10 16B 1 12 2 B 4.000 GA M0 AC 0 PIT RR STC 0 STO Q Function : RHR Pump Discharge Mini Flow Return to suppression Pool ,

v10-17 G 08 2 A 20.000 GA MO-AC C LT RR P!V Test  !

PIT RR STC CS CSJ V08 ST0 CS CSJ V08 Function : Recirc Supply to RHR Ptap Suct. Outbd. Isolation Valve V10-18 F-08 2 8 20.000 GA MO-AC C LT RR P!V Test t P!T RR ,

STC CS- CSJ VOS ST0 CS CSJ.V08 Function : Recirc Supply to RHR Pug Suction Inbd Isolation Valve i

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Table 5-1 Valve Listing ,

-(Sorted by Drawing Number) i i

.. Drawing G 191172 I

Drawing Title : Residual Heat Removal System T Refuel I Or Cold '

Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor Class Cat - (Inch) Body Act Pos -Type Freq Request Justif.  : Remarks  ;

V10-19A L 05 2 C 3.000 CK SA SYS SC Q Note 5 't 30 0 Note 5 &

Function : RHR Minimum Flow Check Valve [

V10 19B L 12 2- C 3.000 CK SA SYS SC Q Note 5 '

SO Q Note 5 i

. Function : RHR Minimum Flow Check Valve >

V10 19C J-05 2 C 3.000 CK SA SYS SC Q Note 5 50 Q Note 5 '

Function : RHR Minimum Flow Check Valve V10 190. J-12 2 C 3.000 CK SA SYS SC Q Note 5 '

50 Q. Wote 5

i. Function : RHR Minimum Flow Check Valve e

................................................................................................................... .7 V10-20 H-05 2 B 20.000 GA MO-AC C None NA Passive  !

Function : RHR Loop Crossconnect Valve V10 25A E 06 2 B 24.000 GA MO AC 0 PIT RR '

STC Q '

STO Q Function : RHR to Rectre Loop Isolation valve j V10 258 E 12 2 5 24.000 GA MO AC 0 PIT RR STC 0 STO Q Function : RNR to Recirc Loop Isolation Valve f V10-26A C-07 2 B 12.000 GA MO-AC C PIT RR ,

STC 0  ;

STO Q ,

Function : RHR To Containment Spray Isolation Valve ,

V10 26B C 10 2 B 12.000 GA MO AC C PIT RR t STC Q.

• i STO Q s Function RHR To Containment Spray Isolation Valve ,

V10-27A D 06 2 A 24.000 GL MO AC C LT RR P!V Test PIT RR STC 0 STO Q ,

Function : RHR to Recirc Loop Isolation Valve ,

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~ Table 5-1 valve Listing (Sorted by Drawing Number)

Drawing G 191172 Drawing Title : Residual Heat Removal System Refuel or Cold Dwg Safety OM Size Norm Test. Test Relief ' Shutdown Valve Naber Coor Class Cat (!nch) Body Act Pos Type 'Freq Request Justif. Remarks V10 27B D 12 2 A. 24.000 GL MO-AC C LT RR PIV Test PIT RR STC 0 STO Q Function : RHR to Recirc Loop Isolation Valve V10 31A C 08 2 8 12.000 GA MO AC C PIT RR STC Q STO Q Function : RHR To Containment Spray Isolation Valve V10-31B C-10 2 B 12.000 GA MO-AC C P!T RR STC Q STO Q Function : RHR To Containment Spray Isolation Valve V10-34A E-03 2 B 10.000 GL MO-AC C PIT RR -

STC Q STO Q Function : RHR Suppression Pool Cooling Supply Valve V10 345 E.14 2 B 10.000 GL MO-AC C PIT RR STC Q FTO Q Function : RHR Suppression Pool Cooling Supply Valve V10 36A J 03 2 C 1.000 CK SA SYS SC 0 Fmction : RHR Pump Discharge Pressurizing Line Check Valve V10 368 J-14 2 C 1.000 CK SA SYS SC 0 Function : RHR Pump Olscharge Pressurizing Line Check Valve V10 38A E-04 2 B 4.000 GL MO-AC C PIT RR STC Q STO Q Function : Suppression Chamber RHR Spray Ring Supply Valve V10 388 F 13 2 B 4.000 GL MO-AC C PIT RR STC Q STO Q Function : Suppression Chamber RHR Spray Ring Supply Valve Revision 16 5-40

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l Table 5-1 Valve Listing (Sorted by Drawing Number) i l

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Drawing : G-191172 Drawing Title : Residual Heat Removal System Refuel or Cold Dwg Safety OM Site Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks  ;

j V10 39A D 04 2 B 12.000 GA MO-AC C PIT RR STC 0 STO Q Function : RHR Cont Spray / Suppression Pool Cooling Supply Valve V10 398 D-13 2 8 12.000 GA MO-AC C- PIT RR STC Q  !

STO Q.

Function : RNR Cont Spray / Suppression Pool Cooling SLpply Valve V10-46A E-07 2 C 24.000 CK SA SYS LT Q Note 10 SC CS CSJ-V14

$0 CS CSJ V14 LT RR P!V Testing Function : RHR to Recirc Injection Check Valve >

V10-468 E 10 2 C 24.000 CK SA SYS LT Q Note 10 SC CS CSJ V14 t 50 CS CSJ-V14 LT RR P!V Testing i Function : RHR to Recirc Injection Check Valve V10 48A L 05 2 C 16.000 CK SA SYS SC CS CSJ V15 So CS CSJ-V15 PS0 Q =

PSC Q Function : RHR Pump Discharge Check Valve v10 688 L 13 2 C 16.000 CK SA SYS SC CS CSJ-V15 So CS CSJ V15 PSD Q PSC 0 Function : RHR Pump Discharge Check Valve V10-48C J 05 2 C 16.000 CK SA SYS SC CS CSJ V15 50 CS CSJ V15 PSO Q PSC Q Function : RHR Pump Discharge Check Valve ,

V10-480 J 13 2 C 16.000 CK SA SYS SC CS CSJ-V15 i

$0 CS CSJ-V15 PS0 Q PSC Q Function : RHR Punp Discharge Check Valve V10 57 H-13 2 A 4.000 GA MO-AC C LJ RR PIT RR STC 0 Ftmetion RHR Loop Crossconnect To RadWaste Isolation Valve v10 65A J-03 2 8 20.000 GL MO-AC 0 PIT RR ,

STC Q STO O Function RHR HM 8ypass Valve ,

Revision 16 5-41  ;

Tablo 5-1 Valve Listing (Sort'ed by Drawing Number)

Drawing G-191172 Drawing Title : Residual Heat Removal System Refuel or Cold Dwg Safety OM Size Norm Test Test Rollef Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks V10-658 K 15 2 8 20.000 GL MO-AC 0 PIT RR STC 0 STO Q Function : RHR HX Bypass Valve V10 66 H.13 2 A 4.000 GA MO-AC C LJ RR PIT RR STC Q Function : RHR Loop Crossconnect To RadWaste Isolation Valve V10 81A E 07 2 8 24.000 CA MAN 0/LO PIT RR Passive Function : RHR to Recirc Loop Injection Valve V10-818 E.10 2 8 24.000 GA MAN 0/LO P!T RR Passive Function : RHR to Rectre Loop Injection Valve V10 89A M.01 3 8 12.000 GL MO-AC C PIT RR STC Q STO Q Function : RHR HX Service Water Outlet Valve V10 898 n 17 3 8 12.000 GL MO AC C PIT RR STC 0 STO Q Function : RHR HX Service Water Outlet Valve V10 182 I-02 2 C 10.000 CK SA C None NA Passive Function : RHR$W to RHR Emergency Fill Check Valve V10 183 J 02 2 8 10.000 CA MO-AC C PIT RR Passive Function : RNRSW to RHR Emergency Fill Isolation Valve V10 184 J.02 2 8 10.000 CA MO-AC C PIT RR Passive Function : RHRSW to RHR Emergency Fill Isolation Valve I

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Revision 16 5-42 i

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.l Table 5-1 J valve Listing  ;

(Sorted'by Drawing Number) i Drawing G-191173 Sheet 1 & 2 l Drawing Title : Fuel Pool Cooling & Cleanup System j Refuel 'i or Cold -

Owg Safety DM Size Norm Test Test Relief Shutdown  !

Valve Number coor Class Cat (Inch) Body Act Pos Type Freq Request 'Justif. Remarks RV 19 232A C 07 3 C 1.000 RV SA SYS SP 10Y Function : Standby Fuel Pool Heat Exchanger FPC Side Relief Valve j RV 19-2328 F-11 3 C 1.000 RV SA SYS SP 10Y Function : Standby Fuel Pool Heat Exchanger FPC $1de Relief Valve t V19 18 t 13 3 C 6.000 CK SA SYS SC 0 -

+

Function : Fuel Pool Domineralizer Return Check Valve j V19-21A B-07 3 C 6.000 CK SA SYS SO O ,

Function : Fuel Pool Cooling Return to Fuel Pool Check Valve V19 21s B-07 3 C 6.000 CK SA SYS SO Q ,

Function : Fuel Pool Cooling Return to Fuel Pool Check Valve ,

t V19 220 G-07 3 8 8.000 GA MO-AC 0 PIT RR STC Q  ;

Function : Normal Fuel Pool Cooling Subsystem Isolation Valve  !

V19-221 G-08 3 8 8.000 GA MO AC 0 Plf RR STC 0 Function : Normal Fuel Pool Cooling Subsystem Isolation Valve V19 230A G-10 3 C 6.000 CK SA SYS SC Q ,

SO Q l Fun:: tion : Standby Fuel Pool Cooling Pump Discharge Check Valve

...............................................................................................................~....  ;

V19 2308 H 10 3 C 6.000 CK SA SYS SC Q SO Q Function : Standby Fuel Pool Cooling Pump Discharge Check Valve  !

V70 257A E 11 3 8 4.000 GL MO-AC C P!T RR STC 0 STO Q -

1 Function : SFPC Hx Service Water Outlet Throttling /! solation Valve v70-2575 F 11 3 8 4.000 GL M0-AC C P!T RR ,

0 STC l STO Q Function SFPC Hx Service Water Dutlet Throttling / Isolation valve  ;

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Table 5-1 valve Listing (Sorted by Drawing Number)

Drawing : G 191174 Sh 1 Drawing Title : Reactor Core Isolation Cooling System Refuel or Cold Dwg Safety OM Site Norm Test Test Relief Shutdown Valve Nunber Coor Class Cat (!nch) Body Act Pos Type Freq Request Justif. Remarks SL 13-55A B 08 2 A/C .750 EFC SA SYS LEF RR SC RR R0J-V01 Function : RCIC Instrumentation Excess Flow Check valve SL.13 558 C-08 2 A/C .750 EFC SA SYS LEF RR SC RR ROJ-V01 Function : RCIC Instrumentation Excess Flow Check Valve SL-13-55C s 08 2 , A/C .750 EFC SA SYS LEF RA SC RR ROJ V01 Function : RCIC Instrunentation Excess Flow Check Valve SL-13-55D C 08 2 A/C .750 EFC SA SYS LEF RR SC RR R0J.V01 Function : RCIC Instrumentation Excess Flow Check Valve SSC 13-9 K-08 2 C 8.000 GSC SA SYS 50 Q Function : RCIC Steam Exhaust Stop Check Valve SSC-13 10 K-09 2 C 2.000 CSC SA SYS SO Q Function : RCIC Barometric Cond Vacuum Punp Disch Stop Check Valve V1315 E-07 1 A 3.000 CA MO-AC 0 LJ RR PIT RR STC Q STO Q Function : RCIC Steam Supply Inboard Containment Isolation Valve V13 16 E-09 1 A 3.000 CA MO-DC 0 LJ RR PIT RR STC Q STO Q .

Function : RCIC Steam Supply Outboard Containment Isolation Valve V13 18 E 14 2 8 6.000 GA MO DC 0 PIT RR STC Q STO Q Function : Condensate Supply to RCIC Pump Suction Valve ,

V13 19 E-14 2 C 6.000 CK SA SYS SO Q Function : Condensate Supply to RCIC Punp Suction Check Valve V13 20 C 10 2 8 4.000 GA MO-DC 0 PIT RR STO Q Function : RCIC Pump Discharge Isolation Valve I

Revision 16 5-44

Tablo 5-1 Valve Listing (Sorted by Drawing Number)

Drawing : G-191174 Sh 1 Drawing Title : Reactor Core Isolation Cooling System Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor Class Cat (!nch) Body Act Pos Type Freq Request Justif. Remarks V13-21 G 09 2 B 4.000 GA MO-DC C PIT RR STO Q ,

Function : RCIC Injection Isolation Valve 50 CS CSJ-V10 Function : RCIC Injection Check Valve v13-27 I 11 2 8 2.000 GL MO-DC C PIT RR STC Q STO Q Function : RCIC Pump Discharge Minimum Flow Valve V13 29 - J-10 2 C 2.000 CK SA SYS SO Q Function : RCIC Punp Discharge Min { mum Flow Check Valve V13 30 E 10 2 B 4.000 GL MO-DC C PIT RR STC Q Function : RCIC Pump Discharge Return to Condensate Storage Tank V13 38 K 11 2 C 2.000 CK SA SYS SO Q Function : RCIC Vacuum Pump Discharge Check Valve V13 39 F-13 2 8 6.000 GA HO DC C P!T RR STC Q STO Q Function : Supp Pool Supply to RCIC Punp Suct Inbd Isol Valve V13 40 N 11 2 C 6.000 CK SA SYS SC CS CSJ V11 Function : Suppression Pool Supply to RCIC Pump Suction Check Vlv.

V13-41 N-10 2 8 6.000 GA MO-DC C PIT RR STC 0 STO Q Function : Supp Pool Supply to RCIC Punp Suct Inbd Isol Valve V13-50 K.08 2 C 8.000 CK SA SYS SO Q Note 2 Function : RCIC Turbine Exhaust Check Valve V13-817 K-07 2 C 1.000 GSC SA SYS SO Q SC Q Function : RCIC Turbine Exh vac Skr Stop Check Valve

%13 818 K-07 2 C 1.000 CK SA SYS SO Q Function : RCIC Turbine Exh vac Bkr Check Valve Revision 16 5-45 i

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Tablo 5-1 Valve Listing )

(Sorted by Drawing Number) l 1

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I Drawing G 191174 sh 2 f Drawing Title : Reactor Core Isolation Cooling System Refuel Or Cold l Dwg Safety CM $12e Norm Test Test Relief Shutdown i Valve Nunber Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks  !

.................. .... ...... ... ...... .... ..... .... ..... .... ....... ........ ............... {

LCV 13 12 L-10 3 B 1.000 CA A0 C/FC FST Q '

(

PIT RR STC Q STO Q l

Function : RCIC Baro Cond Condensate Pump Disch Drain LCV t

.................................................................................................................., l LCV 13 13 L 10 3 8 1.000 CA A0 C/FC FST Q j P!T RR i STC Q k STO Q l Function : RCIC Baro Cond Condensate Pump Disch Drain LCV l

i RCIC CONTROL D-12 2 8 2.000 GL H0 0 PIT RR I STC Q RR-V11 STO Q RR V11 l

' Function : RCIC Turbine Governing valve l l ...................................................................................................................

5 13-3 E 11 2 C 8.000 RD SA C RD SY Function : RCIC Turbine Steam Exhaust Rupture Disc j 5 13 4 E 09 NC C 8.000 RD SA C RD SY Function : RCIC Turbine Steam Exhaust Rupture Disc SR-13 26 I-07 2 C 1.500 RV SA SYS SP 10Y Function : RCIC Pump Discharge Line to Barometric cond Relief Viv SR 13 27 J 14 3 C 1.500 RV SA SYS SP 10Y Function : RCIC Barometric Condenser Relief Valve V13-70 K 13 3 C 1.250 CK $A SYS SC RR ROJ V09

$0 0 Function : RCIC Baro Cond Condensate Pump Disch Check Valve V13 131 E 15 2 B 3.000 GL MO-DC C PIT RR STC Q STO Q Function : RCIC Steam Supply Valve V13 132 G-06 2 8 2.000 GL MO-DC C P!T RR STC Q STO Q Function : RCIC Pump Discharge Valve to Barometric Condenser

................................................................................................................... ROJ V09 V13-133 K 10 2 C 2.000 CK SA SYS SC RR '

SO Q Function : RCIC Barometric Cond Condensate Punp Disch Check Valve 1,

l Revision 16 5-46 1

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,Tablo 5.1E

, Valve Listing. _ .

(Sorted by Drawing Number) _

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3 Drawing a G 191175 Sh 1 Orawlng Title : Primary containment & Atmosphere Control 'l.

i Refuel- ,

Or Cold . -.

Dws' Safety OM , Site Norm Test Test Relief' Bhutdown .

Valve Nunber ! Coor ' Class Cat (!nch) ' Body Act Pos . Type Freq Request Justif. Remarks- 1 -v

$5 16 19 6 0 01 2 A 8.000 STF - A0 0/FC FST Q .[

LJ , RR -

PIT RR r

^

STC_ Q -I

, Function

• PCAC to S8GT Containment Isolation Valve - :r

-..................................................................e................................................ l 58 16 19 6A F-02 2 A 3.000 BTF A0 C/FC FST Q  :(

LJ RR PIT AR

~

STC Q Function : PCAC Drywell Purge & Vent Outlet Bypass Cont Isol Valve

................................................................................................................... i 85 16 19-68 L 03 2- A 3.000 BTF A0 0/FC FST 0 .

LJ RR . l PIT RR STC 0 f Function : PCAC Supp Chb Prg & Vent Line Bypass Inbd Cont Isol Vlv  !

.2 C/FC FST 58 16 19-7 0 01 A '18.000 -BTF A0 Q LJ RR .

P!T RR STC 0 j Function : PCAC Purge & Vent Exhaust Containment Isolation Valve r f

SB 16-19 7A E 02 2 A 18.000 BTF A0' C/FC FST CS . CSJ V12

. LJ RR ~j PIT' RR STC- CS - CSJ V12 -l Function : PCAC Drywell Purge & Vent Outlet Cont Isol Valve  :

SB 16 19 78 K-03 2 A 18.000 BTF -A0 'C/FC FST. CS CSJ V12 _

LJ RR PIT RR STC CS CSJ V12 Funct{on : PCAC Supp Chb Purge & Vent Outlet Inbd Cont Isol Valve .

SB 16-19 8 l 12 2 A 18.000 STF A0 C/FC .FST CS- CSJ v12 LJ RR PIT. RR STC CS CSJ v12 Function : PCAC Drywell Air Purge Inlet Containment Isol Valve - [

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-Tablo'5-1 '

Valve Listing

'(Sorted by Drawirig Number)

Drawing G-191175 Sh 1 Drawing Title : Primary Containment & Atmosphere Control  !

Refuel ,

or Cold Dwg Safety OM _ Size Norm Test Test Relief Shutdown l Valve Number- Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks  ;

88 16 19-9  !.16 2 A 18.000 BTF A0 C/FC FST Q LJ RR P!T RR STC 0 Function : PCAC Air Purge Supply From Rx Blds Cont Isol Valve SB 16 19 10 J 13 2 A 18.000 BTF A0 C/FC FST CS CSJ V12 LJ RR

~

P!T RR STC CS CSJ-V12 Function : PCAC Supp Chamber Purge Supply Cont ! sol Valve

- SB 16 19 11A K-15 2 A 20.000 BTF A0 C/F0 FST Q LJ RR -

PIT RR .

STC 0 f STO Q  ;

Function : PCAC Vacuun Relief From Secondary Containment Iso Valve SB 16 19-11B M-15 2 A 20.000 BTF A0 C/F0 FST Q i LJ RR  ;

PIT RR STC Q STO Q .

Function PCAC Vacuum Rellef From Secondary Containment Iso Valve SB 16 19-23 H 15 2 A 6.000 BTF A0 C/FC FST CS CSJ V12 LJ RR PIT RR STC CS CSJ v12 -

I Function PCAC Containment Purge Supply containment Iso Valve V16 19 5A J 08 2 A/C 18.000 CK SA SYS LT RR RV SA SYS PSO Q CSJ V13 SC CS - CSJ V13  :

50 CS CSJ V13 SP - RR Note 6 i Function : Drywell To Suppression Chanber Downcomer vacuum Breaker V16-19-58 J 08 2 A/C 18.000 CK SA SYS LT RR  ;

7 RV SA SYS PSO Q CSJ V13 SC CS CSJ V13  ;

50 CS CSJ-V13 SP RR Note 6 Function : Drywell To Suppression Chamber Downcomer vacuum Breaker Revision 16 5-48

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Tablo 5-1 l Valve Listing 1 (Sorted by Drawing Number)

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Drawing : G-191175 Sh 1 Drawing Title : Primary Containment & Atmosphere Controt Refuel or Cold ,

Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor Class. Cat ......'

(Inch)Body Act Pos , Type freq Request Justif. Remarks ,

V16 19-5C J 08 2 .A/C 18.000 CK SA SYS LT RR RV SA SYS PSC 0 CSJ-V13 l SC CS CSJ V13  ;

SO CS CSJ V13 ,

SP RR Note 6

• Function : Drywell To suppression Chamber Downcomer Vacuta Breaker V16 19 50 K-08 2 A/C 18.000 CK SA SYS LT RR RV SA SYS PSO Q CSJ V13 i SC CS CSJ-V13 S0 CS CSJ-V13 SP RR Note 6 ,

Function Drywell To suppression Chamber Downcomer vacuum Breaker ,

V16-19 5E J 08 2 A/C 18.000 CK SA SYS LT RR 5 RV SA SYS PSO Q CSJ-V13 SC CS. CSJ V13 50 CS CSJ V13 SP RR Note 6 Function : Drywell To Suppression Chamber Downcomer Vacuum Breaker ,

V16 19 5F J 08 2 A/C 18.000 CK' SA SYS LT RR -

RV SA SYS PSO Q CSJ-V13 SC CS CSJ V13 ._

$0 CS CSJ V13  ;

SP RR Note 6 Function : Drywell To suppression Chamber Downcomer Vacuum Breaker v16 19 5G J 08 2 A/C 18.000 CK SA SYS LT RR RV SA SYS PSO Q CSJ V13 SC CS CSJ V13 .

, 50 CS CSJ V13 '

SP RR Note 6 Function : Drywell To Suppression Chamber Downcomer Vacuum Breaker V16 19 5H J 08 2 A/C 18.000 CK SA SYS LT RR RV SA SYS PS0 Q CSJ V13 l SC CS CSJ-V13 50 CS CSJ-V13 SP RR Note 6 Function : Drywell To Suppression Chamber Downcomer Vacuum Breaker V16-19 51 K-08 2 A/C 18.000 CK SA SYS LT RR RV SA SYS PSO Q CSJ V13 ,

SC CS CSJ V13

$0 CS CSJ V13 SP RR Note 6 Function Drywell To Suppression Chamber Downcomer Vacuum Breaker Revision 16 5-49 t

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Tablo 5-1 3 valve Listing' I (Sorted by Drawing Number) {,

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z Drawing : G-1911F5 Sh 1 [

Drawing Title : Primary Containment & Atmosphere Control. {

i Refuel l Dr. Cold  !

Dwg Safety DM Size Norm Test Test Relief Shutdown  :

Valve Number- Coor Class Cat (Inch) Body Act- Pos Type Freq Request Justif. Remarkt

.................. .... ...... ... ...... .... ..... .... ..... .... ....... ........ ............... +

b V16 19 5J J-08 2 A/C 18.000 CK SA SYS LT RR l EV SA SYS PSO Q- CSJ V13 SC CS CSJ V13  ;

So CS CSJ v13 SP RR Note 6 Function : Drywell To Suppression Chambe. Downcomer vacuum Breaker ,

- V16 19 12A K 16 2 A/C 20.000 CK SA SYS LJ RR RV SA SYS SC 0 SO O  !

SP RR Note 6 6 Function : PCAC Vacuum Relief From Secondary Containment Check Vlv l;

................................................................................................................... p V16 19-128 M-16 2 A/C 20.000 CK SA STS LJ RR RV SA SYS SC 0 ,

i- 90 0 t SP RR Note 6 {

Function : PCAC Vacuum Relief From Secondary Containment Check Vlv 1

............................................................................................~......................

V16 19-51 J-11 2 A/C 2.000 CK SA SYS LJ RR Passive f Function Gas Leak Monitoring Supply CIV Check valve ,

V16 19 52 J-11 2 A/C 2.000 CK SA SYS LJ RR Passive  ;

Function : Gas Leak Monitoring Supply CIV Check Valve .!t V16 20 20 H 12 2 A 1.000 GA SO 0/FC FST Q ,

LJ RR .;-

P!T RR STC 0 Function : PCAC Containment Purge Makeup Outbd Cont Isol Valve [

V16 20 22A H 11 2 A 1.000 CA S0 C/FC FST Q ,

t LJ RR i PIT RR '!

Q '

STC Function : PCAC Containment Purge Makeup Cont Isol Valve V16 20-228 H 12 2 A 1.000 GA S0 0/FC FST Q LJ RR  !

PIT RR $

r STC' 0 .;

Function : PCAC Containment Purge Makeup Cont Isol Valve  ;

.V20-400A bid 9 2 B 2.000 GL MAN C/LC None NA Passive l Function : forus Driin"Velve r V20 4005 b207 2 8 2.000 GL MAN C/LC None NA Passive [

Function : Torus Dr5Tn" Valve 1

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. Tablo'5-1 i

, Valve Listing' (Sorted by Drawing Number) a i

t Drawing : G 191177 Sh 1 .

Drawing Title : Redwaste Sytems

')

Refuel I

or Cold. '

Dwg Safety CM Size Norm Test Test Relief Shutdo6;,a Valve Number Coor' Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks ,

V20 82 3 04 - 2 A 3.000 BL A0 0/FC FST Q >

LJ ' RR ,

PIT RR -

STC Q . .

Function : Drywell Floor Drain Sung Containment Isolation Valve

................................................................................................................... t V20-83 8 05 2 A 3.000 BL A0 0/FC F5T Q LJ RR P!T RR STC 0 r Function : Drywell Floor Drain Sump containment Isolation Valve tE*.*.....................*.=............=....-...=........-=...-.......-...........*.--.=........... .

V20 94 G 04 2 A 3.000 BL A0 0/FC FST Q .

LJ RR t

. t-PIT RR STC Q Function : Drywell Equipment Drain Sump Containment Isolation Vlv V20 95 G 05 2 A 3.000 BL A0 0/FC FST Q .

LJ RR PIT ' RR STC Q  :

Function : Drywell Equipment Drain Sunp containment Isolation Vlv .t V20 319A' D 06 2 8 1.500 GA MAN C None NA Passive 'h Function : Rx Bldg Floor Drain Pump To Suppression Pool Iso Valve

...........................~....................................................................................... ,

v20 319e D 06 2 8 1.500 GA - ~ MAN C None NA Passive Function : Rx stdg Floor Drain Punp To suppression Pool Iso Valve V20 319C C.08 2 8 1.500 GA MAN C None NA Passive Function : Rx Bldg Floor Drain Pung To suppression Pool Iso Valve V20 3190 C-08 2 5 1.500 GA MAN C None WA Passive .

Function : Rx Bldg Floor Drain Punp To suppression Pool Iso Valve .

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Revision 16 5-51 i

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Table 5-1 valve Listing (Sorted by Drawing Number)

Drawing : G-191178 Sh 1 Drawing Title : Reactor Water Clean Up System i

Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Yalve Nunber Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks V12 15 D-02 1 A 4.000 GA MO-AC 0 LJ RR P!1 RR STC Q Function : Remetor Water cleanup containment Isolation Valve V12 18 D-03 1 A 4.000 GA MO AC 0 LJ RR PIT RR STC Q Function : Reactor Water Cleanup containment Isolation Valve V12 28A D-08 3 C 3.000 CK SA SYS SC Q Function : RWCU Pump Discharge Check Valve V12 288 G 08 3 C 3.000 CK SA SYS SC Q Function : RWCU Pump Discharge Check Valve V12-62 B 05 2 C 4.000 CK SA SYS CD RR Note 11 Function : RWCU Flow to Feedwater System Isolation Check Valve V12 62A B-05 3 C 4.000 CK SA SYS CD RR Note 11 Function : RWCU Flow to Feedwater System Isolation Check Valve Revision 16 5-52

t Table 5-1  :

Valve Listing I (Sorted by Drawing Number) {

Drawing : G 191237 Drawing Title : HVAC Turbine, Service & Control Room Big Refuel or Cold Dwg Safety OM Site . Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pc . Type Freq Request Justif. Remarks SACC 1A CHECK A 18 3 .C 1 000 CK SA SYS so e functfon : Cont Room HVAC Chiller Refrigerrt Piping Check Valve

,. SACC u RELIEF A 18 3 C 1.000 RV SA SYS SP 10Y Function : Cont Room HVAC Chlller Refrigerant Piping Relief Valve f' SACC-1B CHECK A 19 3 C 1.000 CK SA ~ sYs so e Function : Cont Room HVAC Chiller Refrigerant Piping Check Valve SACC 1B RELIEF -A-19 3 C 1.000 RV- SA SYS SP 10Y Function : Cont Room HVAC Chiller Refrf geran Piping Relief Valve SCW-8A I-11 3 C 3,000 CK SA SYS so e Function Control Room HVAC Chilled Water Pump Ditch Check Valve i ~ SCW 65A H 11 3 B .750 GL . SA C None NA Passive I Function : Control Room HVAC Chilled Water Makeup ! solation Valve Revision 16 5-53

r Tablo 5-1

, Valve Listing (Sorted by Drawing Number)

Drawing : G 191238 Drawing Title : HVAC - Reactor Building Refuel or Cold Dwg Safety CM Site Norm Test Test Relief Shutdown Valve Number coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks SB 1 125 1A G OS 2 8 12.000 BTF A0 C/F0 FST Q PIT RR STC 0 STO Q Function : Standby Gas Treatment Train Inlet valve SB 1 125 1B G 07 2 8 '12.000 BTF AC C/F0 FST Q P!T RR STC 0 STO Q Function : Standby Gas Treatment Train Inlet Valve SB.1 125 2A H 06 2 B 12.000 BTF A0 0/F0 FST Q P!T RR STC 0 STO Q Function : Standby Gas Treatment Train Inlet Valve 58 1 125 2B H-06 2 B 12.000 BTF AC C/F0 FST Q >

P!T RR STC 0 STO Q ,

Function : Standby Gas Treatment Train Inlet valve +

SB 1 125-3A G 06 2 8 12.000 BTF A0 0/F0 FST Q P!T RR STO O Function Standby Gas Treatment Train Discharge Valve 58 1 125 38 G-06 2 B 12.000 BTF A0 C/F0 FST Q PIT RR -

. STO Q ,

Function : Standby Gas Treatment Train Discharge Valve

. 58 1 125 4A H 07 2 B 12.000 BTF A0 C/FC FST Q PIT RR STC Q .

STO Q ,

Function Standby Gas Treatment Train Dilution Valve 58 1-125-48 H 06 2 B 12.000 BTF A0 C/FC FST Q P!T RR STC 0 ,

STO Q Function : Standby Gas Treatment Train Dilution valve 58 1 125-5 G 06 2 B 4.000 BTF A0 C/FC FST Q PIT RR STC 0 STO Q Function : Standby Gas Treatment Train Xconn valve j

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l .. Valve Listing  ;

(Sorted' by Drawing. Number) ,

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Drawing G 191238 Drawing Title : MVAC . Reactor Building Refuel i' or Cold I

=

Dwg Safety OM Size Norm Test Test Relief Shutdown Freq' Request- Justif.

Valve Number Coor Class Cat (!nch) Body Act 'Pos Type Remarks 581 125 7A F-07 2 C 12.000 CK SA C SC 0 50 o '  ;

Function : Standby Gas Treatment Train Discharge Check Valve 58 1 125-73 7-07 2 C 12.000 CK SA C SC 50 Q

Q '

i Function : Standby Gas Treatment Trafn Discharge Check Valve

$8*9 H-09 2 8 54.000 BTF A0 0/FC FST C P!T RR J STC 0 Function : RX Building Supply Isolation valve 58 10 H-08 2- B 54.000 BTF A0 0/FC FST Q PIT RR l t

STC 0 I

Function : RX Building Supply Isolation Valve 58 11 G-08 2 8 54.000 BTF A0 0/FC FST C P!T , RR .

STC Q Function : Rx Blds Exhaust to stack Sec Cond Isolation Valve SB 12 G 09 2 8 54.000 87F A0 0/FC FST C PIT RR STC Q Function : Rx Blds Exhaust to Stack Sec cond Isolation Valve

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Table 5-1 Valve Listing (Sorted by Drawing Number)

Drawing : G-191267 Sh 1 Drawing Title : Nuclear Boller Vessel Instrumentation Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor Class Car (Inch) Body Act Pos Type Freq Request Justif. Remarks SL 2 3-11 C 06 2 A/C 1.000 EFC SA SYS LEF R9 S0 RR ROJ V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2-3-13A D 06 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve SL 2-3-13B C-12 2 A/C 1.000 EFC SA SYS LEF RR SC RR R0J-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL-2-3 15A D-06 2 A/C 1.000 EFC SA SYS LEF RR Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2-3 15B D 12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL-2-3 17A E-06 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function Nuclear Boller vessel Inst Excess Flow Check valve SL-2-3-17B E 12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL*2 3 19A F 06 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 3 19B F-12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 3-21A H 06 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve SL 2-3 218 I 04 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function Nuclear Boller vessel Inst Excess Flow Check Valve 1

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'fatt>1ae 5 - 1 I Valve Listing l (Sorted by Drawing Number) i i

Drawing : G 191267 sh 1 Drawing Title : Nuclear Boller Vessel Instrumentation Refuel or cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks SL-2 3 21C H-12 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL.2 3 21D l 12 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 3 23A G-06 1 A/C 1.000 EFC CA SYs LEF RR SC RR ROJ V01 Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve SL 2 3-23B G-04 1 A/C 1.000 EFC SA SYS LEF RR SC RR R0J*V01 Function Nuclear Boiler Yessel Inst Excess Flow Check Valve SL-2 3-23C G 12 1 A/C 1.000 EFC SA SYS LEF RR SC RR R0J V01 Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve SL.2 3-230 G-12 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 3-25 I 04 2 a/C 1 000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL-2 3 27 1 06 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 3-31A G-04 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve

' Revision 16 5-57

T Table 5-1 Valve Listing (Sorted-by Drawing Number)

Drawing G-191267 Sh 1 Drawing Title : Nuclear Boller Vessel Instrumentation

! Refuel

[ Or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks SL-2-3-31B F-06 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve j ...................................................................................................................

SL 2 3 31C F 06 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 3 31D F-06 i A/C 1.000 EFC SA SYS LEF RR l SC RR R0J-V01

! Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2-3-31E F 06 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01

) Fuiction : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2-3-31F F-06 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL-2-3-31G F-06 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 3 31H F 06 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL-2-3 311 F 12 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function Nuclear Boller Vessel Inst Excess Flow Check valve SL 2 3 31J F-12 1 A/C 1.000 EFC SA SYS LEF RR SC RR R0J-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 3 31A F 12 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2-3 31L F-12 1 A/C 1.000 EFC SA SYS LEF RR SC RR R0J V01 Fu3ction : Nuclear Boller vessel Inst Excess Flow Check Valve 1

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Valve Listing.

(Sorted by Drawing Number)  ;

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Drawing : G 191267 Sh 1

• Drawing Title : Nuclear Boller Vessel Instrunentation t

[' Refuel ,

r' or Cold l Dwg Safety OM Size -Norm Test Test Relief Shutdown ,

Valve Nunber Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. . Remarks l.' SL-2 3-31M F 12 1 A/C 1.000 EFC SA SYS LEF RR SC RR R0J V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve If SL 2 3 31N- F 12 1 A/C 1.000 EFC SA SYS LEF RR ,

f; SC RR ROJ-V01 }

Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve  ;

SL-2 3-31P F 12 1 A/C 1 000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve r SL-2 3 310 F 12 1 A/C 1.000 EFC SA SYS LEF RR [

SC RR ROJ-V01 Function : Nuclear Boiler Vetsel Inst Excess Flow Check Valve

• SL 2 3-33 1 12 2 A/C 1.000 EFC SA SYS LEF KR }

SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve

• SL 2 3-35 J-06 2 .A/C 1.000 EFC SA SYS LEF RR {

l SC RR R0J-V01 r Fu7Ct{on: Nuclear Boller Vessel Inst Excess Flow Check Valve i

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Table 5-1 valve Listing i (Sorted by. Drawing Number) l Drawing G 191267 Sh 2 Drawing Title : Nuclear Boller Vessel Instrunentation k Refuel Or Cold Dwg - Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks V 2-3 430A C 09 2 A/C 0.3 75 CK . SA SYS .LJ RR SC RR ROJ V15-Function : Reference Leg Back Fill Inlet Check Valve V 2 3-4308 E-09 2 A/C 0.3 75 CK SA SYS LJ RR SC RR ROJ-V15 p- Function : Reference Leg Back Fill Inlet check Valve

}

V-2-3 432A C 10 2 A/C 0.375 CK SA SYS LJ RR SC RR ROJ V15 i Function : Reference Leg Back Fill Inlet Check Valve f V-2 3 4328 E 10 2 A/C 0.3 75 CK SA SYS LJ RR SC RR R0J-vi5

r. Function : Reference Leg Back Fill Inlet Check Valve V 2 3 433A F 09 2 A/C 0.3 75 CK SA SYS LJ RR SC RR ROJ-v15 Function : Refersnee Leg Back Fill Inlet Check Vstve V 2-3 4338 H-09 2 A/C 0.3 75 CK SA SYS LJ RR SC RR ROJ V15 Function : Reference Leg Back Fill Inlet Check Valve

V 2 3 435A F-10 2 A/C 0.3 75 CK SA SYS LJ RR l SC RR R0J V15 Functlon

Reference Leg Back Fill Inlet Check Valve V 2 3-4358 H 10 2 A/C 0.375 CK SA SYS LJ RR SC RR R0J V15 Function : Reference Leg Back Fill Inlet Check Valve l

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E Tablo 5-1 Valve-Listing (Sort'ed by Drawing Number)

Drawing VY E.75 002

- Drawing Title : Containment Atmosphere Ollution System Refuel  !

Or Cold

~!

Dwg safety OM ' Site Norm Test . Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks FSO.109 75A.1 J.13 2 8 1.000 GA 30 C/FC FST Q Note 7 PIT RR i Q i STC STO Q Function : CAD Sample Torus Inboard IsotatIon Valve FSO 109 75A 2 J-14 2 8 1.000 GA 30 C/FC FST Q Note 7 PIT RR STC 0 STO Q Function : CAD Sample Torus outboard Isolation Valve FS0-109 75A-3 J 14 2 B 1.000 GL SC C/FC FST Q Note 7 ,

PIT RR STC Q STO Q Function : CAD Supply Torus Inboard Isolation Valve FSO-109 75A 4 J-14 2 5 1.000 GL SC C/FC FST Q Note 7 .

P!T RR l STC Q STO Q Function CAD Supply Torus outboard Isolation Valve FS0 109 758 1 1-12 2 8 1.000 GA SO 0/FC FST Q Note 7 PIT RR 1 STC Q STO Q ,

Function : CAD Sample Lower Drywell Inboard Isolation Valve FSO 109 758 2 I 12 2 B 1.000 GA SO 0/FC FST Q Note 7 PIT RR '

STC 0 STO Q Function : CAD Sample Lower Drywell Outboard Isolation Valve ,

...................................................................................................................- )

FSO.109 75C 1 G 12 2 B 1.000 GA $0 0/FC FST Q Note.7  ;

PIT RR  ;

STC Q j FTO Q Function : CAO Sample Mid Drywell Inboard isolation Vatve l

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Valve Listing (Sorted by Drawing Number) i Drawing i VY-E M 002 Drawing Title : Containment Atmosphere Dilution System Refuel .!

Or Cold

- Dwg Safety CM Size Norm Test Test Relief Shutdown Valve Number coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks a PSO 109 M C 2 G.12 2 B 1.000 CA So C/FC FST Q Note 7 P!T RR STC 0  ;

STO Q  !

Function i CAD Sample Mid Drywell outboard Isolation Valve ,

4 FSO.109-MD-1 G 12 2 8 1.000 GA . SO 0/FC FST Q Note 7 PIT RR STC Q STO Q .

Function : CAD Semple Upper Drywelt Inboard Isolation valve '[

F50 109 MD-2 G 12 2 B 1.000 GA $0 0/FC FST Q . Note 7 ,

PIT RR '

STC Q FTO Q .i Fmction : CAD Sample Upper Drywell Outboard Isolation Valve FSO-109 76A L.13 2 A 1.000 GA SO 0/FC FST Q >

I LJ RR PIT RR STC Q STO Q Function : CAD CAM Return Containment Isolation Valve FSO 109 768 L.13 2 A 1.000 GA SO 0/FC FST Q  !

LJ. RR PIT RR I STC Q t STO Q ,

Function CAD CAM Return Containment Isolation Valve  !

NG 11A H 09 2 A 1.000 GL So C/FC FST Q LJ RR P!T - AR .

STC C STO Q Function : CAD N2 Supply Containment !aolation Valve NG 118 H 08 2 A 1.000 GL S0 C/FC FST Q .

LJ RR  !

P!T RR STC Q v STO Q Function : CAD N2 Supply Containment Isolation Valve }

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Tablo 5-1 valve Listing (Sorted by Drawing Number) {

r Drawing VY E 75 002 Drawing Title : Containment Atmosphere Dilution System  ;

Refuel  ;

Or Cold ,

Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Nunber Coor Class Cat (Inch) Body Act Pos Type- Freq Request Justif. Remarks ,

. .t NG 12A J 09 2 -A 1.000 GL SO C/FC FST Q-LJ RR .

PIT RR STC Q STO Q.

• Function : CAD N2 Supply Containment Isolstion valve i NG 128 J 08 2 A 1.000 GL 50 C/FC FST Q LJ RR '

P!T RR STC 0 STO Q Function 2 CAD N2 Supply containment Isolation valve

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NG 13A I 09 2 A 1.000 GL' SD C/FC 'FST Q .

t LJ RR r P!T RR STC Q STO Q Function : CAD N2 Supply Containment isolation valve

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NG 13B H 09 2 A 1.000 GL $0 C/FC FST Q LJ RR j P!T RR 4 STC Q STO Q i Function : CAD N2 Supply Containment Isolation valve VG 9A H 12 2 A 1.000 GL $0 C/FC FST Q LJ RR i i

PIT RR f

STC 0 STO Q  !

Function : CAD To SBGT System containment Isolation Valve

................................................................................................................... l VG 9B 1 14 2 A 1.000 GL $0 C/FC FST Q- }

5 LJ RR P!T RR I

STC Q STO Q Function : CAD To $8GT System containment Isolation valve Revision 16 5-63 l

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Tablo 5-1 Valve Listing (Sorted by Drawing Number)

Drawing VY E 75-002 Drawing Title : Containment Atmosphere Dilution System  ;

Refuel Or Cold i Dwg Safety OM ' Size Norm Test Test Retfef Shutdown i Velve Number coor Class Cat (Inch) Body Act Pos . Type Freq Request Justif. Romerks VG 22A B 16 2 A 1.000 GL MO AC C LJ RR  ;

P!T RR STC Q STO Q ,

. Function : CAD To SBGT System contairveent Isolation valve ,

VG 228 E 16 2 .A 1.000 GL MO AC C LJ RR -

P!T RR STC 0 '

STO Q Function : CAD To $8GT System Containment Isolation Valve ,

VG 23 J-19 2 A 1.000 GL 50 O/FC FST Q LJ RR PIT RR STC Q STO Q Function : CAD Rad Monitor supply containment Isolation Valve VG 24 L 11 2 8 1.000 GL SO 0/FC FST Q Note 7 PIT RR STC Q STO Q Function : CAD H202 Analyzer Return Isolation Valve i VG 25 L.11 2 8 1.000 GL SO 0/FC FST Q Note 7 PIT RR STC 0 +

STO Q .

Function : CAD H202 Analyzer Return Isolation valve c VG 26 J.19 '2 A 1.000 GL S0 c/FC FST Q LJ RR PIT RR STC Q STO Q  ?

Fmction : CAD Rad Monitor Supply Contairvnent Isolation valve . .

VG 33 - L 11 2 B .1.000 GL SO 0/FC .FST Q Note 7 PIT - RR STC. Q .

STO Q Function : CAD H202 Analyzer Return Isolatlon Valve I

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t Tablo 5-1 .

Valve Listing .

(Sort'ed by Drawing. Number)  !

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Orawing  !

VY-E 75-002' Drawing Title : Containment Atmosphere Dilution System Refuel  !

Or Cold ,

Dwg Safety OM Site Norm . Test Test Relief ' Shutdown i Valve Number coor Class Cat (Inch) Body Act Pos Type Freq Request Justlf. Remarks VG 34 L 11 2 8 1.000 GL 50 0/FC FST C Note 7 l PIT RR STC 0 STO Q Function : CAD H202 Analyzer Return ! solation Valve 4

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Revision 16 5-65

1'cdals) 5-1 Valve Listing (Sorted by Drawing Number)

Drawing : 5920-271 Drawing Title : Neutron Monitoring System Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Reserks BV71 C 07 2 A .3 75 BL SC C/FC FST Q LJ RR PIT RR Note 8 STC Q Function : Neutron Monitoring System Tip Tube Ball Valve BV72 C-07 2 A .3 75 BL SD C/FC FST Q LJ RR

- PIT RR hote 8 STC Q Function Neutron Monitoring System Tip Tube Ball Valve BV.7-3 C-07 2 A .3 75 BL $0 C/FC FST Q LJ ' RR PIT RR Note 8 STC Q Function Neutron Monitoring System Tip Tube Ball Valve S 7-1 C 07 2 D .3 75 Scu!B EXP 0 ET RR Function : Neutron Monitoring System Tip Tube Shear Valve S72 C 07 2 0 .3 75 Sau!B EXP O ET RR Function Neutron Monitoring System Tip Tube Shear Valve S73 C 07 2 D .3 75 SCUIB EXP O ET RR Function : Neutron Monitoring System Tip Tube Shear valve V 7-113 C-08 2 A/C .500 CK SA SYS LJ RR SC RR RCJ V11 Function : Neutron Monitoring System Tip Purge Iso. Check Valve Revision 16 5-66

t. 5.3 Valva NotGa In addition to the acceptance criteria established in accordance with Part 10 of the Code, the below criteria will also be applied for the valves so noted in the Valve Listing (Table 5-1).

Note Criteria

1. Full stroke exercising and timing tests are accomplished quarterly when reactor power is decreased to less than 75 percent. At least twice a week, the MSIVs are also exercised by e partial closure and subsequent reopening.

2. Valves will also be disassembled and inspected at least once every 10 years. (LER 87-18 and NRC Inspection Report 50-271/87-21)

3. Testing of valve V3-138 is not required when the corresponding i control rod has been declared inoperable and its directional f control valves disarmed in accordance with the provisions of

Technical Specifications 3.3.A.2.

4. During each refueling outage, explode one of the three charges manufactured in the same batch to verify proper function. Then install the untested charges in the explosive actuator.

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5. Proper valve operation is shown by the decrease in pump discharge pressure upon opening of valves V10-16A/B and by

, proper automatic closure of V10-16A/B at approximately 2000 gpm.

6. Each refueling outage, each valve will be set pressure tested to determine the force required to open each valve from fully closed to fully open. This test satisfies the set pressure requirements of paragraph 3.3.2.3 'a) of Part 1 of the Code.

7. Only one valve in each line is required to be operable in accordance with Technical Specifications Table 4.7.2.b.

8. Positive verification of full opening'of the valves is shown by  ;

successful insertion of the Transversing In-Core Probe through the valve. Positive verification of full closing of the valve is shown during each 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. j i

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5.3 Valve Notes (Con' t)

9. The SRV's will be tested in accordance with the requirements'of OM-1 only.

10 . - These valves are verified closed and essentially leaktight on a:

quarterly basis in accordance with OP'4124.

11. . These valves will be partially disassembled, inspected and manually exercised each refueling outage in accordance with-subsection 4.3.2.4 (c) of Part 10'of the Code.

12. These valves are considered passive. These valves are not tested.in accordance'with Part 10 of the Code. These valves shall be cycled once each. refueling as part of an augmented testing program due to the 1994 Service Water System Self Assessment Report.

13. These valves are part-stroke exercised on a quarterly. basis during plant operation and during cold shutdowns when all-four.

Service Water pumps are in operation. Refer to ROJ-V14.

Revision 16 5-68

[_

l f2 COLD SHUTDOWN' JUSTIFICATION Numbers' CSJ-V01, Revision IL (Sheet 1 of 1)

SYSTEM: ' Reactor Building Closed Cooling Water i

COMPONENTS: f 1

i OM Safety- .

Dwg i

Valve Number Cat Class Drawing Number Coor l 1

IV70-113' CL 2 G-191159'Sh 3 K-08 .

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V70-117 B 2 G-191159 Sh 3 L-12 ]

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. Valves V70-113 and V70-117 are reactor buildingLclosed cooling water'  ;

supply and return containment. isolation valves. .They have a safety i function in the closed position to provide primary containment . isolation. l

'I JUSTIFICATION:

These valves' cannot be tested during normal (power) operation since i shutting these valves would stop cooling water flow to' vital primary j containment equipment, ' including the primary containment air coolers and the-reactor recirculation pumps. .j P

These valves will be exercised during Cold Shutdowns and each' Refueling Outage in' accordance with Paragraphs 4.2.1.2 (f) & (g).and 4.3.2.2(f) & (g) l

'of Part 10 of the Code. j l

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i COLD SHUTDOWN JUSTIFICATION Number: CSJ-V02, Revision 1 (Sheet 1 of 1)

SYSTEM: Instrument Air j COMPONENTS:

l. OM Safety Dwg Valve Number Cat Class Drawing Number Coor <

V72-89B A/C 2 G-191160 Sh 3 J-12

'V72-89C A/C 2 G-191160 Sh 3 K-15 k

I These check valves are the drywell instrument nitrogen supply header o isolation valves. They have a safety function in the closed position to provide primary containment isolation.

JUSTIFICATION:

These valves cannot be tested during normal (power) operation since isolating these valves for testing could result in closure of the air operated Main Steam Isolation valves, thereby causing a reactor scram.

These valves will be exercised during Cold shutdowns and each Refueling Outage in accordance with Paragraphs 4.3.2.2 (f) & (g) of Part 10 of the Code.

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3 COLD SHUTDOWN JUSTIFICATION Number: CSJ-V03, Revision 1 (Sheet 1 of 1)

SYSTEM: Nuclear Boiler

' COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor SR-2-14E C 2 G-191167 L-12 SR-2-14F C 2 G-191167 L-12 SR-2-14G C 2 G-191167 L-12 SR-2-14H C 2, G-191167 L-12 SR-2-14I C 2 G-191167 L-12 SR-2-14J C 2 G-191167 -

L-12 SR-2-14K C 2 G-191167 L-12 SR-2-14L C 2 G-191167 L-12 These valves are the main steam relief valve discharge line vacuum breakers. They have a safety function in the open position to break a vacuum in the relief valve discharge lines due to steam condensation following a relief valve actuation. Formation of a vacuum would result in drawing up water from the suppression pool into the discharge line and excessive backpressure at the relief valve discharge upon successivd relief valve actuations. ,

THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 15 OF THE IST PROGRAM.

Revision 16 5-71

COLD SHUTDOWN JUSTIFICATION Number: CSJ-V04, Revision 1 (Sheet 1 of 1)

SYSTEM: Nuclear Boiler COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor 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.

JUSTIFICATION:

These valves cannot be exercised during reactor power operation since cycling these valves would result in a reactor recirculation pump trip.

These valves will be exercised and verified operable during Cold Shutdowns and each Refueling Outage in accordance with Paragraphs 4.2.1.2 (f) & (g) of Part 10 of the Code.

Revision 16 5-72

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y COLD SHUTDOWN JUSTIFICATION Number: CSJ-V05, Revision 1 (Sheet 1 of 1)

SYSTEM: Core Spray COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor 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.

JUSTIFICATION:

These valves cannot be exercised during normal (power) operation since core spray. pump discharge cannot overcome reactor pressure. Manual exercising is precluded during power operation since the valves are inside the inerted drywell.

These valves will be manually exercised during Cold shutdowns when the drywell is accessible and during each Refueling Outage in accordance with Paragraph 4.3.2.2. (f) & (g) of Part 10 of the Code.

t Revision it 5-73

COLD SEUTDOWN JUSTIFICATION ,

Number CSJ-V06, Revision 0 (Sheet 1 of 1)

SYSTEM: High Pressure Coolant Injection COMPONENTS: ,

OM Safety- Dwg Valve Number Cat Class' Drawing Number Coor 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 clossd position to prevent backflow in the event of a HPCI high energy line break.

JUSTIFICATION: ,

This valve cannot be exercised 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 during Cold Shutdowns and each ,

Refueling Outage in accordance with Paragraphs 4.3.2.2 (f) & (g) of Part 10 l of the Code.

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COLD SHUTDOWN JUSTIFICATION Number: CSJ-V07, Revision 0 (Sheet 1 of 1)

SYSTEM: High Pressure Coolant' Injection COMPONEN'I'S :

OM Safety Dwg Valve Number Cat Class Drawing Number Coor V23-61 C 2 G-191169 Sh 1 L-06 This valve is the High Pressure Coolant Injection (HPCI) torus suction check valve. The valve has a safety function in the open position to permit HPCI pump suction from the suppression pool after system realignment upon a condensate storage tank low level condition.

JUSTIFICATION:

This valve cannot be exercised during normal (power) operation since no full flow test loop is available to recirculate the water back to the suppression pool. There is no means to manually exercise the valve.

This valve will be exercised during Cold Shutdowns and each Refueling Outage in accordance with Paragraphs 4.3.2.2 (f) & (g) of Part 10 of the Code.

Revision 16 5-75

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COLD SHUTDOWN JUSTIFICATION Number: CSJ-V08, Revision 1 (Sheet 1 of 1)

SYSTEM: Residual Heat Removal COMPONENTS:

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OM Safety Dwg

, Valve Number Cat Class Drawing Number Coor V10-17 A 2 G-191172 G-08 V10-18 B 2 G-191172 F-08 l

These valites are the Residual Heat Removal (RRR) shutdown cooling supply l isolation valves. They have a safety function in the closed position to 3

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i provide primary containment and pressure isolation, and in the open position to provide RHR pump suction during shutdown cooling operation. l

! i JUSTIFICATION:

Th'se e valves cannot be exercised during reactor power operation since there is a 100 psig 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 exercised during Cold shutdowns and each Refueling Outage in accordance with Paragraphs 4.2.1.2 (f) & (g) of Part 10 of the Code.

Revision 16 5-76 I

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COLD SHUTDOWN JUSTIFICATION

. Number CSJ-V09, Revision ~ 1 -(Sheet 1 of 1) i SYSTEM: Residual Heat Removal COMPONENTS:

OM Safety. Dwg Valve Number Cat Class Drawing Number Coor-V10-46A C 2 G-191172 E-07

V10-46B C 2 G-191172 E-10 These. valves are the Low Prassure Coolant Injection (LPCI) primary

-containment isolation check valves. They have a safety function in the open position to pass LPCI f2cw to the reactor, and in the closed position for primary containment and pressure isolation.

THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 15 OF THE.IST PROGRAM PLAN.

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Revision 16 5-77 6

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COLD SHUTDOWN JUSTIFICATION Number: CSJ-V10, Revision 1 (Sheet 1 of 1) i SYSTEM: Reactor Core Isolation Cooling gCMPONENTS:

OM Safety Dwg Valve Number Cat . Class Drawing Number Coor V13-22 C 2 G-191174 Sh 1 G-09 This valve is the Reactor Core Isolation Cooling (RCIC) discharge to Feedwater Line "B" check valve. The valve has a safety function in the open position to pass RCIC flow to the reactor and in the closed position to prevent backflow following a RCIC high energy line break.

JUSTIFICATION:

This valve cannot be exercised in the open direction 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.

This valve is located in the steam tunnel which is inaccessible during power operations. Additionally, there is no means to manually exercise this valve.

This valve will be exercised during Cold Shutdowns and each Refueling

, Outage in accordance with Paragraphs 4.3.2.2 (f) & (g) of Part 10 of the Code.

Revision 16 5-78 I

COLD SHUTDOWN JUSTIFICATION Number: CSJ-Vil, Revision 1 (Sheet 1 of 1) l SYSTEM: Reactor Core Isolation Cooling j COMPONENTS:

I OM Safety Dwg Valve Number Cat. Class Drawing Number Coor V13-40 C 2 G-191174 Sh 1 N-11 l

1 This valve is the Reactor Core Isolation Cooling (RCIC) torus suction i check valve. The valve has a safety function in the open position to .

l permit RCIC pump suction from the suppression pool after system j realignment upon a condensate storage tank low level condition.

I, JUSTIFICATION:

This valve cannot be exercised during normal (power) operation since no full flow test loop is available to recirculate the water back to the suppression pool. There is no means to manually exercise the valve.

This valve will be exercised during Cold Shutdowns and each Refueling Outage in accordance with Paragraphs 4.3.2.2 (f) & (g) of Part 10 of the Code.

Revision 16 5-79

COLD SHUTDOWN JUSTIFICATION Number: CSJ-V12, Revision 1 (Sheet 1 of 1)

SYSTEM: Primary Containment Atmospheric Control COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor SB-16-19-7A A 2 G-191175 Sh 1 E-02 SB-16-19-7B A 2 G-191175 Sh 1 K-03 SB-16-19-8 A 2 G-191175 Sh 1 I-12 SB-16-J9-10 A 2 G-191175 Sh 1 J-13 SB-16-23 A 2 G-191175 Sh 1 H-15 These valves are Primary Containment Atmospheric Control (PCAC) system primary containment isolation valves. They have a safety function in the closed position to previde primary containment isolation and to maintain the required differential pressure between the drywell and the suppression chamber during power operation.

JUSTIFICATION:

These valves can only be exercised with the drywell to suppression chamber pressure equalized. The drywell to suppression chamber differential pressure is maintained during reactor operation to ensure proper downcomer submergence. Proper downcomer submergence ensures integrity of the suppression chamber when subjected to post-LOCA suppression pool hydrodynamic forces.

To minimize reactor operation without the differential pressure between the drywell and the suppression chamber, these valves will be exercised during Cold Shutdowns and each Refueling Outage in accordance with Paragraphs 4. 2.1.2 (f) & (g) of Part 10 of the Code.

Revision 16 5-80 1

I COLD SHUTDOWN JUSTIFICATION Number: CSJ-V13, Revision 1 (Sheet 1 of 2)

KYSTEM: primary Containment Atmospheric Control .

COMPONENTS:

OM Safety Dwg Drawing Number Valve Number Cat Class Coor V16-19-5A A/C 2 G-191175 Sh 1 J-08

'V16-19-5B A/C 2 G-191175 Sh 1 J-08 .

V16-19-5C A/C 2 G-191175 Sh 1 J-08 V16-19-5D A/C 2 G-191175 Sh 1 K-08 V16-19-5E A/C 2 G-191175 Sh 1 J-08  ;

V16-19-5F -

A/C 2 G-191175 Sh 1 J-08 V16-19-5G A/C 2 G-191175 Sh 1 J-08 e V16-19-5H A/C 2 G-191175 Sh 1 J-08 V16-19-5I A/C 2 G-191175 Sh 1 K-08 V16-19-5J A/C 2 G-191175 Sh 1 J-08 These valves are the drywell to suppression chamber downcomer vacuum 3 breakers. They have a safety function to operate to maintain the required-differential pressure between the drywell and the suppression chamber during power op'eration. ,

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Revision 16 5-81

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COLD SHUTDOWN JUSTIFICATION Number: CSJ-V13, Revision 1 (Sheet 2 of 2)

JUSTIFICATION:

These valves can en~y be exercised with the drywell to suppression chamber pressure equalized. The drywell to suppression chamber differential pressure is maintained during reactor operation to ensure proper downcomer submergence. Proper downcomer submergence ensures integrity of the suppression chamber when subjected to post-LOCA suppression pool hydrodynamic forces.

To minimize reactor operation without the differential pressure between '

the drywell and the suppression chamber, yet provide assurance of operability, each drywell to suppression chamber downcomer vacuum breaker will be manually full stroke exercised quarterly and following any release of energy to the suppression chamber, but breakaway force will not b2 measured.

~

During Cold Shutdowns and each Refueling Outage, each drywell to suppression chamber downcomer vacuum breaker will be full stroke exercised and both breakaway and opening forces will be measured in accordance with Paragraph 1.3.4.3 of Part 1, and Paragraphs 4.3.2.2 (f) , (g) and (h) and 4.3.2.4 of Part 10 of the Code.

During each Refueling Outage, at least two (2) of the ten (10) drywell to suppression chamber downcomer vacuum breakers will also be disassembled and inspected. If deficiencies are found such that the requirements of Vermont Yankee Technical Specifications section 3.7.A.6 are not satisfied, all of the drywell to suppression chamber downcomer vacuum breakers will be disassembled and inspected and deficiencies corrected.

Revision 16 5-82 4

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1 COLD SHUTDOWN JUSTIFICATION Number: CSJ-V14 Revision 0 (Sheet 1.of 1)

SYSTEMS. Residual Heat Removal  ;

COMPONENTS:

OM Safety Dwg '

Valve Number. Cat Class Drawing Number Coor  ;

i V10-46A C 2 G-191172- E-07 Vla-4dB C 2 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 during normal (power) operation since the Residual Heat Removal (EER) pump discharge cannot overcome reactor pressure. Manual exercising is not possible during plant operation because the valves are located inside the inerted drywell and are not accessible during plant operation.

These valves will be exercised with flow during Cold Shutdown and~

Refueling Outages in accordance the Code. Full stroke exercising to the open position will be verified by passing the maximum required accident condition flow through the valves.

Revision 16 5-83 I

COLD SHUTDOWN JUSTIFICATION Number: CSJ-V15 Revision 0 (Sheet 1 of 1)

SYSTEM: Residual Heat Removal COMPONENTS:

J OM Safety Dwg

} Valve Number Cat Class Drawing Number Coor V10-40A C 2 G-191172 L-05 j 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 'dle RHR pump.

Justification:

It is not practical to perform a full-stroke 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 exercised during plant operation and will be full-stroke exercised during cold shutdowns and refueling outages.

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3 Revision 16 5-84

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> :- REFUELING OUTAGE JUSTIFICATION Number: ROJ-V01, Revision 1--(Sheet 1 of 4)

SYSTEM:- Nuclear Boiler High Pressure Coolant Injection

,_ Reactor Core' Isolation Cooling

Recirculation Pump Cooling Water I- -

COMPONENTS:

). '-

li .

OM Safety -

Dwg H

p -Valve Number- Cat Class Drawing Number Coor L

+

SL-13-55A A/C 2 G-191174 Sh 1 B-08 SL-13-55B A/C 2 G-191174 Sh 1 C-08 i: ~

L. SL-13-55C A/C 2 G-191174 Sh 1 B-08 r

SL-13-55D A/C 2 G-191174 Sh~1' C-08 L SL-14-31A A/C 2 G-191168 F-07 SL-14-31B A/C 2 G-191168 E-07 l.

SL-2-62A A/C 2 G-191167 I-13 G-191167 SL-2-62B A/C 2 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 A/C 2 G-191167 ,

K-13 SL-2-64B ,

A/C 2 G-191167 K-13 SL-2-64C A/C 2 G-191167 K-13 1

SL-2-64D A/C 2 G-191167 L-13

• SL-2-73A A/C 2 G-191167 F-12 SL-2-73B A/C 2 G-191167 .F-12 . y u

SL-2-73C A/C 2 G-191167 G-12 SL-2-73D A/C 2 G-191167 G-12 Revision 16 5-85 h

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i REFUELING OUTAGE JUSTIFICAT70N Number: ROJ-V01, Revision 1 (Sheet 2 of 4)

OM Safety -

Dwg Valve Number Cat Class Drawing Number Coor SL-2-73E A/C 2 G-191167 G-12 l SL-2-73F A/C 2 G-191167 G-12A SL-2-73G A/C 2 G-191167 H-12 SL-2-73H A/C 2 G-191167 H-12 SL-2-2-7A A/C 2 G-191159 Sh 5 G-02 f SL-2-2-7B A/C 2 G-191159 Sh 5 G-02 SL-2-2-8A A/C 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 D-04 SL-2-3-13A A/C 2 G-191267 E-04 SL-2-3-13B A/C 2 G-191267 E-12 SL-2-3-15A A/C 2 G-191267 F-04 SL-2-3-15B A/C 2 G-191267 F-12 SL-2-3-17A A/C 2 G-191267 F-04

, SL-2-3-17B A/C 2 ,

G-191267 F-12 SL-2-3-19A A/C 2 G-191267 G-04 SL-2-3-19B A/C 2 G-191267 G-12 SL-2-3-21A A/C 1 G-191267 I-04 SL-2-3-21B A/C 1 G-191267 I-04 SL-2-3-21C A/C 1 G-191267 I-12 SL-2-3-21D A/C 1 G-191267 I-12 SL-2-3-23A A/C 1 G-191267 G-04 Revision 16 5-86

i REFUELING OUTAGE JtWiTIFICATION

' Number: ROJE V01,iRevision 1 (Sheet 3 of 4)

F- 3 OM Safety ~ .

Dwg l v Valve' Number Cat Class Drawing Number Coor G-191267.

g .SL-2-3-23B A/C 1 G-04

) SL-2-3-23C .A/C 1 G-191267 G-12 -

i SL-2-3-23D' A/C 1 G-191267L G SL-2-3-25. A/C 2 G-191267- I-04'-

SL-2-3-27 A/C 2 G-191267 'J-04 SL-2-3-31A .A/C 1 G-191267 G-04

~

SL-2-3-31B A/C 1 G-191267 G L SL-2-3-31C A/C 1 G-191267 G-04 4 SL-2-3-31D A/C 1 G-191267 . G-04 SL-2-3-31E A/C 1- G-191267 G-04 SL-2-3-31F A/C. 1 . G-191267 G-04 SL-2-3-31G A/C 1 G-191267 G-04 SL-2-3-31H A/C 1 G-191267 G-04 SL-2-3-31I A/C 1 G-191267 H-12 SL-2-3-31J . A/C 1 G-191267 H-12 SL-2-3-31K A/C 1 G-191267 H-12 SL-2-3-31L A/C 1 -

G-191267 H-12  !

SL-2-3-31M A/C 1 G-191267 H-12 j SL-2-3-31N A/C 1 G-191267 H-12 _

SL-2-3-31P A/C 1 . 3,91267 H-12  !

Revision 16 5-87

REFUELING OUTAGE JUSTIFICATION Number: ROJ-V01, Revision 1 (Sheet 4 of 4)

OM Safety Dwg Valve Number Cat Class Drawing Number Coor t SL-2-3-31Q A/C 1 G-191267 H-12 SL-2-3-33 A/C 2 G-191267 I-12 SL-2-3-35 A/C 2 G-191267 J-04 l

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-04 SL-23-37B A/C 2 G-191169 Sh 1 F-04 SL-23-37C A/C 2 G-191169 Sh 1 F-04 SL-23-37D A/C 2 G-191169 Sh 1 F-04 These valves are instrumentation line excess flow check valves. They are required to be verified operable in accordance with Vermont Yankee Technical Specification 3.7.0.1.

JUSTIFICATION: 1 These valves cannot be exercised during power operation since shutting these valves would isolate instrumentation required for power operation.

These valves can only be verified to shut by leak testing performed during the primary system inservice pressure test performed each refueling outage. This test cannot be repeated during each Cold Shutdown since the reactor vessel is not at pressure during Cold Shutdowns.

These valves will be exercised each Refueling Outage during leakage rate testing performed in accordance with Paragraph 4.2.2.3 of Part 10 of the code.

Revision 16 5-88

R3 FUELING OUTAGE JUSTIFICATION Number: ROJ-V02, Revision l' (Sheet 1 of 2)

SYSTEM: Nuclear Boiler eCOMPONENTS:

L r

OM Safety .

Dwg Valve Number Cati Class Drawing Number -Coor i l

RV-2-71A C 1 G-191167 D  ;

RV-2-71B C 1 'G-191167 G-08  ;

RV-2-71C C 1 G-191167 G-08 RV-2-71D C 1 G-191167 H-08

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1 Valves RV-2-71A through D are the nuclear boiler main steam safety / relief valves. They have a safety function in the open position for Automatic ,

Depressurization System (ADS) operation and for overpressure protection, and in the closed position to maintain reactor coolant inventory. ,

JUSTIFICATION:  ;

Stroke testing of these valves quarterly during power operation is not recommended. As recommended by NUREG-0737 and the corresponding study by  :

the BWR Owners Group (BWR Owners Group Evaluation of NUREG-0737, Item j II.K.3.16, " Reduction of Challenges and Failures of Relief Valves"), the 1 exercising of these valves should be minimized to reduce the number of challenges to safety / relief valves.

Revision 16 5-89

i REFUELING OUTAGE JUSTIFICATION Number: ROJ-V02, Revision 1 (Sheet 2 of 2)  !

JUSTIFICATION (con't): l 1

The~ failure of any relief valve to close during stroking at power l operation would cause an uncontrolled rapid depressurization of the

- primary system (stuck oopen-relief valve transient) along with an  !

undesired positive reactivity excursion.

These valves can only be tested with primary system pressure greater than i 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. '

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i Revision 16 5-90  !

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REFUELING OUTAGE JUSTIFICATION Number: -ROJ-V03, Revision 1-(Sheet 1 of 2)

V: I g SYSTEM - Nuclear Boiler -

COMPONENTSt I l

OM Safety Dwg Valve Number Cat Class Drawing Number Coor V2-27A A/C 2 G-191167 F-03 V2-27B C 2 G-191167 H-02 V2-28A A/C 2 G-191167 F-05 .I i

V2-28B A/C 2 G-191167 H-05 ,

l V2-96A A/C 2 0 191167 H-03 l V2-96B C 2 G-191167 F-03  :

t

=  ?

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 primary  !

containment isolation, and in the open position to pass High Pressure Coolant Injection flow to the reactor.

Valves V2-96A and V2-28B are the outboard and inboard containment j for the "B" Feedwater Line, respectively. They isolation check valves

, 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. >

f 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.  :

i 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. f i

Revision 16 5-91 l

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REFUELING OUTAGE JUSTIFICATION ]

Number: ROJ-V03, Revision 1 (Sheet 2 of 2) l JUSTIFICATION: ,

/ ,

t These valves cannot be tested during normal (power) operation because the feedwater system is required to maintain reactor vessel water level.

Interruption of feedwater to perform the exercise test of these valves  :

would result in a reactor scram.

These valves can only be backflow tested via a leak type or non-intrusive test. Testing during Cold Shutdowns is impractical due to the significant system and test equipment configurations required. Additionally, valves i 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 Cleanup System) .

These valves will be backflow exercised each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.2.2.3 of Part 10 of the Code. Valves V2-27A, V2-28A, V2-28B and V2-96A will be exercised to the full open position by the proper operation of the feedwater system at plant startup.

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t Revision 16 5-92 f

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REFUELING OUTAGE JUSTIFICATION J Number ROJ-V04, Revision C (Sheet 1 of 1)

SYSTEM: Nuclear Boiler COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor V2-37A A/C 2 G-191167 B-08 V2-37B A/C 2 G-191167 G-09 V2-37C A/C 2 G-191167 G-09 V2-37D , A/C 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 backflow exercised during normal power operations or Cold shutdowns when the drywell is inerted. These valves can only be backflow tested via a leak type or non-intrusive test which would require isolating the instrument nitrogen supply to the MSRVs. Testing during Cold Shutdowns is impractical due to the significant system and test equipment configurations required. ,

These valves will be backflow exe'rcised each Refueling Outage during leakage rate testing performed in accordance with Paragraph 4.2.2.3 of Part 10 of the Code.

i II Revision 16 5-93 i

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4 REFUELING OUTAGE JUSTIFICATION Number: ROJ-V05, Revision 0 (Sheet 1 of 1)

SYSTEM: Nuclear Boiler .

COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor V2-82A A/C 2 G-191167 B-10 V2-82B A/C 2 G-191167 B-10 V2-82C A/C 2 G-191167 B-10 V2-82D A/C 2 G-191167 B-10 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 of instrument air or nitrogen supply.

JUSTIFICATION:

Valves V2-82A through D are located in the drywell and thus cannot be backflow exercised during normal power operations or Cold Shutdowns when the drywell is inerted. .

Valves V2-87A through D are located in the main steam tunnel which is inaccessible during power operations, thus, these valves cannot be backflow exercised during normal power operations.

These valves can only be backflow 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 impractical due to the significant system and test equipment configurations required.

These valves will be backflow exercised each Refueling Outage during leakage rate testing performed in accordance with Paragraph 4.2.2.3 of Part 10 of the Code.

Revision 16 5-94

REFUELING OUTAGE JUSTIFICATION Number: ROJ-V06,cRevision 1 (Sheet 1. of 2)

SYSTEM: Control Rod Drive Hydraulic COMPONENTS: (Typical of 89)  !

OM Safety Dwg l Valve Number Cat Class. Drawing Number Coor CV-3-126 B 2 G-191170 C-16 1 CV-3-127 B 2 G-191170 C-18 SE-3-120 B 2 G-191170 D-16 ,

SE-3-121 B 2 G-191170 D-18  ;

SE-3-122 B 2 G-191170 C-16 SE-3-123 B 2 G-191170 -C-17 V3-114 C 2 G-191170 C-18 ,

t V3-115 A/C 2 G-191170 B-16 Valves CV-3-126 & 127 are the Control Rod Drive-(CRD) scram valves. These valves have a safety function in the open position to pass scram ,

accumulator discharge to the control rod drives for a reactor scram. -l Valves SE-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 discharge into the exhaust water header or the drive water header. l Valves SE-3-121 & 122 are the manual control exhaust and withdrawal valves, respectively, for the CRO over piston area. These valves have a ,

safety function in the closed position to ensure that scram exhaust flow  ;

is properly directed to the discharge volume.

Valve V3-114 is the scram exhaust to the discharge volume check valve. l This valve has a safety function in the open position to pass scram  ;

exhaust flow to the discharge volume.

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1 Revision 16 5-95 l

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REFUELING OUTAGE JUSTIFICATION Number ROJ-V06, Revision 1 (Sheet 2 of 2) valve V3-115 is the charging water.to the CRD accumulator check valve.

This valve has a safety function in the closed position to prevent diversion of scram accumulator discharge into the charging header. t JUSTIFICATION: (

Exercising valves CV-3-126, CV-3-127, V3-114'and V3-115 during power

. operation would require scramming the plant solely for testing purposes.

Since scram insertion times are representative of valve operability and i 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 a refueling outage basis and that 50% of the control rods be measured for scram times every 16 to 32 weeks. An evaluation is required that provides reasonable assurance .

t that proper control rod drive performance is being maintained. These '

tests will adequately verify valve operability and stroke times.  !

Valves SE-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 l 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 control rod is fully inserted will not i result in an increase in safety or quality. All control rods drives are I verified operable in accordance with Technical Specifications 4.3.B.1 each i Refueling Outage, thus stroke testing of these valves for control rods  !

that remained fully inserted throughout the operating cycle will occur each Refueling Outage.  !

t 1

These valves will be exercised as a minimum each Refueling Outage in l accordance with Paragraphs 4.2.1.2(h) and 4.3.2.2 (h) of Part 10 of the  !

Code. >

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e Revision 16 5-96 ,

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V; REFUELING OUTAGE JUSTIFICATION i

Number ROJ-V07,. Revision 1 (Sheet 1 of 1)  ;

SYSTEM: Control Rod Drive Hydraulic COMP.ONENTSt o

OM Safety Dwg-  !

{.

i Valve Number Cat Class Drawing Number Coor r

V3-412A A/C 2 G-191170 E-12 V3-412B A/C 2 G-191170 E-12 4

i V3-413A A/C 2 G-191170 E-12

{ V3-413B A/C 2 G-191170 ,

E-12 l i

These valves are the recirculation pump _ seal purge supply check valves, d

They have a safety. function in the closed position to provide primary' containment isolation.

JUSTIFICATION: [

These valves can only be backflow tested via a leak type or non-intrusive  !

test which would require iso'.ating the seal purge to the recirculation pumps. To preclude adverse affects on seal life, the recirculation pumps ,

would have to be secured. Testing during Cold Shutdowns is impractical due to the significant system and test equipment configurations required.

a These valves will be backflow exercised each Refueling Outage durino leakage rate testing performed in accordance with Paragraphs 4.2.2.'2 and a 4.2.2.3 of Part 10 of the Code.

l Revision 16 5-97

i REFUELING OUTAGE JUSTIFICATION ,

Number: ROJ-V08, Revision 1 (Sheet 1 of 1)

SYSTEM: Standby Liquid Control-COMPONENTS:

E OM Safety Dwg Valve Number Cat Class Drawing Number Coor l V11-16 A/C 1 G-191171 H-03 V11-17 A/C 1 G-191171 I-02 These valves are the Standby Liquid Control (SLC) injection line check valves. They 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 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 I actuated valves. Backflow testing requires drywell entry and the removal of at least one explosive actuated valve. ,

These valves will be backflow exercised each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.2.2.3 of Part 10 of the Code. -

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Revision 16 5-98 i

1

REFUELING OUTAGE JUSTIFICATION -!

i Number: ROJ-V09, Revision 0 (Sheet 1 of 1)

SYSTEM:. Reactor Core Isolation Cooling COMPONENTSt  ;

OM Safety .

, Dwg Valve Number Cat Class Drawing Number Coor.  ?

V13-70 C 3 G-191174 Sh 2 K-13

. i G-191174 Sh 2 V13-133 C 2 K-10 These valves are the Reactor Core Isolation Cooling (RCIC) barometric condenser condensate pump discharge check valves. They have a safety 3 function in the' open position to allow pump down of the-RCIC barometric condenser hotwell for level control, and in the closed position to prevent backflow of condensate storage tank water into the RCIC barometric condenser.

JUSTIFICATION:

These valves can only be tested via a leak type or non-intrusive test that requires that RCIC to be taken out of service for an extensive period of time. Testing during Cold shutdown is also impractical due to the significant system and test equipment configurations required.

These valves will be exercised each Refueling Outage in accordance with Paragraph 4.3.2.2 (h) of Part 10 of the Code.,

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Revision 16 5-99

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l REFUELING OUTAGE JUSTIFICATION Number: ROJ-V10, Revision 0 (Sheet 1 of 2) j SYSTEM: Reactor Water Clean Up COMPONENTS o

l OM Safety Dwg-Valve Number Cat Class Drawing Number Coor ,

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 V12-62A C 3 G-191178 Sh 1 B-05  ;

Valves V12-28A and V12-28B are the Reactor Water Clean Up (RWCU) pump discharge check valves. These valves have a safety function in the closed position to prevent the backflow of RWCU water into the RWCU pump space in ,

the event of a RWCU high energy line break.

Valves V12-62 and V12-62A are check valves at the discharge of the RWCU system to the "B" Feedwater Line. These valves have a safety function in the closed position to' prevent backflow of Feedwater or. Reactor Core Isolation Cooling (RCIC) into the RWCU system in the event of a RWCU high -

energy line break.

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Revision 16 5-100

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REFUELING OUTAGE JUSTIFICATION j Number: ROJ-V10, Revision 0 (Sheet.1 of 2) {

SYSTEM: Reactor Water Clean Up-c COMPONENTS:

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, OM Safety Dwg Valve Number Cat Class Drawing Number Coor' I f

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 ,

V12-62A C 3- G-191178 Sh 1 B-05 t i

I Valves V12-28A and V12-28B are the Reactor Water Clean Up. (RNCU) pump discharge check valves. These valves have.a safety function in the closed position to prevent the backflow of RWCU water into the RWCU pump space in i the event of a RWCU high energy line break. j Valves V12-62 and V12-62A are check valves at the discharge of the RWCU i system to the "B" Feedwater Line. These valves have a safety function in the closed position to prevent backflow of Feedwater or Reactor Core Isolation Cooling (RCIC) into the RWCU system in the_ event of a RWCU high.

energy line break.

THIS COLD SHUTDOWN JUSTIFICATION WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM. -

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1 3 KEFUELING OUTAGE JUSTIFICATION

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Number:c ROJ-V10, Revision 0- (Sheet '2 of 2)

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REFUELING OUTAGE JUSTIFICATION Number: ROJ-Vil,_ Revision 1 (Sheet 1 of 1) J SYSTEM: Neutron Monitoring System ,

i COMPONENTS:

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OM Safety .

Dwg ,

Drawing Number-

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Valve Number Cat Class Coor V-7-113 A/C 2 5920-271 -C-08 ,

This valve is the Neutron Monitoring System (NMS) Tip Purge primary [

containment. isolation valve. This valve 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 l nitrogen purge is required during operation-and Cold shutdown to prevent ,

condensation and corrosion in the NMS Tip system. ,

These valves will be backflow exercised each Refueling Outage during i leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.2.2.3 of Part 10 of the Code. ,

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Revision 16 5-102

REFUELING OUTAGE JUSTIFICATION Number: ROJ-V12, Revision 0 (Sheet 1 of 1)

SYSTEM: Control Rod Drive Hydraulic i COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number .Coor V3-162A A/C 2 G-191170 A-09 V3-162B A/C 2 G-191170 A-01 l

} These valves are the Control Rod Drive (CRD) scram discharge volume vent

! check valves. They have a safety function in the closed position to l isolate the scram discharge volume during a scram condition, thereby l preventing reactor coolant inventory loss.

I JUSTTFICATION:

These valves cannot be exercised during normal (power) operation since this would require taking the CRD system out of service, f

These valves can only be backflow tested via a leak type or non-intrusive test which would require removing the CRD system from service. Testing during Cold shutdowns is impractical due to the significant system and test equipment configurations required.

These valves will be backflow exercised each Refueling Outage during leakage rate testing performed in accordance with Paragraphs 4.2.2.2 and 4.2.2.3 of Part 10 of the Code.

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REFUELING OUTAGE JUSTIFICATION Number: ROJ-V13, Revision 1 . (Sheet 1~of.1) *

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SYSTEM: ' Residual Heat ~ Removal' COMPONENTS,:  :

OM -Safety. Dwg  ;

Valve Number Cat- Class Drawing Number Coor  ;

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V10-46A C 2 G-191172 E-07

• V10-46B C 2 G-191172 E-10 i i

l This refueling outage justification has been withdrawn. Refer to CSJ-V14.

This item was changed in Revision 16 of the Inservice. Test Program Plan.  ;

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REFUELING OUTAGE JUSTIFICATION Number: ROJ-V14, Revision 0 (Sheet l'of 2)

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SYSTEM: -Service Water COMPONENTS:

y OM Safety .

Dwg Valve Number Cat Class Drawing Number Coor I

V70-1A C 3 G-191159 Sh 1 C-03 V70-1B C 3 G-191159 Sh 1 B-03 V70-1C C 3 G-191159.Sh 1 I i V70-1D C 3 G-191159 Sh 1 H-03 l-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 operation. They have a function in the closed position to prevent the diversion of cooling water through an idle station Service Water pump. -

EXAM OR TEST CATEGORY:

Category C.

CODE REQUIREMENT: 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."

Revision 16 5-105 7

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REFUELING OUTAGE JUSTIFICATION Number: ROJ-V14, Revision 0 (Sheet 2 of 2)

I JUSTIFICATION:

Vermont Yankee's operating, shutdown and refueling history indicates that operation of all four (4) service water pumps is required during power

operations and at cold shutdowns during approximately 7 months of the year to meet operating and shutdown cooling heat load requirements. Because of ultimate heat sink temperatures and required service water loads, operating three (3) service water pumps during these periods does not provide adequate cooling capacity.

The check valves will be part-stroke exercised during the regularly i scheduled quarterly service water pump tests. These valves will be full- I stroke exercised during each cold shutdowns and refueling outage, only if operation with three (3) service water pumps is permissible based on the ultimate heat sink temperature and required cooling loads.

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Revision 16 5-106

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REFUELING OUTAGE JUSTIFICATION

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Number ROJ-V15, Revision 0 (Sheet 1 of 1)

. SYSTEM: Nuclear Boiler. Vessel Instrumentation OM Safety Dwg Valve Number Cat Class Drawing Number Coor i

L V-2-3-430A A/C 2 G-191267 Sh 2 C-09

-V-2-3-430B A/C 2 G-191267 Sh 2 E-09 V-2-3-432A A/C 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 F-09 V-2-3-435A A/C 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: ,

i These valves cannot be exercised during power operations or during cold r 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 backfil, system is to ensure that the reactor water level reference leg fluid does not become saturated with-non-condensible 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-condensible gases to the reference legs.

These valves will be verified closed each Refueling Outage during 10 CFR 50 Appendix J leakage rate testing performed in accordance with Paragraph 4.2.2.2'of Part 10 of the Code.

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Revision 16 5-107 l

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REFUELING OUTAGE JUSTIFICATION Number: ROJ-V16, Revision 0 (Sheet 1 of 1)

SYSTEM: Service Water OM Safety Dwg Valve Number Cat Class Drawing Number Coor 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 V70-2B B 3 G-191159 Sh 1 B-03 V70-2C B 3 G-191159 Sh 1 J-03 V70-2D B 3 G-191159 Sh 1 J-03 These valves are the Service Water System Header Supply Isolation Valves.

The safety function of these valves is to close in order to isolate the upstream portions of the Service Water System when transferring to the Alternate Cooling mode of operation.

JUSTIFICATION:

It is impractical 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 crains to the Reactor Building Closed Cooling Water system heat exchangers (E-8-1A or E-8-1B), the RHR heat exchangers (E14-1A or E14-1B) and the emergency diesel generator lube oil and jacket water coolers. Interruption of flow to these components could cause damage to equipment. These valves shall be full-stroke exercised during refueling outages when cooling flow to these components can be isolated.

Revision 16 5-108 i

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REFUELING OUTAGE JUSTIFICATION Numbert ROJ-V17,' Revision 0 (Sheet 1 of 1) j

'l SYSTEM: Service Water l t

q OM- Safety Dwg ]

j Valve Number Cat Class Drawing Number Coor i

1 V70-15A B 3 G-191159 Sh 1- J-08  !

.V70-15B B 3 G-191159 Sh 1 B ,

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t These valves are the Service Water System Header Supply Isolation Valves.

The safety function of these valves is to close in order eliminate the of'

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Alternate Cooling Flow from bypassing the cooling tower while the Service Water System is in the Alternate Cooling mode of operation. l i

JUSTIFICATION:

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It is impractical to full or part-stroke exercise these. valves on a  :

quarterly basis or during cold shutdowns. Closure of either of these i 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 (E9-1A 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 when these cooling loads can be l safely isolated. l

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Revision 16 5-109  !

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REFUELING OUTAGE JUSTIFICATION Number: ROJ-V18, Revision 0 (Sheet 1 of 1)

SYSTEM: Service Water' OM Safety Dwg Valve Number Cat Class Drawing Number Coor ,

V70-187A B 3 G-191159 Sh 1- J l V70-187B B 3 G-191159 Sh 1 'B-06 i

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 Alternate Cooling mode of operation.

JUSTIFICATION:

l It is impractical 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 to the Service Water Pump gland seals.

Interruption of gland seal flow to these pumps could cause damage to the mechanical seals which could prevent it from performing its intended safety function. The Service Water Pumps are required to be operable >

during power operation and cold shutdowns for cooling to other loads. i These valves shall be full-stroke exercised during refueling outages.

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Revision 16 5-110 l I

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REFUELING OUTAGE JUSTIFICATION Number: ROJ-V19, Revision 0 (Sheet 1 of 1)

SYSTEM: Service Water OM Safety Dwg Valve Number Cat Class Drawing Number Coor V70-17 B 3 G-191159 Sh 2 D-06 V70-11 B 3 G-191159 Sh 2 D-07 SB-70-1 B 3 G-191159 Sh 2 D-09 Valve V70-11 when open provides water to the Cooling Tower Basin to prevent the development of ice in the basin. Valve V70-17 when open provides flow to the Cooling Tower spray header to provide an alternate cooling path for the Service Water System. The Main Condensor Discharge Block Valve (SB-70-1) when open provides 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 Alternate Cooling mode of operation.

JUSTIFICATION:

It_is impractical to full or part-stroke exercise these valves during power operation or during cold shutdowns. The design of the-Service Water-System requires that whenever the Connecticut River temperature is greater than 4 5'F, the Service Water System discharge is aligned to the Circulating Water Discharge to the river. Whenever the river temperature is less than 45'F, the Service Water System is aligned to the cooling tower basin to ensure that the basin water does not freeze.

Valves V70-11 and SB-70-1 should not be opened simulataneously, except for the minimum time required for system lineup changes, because the potential exists for the tower basin to be drained. A minimum level is required in the cooling tower basin for the alternate cooling mode of operation.

V70-17 will be full-stroke exercised on a quarterly basis when V70-11 is open during the colder months of plant operation. The opening of V70-17 when SB-70-1 is open could cause the pipework upstream of V70-17 to drain.

The draining of the upstream pipework could cauce a pressure transient and potentially damage pipework if flow were initiated to the spray header.

Valves V70-11 and SB-70-1 shall be full-stroke exercised when the cooling configuration of the Service Water System is changed due to the change in river water temperature. V70-17 shall be full-stroke exercised on a quarterly basis when SB-70-1 is closed. As a minimum each valve will be full-stroke exercised at least once per refueling cycle.

4 Revision 16 5-111

l REFUELING OUTAGE JUSTIFICATION Number: ROJ-V20, Revision 0 (Sheet 1 of 1)

SYSTEM: Service Water I-OM Safety Dwg Valve Number Cat Class Drawing Number Coor-o V70-18 B~ 3 G-191159 Sh 2 E-07.

i This valve is the Service Water Header Discarge Isolation Valve. The safety function of these valves is to close in order to contain inventory of vital cooling water when the Service Water System is in the Alternate Cooling mode of operation.

JUSTIFICATION:

It is impractical to full or part-stroke exercise this valves on a quarterly basis or during cold shutdowns. Closure of this valva'could l

interrupt cooling flow from plant components such'as the Reactor Building Closed Cooling Water system heat exchangers (E-8-1A or E-8-1B), and the emergency diesel generators 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 when these cooling loads can'be safely isolated.

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RELIEF REQUEST I i

Numbers RR-V01, Revision 1 (Sheet 1 of 1) l l

SYSTEM: Service Water COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor 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- 3 in the open position to provide cooling for the RHRSW pump motor during l operation.

EXAM OR TEST CATEGORY:

Category B.

THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.

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i Revision 16 5-113 l

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l RELIEF REQUEST Number: RR-V02, Revision 1 (Sheet 1 of 1) i SYSTEM: Service Water  ;

COMPONENTS: -

i OM Safety Dwg l Valve Number ., - Cat Class Drawing Number .Coor-

'V70-1A C 3 G-191159,,Sh 1 C-03 -

V70-1B C 3 G-191159 Sh 1 B-03 t

l V70-1C -C 3. G-191159 Sh 1 I-03 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 provi'de cooling water .

to systems and equipment required to operate under accident conditions and  !

to provide an inexhaustible supply of water for standby coolant system. i operation. They have a function in the closed position to prevent the i diversion of cooling water through an idle station Service Water pump. j EXAM OR TEST CATEGORY:

1 Category C. 4 THIS RELIEF REQUEST WAS WITHDRAWN IN REVISON 16 OF THE IST PROGRAM PLAN. '

REFER TO REFUELING OUTAGE JUSTIFICATION ROJ-V14.

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RFLIEF REOUEST Number: RR-V03, Revision 1 (Sheet 1 of 3)

EXHTEM: Diesel Generator Starting Air COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor 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 EDG, to prevent EDG and/or piping damage after the EDG starts, and to prevent inadvertent EDG starts.

EXAM OR TEST CATEGORY:

Category B.

CODE REQUIREMENT: 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."

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Revision 16 5-115

RELIEF REOUEST Number: RR-V03, Revision 1 (Sheet 2 of 3)

CODE REOUIREMENT (con' t) : Part 10 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."

l REOUEST FOR RELIEF:

Relief is requested on the basis that compliance with the Code requirements is impractical and that the proposed alternatives would provide an acceptable level of quality and safety.

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.

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 performed 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 EDG 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.

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.

Revision 16 5-116

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RELIEF RECUEST Number RR-V03, Revision 1 (Sheet 3 of 3)

ALTERNAT? METHOD (con' t) :

During EDG fast start testing performed every six months, indirect measurement that at least one of the 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 start times.

In addition, to further assess the operational readiness of each air start inlet valve, an independent operability test is performed once per operating cycle. This test will be accomplished by alternately 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:

l Relief was granted in the March 1994 SER [ Reference (u)] for Relief Request RR-V03, Revision 1.

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RELIEF REQUEST Number RR-V04, Revision 1 (Sheet 1 of 1)

RYSTEEL Fuel-Oil Transfer-COMPONENTS:

OM Safety Dwg Valve Number Cat Class ' Drawing Number Coor V78-2 C 3 G-191162 Sh 2 E-02 Valve V78-2 is the fuel oil-storage tank' fill line check valve. It has a safety function in the_close positicn to ensure fuel oil system integrity upon loss of the non-safety related fill line piping.

EXAM OR TEST CATEGORY:

Category C.

THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM.

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Revision 16 5-118 l

RELIEF. REQUEST l Number: RR-VOS, Revision 1 (Sheet 1 of 1)

SYSTEM: Nuclear Boiler. j COMPONENTS:

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_OM Safety .Dwg Valve Number Cat Class Drawing Number Coor i

S' RV-2-71A B/C 1 'G-191167 D-08 RV-2-71B B/C 1 G-191167 G-08

'RV-2-71C- B/C 1 G-191167 G-08 l

, RV-2-71D B/C 1 G-191167 H-08 SV-2-70A C 1 G-191167 D-08 SV-2-70B C' 1 G-191167 H-08 ,

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Valves SV-2-70A and SV-2-70B are the main steam safety valves. They have-  :

a safety function to prevent over-pressurization of the-reactor coolant system.

t 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 reactor coolant Automatic l Depressurization System (ADS).

EXAM OR TEST CATEGORY:

Category C -l THIS RELIEF REQUEST WAS WITHDRAWN IN REVISION 16 OF THE IST PROGRAM. ,

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Revision 16 . 5-119 l

l RELIEF REQUEST t lRumber: RR-V06, Revision 0 (Sheet 1 of 2)  !

SYSTEM: High' Pressure Coolant Injection COMPONENTS:  !

OM Safety Dwg .

Valve. Number. Cat Class Drawing Number Coor.

HPCI-CONTROL B 2 G-191169 Sh 2 F-13 l

1 This valve is the High Pressure Coolant Injection (HPCI) turbine steam inlet control valve. It has a safety function to operate to provide and-  ;

regulate steam to the HPCI turbine.

EXAM OR TEST CATEGORY

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Category B.

d CODE REQUIREMENT: Part 10 Para. 4.2.1.8(b) " Stroke Time Acceptance Criteria" "Other power-operated valves with reference stroke times greater than 10 see shall exhibit no more than i 25% change in stroke time when compared to the reference value."

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i REQUEST FOR RELIEF: .

Relief is requested on the basis that compliance with the Code ,

requirements is impractical and that the proposed alternatives would provide an acceptable level of quality and safety.

The motive force for the HPCI turbine Stop and Control valves is supplied from the Turbine force feed lubrication system. A review of historical data indicates that variations in valve stroke times exist between tests run with a primed versus an unprimed hydraulic system. Similar effects have been seen at other plants, as described in General Electric SIL No.

336, Revision 1.

Revision 16 5-120

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RELIEF REQUEST Number: RR-V06, Revision 0 (Sheet 1 of 2)

SYSTEM: High Pressure Coolant Injection COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor HPCI-CONTROL B 2 G-191169 Sh 2 F-13 This valve is the High Pressure Coolant Injection (HPCI) turbine steam inlet Control valve. It has a safety function to operate to provide and regulate steam to the HPCI turbine.

EXAM OR TEST CATEGORY:

Category B.

CODE REQUIREMENT: Part 10 Para. 4. 2.1. 8 (b) " Stroke Time Acceptance Criteria" "Other power-operated valves with reference stroke times greater than 10 see shall exhibit no more than i 25% change in stroke time when compared to the reference value."

REQUEST FOR RELIEF: .

Relief is requested on the basis that compliance with the Code requirements is impractical and that the proposed alternatives would provide an acceptable level of quality and safety.

The motive force for the HPCI turbine Stop and Control valves is supplied from the Turbine force feed lubrication system. A review of historical data indicates that variations in valve stroke times exist between tests run with a primed versus an unprimed hydraulic system. Similar effects have been seen at other plants, as described in General Electric SIL No.

336, Revision 1.

Revision 16 5-120

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F RELIEF REQUEST Number RR-V06, Revision 0 (Sheet 2 of 2)

REQUEST FOR RELIEF (con' t) :

To minimize the amount of variability induced by the degree of hydraulic system priming, the Turbine Stop and Control valves are timed from onset of valve movement as shown by receipt of intermediate position indication to full open indication during valve surveillance testing. This timing method minimizes the affects that the time required for hydraulic priming would otherwise have on the valve's stroke time. Although the hydraulic  !

. priming affect is reduced, the historical data still indicates average variations in valve stroke times as follows:

HPCI-CONTROL Open 29%

Close 43%

HPCI-STOP Open 13%-

Close N/A - Rapid Acting The average variations for the HPCI-Control valve are greater than the Code accept ence criteria of i 25% of the reference value.

ALTERNATE METHOD:

The acceptance criteria for the HPCI turbine Control valves will be expanded to i 35% in the open direction and i 50% in the closed direction.

In addition, a time-to-rated flow test for the HPCI system will be  ;

performed once each operating cycle to demonstrate satisfactory integrated '

response of the control, hydraulic and mechanical components.

USNRC EVALUATION STATUS:

Relief was granted in the September.1993 SER (Reference (s)] for Relief ,

Request RR-V06, Revision 0. ,

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i Revision 16 5-121

RELIEF REQUEST Number: RR-V07, Revision 2 (Sheet 1 of -1) .;

1 SYSTEM: Control Rod' Drive-Hydraulic l COMPONENTS: ,

OM Safety Dwg Valve Number Cat Class Drawing Number _ Coor ,

V3-162A A/C 2 G-191170 A-09 V3-162B A/C 2 G-191170 A-01 l These valvee 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.

.THIS RELIEF REQUEST WAS DELETED IN REVISION 15 OF THE'IST PROGRAM. REFER TO REFUELING OUTAGE JUSTIFICATION ROJ-V12. THESE VALVES HAVE NO OPENING _

FUNCTION. THEREFORE, THEY ARE CONSIDERED PASSIVE VALVES. j i

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Revision 16 5-122 I

BELIEF REOUEST Number: RR-V08, Revision 0 (Sheet 1 of 2)

SYSTEM: Standby Liquid Control COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor SR-11-39A C 2 G-191171 G-08 SR-11-39B C 2 G-191171 K-08 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 OR TEST CATEGORY:

Category C CODE REOUIREMENT: Part 1 Para. 1. 3 . 4 .1 (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.

This 20% shall be previously untested valves, if they exist."

Para. 1. 3.4.1(e) (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.

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Revision 16 5-123 j

i RELIEF REQUEST j t Number: RR-V08, Revision 0 (Sheet 2 of 2) r REQUEST FOR RELIEF:

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

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

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plant site. 4 The acceptable range of relief valve actuation given in Technical .

Specifications 4.4.A is 1400 psig to 1490 psig. The 1400 psig value I 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 i the Part 1 tolerance of 3% to the current setpoint would unnecessarily reduce the acceptable range to 1400 psig to 1442 psig (1442 psig = 96% of ,

system design pressure). l The increased testing frequency and present setpoint requirements provide }

adequate assurance of the operational readiness of valves SR-11-39A & 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: l 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: i Relief was granted in the September 1993 SER [ Reference (s)) for Relief Request RR-V08, Revision O.

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Revision 16 5-124

i RELIEF REQUEST Number: RR-V09, Revision 1 (Sheet 1 of 1) i SYSTEM: Residual Heat Removal' l l

COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor 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 containment 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 irolation 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 coolant injection water to the reactor.

USNRC EVALUATION STATUS:

This relief request was withdrawn in Revision 16 of the Inservice Test Program Plan.

I Revision 16 5-125

RELIEF REQUEST Number: RR-V10, Revision 0 (Sheet 1 of 2)

SYSTEM: Residual Heat Removal Service Water COMPONENTS:

OM Safety Dwg Valve Number Cat Class Drawing Number Coor V10-89A B 3 G-191159 Sh 2 G-01 V10-89B B 3 G-191159 Sh 2 C-01 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.

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

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Revision 16 5-126 l

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RELIEF REQUEST Number: RR-Vil, Revision 0 (Sheet 1 of 2) l l

gYSTEM: Reactor Core Isolation Cooling COMPONENTS:

i OM Safety Dwg Valve Number Cat Class Drawing Number Coor RCIC-CONTROL B 2 G-191174 Sh 2 D-12 i

[ This valve is the Reactor Core Isolation Cooling (RCIC) turbine governor i

control valve. This valve has a safety function to operate to provide and i regulate steam to the RCIC turbine.

, EXAH OR TEST CATEGORY:

Category B.

CODE REQUIREMENT: Part 10 Para. 4. 2.1. 4 (b) " Power-Operated Valve Stroke Testing" "The stroke time of all power-operated valves shall be measured to at least the nearest second."

REOUEST FOR RELIEF:

Relief is requested on the basis that compliance with the Code requirements is impractical and that the proposed alternatives would provide an acceptable level of quality and safety.

This is a modulating type governor valve, and has no manual control switch for testing purposes. This valve is controlled by the RCIC turbine control circuitry, thus making accurate stroke time for this valve very difficult to obtain. The system modifications necessary to directly measure the stroke time of this valve would be costly and burdensome to Vermont Yankee.

Stroke time is not an appropriate reference parameter for this valve.

3 Revision 16 5-127 l

RELIEF REQUEST Number RR-Vil, Revision 0 (Sheet'2 of 2)

ALTERNATE METHOD:

Proper valve operation will be verified through normal system operation during RCIC pump tests. Valve degradation will be identified by inadequate system response during pump testing.

USNRC EVALUATION STATUS:

Relief was granted in the September 1993 SER [ Reference'(s)] for Relief

' Request RR-Vil, Revision 0.

P 2

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RELIBF.. REQUEST Ntsaber?.

- , '7'RRIV12.79i:lReVisiiiiiF_0NT.,ShssE,276f'2 4_. s ~.

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ALTERNATEITEST*METHODI These' valVss' afe~ 8" inch5sirig "ch6ck~ 'valV~e's"'of"'the :haine design /

inanufacturer, size, model and materials of construction. Additilo^n illy 7 these valves are both oriented in the horizontal position and see similar

' service conditions. These valves swill be partially disassembled / inspecte'd

'and manually exercised on a , sampling bxfis ' (one valve per refueling" ~~ '~ '~

outage), when the Service Water System flow to the ' required' loads can" bd isolated in accordance with NRC Staff Position 2 identifie'd in NRC Genefid Letter' 89-04. During the valve disassembly; the internals of the , valve"" '"

will 'be verified to b'e structurally, sound (no loose'or corr 2:ded parts).' ~

If the disassembled valve is not capable of being full-stroke exercised oic

" here is binding or 'fallure of, the valve ' internals, the other valve will'

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also'be' disassemble 4 inspected _an,d,manu' ally exerpised during ;the';samef~'~

ggtagey USNRC9 EVALUATION ?STATUS ThTsiys1'lifjyd4Hisy[gsygpj6y@j{ijQf($fp5ejifQSy{p@psM8gg@RC

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