ML20078G158
| ML20078G158 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/26/1995 |
| From: | Cappuceio G, Connolly J, Pelletier J VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20078G157 | List: |
| References | |
| PROC-950126, NUDOCS 9502020432 | |
| Download: ML20078G158 (169) | |
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1 INSERVICE TESTING PROGRAM PLAN Vermont Yankee Nuclear Power Station Commercial Service Date: November 29, 1972 l Implementation Date: March 15, 1995 Revision 16 Prepared By: Reviewed By:
&rXW $N. /J'2b?f M c. & A J ~') C
. W."Connolly [/ T.Cf Trask lant IST CoordinaYor Senior Mechanical Engineer Approved By:
/G.~C 44 pt3d e'io 44
// B.R. Bdteau
.\ '
\ ,s ME Manager Engineering Director
- N W [ 9['00/ //$/9( )
s ///g,/ff Plant Operations Revi'ek .
. Wan6z?k Committee P nt Manage [r/ g
/lAdl95 J .@ . ~Pelletier ' '
Vice President - Engineering i
Vermont Yankee Nuclear Power Corporation
, Governor Hunt Road Vernon, Vermont 05354 9502020432 DR 950130 p ADOCK 05000271 '
PDR m , _ , . . . .l
i; Revision Summary Revision Affected Number Pages Summary 13 All Third Ten-Year Interval Update.
14 5-14, 5-15 Revise valve listing for Diesel Generator Starting Air System to reflect changes made under PDCR 92-18, DCN 1. Minor revisions.
15 Cover, 1-1, 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 19, 4-21 to implementing procedures, 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 5-30, 5-32 to 5-34, 5-36 to 5-71, 5-74 to 5-84, 5-87, 5-88, 5-91 to 5-94, 5-98 to 5-98b, 5-100, 5-102, 5-105, 5-107, 5-113, 5-115, 5-117, 5-119, 5-122 to 5-124, 5-126 1
O Revision 15 i
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I Revision Summary i
j Revision Affected I Number Pages Summary l 16 Cover,4-3, Revice to reflect changes made 4-7 to 4-10, due to the responses to the l 4-30, 4-31, USNRC Safety Evaluation Report 5-5, 5-7 to issued on September 3, 1994, l 5-11, 5-17, Alternate Cooling Water System l 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 l to 5-41, 5- relief request and correction 43, 5-52, 5- of typographical errors.
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53, 5-56 to 1 5-59, 5-60, i 5-68, 5-77, 5-83 to 5-84, 5-89 to 5-90, 5-104 to 5-112, 5-107, 5-113, 5-114, 5-118, 5-119, 5-122, 5-125 I
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i Revision 16 11 l
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Table of Centanto Section Pace
- 1.0 Introduction 1-1 1.1 Purpose 1-1 j 1.2 Discussion 1-1 e
2.0 Program Plan Description 2-1 2.1 Justifications 2-1 2.2 Relief Requests 2-2 2.3 Flow Diagrams 2-3 Table 2-1:
List of Inservice Testing Flow Diagrams 2-4 i
t j 3.0 References 3-1 i
s i 4.0 Pump Inservice Testing Progran Plan 4-1 4.1 Scope 4-1 1 4.2 Pump Program Listing 4-1 i Table 4-1: Pump Listing 4-3 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 5-1 5.2 Valve Program Listing 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 3
Revision 16 iii
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1.0 Introduction 1.1' Purpose :
The Third-Interval Vermont Yankee Inservice Testing (IST) l Program establishes testing requirements to assess the l operational readiness of certain Safety Class 1, 2, and 3 pumps and valves which are required to:
a) Shut down the reactor to the cold shutdown condition, b) Maintain the reactor in the cold shutdown condition, or c) Mitigate the ccnsequences of design-basis accidents.
The Third-Interval IST Program is applicable for the interval-from September 1, 1993 through and including August 31, 2003
[ References (q) and (r)].
The Third-Interval IST Program is part of the Vermont Yankee Component Testing Program, i
1.2 Discussion The Third-Interval Vermont Yankee IST Program was developed in accordance with the requirements of the 1989 Edition of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code, " Rules for Inservice Inspection of Nuclear Power Plant Components," and 10 CFR 50.55a (Reference (b)]. The Third- ;
Interval IST Program provides compliance with Vermont Yankee Technical Specifications 4.6.E.
I 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 pump and valve testing requirements were based on the ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM-1987, " Operation and Maintenance of Nuclear Power Plants".
The additional requirements described in 10 CFR
- 50. 55a (b) (2) (vil) and the recommendations described in Generic Letter 89-04 and its supplements were also included as applicable. Request for use of the ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM-1987, with the additional requirements, was submitted by Vermont Yankee and approved by the USNRC
[ References (e) and (f)].
All references to the " Code" made within this IST Prograt Plan will 1987 refer to theotherwise unless ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM-specified.
Revision 15 1-1
1 T' a y.
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 y 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).
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l Revision 15 1-2
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*
XXJ: CSJ for Cold Shutdown Justifications, )
ROJ for Refueling Outage Justifications. j J
V: for Valves. l l
NN: A unique sequential number, (e.g. CSJ-V03, Rev 0, I would be the third Cold Shutdown Justification for Valves). !
Z: Revision Status.
l Revision 13 2-1
.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 unusual difficulty without a compensating increase in the level of quality and safety, alternate testing is proposed that would provide useful information to assess the operational readiness of the component tested.
The Relief Requests define the component (s) and test (s) involved, the basis for relief, the proposed alternate :'
testing, and the status of the USNRC evaluation to the Relief Request.
r If testing requirements are determined to be impractical during the course of the interval, additional or modified Relief Requests will be submitted in accordance with 10 CFR
- 50. 55a (f) (4 ) (iv) . ;
Relief Requests are numbered in a "RR-YNN, Revision Z" format, where:
RR: for Relief Request.
Y: P for Pumps, V for Valves.
NN: A unique sequential number, (e.g. RR-V09, Rev 0, would be the ninth Relief Request for Valves).
2: Revision Status.
I Revision 13 2-2 s
t 2.3 Flow Diagrams Table 2-1 provides a. listing offthose Flow Diagrams which depict the components, subsystems, and systems contained within the Third-Interval IST Program. Drawing number G-191155 explains the symbols and designations provided on the Flow Diagrams.
The Safety Classifications depicted on the Flow Diagrams are subject to the limitations stated in procedure AP 0014,
" Safety Class Determination Instructions," and the Vermont Yankee Safety Classification Manual.
"For Information Only" copies of the Flow Diagrams shall be provided with each USNRC Submittal. The copies shall be current as of the date of the IST Program Plan submittal.
Controlled copies of the Flow Diagrams are maintained at Vermont Yankee to ensure that all system additions and modifications are addressed in the Third-Interval IST Program.
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Revision 13 2-3
Table 2-1
' LIST OF INSERVICE TESTING FLOW DIAGRAMS ,
(sorted by flow diagram number)
Flow Diagram System Number Name G-191155 Piping and Instrument Symbols G-191159 Sh 1 Service Water System G-191159 Sh 2 Service Water System i
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 G-191160 Sh 8 Instrument Air System G-191162 Sh 2 Fuel Oil - Miscellaneous Systems G-191165 Sampling System G-191167 Nuclear Boiler G-191168 Core Spray System l I
i G-191169 Sh 1 High Pressure Coolant Injection System G-191169 Sh 2 High Pressure Coolant Injection System G-191170 Control Rod Drive Hydraulic System G-191171 Standby Liquid Control System G-191172 Residual Heat Removal System ,
i G-191173 Fuel Pool Cooling & Cleanup System
- a. i Revision 13 2-4
j '4 Table'2-1 LIST OF INSERVICE TESTIEJ FLOW DIAGRAMS (sorted by-flow dia[, ram number)
Flow Diagram System Number Name G-191174 Sh 1 Reactor Core Isolation Cooling System G-191174 Sh 2 Reactor Core Isolation Cooling System G-191175 Sh 1 Primary Containment & Atmosphere Control G-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 !
l G-191267 Nuclear Boiler Vessel Instrumentation VY-E-75-002 Containment Atmosphere Dilution System 1
5920-271 Neutron Monitoring System '
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Revision 13 2-5
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. 3.0 References a) License No. DPR-28 (Docket No. 50-271).
b) United States Code of Federal Regulations, Title 10 l Chapter 1, Part'50, Section 50.55a (57FR34666, dated August 6, 1992).
c) ASME Boiler and Pressure Vessel Code,Section XI, Division 1, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1989 Edition. I l
d) ASME/ ANSI Standard OMa-1988 Addenda to ASME/ ANSI OM-1987,
" Operation and Maintenance of Nuclear Power Plants". )
1 e) Letter, Mr. P.M. Sears, USNRC, to Mr. L.A. Tremblay, l VYNPC, " Vermont Yankee Nuclear Power Station, Approval of I 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. ;
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l 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 '
l 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. .
1 i) Letter, Mr. W.P. Murphy, VYNPC, to Document Control Desk, l USNRC, " Response to USNRC Generic Letter 89-04: Guidance j on Developing acceptable Inservice Testing Programs", BVY l 89-90, dated October 3, 1989. l l
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.
1 k) Letter, Mr. W.P. Murphy, VYNPC, to Dr Thomas E. Murley, I 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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Revision 15 3-1
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- 1) Letter, Mr. R.W. Reid, USNRC, to Mr. R.H. Groce, YAEC, "NRC Staff Guidance for Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests Pursuant to 10 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 of 10 CFR 50.55a(g), ' Inservice Inspection Requirements'," dated November 17, 1976.
n) Vermont Yankee Final Safety Analysis Report.
o) Vermont Yankee Technical Specifications.
p) Vermont Yankee Component Testing Program Plan.
q) Letter, Mr. J.P. Pelletier, VYNPC, to Document Control Desk, USNRC, " Submittal of Vermont Yankee Nuclear Power Corporation Third-Interval Inservice Testing Program Plan and Safety Evaluation Responses," BVY 92-133, dated November 30, 1992.
r) Letter, Mr. D.H. Dorman, USNRC, to Mr. J.P. Pelletier, VYNPC, " Relief from the ASME Section XI Requirement to Update (.O n a 120-Month Interval) the Inservice Inspection and Testing Programs at Vermont Yankee (TAC No. M85067),"
NVY 93-031, dated April 6, 1993.
l s) Letter, Mr. D.H. Dorman, USNRC, to Mr. D.A. Reid, VYNPC,
" Safety Evaluation of the Inservice Testing Program Relief Requests for Pumps and Valves, Vermont Yankee Nuclear Power Station (TAC No . M85 067 ) , " NVY 93 - 151, dated September 3, 1993, t) Letter, Mr. D.A. Reid, VYNPC, to Document Control Desk, USNRC, " Proposed Change No. 168 to the Vermont Yankee Technical Specifications - Auxiliary Electric Power ;
System Technical Specifications and Associated Revision ;
to the Vermont Yankee Inservice Testing Program," BVY 93- ,
30, dated August 4, 1993. !
i 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 j (TAC No. M87171)," 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) .
Revision 16 3-2
4.0 Pump Inservice-Testing Program
- g. 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 snutdown condition, or c) Mitigate the consequences of design-basis accidents.
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 l corresponds to the MPAC Database utilized at Vermont Yankee.
Table 4-1 is sorted by Pump Number.
Function The common name for the pump.
Drawing Number The Flow Diagram which depicts the pump. If the pump appears on multiple Flow Diagrams, then the primary Flow Diagram i identifier is listed.
Dwg Coor The coordir. ate location (e.g., D-05) on the Flow Diagram where the pump appears.
Revision 15 4-1
- Safety class The safety classification of the pump, as determined in accordance with procadure AP 0014, " Safety Class Determination Instructions," and the Vermont Yankee Safety Classification
' Manual. -
Pump Type The pump type:
CENT for Centrifugal pumps.
VERT for Vertical line shaft pumps.
PD-RECIP for Positive Displacement Reciprocating pumps.
PD-ROT for Positive Displacement Rotary pumps.
Test Type The Inservica Test Parameters to be determined and recorded during testing performed in accordance with Paragraph 5 of Part 6 of the Code. The abbreviations correspond to those provided in Table 2 of Part 6 of the Code:
N for Speed, (if variable speed).
dP for differential Pressure, (for centrifugal and vertical line shaft pumps).
P for discharge Pressure, (for positive displacement pumps).
Q for Flow Rate.
Vd 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):
CS for Cold Shutdown OC for Once Per Operating Cycle Q for Quarterly RR for Reactor Refueling Outage Relief Request The Relief Request number associated with the subject pump and ,
test type or test frequency, where applicable. l Remarks Clarifying comments or other remarks related to the subject pump and test type or test frequency, where applicable.
l Revision 15 4-2 l
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.A Table 4-1 Pump Listing i
[ Dws Safety Puup Trit Test Relief Pump Nuuber Drawing No - Coor Class Type Type Freq Request Remarks
- 1: .................. .............. .... ..... .... ..... .... ....... .............................
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'PT*1A G 191159 sh 1 C 02 3 VERT Q Q RR P01 See Table 4 2
Q RR RR P01 VV Q Function : Service Water Pulp
- G $$
b PT 18 G 191159 sh 1 B 02 3 VERT Q Q RR P01 See Table 4 2 0 RR RR P01 vv Q Function Service Water Puup f ............................................................................................................
? PT 1C G 191159 Sh 1 1 03 3 VERT Q Q RR P01 See Table 4 2 0 RR RR-P01 l W Q
-[
,l- Function : Service Water Puup
@ Q hM i
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3 PT 1D G 191159 Sh 1 el 03 3 VERT Q Q RR-P01 See Table 4-2
? Q RR RR-P01 I Vy 'o s Function : Service Water Puup
............................................................................................................ j P8 1A - G 191159 Sh 1 J 12 3 VERT Q Q See Table 4 2 Yv Q
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Ftsiction : RNA Service Water Puup P8 1B G-191159 Sh 1 I.12 3 VERT Q Q See Table 4 2 vv Q ;
& Q Function : RMR Service Water Pulp ,
P81C G 191159 sh 1 B 12 3 VERT Q Q See Table 4 2 i' VV Q j @ Q '
Function : RNR 3ervice Water Ptsp
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s a P8 1D G 191159 Sh 1 A-12 3 VERT Q Q See Table 4 2 VV Q dP Q Function : RNR Service Water Pulp ,-
P10 1A G 191172 L.05 2 CENT Q Q See Table 4 2 vv Q
@ Q
- Function : Residual Heat Removal Pump P10 15- G 191172 L-12 2 CENT Q Q See Table e 2 f vv Q
@ Q v Function : Residjel' Heat Removal Puup 3 Revision 16 4-3 ,
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Table 4-1 Pump Listing i
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Dwg Safety Ptap Test Test Rollef Pump Ntsuber Drawing No Coor Class Type Type Freq Request Remarks P10-1C G 191172 J-05 2 CENT Q Q aee Table 4 2 Vv Q dP Q Function : Reslebel Heat Removal Ptap P10-10 G 191172 J 12 2 CENT Q Q See table 4-2 Vv Q dP Q Function : Residual Heat Removal Puap P19 2A G 191173 G-11 3 CENT Q Q Vv Q
@ Q Function : Stan t y Fuel Pool Cooling Ptap P19 2B G 191173 H-11 3 CENT Q Q VV Q
- Q Function : Standby Fuel Pool Cooling Pump P44-1A J 191169 Sh 2 G-11 2 CENT N Q See Table 4-2 Q Q RR-P02 i VV Q RR PO4 dP Q RR-P02 RR P03 Function : High Pressure Coolant Injection HP Ptap P44 18 G 191169 Sh 2 G 08 2 CENT N Q See Table 4 2 0 Q RR-P02 vv Q Q RR P02 RR-P03 :
Function : High Pressure Coolant Injection Booster Pung '
P45-1A G 191171 H-08 2 PD- Q Q See Table 4 2 RECIP Vv Q i P Q Function Stan&y Liquid Control Pung P45 18 G-191171 J-08 2 PD- Q Q See Table 4 2 RECIP Vv Q '
P -Q
, Fmetion : Stan&y Liquid Control Punp P46 1A G 191168 J 11 2 CENT Q Q See Table 4-2 vv Q dP Q RR POS ,
Function : Core Spray Punp P46-1B G 191168 J 14 2 CENT Q Q See Table 4 2
. Vv Q !
dP Q RR-POS i Function : Core Spray Puip 1
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i Revision 15 4-4 I
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Table 4-1 Pump Listing Dwg Safety Pump Test Test Relief Puup Nimber 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 Q Q-vv Q 4
& Q RR P06 Function : Reactor Core Isolation Cooling Pump P59-1A G-191159 Sh 3 A-07 3 CENT Q Q i Yv Q '
9 & Q RR P08 Function : Reactor Building Closed Cooling Water Puup '
P59 18 G 191159 Sh 3 B-07 3 CENT Q 0 Vv Q '
dP Q RR P08 Fteiction : Reactor Building Closed Cooling Water Puup P92 1A G-191162 Sh 2 E-05 3 PD-ROT Q Q RR P09 Q OC RR P09 VV Q i P Q Function : Diesel Fuel all Transfer Punp P92-19 G-191162 Sh 2 0 05 3 PD-ROT Q Q RR P09 !
Q OC RR P09 l Vv Q '
P Q Function : Diesel Fuel 011 Transfer Punp SP 1 G-191237 l-11 3 CENT Q Q Vv Q -
@ Q Function : Control Room HVAC Chilled Water Punp J
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Revision 15 4-5 4
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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 valdes cannot be met, the pump shall be declared inoperative.
Ptsnp/ System Minimum Flow Requirements Flow Path Operability Frequency P7-1A-D SW 2700 GPM against a TDH of Normal system lineup Per Paragraph 5 of 250 feet Part 6 P8 1A-D RHRtw 2700 GPM at 70 PSIA Normal r,. tem lineup Per Paragraph 5 of Part 6 P10-1A-D RHR 7450 t 150 GPM Vessel to Vessel Each Refueling Outage P44-1A/B HPCI 4250 GPH st normal reactor Recirculate to Ottce per Operating operating pressure Condensate storage Tank Cycle P45 1A/B SLC 35 GPM at 1275 PSIG Recirculate to Test Tank Per Paragraph 5 of using Demineralized Part 6 Water P46 1A/8 CS 3000 GPM against a system Torus to Torus Each Refueling Outage head of 120 PSIG P47-1A RClc 400 GPM at normal reactor Recirculate to Per Paragraph 5 of operating pressure Condensate Storage Tank Part 6 Prest,ure measured at the RHR heat exchanger service water outlet when the corresponding pairs of RHR service water pumps and station Service Water pumps are operating.
Revision 13 4-6
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RELIEF REQUEST Number: RR-P01, Revision ] (Sheet 1 of 4)
RYSTEM: 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 1
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:
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l CODE REOUIREMENT! Part 6
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Para. 5.1 " Frequency of Inservice Tests" l "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
RELIEF REQUEST Numbert RR-P01, Revision j (Sheet 2 cf 4)
REQUEST FOR RELIEF: l 1
Relief is requested on the basis that compliance with the Code l requirements is impractical and that the proposed alternatives j would provide an acceptable level of quality and safety. ;
i During normal operations, neither differential pressure nor flow rate can be fixed or directly measured. Pump vibration levels may also vary due to the inability to establish a repeatable reference condition.
The four Service Water pumps :.re vertical, two-stage, I centrifugal-type pumps which are submerged in and take suction l from the Connecticut River. They supply all the station Service !
Water System requirements. The station Service Water System is a dual header system using two parallel headers each containing two pumps. The two parallel headers supply both the turbine and reactor auxiliary equipment, including the Residual Heat Removal I
Service Water System. A header interconnection is provided downstream of the pumps. Normally, the valves in the interconnecting line are open, permitting any of the pumps to supply the cooling water to both headers and to balance system operation. In addition, a cross-tie is provided to the non-nuclear safety station Fire Protection System. The 12-inch cross-tie valve is normally closed, with a 1-inch cross-tie and a restricting orifice providing pressurization of the Fire Protection System header.
The Service Water System contains both automatic temperature and flow control valves used to independently regulate the cooling provided to the various turbine and reactor auxiliary equipment.
Due to seasonal variations in Connecticut River water temperature and level and constantly changing heat loads, the system resistance and flow rate vary. The number of station Service Water pumps in operation is also varied dependent on system requirements. Due to these variations and the need to maintain prcper cooling, it is considered impracticable to establish repeatable reference values during quarterly inservice testing.
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Revision 16 4-8
1 i
1 l
RELIEF REQUEST Number RR-P01, Revision ] (Sheet 3 of 4) )
l i
I REQUEST FOR R2 LIEF fcon't)' I i
l The only sufficient straight sections of piping in each of the l two parallel headers exist between the i.. cake 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 P ii P ng. )
i b) As discussed above, each parallel header is common to two i pumps and is cross-connected to the other header. Thus, in i
. 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 i result in single pump operation for the portion of the ]'
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 pump flow. Such redesign and modification would be costly and burdensome to Vermont Yankee.
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I Revision 16 4-9 i
i
l RELIEFREQUEST l l
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provide a mechanism to' assess thechydraulic condition:of the' punip, '
and,to detect pump degradation against the code' required limits'. '
An additional . reference' condition, will be, e.stablished with'._the."~J '
pump atJa dead head condition whe<r_e pump' vibration and - l differential' pressure ^ can be measured'for comparison i^n~thIeysiiE l that' maintenance ~~ _i.,s- re.qu,ir_ed.---to--~ be perform,ed,_between c- ~ refu_e_ ling'~~
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RELIEF REQUEST Number: RR-P02, Revision 0 (Sheet 1 of 2)
SYSTEM: High Pressure Coolant Injection ,
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 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 and isolation. ,
EXAM OR TEST CATEGORY:
Differential Pressure (dP). ,
Flow Rate (Q). l CODE REQUIREMENT: Part 6 Para. 4.6.2.2 " Differential Pressure" l
"When determining differential pressure across a l 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 of 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 i
i
.~ , - -- ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _
RELIEF REQUEST Number: RR-P02, 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.
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 Vermont Yankee.
ALTERNATE METHOD:
Differential pressure and flow rate parameters will be measured e across both HPCI pumps as an integral unit. Vibration monitoring will be performed for each pump individually. Both pumps will be inspected and repaired as necessary if any abnormal conditions in differential pressure or flow rate occur.
USNRC EVALUATION STATUS:
This Relief Request is first submitted under Revision 13 to the IST Program Plan.
In addition, these testing techniques are consistent with those previously approved by the NRC [ Reference (s), Enclosure 1, Section 2.3]. 1 l
I 1
l I
l l
1 Revision 13 4-12
RELIEZ_EEQUEST Number RR-P03, Revision 0 (Sheet 1 of 2)
[
SYSTEM: High Pressure Coolant Injection COMPONENTS: i 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 .
t 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 and isolation.
f I
EXAM OR TEST CATEGORY:
Differential Pressure (dP).
l l
CODE REQUIREMENT: Part 6 l 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."
Revision 13 4-13
RELIEF REQUEST Number: RR-P03, Revision 0 (Sheet 2 of 2)
REOUEST FOR RELIEF:
Relief is requested on the basis that the proposed alternatives i would provide an acceptable level of quality and safety.
Differential pressure across the HPCI pumps is determined by the 1 difference between pressure measurements taken at a point in the I 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 j 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 I sufficient for a post accident condition when the suppression l 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 = 78 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 operation.
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 +/- 0.12% (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 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-P03, Revision 0.
Revision 15 4-14
I RELIEF REQUEST Numbert RR-P04, Revision 0 (Sheet 1 of 3) l SYSTEM: High Pressure Coolant Injection I COMPONENTS:
Safety Dwg Pump Number Class Drawing Number Coor l
P44-1A 2 G-191169 Sh 2 G-11 i I
i l
P44-1A is the High Pressure Coolant Injection (HPCI) main (high pressure) pump. The main pump has the safety function to operate l in series with the booster pump, P44-1B, to provide 1) adequate core cooling and reactor vessel depressurization following a small break loss of coolant accident, and 2) reactor pressure control during reactor shutdown and isolation.
EXAM OR TEST CATEGORY:
Vibration Velocity (Vv).
CODE REQUIREMENT: Part 6 !
I l
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 1 from the reference values shall be compared with the limits given in Table 3 and corrective action taken as specified in para. 6.1." l l
l Revision 13 4-15 i
I
RELIEF REQUEST Mumber: RR-P04, Revision 0 (Sheet 2 of 3)
REQUEST FOR RELIEF:
4 Relief is requested on the basis that the proposed alternatives would provide an acceptable level of quality and safety.
A 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 inten+ 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 i 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 l prevent the HPCI pump from performing its intended function. l Revision 13 4-16
l RELIEF REQUEST Number: RR-PC4, Revision 0 (Sheet 3 of 3)
ALTEkNATE 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 for the HP pump:
Test Parameter Acceptable Rance Alert Ranae Reauired Action Rance VV s 2.5VI > 2.5VI to and > 6Vr 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 limit 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:
Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-P04, Revision O. ,
l Revision 15 4-17 1
J l
RELIEF REQUEST Number: RR-P05, Revision o (Sheet 1 of 2)
I SYSTEM: Core Spray COMPONENTS:
l Safety Dwg Pump Number Class Drawing Number Coor P46-1A 2 G-191168 J-11
~
P46-1B 2 G-191168 J-14 l 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 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."
Revisien 13 4-18
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.
Differential pressure across the Core Spray 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 Core Spray pump inlet pressure indicators are designed to provide adequate inlet pressure indication during all expected operating and post accident conditions. The full scale range, 60 psig, is sufficient for a post accident condition when the suppression chamber is at the maximum pressure. This, however, exceeds the full-scale range limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 7.5 psig, Limit = 22 psig).
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 suitable for determining that adequate NPSH is available for Core Spray pump operation.
Pump discharge pressure during testing is approximately 240 psig, which results in a calculated differential pressure of approximately 232.5 psig. The resulting inlet pressure inaccuracy of +/- 1.2 psi represents an error in differential pressure measurement of +/- 0.5% (1.2 psi /232.5 psid = 0.0052).
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-POS, Revision 0. -
Revision 15 4-19
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 P47-1A 2 G-191174 Sh 2 F-08 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."
l l
i Revision 13 4-20 1
I a
RELIEF REQUEST Number: RR-P06, Revision o (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 taken at a point in the inlet pipe and at a point in the discharge pipe as allowed by Paragraph 4.6.2.2 of Part 6 of the Code. The installed RCIC pump inlet pressure indicators are designed to provide adequate inlet pressure indication during all expected operating and post accident conditions. The full scale range, 85 psig, is sufficient for a post accident condition when the suppression chamber is at the maximum pressure. This, however, exceeds the full-scale range limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 20 psig, Limit = 60 psig).
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 !
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, 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-P06, Revision O. ,
P Revision 15 4-21
- RELIEF REQUEST Number: RR-P07, Revision 0 (Sheet 1 of 2)
SYSTEM: Reactor Building Closed Cooling Water 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 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. ,
THIS RELIEF REQUEST WAS DELETED IN REVISION 15 OF THE IST PROGRAM.
l 1
I i
Revision 15 4-22
I RELIEF REQ *EST Number: RR-P07, Revision n (Sheet 2 of 2)
THIS RELIEF REQUEST WAS DELETED IN REVISION 15 OF THE IST PROGRAM. !
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1 1
l Revision 15 4-23 I
I RELIEF REQUEST
- i. Number: RR-P08, Revision 0 (Sheet 1 of 2)
SYSTEM: Reactor Building Closed Cooling Water COMPONENTS:
i Safety Dwg Pump Number Class Drawing Number coor
, P59-1A 3 G-191159 Sh 3 A-07 ;
1 I
P59-1B 3 G-191159 Sh 3 B-07 I
These pumps are the Reactor Building Closed Cooling Water (RBCCW) l pumps. They have a safety function to provide cooling water to l 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." )
l l
t Revision 13 4-24
RELIEF REQUEST Number: RR-P08, 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.
Differential pressure across the RBCCW pumps is determined by the difference between pressure measurements taken at a point in the inlet pipo and at a point in the discharge pipe as ellowed by Paragraph 4.6.2.2 of Part 6 of the Code. The installed RBCCW pump inlet pressure indicators, with a full scale range of 30 psig, are designed to provide adequate inlet pressure indication during all expected operating and post accident conditions.
-This, however, exceeds the full-scale range limit of three times the suction pressure reference value as required by Paragraph 4.6.1.2(a) of Part 6 of the Code (Value = approximately 6.5 psig, Limit = 19 psig).
The suction pressure measurement is used to verify prescribed NPSH requirements and to determine pump differential pressure.
The installed gauges are calibrated to within +/- 0.4% accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be +/ .12 psi. This is considered to be suitable for determining that adequate NPSH is available for RBCCW pump operation.
Pump discharge pressure during testing is approximately 80 psig, which results in a calculated differential pressure of approximately 73.5 psig. The resulting inlet pressure inaccuracy i of +/- .12 psi represents an error in differential pressure measurement of +/- 0.16% (.12 psi /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 COMPONENTS:
Safety Dwg Pump Number Class Drawing Number Coor P92-1A 3 G-191162 Sh 2 E-05 P92-1B 3 G-191162 Sh 2 D-05 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.
EXAM OR TEST CATEGORY:
Flow Rate (Q).
CODE REQUIREMENTL 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."
Revision 13 4-26
l RELIEF REOUXET Number: RR-P09, Revision 0 (Sheet 2 of 4)
I BEQUEST 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 Diu'el Generator fuel oil supply system consists of two parallel tr_2ns, 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 Number RR-P09, Revision 0 (Sheet 3 of 4)
REQUEST FOR RELIEF fcon't):
Disabling the automatic start feature of the Diesel Fuel Oil Transfer pump on low diesel d. 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.
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
4 RELIEF REQUEST Number: RR-P09, Revision 0 (Sheet 4 of 4) l l
ALTERNATE METHOD (con' tit 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 degradation, provided that pump bearing vibration is not excessive. Assurance of acceptable pump bearing vibration levels is provided through the full spectrum vibrational i monitoring. )
l 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 l (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. s 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) ,
l were related to electrical components and two (2) were related to high bearing vibrations. l l
Each of the above failure modes is adequately monitored during the quarterly inservice testing through visual i inspection of the pump seals, proper starting and operation i of the pump upon low diesel day tank level, and full i spectrum vibrational monitoring.
l I
USNRC EVALUATION STATUS: )
i Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-P09, Revision 0.
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l Revision 15 4-29 l
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2
RELIEF REQUEST Number 'RR iP10, J Revision. O (Sheet 2 of 2) f
]l ASIS FOR' RELIEF F "(cdn' t)l Past?testinq[ind ah51psisipsiformedian theiRCICipump blp Vermont Yankee,4the; pump manufacturer,landsby independent i vibration:; consultants:-hassrevealed characteristicf pump vibrationilevelsbwhich exceedithe1 acceptance criteria st'atWd iniTable."3.of1Part 6Tof theJCode. The causes'of'the: higher' vibration (levelsjhave been determined,as.the following! '~
131 Thigh'Vib'raEion"lbbsis'at ths71mpelleWyansy^
T ssd
~ ~ frequency.;f4,Xiand-5X. running gpeed)j 2~ +7SEEUctiu.rallreschance?
- ~ -
The"re'fsrshesNibrstion ValdsFfdrTthis.Tj3 ump 7Esnge~ashhigh a s ..0 . 3 1 6 7 n / s e c '. :TheimeanLpeak velocity;-value,Jfor the~ "
highest-Yibration point,.' utilizing.. data taken since/1990 sis 0.314Lin/sec. *A' review of:thelthe7 hydraulic;and? vibration" testLdata!since119901indic cessthatLthere hastbeeneno degradation;of(thefpump. JDiscussions[withithespump' i manufacturerthave indicated:that the'fvibrationsleve1E foe thisLtypeYof/ pump l driven)byfa;stAamf; turbine"are comm66%dnd. "
do;not; represent;afmechanicalfprob,lemjwith7the:; pump g DUh!!tiditiheFsidslEdsVlaEi6di.bsswseElhd[pninpYssfsrsEEEWilIie hndithe10:325lin/sec511mit#specifiediinrtableli3bJof.CPsEtJ6~
off thei Codephormain fluctuations $(data?scatt'er)dinNibrahi33 '
Ee Adings i causel t hi'sipumpi toibe h unnsee ssaril@placdcEin i the~
alertirange)and.;theifreqency/6ptestingEincreased;~"^"~~~
XLTERNATIVEITESTINGt YHT6rdeE to ;bbtsi'sPaF ale EYahgs'liihi Cf 6rTt h5~ R'CIC juiid
~
that is more indicativefof' pump degradation, the" alert rahyd ^~
limit - will be extended' than10.50!in/sec. to greater:action LTheircquired than 2.5.
rangeV,'sor greater pecified"ih tabl{3b;of Part)6;offthe; Code'will; remain unchanged) ^ ~
USNRCEEVALUATION'STATUSi-Thrsi relidf Trequsst wasTf frct1dbmitti'ed"in'L Revisi~ohE16Tof the.IST' Program' Plan.
~
' Approval of this relief f request Lis'
~ ~~ '"
pending_.
Revision 16 4-31
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 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.
Revision 15 5-1
_ _ _ :r__ ___ ___ _ ___ _
, l i
l i .
5.2 Valve Program ?isting ;
Table 5-1, " Valve Listing" lists all valves and pressure ,
g 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:
5 Drawing The Flow Diagram which depicts the valve or pressure relief s device. If the valve or pressure relief device appears on j multiple Flow Diagrams, then the primary Flow Diagram ;
identifier is listed. Table 5-1 is sorted by Drawing. ,
Drawing Title The title of the Flow Diagram.
Valve Number l
The unique number that identifies the valve or pressure relief device. The valve number corresponds to the MPAC Database utilized at Vermont Yankee. 1 Function The common name for the valve or pressure relief device.
Dwg Coor j The coordinate location (e.g., D-05) on the Flow Diagram where the valve or pressure relief device appears. j 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.
Revision 13 5-2 i
OM C3t The valve category as defined by Paragraph 1.4 of Part 10 of the Code. All categories are identified for those valves which have more than one applicable category (i.e. A/C for category C valves that also have leakage requirements).
A: Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required function (s).
B: Valves for which seat leakage in the closed position ;
is inconsequential for fulfillment of their required function (s).
C: Valves which are self-actuating in response to some system characteristic, such as pressure (relief 1
^
valves) or flow direction (check valves) for i fulfillment of their required function (s), i D: Valves which are actuated by an energy source !
capable of only one operation, such as rupture disks or explosively actuated valves.
size (Inch) 2 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 Chech Valves PLG for Plug Valves RD for Rupture Discs RV for Relief Valves SQUIB for explosively actuuted valves SRV for SLfety/ Relief Va7/es I
Actuator The type of actuator provided with the valve body where: j AO for Air Operated EXP for Explosive Charge HO for Hydraulically Operated MAN for Manually Operated MO-AC for Motor Operated, AC powered motor MO-DC for Motor Operated, DC powered motor SA for Self Actuated (i.e. Relief Valves, etc.)
80 for solenoid operated Revision 15 5-3
Normal Position Tnis field details the valve's position during normal plant operation (if the subject system does not operate during ,
normal power operation, the valve's normal position is the ,
. position of the valve when the system is not in operation),
.where: j C for Closed C/FC for closed, Fails Closed C/FO for Closed, Fails Open C/LC for Closed, Locked closed C/KL for Closed, Key Locked Closed ,
O for Open O/FC for Open, Fails Clched O/FO for Open, Fails Open O/LO for Open, Locked Open O/KL for Open, Key Locked Open D-V for De-energized, Vented '
E-P for Energized, Pressurized SYS for System function dependent (e.g. Check Valves, etc.) '
Test Type (and Stroke Direction)
The test type is an abbreviation of the type of test required 1 to be performed and the stroke direction in which the test is performed.
LJ OM Category A Valves, which are containment isolation valves and do not provide a reactor .
coolant system pressure isolation function. These i valves are leakage rate tested, the results analyzed, and_ corrective action performed in accordance with the Vermont Yankee Primary Containment Leak Rate Testing Program. The Vermont Yankee Primary Containment Leak Rate Testing Program ,
provides compliance with Paragraphs 4.4.2.1, .
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) .
LT OM Category A Valves, which perform a function other than containment isolation and are not Excess Flow Check Valves. These valves are leakage rate tested, l the results analyzed, and corrective action i performed in accordance with Paragraphs 4.4.2.1 and l 4.2.2.3 of Part 10 of the Code. )
LEF OM Category & 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
STC Active Category A and B Power-Operated Valves, which are full-stroked tested in the closed direction and s the stroke times are measured and evaluated in: i accordance with Paragraph 4.2.1~of Part 10 of the Code.
STO Active Category A and B Power-Operated Valve's, which are full-stroked tested in the open direction and ,
the stroke times are measured and evaluated in i accordance with Paragraph 4.2.1 of Part 10 of the i Code. i
~I 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, r
PSC Active Category A and B Valves and Category C Check j 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. .
i PSO Active Category A and B Valves and Category C Check i 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 i Code. The frequency of this verification is specified 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, j RD OM Category D Rupture Discs, which are replaced in ;
accordance with Paragraph 4.4.2 of Part 10 of the !
Code. ;
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Revision 16 5-5 j l
_ .__ _ _ . - - - - .. . _ _ - - _r'
i SP OM Category C Relief and Safety Relief Valves are tested in accordance vith Paragraph 4.3.1 of Part 10 of the Code.
NONE For passive valves with no testing required.
Test Freq The test performance frequency associated with each test type will be specified where:
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 RR for Reactor Refueling Outage NA for Not Applicable Relief Request The Relief Request number associated with the subject valve or pressure relief device and test type or test frequency, where ,
applicable. '
Refuel Or Cold Shutfven Justification The Refueling Outage ur 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, pressure relief device, test type or test frequency.
P Revision 15 5-6
i 1
1 Tablo 5-1 i Ve11vo Lioting j (Sorted by Drawing Number) )
1 Drawing : G 191159 Sh I l Drawing Title : Service Water System l l
Refuel or Cold l Dwg Safety OM Site Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks -
SE.70 4A 6..x.10, 3 8 1.000 CA SC C/F0 FST Q P'#
s s
STO Q P w ' a' y Function : RHRSW Pump Motor Cooling Coll Supply Valve SE.70-48 l@0 3 8 1.000 GA SO C/F0 FST 0 f?@>:
fp eNy y STO Q gg ;
' Function RHRSW Pump Motor Cooling coil Supply Valve i SE.70 4C W10 3 8 1.000 GA SO C/F0 FST Q 8E
. - ~
STO Q %w gM f 2 i
Function : RHRSW Pump Motor Cooling Coll Supply Valve SE 70-40 @0 3 5 1.000 GA So C/F0 FST STO Q
Q $g@h j
Function : RHR$W Punp Motor Cooling Coll Supply Valve ;
SR 70-13A [KyD9 3 C .750 RV SA SYS SP 10Y f Function : RHRSW Pump Motor Cooling Relief Valve i
................................................................................................................... 1 SR-70-138 kMd 3 C .750 RV SA SYS SP 10Y Function : RHRSW Pu$ Motor Cooling Relief Valve
................................................................................................................... 6 SR-70-13C FK;td 3 C .750 RV SA SYS SP 10Y :
I Function RHRSWPUm[MotorCoolingReliefValve SR-70-13D 1 ;id
- K #:-
7 Function : RHRSW Pump Motor Cooling Relief Valve i
v70 1A FO
. LC n.. 2 3 C 14.000 CK SA SYS SC ltR. M.wwER8M9M m
$-gNd ~dd M 3 7
?
SO RR 40Q13 Function : Service Water Pump Olscharge Check Valve V70 1B [Ba02 3 C 14.000 CK SA SYb SC RR N f4ROFV14 k is?13??$R ,
~ '
SO .M Q g [ROJ M bgby l Function : Service Water Pump Discharge Check Valve j v70-tC F02 3 C 14.000 CK SA SYS SC M If6fs937%
So M hQid W-M . gd$jdigg3 9?M[ittiMM Function : Service Water Pump Discharge Check Valve .
~
V70-10 [f~ ^02 3 C 14.000 CK SA SYS SC RR
~ bOk JR0f w . V14 IlotED eunma 3 %@ 2 b @
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Function : Service Water Pump Discharge check Valve V70-6 6 03 m 3 8 8.000 GA MAN O SC Q p_lM. 6.
.. d
~ D._YN. i Function : Isolation to Travelling Screen Wash 1 I
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l Revision 16 5-7 <
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Tcblo 5-1 Valve Listing l (Sorted by Drawing Number) ,
Drawing : G 191159 Sh 1 Drawing Tit'.e : Service Water System Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown l Valve Nunber Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks V70 168 6 09 3 B 24.000 GA MAN C [$C.
_ N W O M E C D@h-L h-&ma+a 7 "U Q P~Al.t....IC$ii.d h Function : Alternate Cooling to SW Supply V70 19A F.0.a a 9 3 B 24.000 GA MO AC 0 PIT RR ,
STC Q STO Q Function : SW Supply Header Crossconnect Valve V70 198 C.r09 3 -8 24.000 GA MO-AC 0 PIT RR STO Q Function : SW Supply Header Crossconnect Valve V70-20 G;1.x.t 4.. x 3 B 20.000 CA MO-AC 0 P!T RR !
STC Q i Function : SW Supply Valve to Turbine Building Cooling L,oads l V70 248 TC. .yd2, 3 B 2.500 GA MAN C $0 N O.vaw E7"WWFA wd @M..W.dwmaawfban@%hhE%..l..t9, o6..(Mi.
Function : Alternate Cooling Supply to RBCCW V70-29 @3 3 B 3.000 GA MAN C h ( $ M f Q i[ [ M I [ A M @ nh ,
Function : Alternate Cooling to SW Supply
................................................................................................................... l V70 29A D,h3
~~
Function : Alternate Cooling to SW Supply 3 8 3.000 GA MAN C _W
$"0M_G,_%UM,g_@m@N_N'id,d_O_rij m, V70 328 ECi12 3 B 2.500 GA MAN C M. nz M M**MNA
- a. TOY *w@ww22Lwwm. lCC_5tini Function : . Alterna't'e' Cooling Supply to RBCCW V70-36A C;13 3 B 3.000 GA PAN C S050.~M#5W9IWMY_A
.m mwC ma% l.t._' C6c. . l_i ni .
~*
Function : Alternate Cooling Supply to RBCCW V70 368 <(C;13=
3 8 3.000 GA MAN C .$.0MMONWY@WMAlf~Cd..(_jr.,Q n~ aw. aw um.wau. -
, Function : Alternate Cooling Supply to RBCCW .
V70-38A W1 u.2_ 3 C 12.000 CK SA SYS SC 0 SO Q Function : RHR$W Pump Discharge Check Valve V70 388 M2 3 C 12.003 CK SA SYS SC 0 SO Q Function : RHRSW Pump Discharge Check Valve V70 40A _6.~12 3 C 12.000 CK SA SYS SC 0 SO Q Function : RHRSW Pump Discharge Check Valve v70 408 49 3 c 12.000 CK SA SYS SC SO Q
Q Function : RHRSW Punp Discharge Check Valve Revision 16 5-8
Tcble 5-1 Vcivo Listing (Sorted by Drawing Number)
Drawing : G 191159 Sh 1 Drawing Title : Service 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 42A K 13 3 8 8.000 GA MAN C SO - M_QP "~% w.^P.m.m.' - ..
NTA.. l t',s C_s.o.li,.n..g .
Function RHRSW Altirnate Cooling to SW Supply V70-428 Bf13 3 B 8.000 GA MAN C .S._017 0 PE.m.M.m". , T"Y
~ %a TAl,t.
w .C. oo. lin"g Function : RHRSW Alternate Cooling to SW Supply V70 43A F12 m 3 C 8.000 CK SA SYS SO . Q - 4.~' s .
Alt' Coclin..g m .
CD_S :. ,1RR,
- + <._.. N. .o..te m 1.1,.
Function : SW Discharge Loop Header Check Valve v70 438 B 12 3 C 8.000 CK SA SYS SO e,.
Q c , e.,
,Al t Cooling CD :
- n , RR :s - .< -x--
+ . ~
.Not.e 11,. -
Function : SW Discharge Loop Header Check Valve V70 504 0 09 3 8 2.000 GA MAN C None NA Passive Function : Alternate Cooling to SW Supply V70-130A C.;05 3 8 3.000 GA MAN O SC Q A_WCo6_L
...... - f._r5. .
Function : Isolation to Chlorination Service Water Supply and Circ Water Pump Cooling V70 1308 F05 3 8 3.000 GA MAN O SC Q N[tECcWid
~~~
Function :
_ _ . . . _ . . . . I. solat . ion"to..nmChlor.m.ina.,t
. ......... - m-ion Se.r_vice. --
. . - . . . .W.a.
v ~--
, . , . . . . . ~ter. .4. , . , . -Su.ppl.ym..,.... ...... a. nd..Ci. . _r_c . . ...... Wat.er .~2<Pump ~.. Cool _ing ...
-,a................,................_
m
{.s . .
..... ~ .
~. . . ..> ~. ~ , .,-
.. 07.y; 0 3 ? .. ' s M,,,24;000 ~?.GA' u.
.,he e
y.. m .....y . - . ; gwy 7 y70 13A' < . ,.- ~ s .
a -nMA.N..n' M,_0.n#S.CN .m. t ,RP.u4 s_- _. . en_R.0._hV16,2 0 A., .lt._C. o.o...l.i.n,.g f!F.
v... un. .....
ctiary SW,$@ ply to .the A Headere!. solation
. . . .. . . .....~......... ....~.....,s.
_n
. . . . . . . . ~ . . . . . . . . . . . . ...n.._.....~..~......._........n...~.,..~..,....,_...~-
...~.c
,v70 13B f
.s.. ..
. . - -3 B 0Tc ':3 . ? By ..::24.000 b GA...Am /M. . . 4 _ . .A.sR.R.m2 /$ #3 uxA% s .: e RO ,J. , s.V..i,.t. , .w.A. J. ~. .l,t,,
coo,l.i..n.i.y. c g
M Funct. ion. s.SW Supply-to. th.e-B: H
. . . . . eader'
......~.........
I__n...~..._.n...n...n.,._...n...,.,........,...n.n..,.n..
s .ol at i on,. ... .;.,-.. +,A..N..,&.
. . . . . _ . . . :.w:.s.O.. . o 1J 08 . . 3,L -
. . F12.000 CA
-B'. - = , .0 .!- c SC:: c. -~ RR. i. . x. . ROJ.V17< ,.i.A.lt' Cool.ing
,.-c. +
L,v70-15A.V Function 3.SW Supply to.t.he. A' R. BCCW n m r~ ~ .
' Heat Exchinger n r .n -
MAN
. _ --n. ~
- ...,.v.-...
~. .......... . . . . ............,........ ........... . . - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . , . . . . . , . . . . . . . . . . . . . _ . . . .
- n. ,
a.
. -. i _A , lt ' Coo. .lin. g
?V.70 158' s
, L B 07 ' 13 . J B n .12.000'i gal : M.AN_? ( 0 J., ." S.CJ - - - u._RR1 ~ , ,. . .m J..:.ROJ
.4 .. . -V. 17
EPCVa104-69Al. ' .~ TJd3: E3 T ~ 7 B T 18.000 ( CCNN .P.*CA.w.e.s.o dW.4 e w TS.T0.91 .s V Qw.mu.w.ud ' Pl c.. z. jC.
w;cw.,ws;..w * ' fAl t ' C. o.o..lin- .w.g 4
C .F i
......3
. ........-- .-...... ...... .....s
,.v._ _....._
TO....... ,.A EDG
..... a.nd
' . ....RRU's
.. . .....5;7w
...,.n-..,..._,....,. ... , .; ..,c. .e o....,.... ---
y , g.y i,PCV.104-69B, .
(B.13 ; 'la :
-- .. ... CA J m xCE ,. 2.~57. 0 a o., , m. m. _.mmrc, ~
LA.tt. C.oo.._lin.g B1. ?8.000 :cLt.8RRU'.s. 6 . m._o.e O
.e.c.
. f. u..n. ct
........<.s.. . . . . . . ....... i.o. .
n
- R.H. RSW .
P. CV. F.m.R.. f..SW TO. .,' B S.
. . .. . . . . .. . . ..... .................................................................. . . . . . . . . ED. G...l a. n. d.
,.n w~.. . ...
c ,
L.V70.,j87A - ._ .. A J 06 m.3. gO_' x.1,.250,CA_' 7 . HAM g,Jo,o. . . .
. . . . ,s. sc, IR. x. RDw.~-, .
- .. :O c dnn.,Rol~.4.,...,18.n+,J
..,....g n Al, t :..Co. o...l. i n.-,
7 Function;: Gt and Seat Supply tolSW Ptmps' A and B (Non-Seismic. , Bran.,ch lLi.n. e.V. a, lve : !s. ola.t. io.n) ,. ... . . .....,. ...~. .
.c......................................................
" 3 6 .~ B 4 . , ::1.250 ; cA C. ' HAN : .107 . Ysti fo. l.. ... ... . 2 ROJ V1.8 ?.afAlt Cool.ing" "
&.. V70-1875 , -
.. . Y B-06.'. . ~ - -
. (...
<.F.u. ..Gland i Branch. L...ne.. i
. . ..nct....... ic.a.. :. . Seel ' Supply, to $. W..P.u. mps C.. =a.nd D. .' (No. n. S.e. l. smic Val ve I so. .lat.~.on),
..j. & ._i,-+vj .%
W . t M,y- A.7 - - - .!-+ *'M. .
4 y a- ,
,. 7 g,y g. ;c y ga ,,,p. g l
$V70227'4,,-- ' '
?-0 02 - .. J-3 , 'Bm. !%51.500 ;.aGA , 3vga,'a mu
- M$'< .s-* no* *at .o.SC:b. C.
,g ,7,-1.1. .. Em u , . , s; A_l t..... Coo.'.. . l. .i. n.'sg j
7< Fu,nct.. ..ion.
4 v. .m... .
s;,S V ,.t. o' Fi..r, ..m..e....W=.at
. . . . . . . .er. . . .Pr.es.
in e (N, o.n-S.e. i..s..m. .i. c. ..,B..r.an.c.h
's.ur i z i.ng L. %
. . ... .s.s...............v.s.v...........3.~.u..v...
~ in V
.L.-w.,e..w a,.lve. .I s..o. l.a.s.t. ~t en.).,
..~............................. 1 l
y ~ . . .,., .. .. . . . . ,w m. e. , . , . . ,w,, a m. . . . ~ . ~.
i TSP;70 3A5. - ,
K-04,. .1v.. 3,,E. ? B ;. . ~.. t 2.000,.,Blm .- . . .. AG E. . . ! Oip. , ..? STh.u.N Q% w. . . ,- o .- _r,.-
~mY A.l t- Coo..l. i..n..-
.. ~
.g ,
y? Function t.IA SW Strainer Backwash. Valve (Non Seismlc Branch Lin.e Va.lv.e).
.......~....,......~........n.n...~....n..........~....~..n.. . .
,..... . . . . . . . . . . . . . . . . . . f. . . . . . . . . . . . . . . . .. . . . . . .
?
, , s .. -
v.
Ac ,& y-
~
,* - STC ,10 ' -
.C-05: -13J" -B' ' /; 2.000'< : BL J . :J A0 2 4
iSP-7638 : -
.. .~. A. l.t. Co' o. lin. g m -
Li .
cFunct ion x.81 W. S Strai.n.e.r Backwas.h... Valve . . . . .(Non.-Selsm.icL. . . ~ . ............................................ Bran. ch .0 ~......
.~........ ......... .. l l
Revision 16 5-9 1
1 1
j I
i
Table ~5-1 Valve Listing (Sorted by Drawing Number)
Drawing t G 191159 sh 2 Drawing Title : Service Water System Refuel Or Cold Dwg Safety OM Site Norm Test Test Relief Shut &wn .
Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks
? M Vr,* D W.WY S8401~ D ,s .09 NC 8 24.000 BTF MAN O ,$C .i.e 2 ys..RR./
, ~, g v
t s
.:M n..L vwv
'*R .
.OJ...i.x.V19,.:n J.nW..
.* A. l.t,.>c.Cosl.i.,n:.s.
.c ,
..g Function : SW To Main Condensor Discharge Block Valve V70 17 19.06 3...B 20.000 ,.GA..~ . MAN . . . .C _ . $0 M RRT~ NPS, y RO. .F. V..1.9..U..A._Lt7Cdo_U,_ni Function : Alternate Cooling .fr_om
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................ . . . . .RNR$. W.~. D.. . . . .I. 6.cIterge. . ~ . . . ~ .. .. : to.. c. o. o..l..in. g :. Tower / I.nl.e.t?.!so..l. a..ti..on LV.a. l..v. e 0 07Ci340. 5. 87.T20.000%F7. miR. CO?*so n E, Tl,.-
FV70Junction MATM . A.lternate OP7 Cooling Deep; Basin' to R. NR$W Punp on Valv.e<C. uc.,_. tion. .f actA ati. -
?$C ...T._J"S.a.P_
. . . . . ,'. . . . . .~........~..... _.. n.. .~ ~... ;. - . ..<._,....,
js........ ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . - .. . . . . . ... * ; . ., > ' L. .... . ,...
_'d.
- . s, , *3 , . , , .- v
- : :.>..y g.-
' - _ - . . .RO. J. ,V_1'g9.. H .A. .l. t. . .Co.
T..V7'0 11L . .' ,' D . 07.i. ?.. 4.0' 00 N GA D . J mu s....1. 3Ys Nsc 1.: RR C.. .
s
,s..~Fun.
.cti.on. s .l S. ervice.
.....u............ .. .. .,.,ha. rge.10e .....n.....s....n n..............
c . Water Dis 31. . . J. B1 M. lc. .ine) ;to Cool,ing . . -
.._.., .m.s., m._,. _,.m.e Tower Basin, < Is n...w . .... ..
.., . .u,..m.~
g , c . . ~ . .. ~ .
.e - ,
.~ . n. m. .
as
- V70-18G . . d'; .1E-079.t31 U ~
^
g^o " ROJf"V20~:M ' ' ~ ~
Alt Cooling E.-
.F.unctionii n....,..........u....,..,.~,....,n.
S: e. rv.ic.e Water, D,is, chMge.S
. . , ..........,n,,..,..n...
,. - - ,. , ,s-,, .y,'.
~....,,+~,'L
.- -..e..
E ,0.-_..n_.n..,,.~.~._.n.n.,.,,
20.000Z n.........
RRy - .... GAT...+.. ,<. . . i. :m4 _ . .
gg
' +"0 ? 'J S
_ ~" ~ 'g
- - -
- Al't cool.in; zgg, ..
g
,,.,...7,_ 7..
Water (L @_ic.f~ "'B?
1'.250 S CAE. ; mW P'^'Of ~ 4"0 w iV7De2035 M . ,... I 8-03 ? $C:. .
&. F.unct f.on, :lService '"
A_.;,. '~~ ^ s~ .'m":ni " ~
r..... .......... ....,, ~ , uppl.y ....n.......u..to. Rat!-9l1 . .. . sola. ~ t ion" .v,.....,_........rn.n..n.n....n...n.-.,.n,.n.,n...n.....,_,,
W- - - . , . . ~ ., ..,,, gggg-g n... .n...n...e. , - . . -.J tC7 J o.ys .Ee.ua. .. . . se . ... .
.. .. . e.. : . . q .g -
sv ,y - :.- 1
,..j .. J..
%sV70.206: ' 7 J-03 ?. . t73.M.._ B s. . G, 3 A:L.J 2.5000 mus .d, 9 .o'.. n _
S A. l. v. ,.c._oo..l. i...n_g
- . m .
,5 Function:; service Water Supplyito RRus <17A,17B. , Iso.l. at..i.o. n : Val. v..es. . . x ,. 8
.n..n..
.....,.......,.._n.,,.~-._.n..~.,.,.,.n.,n...,...,n,g.
s.....,,..
q- . ....~................a......,...n.fy...,,......,.,4 3
,+ n. .+... .
4,.. ,. ,. ......n.. .
' . , ,...._.,..q y .,.,..
._ ...,s. . . , , . .
4 yV70.17. 0., < >
CC.0U J3J .. ,_ ?B6 ?6,0000. GLN S EN i s SY$4. ? tCs.' ? RRb . - ....'.#q.Passiv.en. . , .
%sgs.my.& =S O.QQ.RRjf;thg'gd,P,9ssiVej),. Alt Cool _ing
?l w .l.. . .#1: . . . . . + . . .<
West
..:.~u..,,:...~n .. , ott)2 i Funct . . io.. ... n. :. . . . .. ... ', .Co. o l i ngj; Tower. $. W D is t r:i. but. io. n.,:.T r.ay(, Va. l ve-, n. . . .. . .....n.
. . .........n.. . . -.. .,..,._,
. . .n. 4qg o.~. ., _ . ._. . ., ,~
s". ., -
,. .. . - /:_ ............,.....r.....,.
.:.. (4 .y .p ..
- ;: .- - y , n:.A., ._., .
c.. ,.,. .,s. . s. ;
(V70 17.Bl. . .. 6. 000' ?. .Gt...Jt.AN.':.. E ST.S't j sC f s RR n t . Pas'<- . . . . .sives_s Alt Cool..i..ng
- 6. C .07.). ,13G.. ,15; r . . . + . , , . ..,: . . w._ . aw ,,,.an J_ .
g . . .
a~; -.. w .. , . ., - . . _ , ..
[+ Function:,' #1,: West Cooling Tow .
. . . ...ner. ? SW .....D ....,......
i s tel Wt i ..on.s.T
.. -.., ,j. ,. .r. , .,ay . .j volve -
.;_s
,n.. . u~.m,
.;n .- . .... .
n,. .w.w~~.
. . - . . ~,n., .. ..i,....
,g.
.~.n.m. . n ..n. ~,,
- n. x,...
.y.
.,,n.~.., n n. ..,. v n., e n..-~n..
hV70 17C,,,, . . . . .i .C.074 . . ...nn.......
3 ._, ..
e [3$ J B ? E6.000 J Gb. $sk4 ?$YS b SC', iRR; '/PeasivetFAlt? Cooling 1~'.> ' i*
v .. . . . . . , . .....s . , . . . . n. , .
,s mn iC;(g - 30.i_r._? .u Rg.,nb.__ JP,. _.
,.,.w.assi. v.. e,u_N.ot._e :1_2^
- 1 W V
! Fun.cti. on
, . .. . . . . . . . .... es t-......... n.cooli g T.ower SW D stribut. ion Trayc.alve... _ n.
. - ............ a..........~..~....., ........ , . . . ., . . , .. . ~ ... .n... . .... ._,....._..,.. ,. . , ,
n....
. . _ . . _ ~_.,,
- :. .;w.;.y
&~70-1?DL iV ~ XC 0TL %. ( 38 . 6.000 e GD: ' x m W1 ?SYSi4 sci: { RR W '~:; Passive.rvAlt Cooth10 nn ,'
' ~
Tbd 0 4
_%. wn. i Pa ss,i.ve9.6 n N. o.t..e._s12, ^
(J Functions #1. .We. st: Cooling . Tower $5W Distributionnn.- (TrayLVMve. a am 80..t , .6 RR N y n.n., .n_. .-nn.m - - n.n n n
~
s..n....,.s,...,....n,,.,~..n..,,nn, y - ..'. ..n............. ....n. ._y..
...,,.+........,.....n..n.........,n......,..+.,n,,,,..n.r..
.._.......q . . , . . . . . - ' . . - . . g,g W
..,,,y.,4 ,
(V70413 " D.08/. ,37 : up! ; 0J. 501 gat.. . . . . - i. man. st,s M. soi 4. e ^ w'. .Al..t PAL' . . . coo.,,h.
. .. n,~g t
r:,s..s ' '.. -g( . , r @ 4, . , . . < . ., ,
s
.,#2 piundtiont Ser$e Water [:$upply. ARhdi, on, Nod.from?S. W. Main. Condenser D. i.sch.arge.line ,. e.wa.3
,n.......... c ...
...n.............
- . .. ...........s,.....~.........
y - ..
. .w
.. x
,........._,.n.+..~.,_._.,._..
... . . . . . . . , _ ..v..........+.n
- n -- .. - x.~ mm 37 ;B( j.D.750fc4W r mwJ q sfs ; s so e ;og
';V70 4141 10-08' g g Att,coolipg 2
- y. - , , . . . . .. . . .,. . n*.e .. ..,x ., *SCHg. c'.O '. .a. :
F n CFunctions Servic.e Wat.er . supply to Red Monitort fr om SW D..is. charge;to., D.ee.p Basin w.............................
& r' '
- 3. v.w . > u s,o. A .-w>
.............. .. . . . ....,....... ...... n. .......
i < 'n' '
v vw% ' '
- mw ' " mw.r+ % 'n mm.+O
....w.
.....w....n..n.......n..n.....,w.
www:s %W+e +h.vn4m.ss ' + ' n,:mmana.w
.a:m.nm_. . , , _
Revision 16 5-10
t
?
Table 5-1 Valve Listing (Sorted by Drawing Number) i
.'[ L i
Drawing : G 191159 Sh 3 Drawing Title : RCW Cooling Water System !
t Refuel or Cold Dwg Safety CM Sfre 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 !
L Function : RBCCW Pump Discharge Check Valve i V70-958 B 07 3 C 12.000 CK SA SYS SC Q SO Q Function + RBCCW Pump Discharge Check Valve .
V70 113 K 08 2 C 8.000 CK SA SYS SC CS CSJ V01 t
Function : Primary Containment RBCCW Supply Isolation Valve ,
..... .............................................................................................................. I V70-117 L-12 2 B 8.000 GA MO AC 0 PIT RR r STC CS CSJ V01 {
Function : Primary Containment RBCCW Return Valve
{y7p;240. '". 7. ." _ .?. .Ws 2M. 3FT. m BF32.'50?. GAU. m.MA_SMOWS...C..@m T am T a mQ.mo9fM,,EWNT*WWC_66.. m % m m .,_._ .tM. .. -
M/Functi.on:7RBCCW cool
.e.v.......,.....,... ........... .. . .
.,.,n...._...
r ,
'- , .-<.,...n. . ._.,,. . ~.. ..n.
sv.....,
. ..n. . .. .~
. .,.n..
. . ,,. .,.,,. . n.. g,, . . .
f V704 28 .Q$, Md, . .. . i J3J0iGAbgMANg{CjgSOMQh. n. g ; to. r2D . ena 8./.D. ' .RHR '-d ' Coo, Pumps ng:y. _.
)
- . . . . . . . . . .--s ..r............,,a. ...r;, g,. 7 %p ;f -w'" ,f.- . . '- - yy , .: g.,.pa..,
--/dAl,t;
. . . - ,,,9 .# ,3; y ,.,,.
d;D-10LF34_.)E1. g MM$.dd
- . -. .y f g .
..;, Q' t
- ! Functioni R8CCW Cooli.ng ',toiCRD../ en.d. -RNR3 Pumps ,- , .m _-~ ,- ~,.m ,m-. _ __,.- ,
........,...~yg...w
.. .. ..~. .., , . , . .. . . . ..... , . 4......
~ . . ...... _ ...m.. .y . s #.s..,..,.....- .............. . . .
. . . .:., . g g. . 4
~~ ~.p...........,_....,.,,..........,_
. .Ogschaleighgag;4gg;,Atticoogng
.n.y - < , . . p, :-
- ; . . . , . . - ..,, .a ... s,,.,. ,, , .:.. ..v. 93 g
(. ...z. ...;.
V70 28AN:. 3 C. ,1709,03sM, On XB2e ~...-; 3.00g Gg d MA &w.,
i 7 '
(E P. mu.n. ~c t io.np RB, C. C. W Coo l. i n.. g __ . t.
. . o.
._. CRD.:.
.... . ., ,an.d._:.RNR.
.. ...,,. . ...~ ~.,. i P.us.es
.. . _. .... m..,.. ..
.u.
w.,..........#..w.
x --
......... ............r..s........ .... ~--#'.,ya
.g
.,,W.,,-
",....s gj g e Q.pg.4 LW u' e<.p; 4 mw ' Au.
' ' . _t_Q' ' qA. c4g
- .- . . , ", . hy y J g g: . .' >o..;,'y'p.4,
- ., 02' ,M ' f' w: 4 8;.'W 2 $0i G' A4..u
,-. sa F..g, . ,v, q,.g. ;,, j 3,m.r y .
g 4
e V_70+32C; . . _
,,3 p -wto.. c -v =:+P g F'nv^:e.8..% ; . S MAN k . ._ PA, 0M,,y,'.y.,p.,
n.w.sg _C2 S ,w ;na, gg %s wa r. :.,,
a C_oo,n,, .L y#,...,.....,.e
, u.Funct, s R
BC.CW i, on.s.r. Cooling .s :'.to , Ra, dwe.
>........-.r..,...,....................~.. . . . , . . . . . ;p c ,
s t. e. ,
3., .n. d. A/C.;. R. NR. i pumps. ........#.,,.,vgwev.+A.,.w.ww.w.
..,/g.
w.wpg,w,,.g.ww.v
......,......,,,,,7,,.
..j, .f.? ., ,
- m. ya.
%., , M.
w~.. At t.7 Cool.i.ng e : .
p FunctI.on: R adwest m.... ..... . . . . . ....u Bu . ,.t.- .I .di.....-............
- n. g ' I n l e. t. . . .._ _._. .. ~..- v.m. .. . .,,.~. .. . ._. .._.. . ..... .. .m. ..m.
..... , ; ' . . .,:2--/ . ' ., ..,m..m.. . .^ .,. . . n. ..,. . _.. s.,
,- .* . := , 4, lf
./...,Q
,q g
w'sN,4 '
-
- 0-
.s .J i,-y *:.,- ;.,,. ,,--9:/-. .4 . , ,
E .
4
, B n. ' a..2 00 / Gd, . .' ..; MA. N,' Lr 10.m/:SC.L_ m...; . S
'4'QN.wagun.a]ma? .2wA 'wa';.u t_t) Coot !. . -1
. V_ 704107. .> .. . . . . P.05.' . s 3 9. . a n.n w T.
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i Revision 16 5-11 ,
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Tchlo 5-1 Valve Listing (Sorted by Drawing Number) i l
Deswing : G 191159 Sh 5 Drawing Title : Recirculation Purp Cooling Water 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 SL 2 2 7A G 02 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Recirculation Punp Inst Er. cess Flow l' heck Valve SL 2 2-TB G 02 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Recirculation Punp 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 Function : Recirculation Pump Inst Excess Flow Check Valve SL-2-2-8B G 02 2 A/C 1.000 EFC SA SYS LEF RR SC RR R0J V01 Function : Recirculation Pump Inst Excess Flow Check Valve Revision 16 5-12
Tchls 5-1
~ Valve Listing (Sorted by Drawing Number)
Drawing G-191160 Sh 3 Drawing Title : Instrument Air System Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor class Cat (Inch) Body Act Pos Type Freq Roquest Justif. Remarks V72-38A E.17 2 A 2.000 GL A0 0/FC FST Q LJ RR PIT RR STC 0 Function : PCAC Compressor Inlet Containment Isolation Valve V72-388 F.17 2 A 2.000 CL A0 0/FC FST Q LJ RR PIT RR
- STC Q Function : PCAC Compressor Intet Containment Isolation Valve v72 898 J.12 2 A/C 2.000 CK SA SYS LJ RR SC CS CSJ V02
- Function : Drywell Instrument Air Supply Check Valve V72 89C K-15 2 A/C 2.000 CK SA SYS LJ RR SC CS CSJ V02 Function : Drywell Instrunent Air supply Check Valve V72 103 K-11 2 A/C 2.000 CK SA C LJ RR Passive Function : 'Drywell Instrument Air Supply Check Valve 1
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Revision 16 5-13 l 1
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i 1?cJslan 5-1 l Valve Listing j (Sorted by Drawing Number)
Drawing : G-191160 Sh 7 Drawing Title : Diesel Generator Starting Air System Refuel or Cold Dwg Safety DM Size 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 1.500 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 Function : DG Starting Air Engine Inlet Valve AS 24 1B B-03 3 B 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 Function : DG Starting Air Engine Inlet Valve AS-24-2A B-17 3 B 1.500 GL SO C/FC FST C SO 1H 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 AS-24-28 B.03 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 Function : DG Starting Air Engine Inlet Valve AV-24-1A B 17 3 B .125 GA $0 0/F0 FST Q SC 1M RR-V03 Slow Start STC 6M RR-V03 Fast Start Function : DG Starting Air Engine Inlet Vent Valve AV-24 1B B-03 3 8 .125 GA SO 0/F0 FST G 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 .750 RV SA SYS SP 10Y Function : DG Starting Air Receiver Relief Valve RV 24 60 E-05 3 C .750 RV SA SYS SP 10Y Function : DG Starting Air Receiver Relief Valve RV-24 7A H 12 3 C .75 0 RV SA SYS SP 10Y Function DG Starting Air Compressor Relief Valve RV 24-78 H8 3 C . 75 0 RV SA SYS SP 10Y Function : OG Starting Air Compressor Relief Valve Revision 16 5-14
Tcbio 5-1 Valve Listing (Sorted by Drawing Number)
Drawing : G 191160 sh 7 Drawing Title : Diesel Generator Starting Air 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 V72 76A H 12 3 C .750 CK SA SYS 50 0 Function : DG Starting Air Compressor Outlet Check Valve V72 768 H8 3 C . 75 0 CK SA SYS 50 Q Function : DG Starting Air Compressor Outlet check Valve V72 7BA E-14 3 C 2.000 CK SA SYS SO Q Function : DG Starting Air Receiver Outlet Check Valve 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 SO Q Function : DG Starting Air Receiver Outlet Check Valve VT2-780 E-05 3 C 2.000 CK SA SYS So Q Function : DG Starting Air Receiver outlet Check Valve V72-80AX G-15 3 C .750 CK SA SYS 50 Q Function : DG Starting Air Receiver Inlet Check Valve V72 808X G 13 3 C .750 CK SA SYS SO Q Function : DG Starting Air Receiver Inlet Check Valve V72 80CX G 06 3 C .750 CK SA SYS So o Function : DG Starting Air Receiver Intet Check Valve VT2 800X G 05 3 C .750 CK SA SYS SO Q Function : DG Starting Air Receiver Inlet Check Valve V72-82Ax D 14 3 B 2.000 GA MAN C None NA Passive Function : Service Air to DG Starting Air Crossconnect Valve V72 82Bx D-6 3 8 2.000 GA MAN C None NA Passive Function : Service Air to DG Starting Air Crossconnect Valve Revision 16 5-15
i Tablo'5-1 Valve. Listing .
(Sorted by Drawing Number) !
-t-Drawing : G-191160 Sh 8 Orawing Title.: Service Air System Refuel
, or Cold Dwg Safety-OM Size Norm Test Test Relief Shutdown I Valve Number coor class cat (Inch) Body Act Pos Type Freq Request Justif. Remarks p SE 105 2A C-06 3 B .750 GL SO 0/F0 None N/A Passive (
Function : N2 Supply 3-Way vent Valve _
t SE 105-28 C 12 3 8 .750 GL SO 0/F0 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 Relief Valve ,
SR 72 98 F-04 3 C .750 RV SA SYS SP 10Y I Function i N2 Supply Relief Valve SR 72 10A C-05 3 C .750 RV SA SYS SP 10Y Function : N2 Supply Relief Valve ,
SR-72-108 C-04 3 C .750 RV SA SYS SP . 10Y Function N2 Supply Relief Valve q V72 609 E.04 3 A/C .375 CK SA SYS LT Q SC Q Function s Instrument Air to Reactor Building Railroad Airlock V72 610 E-04 3 A/C .375 CK SA SYS LT Q .
SC 0 Functlan : Instrunent Air to Reactor Building Railroad Airlock i e
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V Revision 16 5-16
Table 5-1 l Valve Listing I (Sorted by' Drawing Number) 4 Drawing : G 191162 Sh 2 Drawing Title : Fuel Oil - Miscellaneous Systems a
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 LCV-108 2A E-08 3 8 1.500 GA A0 C STO -Q Function : Diesel Oil Day Tank Level Control Valve LCV 108 2B C-08 3 8 1.500 GA A0 C STO Q Function Diesel Oil Day Tank Level control Valve l LCV 108 3 E 07 3 8 1.500 GA Fanction : DF0 Pump Discharge to Fuel Oil Day Tank Valve A0 C/FC %3M Passive per PDCR 94 022 ;
t SR*78 3A E-06 3 C .750 RV SA SYS SP 10Y Function : Diesel Fuel Oil Transfer Pump Discharge Relief Valve -
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SR 78 38 D-06 '3 C .750 RV SA SYS SP 10Y Function : Diesel Fuel Oil Transfer Pump Discharge Relief Valve V78-2 E-02 3 C 4.000 CK Function : Fuel Oil Storage Tank Fill Line Check Valve SA SYS .gEBf RM V78 28A E 06 3 C 1.250 CK SA SYS SC Q
$0 Q l Function : Diesel Fuel Oil Transfer Pump Discharge Check Valve l V78-2BB D 06 3 C 1.250 CK SA SYS SC Q SO Q Function : Diesel Fuel Oil Transfer Pump Discharge Check Valve r 6
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Revision 16 5-17
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Table 5-1 1 Valve Listing' (Sort'ed by Drawing Number) .
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M Drawing G 191165 Drawing Title : Sampling System i Refuel or Cold Dwg Safety DM Size Norm Test . Test Relief Shutdown Valve Nuiter Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks e PAS 102 K.16 2 B .750 - GA A0 C/FC FST Q ;
STC 0 t Function : Post Accident Sanpling System Jet Ptsp Sample Velve
- f- _
PAS 104 K 16 2 8 .750 GA A0 C/FC FST Q STC 0 .
Function : Post Accident Sampling System Jet Pump Sanple Valve PAS 106 L 16 2 .8 .750 GA A0 C/FC FST Q t
- STC Q !
Function : Post Accident sampling System Purge Valve 6 i
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4 Revision 16 5-18
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Tablo 5-1 Valve Listing (Sorted by Drawing Number)
Drawing G-191167 Drawing Title : Nuclear Boiler Refuel Or Cold Owg Safety OM SIZE Norm Test Test Relief Shutdown Valve Number Coor class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks FCV.2 17 B 06 2 B 1.000 GL AC C/FC PIT RR Passive Function : Rx Vessel Head Steam Space Vent Flow Control Valve FCV 2 18 B 05 1 B 1.000 GL A0 C/FC P!T RR Passive Function : Rx Vessel Head Steam Space Vent Flow Control Valve FCV-2-20 C 06 1 B 1.000 GL A0 0/F0 PIT RR Passive Function : Rx Vessel Head Seal Leakage Flow Control Valve FCV 2-21 C 05 2 B 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
~
P!T RR STC 0 Function : Rx Recirc Sample Line Flow Control / Isolation Valve FCV 2-40 L 03 2 A . 75 0 GL A0 C/FC FST Q LJ RR PIT RR STC Q Function : Rx Recirc Sanple Line Flow Control / Isolation Valve RV 2-71A D-08 1 C 6 x 10 SRV SA SYS SP m
5Y TdiQ tu Function : Nuclear Boiler Safety / Relief Valve RV-2-718 G 08 1 d. 6 x 10 SRV SA SYS SP SY ko. te.. 9..
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Function : Nuclear Boller Safety / Relief Valve RV-2 71C G 08 1 d 6 x 10 SRV SA SYS SP 5Y Nat
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Function : Nuclear Boller Safety / Relief Valve RV 2 71D H-08 1 C 6 x 10 SRV SA SYS ,SP SY .li..s..i..i. l.
Gsa Function : Nuclear Boller Safety / Relief Valve Revision 16 5-19
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i Table 5-1
- Valve Listing (Sorted by Drawing Number)
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 .
.................. .... ...... ... ...... .... ..... ..... ..... .... ....... ........ . . . . . . . . . . . . . . . t fAu, -.d. iw IF F. A"P.(.V.w%lsiisfd'VatE,~Id.,
. NB. R.~f,n*Ac..i,.d. ---- ~ ts._iBrved'fe_iiii_nFisi.f n ~ Pf6 shim)
~~
SL 2-62A I 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 2 628 1 13 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Functlon Nuclear Boller Vessel Inst Excess Flow Check Valve
................................................................................................................... j e SL 2 62C J 13 2 A/C 1.000 EFC SA SYS LEF RR !
SC RR ROJ V01 1 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 62D J 13 2 A/C 1.000 EFC SA SYS LEF RR SC RR R0J V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve 4 SL 2-64A K.13 2 A/C 1.000 EFC SA SYS LEF RR Functfun : Nuclear Boller Vessel Inst Excess Flow Check Valve l SL 2 648 K 13 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve i
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Revision 16 5-20 l
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2 Tchlo 5-1 Valve Listing !
- (Sorted by Drawing Number)
Drawing a G 191167 l Drawing Title : Nuclear 80iler 6
1 Refuel or Cold i Dwg Safety OM Size Norm Test Test Relief Shutdown -l
' Valve Number Coor Class Cat (Inch) Body Act Pos ~ Type Freq Request J m if. 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 SL 2-64D L-13 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 .
i Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 73A F-12 2 A/C 1.000 EFC* SA SYS LEF RR i SC RR ROJ-V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL-2 73B F-12 2 A/C 1.000 EFC SA SYS LEF RR SC RR . ROJ V01 Function : Nuclear Boller Vessel Inst Fxcess Flow Check Valve ,
SL-2-73C G 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 73D G 12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Nuclear Wolter Vessel Inst Excess Flow Check Valve !
SL 2-73E G-12 2 A/C 1.000 EFC SA SYS LEF RR l SC RR ROJ V01 Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve
' SL 2 73F G-12 2 A/C 1.000 EFC SA SYS LEF RR i 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 .
i SC RR ROJ-V01 Function : Nuclear Boller vessel Inst Encess Flow Check Valve -
t SL 2 73N N-12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve t SL 2 305A M 02 2 f./C 1.000 EFC SA SYS LEF RR SC RR R0J-V01 Function : Nuclear Boller Vessel Inst Excess Flow theck Valve t
i Revision 16 5-21
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Tchle 5-1 ,
, Valve Listing (Sorted by Drawing Number)
Drawing G 191167 Drawing Title : Nuclear Boller 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. Romerks
. SL-2 3058 M-02 2 A/C 1.000 EFC SA SYS LEF RR y .
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 14H L-12 3 C 10.000 RV SA SYS SP 10Y !
Function : SRV Discharge Line Vacuum Rollef Valve SR 2 141 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 Olscharge Line vacuun Rollef Valve SV 2 70A D-06 1 C 6x8 SRV SA SYS SP 5Y RR-VOS !
Function : Nuclear Boller Safety / Relief Valve !
SV-2-708 H-08 1 C 6x8 SRV SA SYS SP 5Y RR V05 Function : Nuclear Boller Safety / Relief Valve l V2 27A F 03 1 A/C 16.000 CK SA SYS LJ RR SC RR ROJ V03
$0 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 i
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1 1:adalta 5-1 ' 'l
- , Valve Listing )
(Sorted by Drawing Number) t 4
i Drawing G 191167 1 Drawing Title : Nuclear Boller ]
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 v2 28A F 05 1 A/C 16.000 CK SA SYS LJ RR SC RR ROJ V03
$0 RR ROJ V03 c Function : Reactor Feedwater Injection L{ne 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 E ...................................................................................................................
V2 37A B 06 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ V04 Function MSRV Actuator Nitrogen Supply Check Valve V2 378 C 09 2 A/C 1.000 CK SA SYS LT RR ,
SC RR ROJ V04 Function : MSRV Actuator Nitrogen Supply Check Vasve- ,
V2-37C G 09 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ V04 Function : MSRV Actuator Nitrogen Supply Check Velve , 's A
V2-37D H-09 2 A/C 1.000 CK SA SYS LT RR t SC RR ROJ-v04 )
Function : MSRV Actuator Nitrogen Supply Check Valve V2 53A L-09 1 5 28.000 GA MO AC 0 PIT RR STC CS CSJ V04 Function : Rx Recirculation Pump Discharge Isolation Valve V2 538 L-09 1 B 28.000 GA MO-AC 0 PIT RR
. . STC CS CSJ V04 Function : Rx Recirculation Pump Discharge Isolatlon Valve V2 54A L-09 1 8 4.000 GA MO AC 0 P!T RR i STC CS CSJ-V04 I
Function : Rx Recirculation Pump Discharge Isolation Velve -
V2 54B L 09 1 8 4.000 GA MO-AC 0 P!T RR STC CS CSJ V04 Function : Rx Recirculation Pump Discharge Isolation Valve h
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Revision 16 5-23 1
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l Talsle 5-1 Valve Listing (Sorted by Drawing Number) l Drawing G.191167 Drawing Title Nuclear Boiler Refuel or Cold
- Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Number' Coor Class Cat (Inch) Body Act Pos Type Freq Req m t 'Justif. Remarts V2 74 Fu 1 A 3.000 GA MO AC C LJ RR
. PIT RR STC Q Function : Main Steam Line Drain Containment 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
..................................................................T................................................
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 Steem 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 : Main 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 fction : Main Steam Isolation Valve V2 800 H 12 1 A '18.000 GL A0 0/FC FST Q Note 1 LJ RR
' Plf RR
. STC Q Nott 1 Function : Main Steam isolation valve V2 82A 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 825 8 10 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ vo5 Function : MSIV Actuator Nitrogen Supply Check Valve ,
................................................................................................................... 1 i
V2 82C B.10 2 A/C 1.000 CK SA SYS LT RR !
SC RR ROJ V05 l Function : MSIV Instrument Nitrogen Supply Check Valve j
................................................................................................................... j V2 820 B.10 2 A/C 1.000- CK SA STS LT RR l SC RR ROJ-VOS 1 Function : MSIV Instrument, Nitrogen Supply Check Valve Revision 16 5-24
l 1EaJals) 5-1 i I
Valve Listing
'(Sorted by Drawing Number)
Drawing : G-191167 j Drawing Title : Nuclear Boller 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 V2 86A D 13 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
................................................................................................................... j V2-868 G 12 1 A 18.000 GL A0 0/FC FST Q Note 1 LJ RR PIT RR
~
SIC Q Note 1 Function : Main Steam Isolation Valve V2 86C G 12 1 A 18.000 GL A0 0/FC FST Q Note 1
. LJ R2 PIT RR STC Q Note 1 Function : Main Steam Isolation Valve V2 860 H 12 1 A 18.000 GL A0 0/FC FST Q Note 1 LJ RR PIT RR
. STC Q Wote 1 ;
Function : Main Ste.m Isolation Valve V2 87A B 13 2 A/C 1.000 CK SA SYS LT RR -
SC RR ROJ V05 Function :'MSIV Actuator Air Supply Check Valve i V2 878 B-13 2 A/C 1.000 LK SA SYS LT RR SC RR ROJ V05 -
J Function ~MSIV Actuator Air Supply Check Valve V2 87C B 13 2 A/C 1.000 CK SA SYS LT RR SC RR R0J V05 Function : MStV Actuator Air Supply Check Valve V2 87D B 13 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ V05 Function : MSIV Actuator Air Supply Check Valve V2 96A H 03 1 A/C 16.000 CK SA SYS LJ RR .
SC RR ROJ V03 50 RR ROJ V03 Function : Reactor Feedwater Injection Line Check Valve V2 968 F.03 2 C 16.000 CK SA SYS SC RR R0J-V03 Function : Reactor Feedwater Injection Line Check Valve l 4
4 5-25 l Revision 16 1 l
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Tc110 5-1 Valve Listing (Sort'ed by Drawing Number)
Drawing : G 191168 Drawing Title : Core Spray 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 SL.14 31A F-07 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Core Spray Inst Excess Flow Check Valve SL-14-318 E 07 2 A/C 1.000 EFC SA SYS LEF RR SC RR R0J-V01 Function : Core Spray Inst Excess Flow Check Valve SA 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 V14 5A H 12 2 8 3.000 GA MO-AC 0 PIT RR STC Q STO Q Function : Core Spray Pump Minimum Flow Valve v14 5B H-13 2 8 3.000 GA MO-AC 0 PIT RR STC Q STO Q Function : Core Spray Pu@ Mininun Flow Valve V14 TA K 11 2 B 12.000 CA MO AC O/KL PIT RR Passive Function : Core Spray Pump suction Valve v14-TB L 11 2 8 12.000 GA MO AC O/KL PIT RR Passive Function : Core Spray Pump Suction Valve v14 BA K 12 2 8 12.000 GA MAN C/LC None NA Passive Function : Core,$ pray Supply From, CST ! solation Valve ,
V14 8B L-14 2 8 12.000 GA MAN C/LC None NA Passive Function : Core Spray Supply From CST ! solation Valve V14-10A I-11 2 C 10.000 CK SA SYS SC Q SO Q Function : Core Spray Pump Olscharge Check Valve V14 108 I-14 2 C 10.000 CK SA SYS SC 'Q
- SO Q Function : Core Spray Punp Discharge Check Valve 1
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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 CM Site Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act. Pos Type Freq Request Justif. Reneks
- V14-11A G 09 2 A 8.000 GA MO-AC 0 LJ RR
< P!T RR .
STC Q STO Q Function : Core Spray Injection Valve V14 118 C 09 2 A 8,000 GA MO AC 0 LJ RR PIT . RR STC Q STO Q Function : Core Spray Injection Valve
- V14 12A G 08 1 A 8.000 GA MO AC C LJ RR I
Function : Core Spray Injection Isolation Valve ,
V14 128 C-08 1 A 8.000 GA MO*AC C LJ RR .
P!T RR STC Q STO Q i N(( INN 5$$$6fdd@EN$6[@dP3NN ;
~
Function : Core Spray Injection isolation Valve v14 13A F.06 1 C 8.000 CK SA SYS (Q@ lite 3}M@R$$P]QUl SC CS CSJ v0$
So CS CSJ VOS Function : Core Spray Injection Check Valve V14 138 D-06 1 I 8.000 CK SA SYS ffDQ[RR]$QTM$Q7d$@@lVjT6j SC CS CSJ-V05 S0 CS CSJ-V05 Function . Core Spray Injection Check Valve V14 14A F 05 1 8 8.000 GA MAN 0/LO P!T RR Passive Function : Core Spray Injection Line Valve V14 148 E-05 1 8 8.000 GA MAN 0/Lo P!T RR Passive Function : Core Spray Injection Line Valve V14 16A L 11 2 8 4.000 GA MAN C None NA Passive 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 Revision 16 5-27
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l Tablo 5-1 Valve Listing (Sorted by Drawing Number) '
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, Drawing : G-191168 Drawing Title : Core Spray 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 V14 21A H.08 2 8 2.000 GA MAN C None NA Passive Function : Cond/Demin to Core Spray Flushing Isolation Valve '
V14 218 8-10 2 8 2.000 GA MAN C None NA Passive ,
Function : Cond/Demin to Core Spray Flushing Isolation Valve ,
, V14 26A F 10 2 8 8.000 GL MO AC C P!T RR STC Q Function : Core Spray Pump Test Line Isolation Valve V14 268 E 10 2 8 8.000 GL MO-AC C PIT RR +
STC Q 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 308 D-0Y 2 A 1.000 .GA MAN C None NA Passive j Function Core Spray Injection Check Valve Bypass Valve V14 33A M-11 2 C 1.000 CK SA SYS SC J Function : Core Spray Discharge Pressurization Line Check Valve V14 338 H 15 2 C 1.000 CK SA SYS SC 0 Function : Core Spray Discharge Pressurization Line Check Valve i
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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 (!nch) Body Act Pos Type Freg Request Justif. Remarks 5-23-6 I 06 2 C 16.000 RD SA C RD 5Y Function : HPCI Turbine Exhaust Line Rupture Disc .
5-23 7 H-06 NC C 16.000 RD SA C RD 5Y Function : HPCI Turbine Exhaust Line Rupture Disc SL-23-37A F-04 2 A/C .75 0 EFC SA SYS LEF RR SC RR R0J 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 .75 0 EFC SA SYS LEF RR SC RR R0J V01 function : Nuclear Boiler Vessel Inst Excess Flow Check Valve SL 23 37D F.04 2 A/C .750 EFC SA SYS LEF RR SC RR ROJ V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SSC 23-12 1-03 2 C 20.000 GSC SA SYS SO Q Function : HPCI Turbine Exhaust Stop Check Valve
$$c-23 13 J-04 2 C 2.000 GSC SA SYS SO Q Function : HPCI Turbine Exhaust Drain Stop Check Valve V23 14 F 13 2 B 10.000 CA MO-DC C P!T RR STO Q Function : HPCI Steam Supply Valve v23 15 0 04 1 A 10.000 GA MO AC 0 LJ RR PIT 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 PIT RR STC Q STO Q Function : HPCI Steam Supply Outboard Contairvnent Isolation Valve Rvision 16 5-29
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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 Size Norm Test Test Relief Shutdown Valve Nunber Coor Class Cat (!nch) Body Act Pos Type Freq Regaest Justif. Remarks V23 17 D-11 2 B 14.000 GA MO-DC 0 P!T RR
. STC Q STO Q Function : HPCI Punp Suction Valve from Condensate Storage Tank V23-18 G 05 2 C 14.000 CK SA SYS SC CS CSJ-V06 So CS CSJ-V06 Function : HPCI Pump Discharge Check Valve to Feedwater
~
V23 19 G 06 2 8 14.000 CA MO-DC C Pli RR STO Q Function : HPCI Discharge Isolation Valve to Feedweter V23 20 G 08 2 B 14.000 GA MO-DC 0 P!T RR .
STO Q Function : HPCI Pump Discharge Valve '
V23-21 E-07 2 B 10.000 GL MO-DC C PIT RR STC Q Function : HPCI Pump Test Return Valve to Condensate Storage Tank I V23 25 F 09 2 B 4.000 GL MO-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 i 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 : HPC! Torus Suction containment Isol. Valve - Outbd V23 58 L 04 2 B 16.000 CA MO-DC C PIT RR STC Q STO Q Function : HPCI Torus Suction Containment teolation Valve VZ3-61 L 06 2 C 16.000 CK SA SYS SO CS CSJ-V07 Function : HPCI Torus Suction Check Valve l
Revision 16 5-30 i i
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Tablo 5-1
, Valve Listing (Sorted by Drawing Number) l i
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5 Drawing G.191169 sh 1 Drawing Title : HighPressureCoolantInjectionsystem Refuet !
<' or Cold Owg safety OM ' size Norm Test Test Relief shutdown i Valve Number Coor Class Cat (!nch) Body Act Pos Type Freq Request Justif. Remarks V23 62 J 10 2 C 4.000 CK 5A sys 50 o Function : HPCI Puup Minfinum Rectre Check Valve V23 65 I 03 2 C 20.000 CK sA sYs so e Note 2 '
Function HPCI Turbine Exhaust Check Valve V23 842 1 2 C 1.000 Gsc SA SYS so o i sc 0 '
Function : HPC! Turbine Exh Vac Skr stop Check Valve V23 843 I 03 2 C 1.000 CK SA sYs so o Function : HPCI Turb!ne Exh Vac Bkr Check Valve .
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Tablo 5-1 :
Valve Listing (Sorted by- Drawing Number) ;
Drawing a G-191169 Sh 2 4 Drawing Title : Nigh Pressure Coolant Injection 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 HPCI CONTROL. F 13 2 8 10.000. GL Ho C PIT RR ,
STC Q RR-V06 STO Q RR V06 l Function : HPCI Steam Supply Turbine Control Valve I HPCI STOP F 15 2 8 10.000 GA HO C PIT RR -
STC Q .
STO Q Function : HPCI Turbine Step Valve LCV-23 39 M.11 3 8 1.000 GL A0 C/FC FST Q l P!T RR 'r STC 0 !
STO Q ,
Function : HPCI Gland Seal Return Level Cont Drn Valve to Radweste I LCV.23-40 M-11 3 8 1.000 GL A0 C/FC rai Q PIT RR 1 STC Q j STO Q '
Function : HPCI Gland Seal Return Level Cont Drn Valve to Redweste SR 23-66 J 12 2 8 1.500 RV SA SYS SP 10Y i Function : HPCI Booster Pump Gland Seal Cond. Line Relief Valve V23-50A J.10 2 8 2.000 GA A0 C/F0 FST Q l PIT RR t
STO Q '
Function : HPCI Gland Seal Cond. Supply Valve V23 130 L 11 2 C 2.000 CK SA SYS $0 Q ;
. Function HPCI Gland Seal Tube Side Return Check Valve , I V23-131 L 11 2 C 2.000 CK SA SYS SC Q SO Q '
Function HPCI Gland Seal Cond. Shell Side Return Check Valve V23-148A G 14 3 C 1.000 CK SA SYS SO Q Function HPCI Steam Ring / Chest Drain Check Valve l
................................................................................................................... i V23 1488- G 14 3 C 1.000 CK SA SYS SO Q j Function : HPCI Steam Ring / Chest Drain Check Valve Revision 16 5-32
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Table 5-l'
. Valve Listing (Sorted by Drawing Number) -
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Drawing a G.191170 Drawing Title : Control Rod Drive Hydraulic System t
Refuel or Cold i Dwg Safety OM Size Norm Test Test Relief . Shutdown I Valve Number Coor Class- Cat (!nch) Body Act Pos Type Freq Request Justif. Remarks CV.3 126- C 16 2 B 1.000 GL AC C/F0 FST RR R0J.V06 ;
PIT RR STO RR R0J V06 Function : Control Rod Drive Scram Inlet Valve (Typical of 89)
CV.3 127 C 18 2 B .750 GL A0 C/F0 FST RR ROJ-V06 PIT RR STO RR ROJ V06 Function : Control Rod Drive Scram Outlet Valve (Typical of 89) .
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LCV-3-33A D-07 2 A 2.000 GL A0 0/FC FST Q LT RR PIT RR STC Q .
}
Function : Scram Olscharge Volume Drain Level Control Valve .
LCV 3-338 D 03 2 A 2.000 GL A0 0/FC FST' Q l LT RR '
t Function : Scram Discharge Volune Drain Level control Valve LCV 3 33C D-08 2 A 2.000 GL A0 0/FC FST Q i LT RR ,
P!T RR :
STC Q i
Function : Scram Discharge Volune Drain Level Contro' Valve LCV 3-330 0 03 2 A 2.000 GL A0 0/FC FST Q LT RR P!T RR Q .
STC _
Function : Scram Discharge' Volume Drain Level Control Valve j
PCV-3-32A A 09 2 A 1.000 GL A0 0/FC FST Q LT RR PIT RR STC Q Function : Scram Discharge Volume Vent Pressure Control Valve 1
Revision 16 5-33 i
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Tablo 5-1 Valve Listing (Sorted by Drawing Number)
Drawing : G 191170 Drawing Title : Control Rod Drive Hydraulic System Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Nurrber Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks PCV-3-32B A 01 2 A 1.000 GL A0 0/FC FST Q
. LT RR PIT RR STC Q Function : Scram Discharge Volume Vent Pressure Control Valve
$6 3-120 D-16 2 9 .500 GA SO C/FC FST RR ROJ-V06
$TC RR ROJ-V06 Function : CRD Manual Control" Exhaust Valve (Typical of 89)
Sd-3-121
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0 18 2 B .500 CA SO C/FC FST RR ROJ-V06 i STC RR ROJ-V06 Function : CR0 Manual Control Exhaust Valve (Typical of 89) .
^^Id-3-122 C-18 2 8 .500 CA So C/FC FST RR ROJ V06 STC RR ROJ V06 Function : CRD Manual Control Withdrawal Valve (Typteal of 89)
S0-3-123
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C-17 2 8 .500 CA $0 C/FC FST RR ROJ-V06 STC RR ROJ V06 Function : CR0 Manual Control insertion Valve (Typical of 89)
V3 114 C 18 2 C .750 CK SA SYS So RR ROJ-V06 Function : Scram Exhaust To Discharge Volume Check (Typical of 89) v3-115 B 16 2 A/C .500 CK SA SYS LT RR SC RR ROJ V06 Function : CRD Charging Water To Accumulator Check (Typical of 89)
V3 138 B-16 2' C .500 CK SA SYS SC Q Note 3 Function : CR0 Cooling Water Supply Check Valve (Typical of 89) . ,
V3-162A A 09 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ-V12 Function Scram Discharge Mune Vent Check Valve V3 162B A 01 2 A/C 1.000 CK SA SYS LT RR SC RR ROJ-V12 I
f Function : Scram Discharge Volume Vent Check Valve Revision 16 5-34
Tablo 5-1
, Valve Listing (Sorted by Drawing Number) ,
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Drawing G 191170 Drawing Title : Control Rod Drive Hydraulic System ;
e Refuel or Cold Owg Safety OM Slze Norm Test Test Relief Shutdown [
Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks j
.................. .... ...... ... ...... .... ..... .... ..... .... ....... ........ ............... [
v3 412A E 12 2 A/C .750 CK SA SYS LJ RR !
SC RR ROJ V07 !
Function : Recirculation Punp Seal Purge Supply Check Valve V3 4128 E 12 2 A/C .750 CK SA SYS LJ RR SC RR A0J V07 Function : Recirculation Pump Seal Purge supply Check Valve V3 413A E 12 2 'A/C .750 CK SA SYS LJ RR l SC RR ROJ v07 !
Function : Recirculation Punp Seal Purge Supply Check Valve i v3-4138 E 12 2 A/C . 75 0 CK SA SYS LJ RR i
. SC RR ROJ V07 Function : Recirculation Pung Seal Purge Supply Check Valve I
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Tcblo 5-1
~ Valve Listing (Sorted by Drawing Number)
Drawing : G.191171 Drawing Title : Standby Liquid Control System Refuel or Cold Dwg Safety OH Size Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks S.11 14A 0 03 2 8 a.500 SQU!B EXP C ET RR Note 4 Function : SLC Injection (Squib) Valve S 11 148 H 03 2 8 1.500 SQU!8 EXP C ET RR Note 4 Function : SLC Injection (Squib) Valve SR-11-39A G 08 2 C 1.000 RV SA SYS SP RR RR-V08 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 V11*16 H 03 1 A/C 1.500 CK SA SYS E.n.na nMS SC RR ROJ-v08 SO RR ROJ V08 Function : SLC Injection Piping Check Valve V11 17 I-02 A/C 1.500 CK SA SYS FT_MM wSC aRR ROJ-V08
$0 RR ROJ-V08 Function : SLC Injection Piping Check Valve V11-18 I-02 1 8 1.500 GA MAN 0/LO P!T RR Passive Function : SLC Injection Valve V11 43A H-07 2 C 1.500 CK SA SYS SO Q 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
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1 Tablo-5-1 Valve Listing (Sorted by Drawing Number)
I Drawing : G-191172 Drawing Title : Residual Heat Removal Systen ,
I 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 l FCV 10 160 F 15 2 8 .750 GL A0 C/FC FST Q PIT RR ,
STC Q l
-Function RHR Return Line Process Sampling Valve l FCV 10 185 J-02 2 5 .750 GL AO 0/F0 None NA Passive i
' Function RHR Leakage To RHR Service Water Leak Detection FCV SR 10-35A D-02 2 C 1.000 RV SA SYS SP 10Y Function : RHR Pump Discharge Relief Valve j
- ****"**** ~~~~~ "~~~ ~ '"~~~~~~~~~~~~~~~~'~~~~~~~~~~" "~~~~~
_jk"jhjjg Dkh 2 b ibbb"~k'~~~~~5I"~~~~5"5'~~5""~~~~ibY !
I Function : RHR Pump Discharge Relief Valve SR 10 40 G 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 Side Relief Valve SR 10 80e L 14 2 C 4x6 RV SA SYS SP 10Y Function : RHR Heat Exchanger Tube Side Relief Valve -
SR 10 86A L 03 2 C 1.000 RV SA SYS SP 10Y Function RNR Heat Exchanger Shell Side Relief Valve SR 10-868 L 14 2 C 1.000 RV SA SYS SP 10Y J
Function : RHR Heat Er. changer Shell Side Relief Valve 1 V10 13A L-08 2 8 20.000 GA MO AC 0/KL PIT RR STC Q STO Q Function : Suppression Pool RHR Pump Suction Valve V10 13e L-09 2 8 20.000 GA MO AC O/KL PIT RR STC Q STO Q
- Function ! Suppression Pool RHR Ptap Suction Valve V10-13C J-08 2 B 20.000 GA MO-AC O/KL PIT RR i STC 0 ;
STO Q 1 Function : Suppression Pool RHR Pump suction valve I
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I Table 5-1 i valve Listing '
(Sorted by Drawing Number)
Drawing : G 191172 Drawing Title : Residual Heat Removal System Refusi 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 V10-13D J 09 2 8 20.000 GA Mo-AC O/KL PIT RR STC 0 .
STO Q
. Function : Suppression Pool RHR Punp Suction Valve V10 15A K-07 2 8 20.000 GA ' MO AC C PIT RR STC Q STO Q Function : Recirculation Loop Supply Valve to RHR Pump Suction e
V10 158 K 10 2 8 20.000 GA MO-AC C Pli RR STC Q STO Q Functlon : Recirculation Loop Supply Valve to RHR Punp Suction .
V10 15C J-07 2 8 20.000 GA MO-AC C PIT RR '
STC Q ,
STO Q Function : Recirculation Loop Supply Valve to RHR Pump Suction V10-15D J-10 .2 B 20.000 GA MO-AC C P!T RR STC Q t STO Q ,
Function : Recirculation Loop Supply Valve to RHR Pump Suction v10-16A 1 05 2 B 4.000 GA MO-AC 0 P!T RR STC Q STO Q Function : RHR Pung Discharge Mini Flow Return to Suppression Pool ;
v10 168 1-12 2 8 4.000 GA MO AC 0 PIT RR STC Q i STO Q Function : RHR Pump Discharge Mini Flow Return to Suppression Pool
- V10 17 G-08 2 A 20.000 GA MO AC C (TSmw ^RA NYWEi:
P!T RR STC CS CSJ-VOS STO CS CSJ V08 1 Function : Rectre Supply to RHR Pupp Suct. Outbd. Isolation Valve (t (
g Q.ltit V10 18 F-08 2 8 20.000 GA MO AC C OETh..ii STC CS CSJ-V08
$10 CS CSJ V08 Function : Recirc Supply to RHR Pump Suction !nbd Isolation Yalve Revision 16 5-38
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(' Tcblo 5-1 j
, Valve Listing (Sorted by Drawing Number)
Drawing G-191172 Drawing Title : Residual Heat Removal 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. Romerks V10 19A- L-05 2 C 3.000 CK SA SYS SC Q Note $
SO Q Note 5 Function : RHR Minimun F[ow Check Velve V10 198 L-12 2 C 3.000 .CK SA SYS SC 0 Note 5 '
SO Q Note 5 Function : RHR Minimum Flow Check Valve
. v10 19C J 05 2 C 3.000 CK SA SYS SC. Q Note 5 SO Q Note 5 '
Function : RHR Minimun Flow Check Valve v10-190 J 12 2 C 3.000 CK SA SYS SC Q Note 5 t
. SO Q Note 5 !
Function : RHR Minimun Flow Check Valve V10 20 N-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 Recirc Loop !solat{on Valve t I
V10-258 E 12 2 8 24.000 GA MO-AC 0 - P!T RR STC Q STO Q ,
Function : RHR to Recirc Loop Isolation Valve V10-26A C 07 2 8 12.000 GA MO AC C PIT RR STC Q .
STO Q .
Function : RHR To Containment Spray Isolation Valve v10 268 c.10 2 8 12.000 GA MO.AC C PIT RR STC Q STO Q Function : RHR To containment Spray Isolation Valve g ............ g ....;........... g ... .....
PIT RR STC 0 STO Q Function : RHR to Recirc Loop Isolation Valve Revision 16 5-39 9, ,, -,r..-,
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Tablo 5-1
, Valve Listing (Sorted by Drawing Number) i crewing : G 191172 Drawing Title : Residual Heat Removal 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 ;
v10 278 D.12 2 A 24.000 GL MO AC C Q$$gipt]Qy}((iyggQ$gg1p{sj ;
f 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 7 unction : RHR To containment Spray ! solation Valve V10-318 C-10 2 B 12.000 GA MO-AC C PIT RR ;
STC Q
. STO Q Function : RHR To Containment Spray Isolation Valve V10 34A E-C3 2 B 10.000 GL MO-AC C PIT RR STC Q .
STO Q j Function : RHR Swpression Pool Cooling Supply Valve ,
v10-348 E.14 2 .B 10.000 GL MO AC C PIT RR STC Q STO Q Function : RFA Suppression Pool Cooling Supply Valve
}
V10-36A J 03 2 C 1.000 CK SA SYS SC Q Function : RHR Pump Olscharge Pressurizing Line Check Valve !
V10-368 J-14 2 C 1.000 CK SA SYS SC 0
' Function : RHR Pump Discharge Pressurizing Line Check Valve ,
V10 38A E 04 2 8 4.000 CL MO AC C PIT RR .
s STC Q I
- STO Q j Function : Suppression Chamber RHR Spray Ring Supply Valve V10 388 F 13 2 B 4.000 GL MO AC C PIT RR STC Q E STO Q Function : Suppression Chamber RHR Spray Ring Supply Valve r
Revision 16 5-40
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. Table 5-1
/ valve Listing (Sorted by Drawing Number) s Drawing : G.191172 i:
Drawing Title : Residual Heat Removal System Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown i
- Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks v10 39A 0 04 2 B 12.000 GA MO.AC C PIT RR STC Q STO O ,
Function : RHR Cont Spray / Suppression Pool Cooling Supply Valve .
V10-398 0-13 2 8 12.000 GA MO AC C PIT RR STC Q STO Q >
Function : RHR Cont Spray / Suppression Pool Cooling Supply Valve
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.o . w.gA V10-46A E-07 2 C 24.000 CK SA SYS LT o Hotesto
~ ~ ' "
SC Cs~*"~* ~PCSJ V14 .
,, CSJ.V14 l SO .,c ,,..RR.w,-.
c CF ~ ~<.,'ns -,.' a n s.' w n.s I.V.,,_est
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Function i RHR to Recirc Injection Check Valve V10 46B E-10 2 C 24.000 CK SA SYS LT o $6ife3 tST2NNMH4
~~'- ~
- SC So CS$bs \ 'OICSMV14 Function : RHR to Recirc Injection Check Valve YANK?.$M$b;N YbWdNS!$$$hh V10 48A L-05 2 C 16.000 CK SA SYS SC D$%%iQM$3sh 11 N'3" #)NNf$'N[5 fh h khif.dri7%e.khf-Mywy/W[y!PSD&ow[$QCSjh$f$$$NM 5 enl[ .
y s J0 ,
O 4 ' " . vc W$e$$s
. > x s h ie .a w u 4ec.new w Enc.MM&hewhMMQ6,eGML Function : RHRPumpOlschargeChec hMn~kveMMshMGMa#h._M8 Va ,
V10 488 L-13 2 C 16.000 CK SA SYS SC EC3FUQC5Fi/15M ,
v.w m 7 m ey ?q e n g % m m,yng:q.d.,.mFM. :, , . .a.w~ . ,nT4, MF750 pef CS..bumJu.md.C_SM,V,_15 e
MM9 md
%w.; %jd g ( W fig ??4$< , -yPS0 kkheg%~l CM@4M, fWcMS@h.MM.u.W&dsMdhm.pgggggSC@yQ d0 1
Functfon: RHR Pump Olscharge Check Valve-
.< um.m V10-48C J.05 2 C 16.000 CK SA SYS SC CS;J V 9 C J3cg J its'.Y15 m 4%
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, fq? ' Mip$PSO h65%}on Funct sW:RHRMPump Y Od3d v kscharge ChecT ValveNN3bd hb M Wdbi$$NdbNu dd b 8$q l
................................................................................................................... j v10-480 J.13 2 C 16.000 CK SA SYS SC bC N MCSFh59 1 ryppW:3pw:wgpyngempympgesppyggMgg;/Wi
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e " M:a x :~ PSO W Q
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Function : RHR Pump Discharge Check Valw V10-57 H 13 2 A 4.000 GA MO-AC C LJ RR P!T RR STC 0 Function : RHR Loop Crossconnect To RadWaste Isolation Valve V10 65A J 03 2 B 20.000 GL MO AC 0 PIT RR STC 0 STO C Function : RHR HX Bypass Valve Revision 16 5-41 1
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]
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 Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq R equest Justif. Remarks V10 65B K 15 2 8 20.000 GL MO AC 0 PIT RR STC Q 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 GA MAN 0/LO PIT RR Passive Function : RHR to Rectre Loop Injection Valve V10-81B E-10 2 B 24.000 CA MAN 3/LO PIT RR Passive Function : RHR to Recirc 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 M 17 3 8 12.000 GL MO AC C P!T RR STC Q STO Q Function : RHR HX Service Water Outlet Valve V10-182 1-02 2 C 10.000 CK SA C None NA Passive Function : RHRSW to RHR Emergency Fill check Valve V10 183 J 02 2 B 10.000 GA MO AC C PIT RR Passive Function : RHRSW to RHR Emergency Fill Isolation Valve V10-184 J 02 2 B 10.000 GA MO AC C PIT RR Passive Function : RHRSV to RHR Emergency Fill Isolation Valve Revision 16 5-42
Tchle 5-1 i Valve Listing-(Sorted by Drawing Number)
L Drawing : G-191173 ShiiiH T 2 i Drawing Title : Fuel Pool Cooling C Cisa M System Refuel Or Cold Dwg Safety CM Site Norm Test Test Relief Shutdown Valve Nunber 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
< RV 19-2325 SJ 3 C 1.000 RV Function : Standby Fuel Pool Heat Exchanger FPC Side Relief Valve SA SYS SP 10Y V19 18 1-13 3 C 6.000 CK SA SYS SC Q ;
Function Fuel Pool Demineraliter Return Check Valve V19 21A F07 3 C 6.000 CK SA SYS SO Q i
Function : FuelPool"C$olingReturntoFuelPoolCheckValve V19-218 FD7 3- C 6.000 CX SA SYS SO Q Function : Fuel Pool' Cooling Return to Fuel Pool Check Valve ,
V19-220 G-07 3 8 8.000 GA MO AC 0 PIT RR i STC Q Function : Normal Fuel Pool Cooling Subsystem Isolation Valve V19 221 G 08 3 8 8.000 GA MO-AC 0 P!T RR STC Q Function : Normal Fuel Pool Cooling Subsystem Isolation Valve V19 230A G 10 3 C 6.000 CK SA SYS SC o S0 Q Function : Standby Fuel Pool Cooling Punp Discharge Check Valve V19 2308 H 10 3 C 6.000 CK SA SYS SC 0 50 0 Function : Standby Fuel Pool Cooling Punp Discharge Check Valve
, V70 257A E-11 3 B 4.000 GL MO-AC C PIT RR STC Q STO Q Function : SFPC Nx Service Water Outlet Throttling / Isolation Valve .
V70 2578 F.11 3 8 4.000 GL MO-AC C PIT RR STC Q STO Q Function : SFPC Hx Service Water Outlet Throttling / Isolation valve t
I i
i i
Revision 16 5-43 l
l i
Table 5-1 Valve Listing (Scrted by Drawing Number)
Drawing a G 191174 Sh 1 Drawing Title : Reactor Core Isolation Cooling System Refuel or Cold Dwg Safety CM Size Norm Test Test Relief Shutdown Valve Number 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 ROJ-V01 Function : RCIC Instrumentation Excess Flow Check Valve SL.13-558 C-08 2 A/C .750 EFC SA SYS LEF RR SC RR R0J V01 Function : RCIC Instrumentation Excess Flow Check Valve SL-13 55C B 08 2 ,, A/C .750 EFC SA SYS LEF RR SC RR R0J-V01 Function : RCIC Instrunentation Excess Flow Check Valve SL 13-550 C 08 2 A/C .750 EFC SA SYS LEF RR SC RR R0J-V01 Function : RCIC Instrunentation Excess Flow Check Valve SSC 13 9 K 08 2 C 8.000 GSC SA SYS SO Q Function : RCIC Steam Exhaust Stop Check Valve SSC-13-10 K-09 2 C 2.000 GSC SA SYS So Q Function : RCIC Barometric cond Vacuum Purp Disch Stop Check Valve V13-15 E-07 1 A 3.000 GA MO-AC 0 LJ RR P!T RR STC Q STO Q Function : RCIC Steam Supply Inboard Containment Isolation Valve V13 16 E-09 1 A 3.000 GA MO-DC 0 LJ RR PIT RR STC Q STO Q Function : RCIC Steam Supply Outboard Containment Isolation Valve V13-18 E-14 2 B 6.000 GA MO-DC 0 PIT RR STC Q STO Q Function : Condensate Supply to RCIC Punp 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 G-10 2 B 4.000 GA MO-DC 0 P!T RR STO Q Function : RCIC Purp Discharge Isolation Valve 1
1 Revision 16 5-44 i
1 1
1 l
1
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 Nutber coor Class Cat (!nch) Body Act Pos Type Freq Request Justif. Remarks V13-21 G 09 2 B 4.000 GA MO DC C P!T RR STO Q Function : RCIC Injection Isolation Valve V13-22 G 09 2 C 4.000 CK SA SYS SC CS CSJ-V10 So CS CSJ-V10 Function : RCIC Injection Check Valve V13 27 l-11 2 B 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 Fuiction : RCIC Pump Discharge Minimum 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 Olscharge Check Valve i v13 39 F 13 2 8 6.000 GA MO-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 B 6.000 GA MO 0C C P!T RR STC Q
~
STO Q Function : Supp Pool Supply to RCIC Pump 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 Bkr Stop Check Valve V13 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 i
)
Tablo 5-1 Valve Listing (Sort ~ed by Drawing Number) l l
l J
Drawing G 191174 Sh 2 Drawing Title : Reactor Core Isolation Cooling 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
. LCV-13 12 L.10 3 8 1.000 GA A0 C/FC FST Q PIT RR STC Q STO Q Function : RCIC Baro Cond Condensate Pump Disch Drain LCV l
......................................................................... q, A .-~ ............................... 1 LCV.13-13 L 10 3 8 1.000 CA A0 C/FC FST Q l PIT RR l STC Q STO Q Function : RCIC Baro Cond Condensate Pung Disch Drain LCV RCIC-CONTROL D-12 2 8 2.000 GL H0 0 PIT RR !
STC Q RR-V11 STO Q RR-V11 Function : RCIC Turbine Governing Valve S.13-3 E.11 2 C 8.000 RD SA C Ro SY Function : RCIC Turbine Steam Exhaust Rupture Disc S.13 4 E-09 NC C 8.000 RD SA C RD SY Function : RCIC Turbine Steam Exhaust Rupture Disc SR.13 26 1-07 2 C 1.500 RV SA SYS SP 10Y Function : RCIC Pump Discharge Line to Baronetric 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 SA SYS SC RR ROJ-V09 SO Q s
Function : RCIC Baro Cond Condensate Pump Disch Check Valve ,
- V13-131 E-15 2 8 3.000 GL MO-DC C PIT RR STC Q STO Q Function : RCIC Steam Supply Valve .
.......... ........................................................................................................ j 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 V13 133 K.10 2 C 2.000 CK SA SYS SC RR ROJ.V09 SO 0 Function : RCIC Barometric cond condensate Punp Disch Check Valve Revision 16 5-46
Tcblo 5-1
, Valve Listing (Sorted by Drawing Number)
Drawing : G-191175 Sh 1 Drawing Title : Primary Containment & Atmosphere Control 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 58 16 19-6 0-01 2 A 8.000 8TF A0 0/FC FST Q LJ RR .
PIT RR STC Q Function : PCAC to SBGT Containment Isolation Valve SB 16-19-6A F 02 2 A 3.000 BTF AS C/FC FST Q LJ RR PIT RR STC Q Function : PCAC Drywell Purge & Vent Outlet Bypass Cont Isol Valve 58 16-19-68 L-03 2 A 3.000 BTF A0 0/FC FST Q LJ RR ,
PIT RR STC Q Function : PCAC Supp Chb Prg & Vent Line Bypass Inbd Cont Isol Vlv 58-16-19 7 D 01 2 A 18.000 BTF A0 C/FC FST Q LJ RR PIT RR STC Q Function : PCAC Purge & Vent Exhaust Containment Isolation Valve SB 16-19 7A E 02 2 A 18.000 BTF A0 C/FC FST CS CSJ V12 -
LJ RR PIT RR STC CS CSJ-V12 Function : PCAC Drywell Purge & Vent Outlet Cont Isol Valve S8 16-19 78 K-03 2 A 18.000 ST* Ao C/FC FST CS CSJ-V12 LJ RR PIT RR STC CS CSJ V12 Function : PCAC Supp Chb Purge & Vent Outlet Inbd Cont Isol Valve .
58-16-19 8 t 12 2 A 18.000 BTF A0 C/FC FST CS CSJ-V12 LJ RR PIT RR STC CS CSJ V12 Function : PCAC Drywell Air Purge Inlet Containment Isol Valve Revision 16 5-47
1 l
l Table 5-1 Valve Listing (Sorted by Drawing Number)
Drawing G 191175 Sh 1 Drawing Title : Primary Containment & Atmosphere Control Refuel
, . Or cold Owg Safety OM Size Norm Test Test Relief Shutdown Valve Number Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks SB 16-19-9 .l'16 2- A 18.000 BTF A0 C/FC FST Q !
l LJ RR PIT RR STC Q Function : PCAC Air Purge Supply From Rx Bldg Cont Isol Valve 58-16-19 10 J 13 2 A 18.000 BTF A0 C/FC FST CS CSJ-V12 LJ RR l
~
PIT RR r STC CS CSJ V12 Function : PCAC Supp Chamber Purge Supply Cont Isol Valve SB-16-19-11A K 15 2 A 20.000 BTF A0 C/F0 FST Q i LJ RR .
P!T RR STC Q STO Q Function : PCAC Vacuun Rellef From Secondary containment Iso Valve SB 16 19 11B M 15 2 A 20.000 BTF A0 C/F0 FST Q LJ RR PIT RR STC Q STO Q Function : PCAC Vacuun Relief From Secondary Containment Iso Velve .
$8 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 >
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 So CS CSJ V13 SP RR Note 6 Function : Drywell To suppression chanber Downcomer vacuun Breaker V16-19 58 J-08 2 A/C 18.000 CK SA SYS LT RR !
RV SA SYS PSO Q CSJ V13 SC CS C3J V13 So CS CSJ-V13 SP RR Note 6 Function : Drywell To Suppression Chanber Downcomer Vacuum Breaker i
h Revision 16 5-48
- Table 5-1 Valve Listing (Sorted by Drawing . Number)
Drawing : G 191175 Sh 1 Drawing Title : Primary Containment & Atmosphere Control 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 V16 19 5C J.08 2 A/C 18.000 CK SA SYS LT RR 7
SC CS CSJ V13 So CS CSJ V13 SP RR Note 6
' Function Drywell To Suppression Chamber Downcomer Vacuum Breaker V16-19 50 K-08 2 A/C 18.000 CK SA SYS LT RR -
RV SA SYS PSO Q CSJ V13 SC CS CSJ-V13 So 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 4 RV SA SYS PSO Q CSJ-V13 SC CS CSJ-V13 ,
So 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 -
Function : Drywell To suppression Chamber Downcomer vacuun Breaker V16-19-5G J-08 2 A/C 18.000 CK SA SYS LT RR RV SA SYS PS0 Q CSJ-V13
^
SC CS CSJ-V13 t 50 , CS CSJ-V13 i 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 SC CS CSJ-V13 50 CS CSJ-V13 i SP RR Note 6
' Function : Drywell To Suppression Chanber Downcomer vacuun 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 SO CS CSJ V13 SP ' RR Note 6 Function : Drywell To Suppression Chamber Downcomer Vacuum Breaker 1
Revision 16 5-49 1
l
Tablo 5-1 Valve Listing (Sorted by Drawing Number)
Drawing : G 191175 Sh 1 Drawing Title : Primary Centainment & Atmosphere Control Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Nurrber Coor Class Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks V16-19-5J J 08 2 A/C 18.000 CK SA SYS LT RR RV SA SYS PSO C CSJ V13 SC CS CSJ-V13 SO CS CSJ-V13 SP RR Note 6 Function : Drywell To Suppression Chamber Downcomer Vacuum Breaker V16-19 12A K-16 2 A/C 20.000 CK SA SYS LJ RR RV SA SYS SC Q SO Q SP RR Note 6 Function : PCAC Vacuum Relief From secondary Containment Check Vlv V16-19 128 M-16 2 A/C 20.000 CK SA SYS LJ RR RV SA SYS SC Q SO Q SP RR Note 6 Function : PCAC Vacuum Relief From Secondary Containment Check Vlv V16-19-51 J 11 2 A/C 2.000 CK SA SYS LJ RR Passive 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 V16 20 20 H-12 2 A 1.000 GA SO 0/FC FST Q LJ RR PIT RR STC Q Function : PCAC Containment Purge Makeup Outbd Cont Isol Valve V16 20 22A H-11 2 A 1.000 GA SC C/FC FST Q .
Function : PCAC Containment Purge Makeup Cont Isol Valve V16-20-228 H-12 2 A 1.000 GA SO 0/FC FST Q LJ RR P!T RR STC Q Function : PCAC Containment Purge Makeup Cont Isol Valve j
................................................................................................................... l V20-400A W!D9 2 8 2.000 GL MAN C/LC None NA Passive '
Function : Torus Driin Valve V20-4008 niG7 2 8 2.000 GL MAN C/LC None NA Passive Function : TorusDrafn"Yelve Revision 16 5-50
'Tablo 5-1
, Valve Listing (Sorted by Drawing Number)
I' l
Drawing : G 191177 sh 1 Drawing Title : Radweste Sytems 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 I
V20 82 B-04 2 A 3.000 BL A0 0/FC FST Q l LJ RR ,
PIT RR t,TC Q Function : Drywell Floor Drain Sump Containment ! solation Valve
!. V20 83 B 05 2 A 3.000 BL A0 0/FC FST Q ]
LJ RR PIT RR STC Q Function : Drywell Floor Drain Sump containment Isolation Valve
- - -*--= - *- *= -* *- =* =* * -- - - - -- = ---=--* ---- --* - - ---**- ------- --*
CB =*----
V20 94 G 04 2 A 3.000 BL A0 0/FC FST Q LJ RR ,
PIT RR STC Q Function : Drydell Equipment Drain Sunp contairment 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 Orsin Sump contairment Isolation Vlv V20 319A D 06 2 8 1.500 GA MAN C None NA Passive Function Rx Bldg Floor Drain Punp To Suppression Pool Iso Valve V20-3198 D-06 2 B 1.500 GA MAN C None NA Passive Function : Rx Bldg Floor Drain Punp To Suppression Pool !so Valve ,
V20-319C C-08 2 8 1.500 GA MAN C None NA Passive Function : Rx Bldg Floor Drain Pump To Suppression Pool Iso Valve V20-3190 C-08 2 8 1.500 CA MAN C None NA Passive Function : Rx Bldg Floor Drain Pump To suppression Pool Iso Valve .
Revision 16 5-51
Tablo 5-1 i Volvo Licting (Sorted by Drawing Number)
Drawing G 191178 sh 1 Drawing Title : Reactor Water Clean Up 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. Remarka V12-15 D 02 1 A 4.000 GA MO-AC 0 LJ RR PIT RR Function Reactor Water Cleanup Contelnment Isolatloa Valve L 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 0 08 3 C 3.000 CK SA SYS SC y ((dQ[1]
Function : RWCU Pump Discharge Check Valve v12 288 G 08 3 C Function RWCU Pump Discharge Check Valve 3.000 CK SA SYS SC l Ej@M3 V12-62 8-05 2 C 4.000 CK SA SYS CD "
RR ggg gipj~g
"'^~^"
Function : RWCU Flow to Feedwater System Isolation Check Valve v12 62A B 05 3 C 4.000 CK SA SYS CD >~
RR Y
@w$.A"B M.. ~El.,t
~
Function : RWCU Flow to Feedwater System Isolation Check Valve .
f I
1 i
b Revision 16 5-52
1 1
Table 5 1 Valve Listing (Sorted by Drawing Number)
Drawing : G 191237 Drawing Title : HVAC Turbine, Service & Control Room Blg 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 SACC 1A CHECK A 18 3 C 1.000 CK SA SYS SO Q Function : Cont Room HVAC Chiller Refrigerant Piping Check Valve SACC-1A RELIEF A 18 3 C 1.000 RV SA SYS SP 10Y Function : Cont Room HVAC Chiller Refrigerant Piping Relief Valve SACC-1B CHECK A 19 3 C 1.000 CK SA SYS SO Q 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 Refrigerant Piping Relief Valve SCW 8A l-11 3 C 3.000 CK SA SYS $0 Q Function : Control Roore HVAC Chilled Water Punp Disch Check Valve SCV 65A H.11 3 B .750 Gl SA C None NA Passive Function : Control Room HVAC Chilled Water Makew i tolation Valve Revision 16 5-53
Tablo 5-1 Valve Listing (Sorted by Drawing Number)
DrawinQ : G 191238 Drawing Title : HVAC . Reactor Building Refuel or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve Ntsber Cow Class Cat (Inch) Body Act pm Type Freq Request Justif. Remarks SB-1 125-1A G 08 2 8 12.000 BTF A0 C/F0 FST Q PIT RR STC Q A
STO Q Function Standby Gas Treatment Train Inlet Valve 58-1 125 1B G 07 2 B 12.000 BTF A0 C/F0 FST Q Pli RR STC Q 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 PIT RR STC Q STO Q Function : Standby Gas Treatment Train Inlet Valve SS 1 125 28 H-06 2 8 12.000 BTF A0 C/F0 FST Q PIT RR STC Q STO Q ,
Function : Standby Gas Treatment Train Inlet Valv* l SB 1 125 3A G.06 2 B 12.000 BTF A0 0/F0 FST Q Plf RR STO Q Function : Standby Gas Treatment Train Discharge Valve J S8 1 125-3B G 06 2 B 12.000 BTF A0 C/F0 FST Q PIT RR
, STO Q ,
function : Standby Gas Treatment Trafn Ofscharge Valve
. SB 1 125 4A H 07 2 B 12.000 BTF A0 C/FC FST 0 PIT RR STC Q STO Q Function : Standby Gas Treatment Train Dilution Valve 12.000 BTF
$8 1-125 4B H 06 2 8 A0 C/FC FST Q PIT RR STC Q STO Q Function Standby Gas Treatment Train Ollution Valve 58 1 125 5 G 06 2 B 4.000* BTF A0 C/FC FST Q PIT RR STC Q STO Q Function Standby Gas Treatment Train Xconn Valve Revision 16 5-54
Tchle 5-1
. Volva Listing !
(Sorted by Drawing Number) 4
\
Drawing G-191238 Drawing Title : l NVAC - Reactor Building \
Valve Nunber Dwg Safety OM Refuel y Size i i
.................. Coor......
Class...Cat...... (Inch) 8cdr or Cold f S8 1 125 7A Act Pos Norm Test
.... Type Test Relief Shutdown
..... Freq Request Justif.
F 07 .... .....
! 2 C 12.000 CK SA
....... Remarks f
Function Stand
.................by C SC Q Q
$81 125 78 GasF 07 Treatment 2 C Train Discharge t, heck Valve..........................................
12.000 CX Function : Stand
.................by SA C SC Q Q
$8 9 Gas H-09 Treatment 2 8 Train Olscharge check Valve..........................................
54.000 8TF A0 Function : RX Sul 0/FC FST Pti Q .
...................lding Supply ! solation Valve Q RR
- (
58-10
.................................................STC H-08 2 8 54.000 BTF A0 l
Fmction : RX S 0/FC FST PIT Q
................ullding Supply 1 solation Valve STC C 58 11 G-08 2 8 54.000 8TF Function : Rx B A0 0/FC ................................................
FST Ptf Q ....
$8 12 Exhaust to Stack Sec Cond Isolation Valve G-09 2 8 54.000 8TF A0 Function : Rx Bld 0/FC FST P!T Q
...................g RR Q
Exhaust to Stack Sec Cond Isolation Valve.......................
1 Revision 16 5-55
_ _L - __ :- ____ - _ _ - --__-__- .~
c .
l Tcbio 5-1 Valve Listing (Sort'ed by Drawing Number)
Drawing : G 191267 Sh 1 Drawing Title : Nuclear Boiler Vessel Instrumentation Refuel or Cold Dwg Safety OM Sitt Norm Test Test Relief Shutdown Valve Number coor class Cat (!nch) Body Act Pos Type Frog Request Justif. Remarks SL 2 3 11 d406
"~~~
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 13A 2 2 A/C 1.000 EFC SA SYS LEF RR D*~06
' ~
SC RR ROJ V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2-3 138 'C;12 2 A/C 1.000 EFC SA SYS LEF RR
~~~
SC RR R0J V01 Function Nuctee* Boiler Vessel Inst Excess Flow Check Valve SL 2 3 15A 6166
~ ^ " "
2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 '
Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL-2-3-158 Dj"t2
^"
2 A/C 1.000 EFC SA SYS LEF RR '
SC RR ROJ V01 l' Function 3 Nuclear Boller vessel Inst Excess Flow Check Valve SL 2 3 17A (396 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 ("T12 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 (106 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 3 198 [jt2 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 "{" "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 2-3-21B I 04 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 tunction : Nuclear Boller Vessel Inst Excess Flow Check Valve Revision 16 5-56
+
-Tablo 5-1 valve Listing (Sort ~ed by Drawing Number)
Drawing : G-191267 Sh 1 Drawing Title : Nuclear Boiler 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 ,
j- .................. .... ...... ... ...... .... ..... .... ..... .... ....... ........ ............... ,
SL 2-3 21C h^112
^ ~ ~
1 A/C 1.000 EFC SA SYS LEF RR i 4
SC RR ROJ V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2-3 210 1 12 1 A/C
~
SC RR ROJ V01 !
Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve !
SL 2-3 23A 'G 706 1 A/C 1.000 EFC SA SYS LEF RR
' ^ ~ ~
- SC RR R0J V01 Function Nuclear Boller Vessel Inst Excess Flow Check Valve '
i ...................................................................................................................
SL-2 3-238 G 04 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Functim) : Nuclear Boller Vessel Inst Excess Flow' Check Valve SL 2 3 23C G 12 1 A/C 1.000 EFC SA SYS LEF RR i SC RR R0J V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL*2 3-230 G 12 1 A/", 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Nuclear Soller Vessel Inst Excess Flow Check Valve SL-2-3-25 !-04 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 >
i Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL 2 3-27 t;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 Boiler Vessel Inst Excess i
. . . . . . . . . . .f. .l ow Ch ec k Va l ve Revision 16 5-57
Tablo 5-1 Valve Listing (Sort'ed by Drawing Number)
Drawing a G-191267 sh 1 Drawing Title : Nuclear Boiler 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 Jtatif. Remarks SL-2-3 318 (' p*D6 "
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 3-31C ('106 "'
1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve SL-2-3-312 f~06
" ^ "
1 A/C 1.000 EFC SA SYS LEF RR I 2 SC RR ROJ-V01
^
Functla. : Nuclear Boiler Vessel Inst Excess Flow Check Valve SL-2-3-31E [;06 1 A/C 1.000 EFC SA SYS LEF RR SC RR R0J-V01 Function : Nuclear Beller 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 Boiler Vessel Inst Excess Flow Check Valve SL-2 3-31G ((p6 1 A/C 1.000 EFC SA SYS LEF RR SC RR R0J-v01 Function : Nuclear Boller vessel Inst Excess Flow Check Valve SL-2-3-31H FiO6 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 9C RR ROJ-V01 Function.: Nuclear Boller vessel Inst Excess Flo.# Check Valve SL 2-3-31K F;12 1 A/C 1.000 ETC SA SYS LEF RR SC RR ROJ-V01 Function i Nuclear Boiler Vessel Inst Excess Flow Check Valve SL 2-3-31L 8;12 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 5-58
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Table 5-1 Valve Listing (Sorted by Drawing NLimber) i 1
1 4
l Drawing : G 191267 Sh 1 ,
Drawing Title : Nuclear Boiler 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 31M ""2 E.1" 1 A/C 1.000 EFC SA SYS LEF SC RR RR ROJ V01 i
Function : Nuclear Boiler vessel Inst Excess Flow Check Valve SL 2-3-31N @' ^2 "
1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve
. SL 2-3-31P k
_P m12 1 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01 (
Function : Nuclear Boiler Vessel Inst Excess Flow Check Valve
. SL-2-3 310 pfi2
~~~
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 33 1-12 2 A/C 1.000 EFC SA SYS LEF RR SC RR ROJ-V01
- Function : Nuclear Boiler vessel Inst Excess Flow Check Valve SL.2-3-35 ~R~ ~ Od 2 A/C 1.000 EFC SA SYS LEF RR ;
SC RR ROJ V01 Function : Nuclear Boller Vessel Inst Excess Flow Check Valve ;
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Tcblo 5-1 Valve Listing (Sorted by Drawing Number)
Drawing : G 191267 Sh 2 Drawing Title : Nuclear Boller Vessel Instrumentation 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 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 Function : Reference Leg Back Fill Inlet Check Valve V 2 3 432A C 10 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 432B E 10 2 A/C 0.3 75 CK SA SYS LJ RR SC RR ROJ-vi5~~
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-Vi$~"
Function : Reference Leg Back Fill Inlet Check Valve V-2 3-4338 H 09 2 A/C 0.3 75 CK SA SYS LJ RR SC RR ROJ-Vi$
Fuaction : Reference Leg Back Fill Inlet Check Valve V 2-3 435A F 10 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 3-4358 H-10 2 A/C 0.3 75 CK SA SYS LJ RR ..
i SC RR ROJ V15 ~'
Function : Reference Leg Back Fill Inlet Check Valve 9
Revision 16 5-60
Table 5-1 Valve Listing (Sorted by Drawing Number)
Drawing : VT E 75 002 Drawing Title : Containment Atmosphere Ollution 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 FSO 109 75A 1 J 13 2 B 1.000 GA SO C/FC FST Q Note 7 PIT RR STC Q STO Q Function : CAD Sample Torus Inboard Isolation Valve FS0-109-75A 2 J 14 2 B 1.000 GA SO C/FC FST Q Note 7 PIT RR STC Q STO Q Function : CAD Sample Torus Outboard Isolation valve FSO-109 75A-3 J-14 2 B 1.000 GL So 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 8 1.000 GL SO C/FC FST Q Note 7 PIT RR STC Q STO Q Function : CAD Supply Torus Outboard Isolation Valve F SO-109-758-1 1-12 2 8 1.000 GA $0 0/FC FST Q Note 7 P!T RR STC Q STO Q Function : CAD Sample Lower Drywell Inboard Isolation Valve FSO-109-75B 2 1 12 2 B 1.000 GA SD 0/FC FST Q Note 7 P!T STC RR Q
STO Q Function : CAD Sample Lower Drywell Outboard Isolation Valve FS0 109-75C 1 G-12 2 8 1.000 CA SO 0/FC FST Q Note.7 P!T RR STC Q STO Q Function : CAD Sample Mid Drywell Inboard Isolation Valve i
Revision 16 5-61
Table 5-1 i
, Valve Listing (Sort'ed by Drawing Number) ,
i r
Drawing : VY-E 75 002 i Drawing Title : Containment Atmosphere Dilution Systein 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 >
t FS0-109 75C 2 G 12 2 B 1.000 GA SO 0/FC FST Q Note 7 i PIT RR STC 0 i STO Q ;
Function : CAD Sample Mid Drywell outboard Isolation Valve , ,
FS0-109-750 1 G-12 2 B 1.000 CA SO 0/FC FST Q Note 7 PIT RR i STC Q STO Q Function : CAD Sample Upper Drywell Inboard Isolation valve F 0 109 750-2 G 12 2 B 1.000 GA SO 0/FC FST Q Note 7 PIT AR '
STC Q ;
STO Q Function : CAD Sanple Upper Drywell outboard Isolation Valve l FSO 109 76A L.13 i A 1.000 GA SO 0/FC FST C LJ RR PIT RR ,
STC Q ,
STO Q !
Function : CAD CAM Return Containment Isolation Valve .
t FS0-109 76B L 13 2 A 1.000 GA SO 0/FC FST Q LJ RR P!T RR l STC Q 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 PIT RR ,
STC Q STO Q Function : CAD N2 Supply Containment Isolation valve j NG 118 H 08 2 A 1.000 GL SD C/FC FST Q LJ RR PIT RR STC 0 STO Q Function : CAD N2 Supply Containment Isolation Valve 1
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Revision 16 5-62 i 7
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N.ble 5-1 Valve Listing (Sorted by Drawing Number) J Drawing : VY-E 75-002 '
Drawing Title : Containment Atmosphere Dilution 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 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 Isolation valve NG 128 J 08 2 A 1.000 GL SO C/FC FST Q LJ RR
- CAD N2 Supply Containmert Isolation Valve NG 13A 1-09 2 A 1.000 GL So C/FC 'FST Q LJ RR P!T RR STC Q STO Q Function : CAD N2 Supply Containment Isolation valve NG 13B H 09 2 A 1.000 GL So C/FC FST Q LJ RR P!T RR STC Q STO Q Function : CAD N2 Supply Containment Isolation Valve VG 9A H-12 2 A 1.000 GL SO C/FC FST Q LJ RR PIT RR STC Q STO Q Function : CAD To SBGT System Containment Isolation Valve VG 98 I 14 2 A 1.000 GL SO C/FC FST Q LJ RR PIT PR STC STO t Fund t on CAD To SBCT System Containment isolation Valve Revision 16 5-63
Table 5-1 valve Listing (Sorted by Drawing Number)
Drawing : VT E-75-002 Drawing Title : Containment Atmosphere Dilution 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 VG 22A B-16 2 A 1.000 GL MO-AC C LJ RR PIT RR STC Q STO Q Function : CAD To SBGT System Containment Isolation Valve VG 228 E 16 2 A 1.000 GL MO-AC C LJ RR PIT RR STC 0 STO Q Function : CAD To SBGT System containment Isolation Valve VG 23 J-19 2 A 1.000 GL So C/FC FST Q LJ RR P!T RR STC Q STO Q Function : CAD Rad Monitor Supply Containment Isolation Valve VG-24 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 Isolation Valve VG 25 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 VG 26 J-19 ,2 A 1.000 GL SO 0/FC FST Q LJ RR PIT RR STC Q STO Q Function : CAD Rad Monitor Supply containment Isolation Valve .
VG-33 L 11 2 B 1.000 GL SO 0/FC FST w Note 7 PIT RR STC Q STO Q Function : CAD H202 Analyzer Return Isolation valve Revision 16 5-64
Tchlo 5-1 Valve Listing (Sort'ed by Drawing Number)
Drawing : VT E 75 002 Drawing Title : Contalrunent Atmosphere Ditution 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. Romerks VG 34 L 11 2 B 1.000 GL SO 0/FC FST Q Note 7 PIT RR STC Q r Q STO Function CAD H202 Anatyrer Return isolation valve 1
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Revision 16 5-65 P
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Table 5-1 Valve Listing
. (Sort'ed by Drawing Number)
Drawing : 5920-271 Drawing Title : Woutron Monitoring System Refuel Or Cold Dwg Safety OM Size Norm Test Test Relief Shutdown Valve NLaber Coor Ciass Cat (Inch) Body Act Pos Type Freq Request Justif. Remarks
.................. .... ...... ... ...... .... ..... .... ..... .... ....... ........ ........s......
By-7 1 C-07 2 A .375 BL $0 C/FC FST C LJ RR PIT RR Note 8 STC Q Function : Neutron Monitoring System Tip Tube Ball Valve BV 7-2 C-07 2 A .375 BL $0 C/FC FST Q LJ RR
- PIT RR Note 8 STC Q Function Neutron Monitoring System Tip Tube Ball Valve 8V 7-3 C 07 2 A .375 BL SO C/FC FST o LJ ' RR PIT RR Note 8 STC Q-Function Neutron Monitoring System Tip Tube Ball Valve S71 C 07 2, D .375 SQU18 EXP O ET RR Function Neutron Monitoring System Tip Tube Shear Valve S 7-2 C 07 2 0 .375 SQU1B EXP O ET RR Function : Neutron Monitoring System Tip Tube Shear Valve S.7 3 C-07 2 D .375 SQu!B EXP O ET RR Function : Neutron Monitoring System Tip Tube Shear Valve i
................................................................................................................... i V 7 113 C-08 2 A/C .500 CK SA SYS LJ RR l SC RR ROJ-V11 Function Neutron Monitoring System Tip Purge Iso. Check Valve ,
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1 Revision.16 5-66 l l
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5.3 Valvo Natos 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 ~5 percent. At least twice a week, the MSIVs are also exercised by 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 control rod has been declared inoperable and its directional 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.
- 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. l
- 8. Positive verification of full opening'of the valves is shown by J successful insertion of the Transversing In-Core Probe through i the valve. Positive verification of full closing of the valve ,
is shown during each Refueling Outage by successful leak testing (LJ). This testing . in compliance with Paragraph 4.1 of Part 10 of the Code which states "Where local observation is not l
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.
Revision 16 5-67 1 1
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Revision 16 5-68 9
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i COLD SHUTDOWN JUSTIFICATION Number: CSJ-V01, Revision 1 (Sheet 1 of 1) t SYSTEM - Reactor Building Closed Cooling Water COMPONENTS: j 1
OM Safety Dwg ,
Valve Number Cat Class Drawing Number Coor '
f V70-113 C 2 G-191159 Sh 3 K-08 V70-117 B 2 G-191159 Sh 3 L-12 Valves V70-113 and V70-117 are reactor building closed cooling water 'I supply and return containment isolation valves. They have a safety function in the closed position to provide primary containment isolation.
UUSTIFICATION: !
These valves cannot be tested during normal (power) operation since shutting these valves would stop cooling water flow to vital primary :
containment equipment, including the primary containment air coolers and the reactor recirculation pumps.
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) of Part 10 of the Code.
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Revision 16 5-69 l l
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i 5 t COLD SEUTDOWN JUSTIFICATION Number: CSJ-V02, Revision 1 (Sheet 1 of 1) ;
SYSTEM: Instrument Air.
COMPONENTS:
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OM Safety Dwg i Valve Number Cat Class Drawing Number Coor V72-89B A/C 2 G-191160 Sh 3 J-12 l t
~
V72-89C A/C 2 G-191160 Sh 3 K-15 l I
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These check valves are the drywell instrument nitrogen supply header j isolation valves. They have a safety function in the closed position to i 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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Revision 16 5-70
A COLD SHUTDOWN JUSTIFICATION Number CSJ-V03, Revision 1 (Sheet 1 of-1) l SYSTEM: Nuclear Boiler COMPONENTS:
OM Safety Dwg Valve Number Cat Class Drawing Number Coor i 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 l SR-2-16H C 2, G-191167 L-12 SR-2 '.4I C 2 G-191167 L-12 SR-2-14J C 2 G-191167 -
L-12 ;
SR-2-14K C 2 G-191167 L-12 l SR-2-14L C 2 G-191167 L-12 l l
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 j drawing up water from the suppression pool into the discharge line and !
excessive backpressure at the relief valve discharge upon successive l relief valve actuations. l l
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? THIS COLD SHUTDOWN JUSTIFICATION WAS DELETED IN REVISION 15 OF THE IST l
- PROGRAM.
Revision 16 5-71
COLD SHUTDOWN JUSTIFICATION i Number: CSJ-V04, Revision 1 (Sheet 1 of 1) i SYSTEM: Nuclear Boiler 1
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-191?67 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 operat' ion since cycling these valves would result in a reactor recirculation pump trip. ,
These valves will be exercised and verified operable during Cold Shutdowns i and each Refueling Outage in accordance with Paragraphs 4.2.1.2 (f) & (g) of Part 10 of the Code.
i Revision 16 5-72
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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 t
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.
i JUSTIFICATION: j 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.
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l Revision 16 5-73 l
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i COLD SHUTDOWN JUSTIFICATION l Number: CSJ-V06, Revision 0 (Sheet 1 of 1) l 1
SYSTEM: High Pressure. Coolant Injection COMPONENTS:
i OM Safety. Dwg- -
Valve Number Cat _ Class Drawing Number Coor i i
l V23-18 C 2 G-191169 Sh 1 G-05 )
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This valve is the High Pressure Coolant Injection (HPCI) discharge to Feedwater Line "A" check valve. The valve has a safety function in the i open position to pass HPCI flow to the reactor and in the closed position ;
to prevent backflow in the event of a HPCI high energy line break. !
l JUSTIFICATION. ;
This valve cannot be exercised during normal (power) operation since flow !
through this valve must be injected into the reactor coolant system. This- l would thermally shock the reactor nozzles and cause a positive reactivity. i excursion. Manual operation of the valve is not possible since the valve !
is located in the steam tunnel which is inaccessible during power l operations. ;
i 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 of the Code. !
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Revision 16 5-74 i
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Number: CSJ-V07, Revision 0 (Sheet 1 of 1)
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SYSTEM: High Pressure Coolant Injection COMPONENTS:
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.
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Revision 16 5-75 )
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SOLD SHUTDOWN JUSTIFICATION Number: CSJ-V08, Revision 1 (Sheet 1 of 1) i RISTEM: Residual Heat Removal COMPONENTS:
i OM ' Safety Dwg Valve Number Cat Class Drawing Number- Coor -t i
V10-17 A 2 G-191172 G-08 f V10-18 B 2 G-191172 F-08 .j i
These valves are the Residual Heat Removal (RHR) shutdown cooling supply ;
isolation valves. They have a safety function in the closed position to -
provide. primary containment and pressure isolation, and in the open-position to provide RHR pump suction during shutdown cooling operation. ,
~
l JUSTIFICATION: ,
Th'ese 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 I Outage in accordance with Paragraphs 4.2.1.2 (f) & (g) of Part 10 of.the l Code.
L
)
i Revision 16 5-76
l COLD SHUTDOWN JUSTIFICATION ;
Number: CSJ-V09, Revision 1 (Sheet 1 of 1)
SYSTEMt 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 Pressure Coolant Injection (LPCI) ' primary containment isolation 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.
THISICOLDISHUTDOWNfJUSTIFICATION? WAs R DELETEDSINSEVISION715?ORETHEEIST
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b Revision 16 5-77 ;
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. . _~_ - -
COLD SHUTDOWN JUSTIFICATION Number: CSJ-V10, Revision 1 (Sheet 1 of 1) l SYSTEM: ' Reactor Core Isolation Cooling
. COMPONENTS: I OM Safety Dwg Valve Number Cat Class Drawing Number Coor V13-22 C 2 G-191174 Sh 1 G-09 !
l I
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 i coolant system. This would thermally shock the reactor nozzles and cause '
a positive reactivity excursion.
S This valve is located in the steam tunnel which is inaccessible during I power operations. Additionally, there is no means to manually exercise l this valve.
This valve will be exercised during Cold shutdowns and each Refueling outage in accordance with Paragr.aphs 4.3.2.2(f) & (g) of Part 10 of the !
Code. .
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i t
f d
l Revision 16 5-78 i
. Number: CSJ-Vil, Revision 1 (Sheet 1 of 1)
.EYSTEM: Reactor Core Isolation Cooling COMPONENTS I
W OM Safety Dwg Valve Number Cat. Class Drawing Number Coor l
l' V13-40 C 2 G-191174 Sh 1 N-11 F
This valve is the Reactor Core Isolation Cooling (RCIC) torus suction check valve. The valve has a safety function in the open position to permit RCIC pump suction from the suppression pool af ter systein 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.
8 Revision 16 5-79
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l COLD SHUTDOWN JUSTIFICATION Number: CSJ-V12, Revision 1 (Sheet 1 of 1) ,
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 i
SB-16-19-8 A 2 G-191175 Sh 1 I-12 SB-16 19-10 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 provide 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 l pressure is maintained during reactor operation to ensure proper downcomer submergence. Proper downcomer submergence ensures integrity of the j 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
COLD SHUTDOWN JtJSTIFICATION' Number: CSJ-V13, Revision 1 (Sheet 1 of 2)
SYSTEM: Primary Containment Atmospheric Control COMPONENTS:
OM Safety Dwg Valve Number Cat Class Drawing Number 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 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 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.
Revision 16 5-81
COLD SHUTDOWN JUSTUICATIOM Number: CSJ-V13, Revision 1 (Sheet 2 of 2)
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 1
i hydrodynamic forces.
To minimize reactor operation without the differential pressure between the drywell and the suppression chamber, yet provide assurance of -
e 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 be 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. i Revision 16 5-82
COLD' SHUTDOWN JUSTIFICATION Numbbril ECSJ-V14 ~RevisionTO .: .(SheetF1T^ofJ 1)! l SYSTEM: FRssidual' Heat' Removal COMPONENTS:
n .. . l l
-OM ~ Safety. .
- Dwg l
Valve' Number.
~
- Cat Class Drawing l Number- :Coor '
1 i2' V10-4CA "C 'G-191172" E i o7
~
.V10-46B- T.C 2- -G4.191172.6. "E 210, l These valves'are'the low Pres' suis Coolant Infe cti6n J; (LPCI)1 inj ect ion Echsck valves ~ . They have a';! safety!. function in.:the open positionfto passELPCI flow to: the:. reactor,: and/in the close'd position ifor: primary contaidmenti
~ ~'
and' pressure, isolation'. ,
l JUSTIFICATION:
Thesel valvss'?csndotlbblexercisediduring~n'ormsl?(poweF)';;[.opesationisis'ce7 the Residual- Heat Removal .:(RHR) / pump' discharge ~ cannot Jovercomelreactor pressure: . Manual ~ exercising:is not"possible during plant;Loperatiod because.:the valves are llocated:inside ' the?inertsd::;dgelli;andy;are :inoti
- accessible during plant': operation. l These' valVss ~ will*be !'exeicissd';'with flow:'during f.'C61d" Shutdown ~and Ref ueling 1.OutagesE int accordance ;; the '~ Code . LFull-l stroke 7exercisingitib5 ths open position :.willL be' . verified- by: passing ;the:: maximum required Taccident'~
condition flow through:the: valves.
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Revision 16 5-83
l i
COLD SHUTDOWN. JUSTIFICATION '
Nu.mberF~ .J.~V15 CS .
Rev.ision}O':7(S.
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SYSTEMO{ResidualtjisatlRemoval l COMPONENTSi i
-OM L LSafety; . . . . ,. ;Dwg[. l
' Valve? Number: ; Cat -' Cl. ass. i.-Drawing:: Number.5 , $Coor ;
, . x m.. . . - m . , , - <> - . m % a- 4
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,", #21c ~~' ' "'7G.~2:191172T . M OS V10,14Of ..
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C27 ' ' "d2 1,9f17. 27 "
~~TV10?48B'- .
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?IR, i3 f J 2 05 IV10 48C.
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JC:
~-m..- '".~*T".2& .
E G01911727 -- -
,V.10?48D'" .m T, C, ? ~ ,
M2I *. , ".G-19.'1172.I
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-J13wa
& A V 7. 'r- e } g 4 4 k
.a e, + .vN '- A 9 O. .* 4/XUvk- / b " a. y 4Y / , t' Thess?jslV5s~aiel)the"RHRTpdmp^[dischargsich56Eivalvesi TThesejalyss[have[a j safety function toLopenS to passiRHRipumpfdischarge flow' for.[allymodesii;lof t
RHR/LPCI' system operation' 'These valvessalsolhave aJeafetyTfunction to' ~ ~
closentofprave'tftheEbackflow)of1;waterfthro.nghanidlefRHRikumpj~
n Justificatiloni I t 'isThot ? prac t icalTWpef f 6ria? f ullTs tfoksIexe rcis elb fS t hshe'N51Vesi6nfa quarterly? basis during~plantfoperation. Theseiv'alves are exercised?durin the performsncelof1theEquarterlyjRHR) pump; surveillance. ;During? plant' ~ g operation, s thelonly practicali floppath1forithese fpumps tis;lin6 thel torss7E6 torusiflow. path. :The;RHRipumpsidoinot?havelsufficient/hesdEtdiflowjtojthe recirculation , loops [with? theareactorf coolant:fsystem?at{normsl ?operatiscf '
pressure. 1Typicalt:RRR Lpump f floWratesTinithe:btorust t o " torus tflow ' " ^ ' " .
~
I configuration arelapproximatelyT6,500fgpmlfor{thesRHR pump. test.[iThs required'.designiaccident c6nditioniflowirateftoiperform?a fullistroke exercisef is17,300 ' gpm1which ;;can; onlyibe.Dachieved2 wherJthe 5 RHRf systemfisfi'n .
^ ^ " " " l theEvessel to!vesselsfl,ow configurationi ;
These valves (willPbsTpartFstrokeTexeicissd(durihg1 plant 76peiEEibiCan~dTwill t l be, full-stroke exercised (duringicold shutdowns LandH refuelingioutagesg: ^ ^ ;
4 l
1 Revision 16 5-84 i
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i
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 COMPONENTS:
OM Safety Dwg Valve Number Cat Class Drawing Number Coor SL-13-55A A/C 2 G-191174 Sh 1 B-08 SL-13-55B A/C 2 G-191174 Sh 1 C-08
~
SL-13-55C A/C 2 G-191174 Sh 1 B-08 S . -55D A/C 2 G-191174 Sh 1 C-08 SL-14-31A A/C 2 G-191168 F-07 SL-14-31B A/C 2 G-191168 E-07 SL-2-62A A/C 2 G-191167 I-13 SL-2-62B A/C 2 G-191167 I-13 9 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 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 .
SL-2-73C A/C 2 G-191167 G-12 SL-2-73D A/C 2 G-191167 G-12 Revision 36 5-85 b
REFUELING OUTAGE JUSTIFICATION 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-191157 G-12 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 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-2-3-175 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
REFUELING OUTAGE JUSTIFICATION Number: ROJ-V01, Revision 1 (Sheet 3 of 4)
OM Safety Dwg Valve Number Cat Class Drawing Number Coor ,
t ),
SL-2-3-23B A/C 1 G-191267 G-04 SL-2-3-23C A/C 1 G-191267 G-12 SL-2-3-23D A/C 1 G-191267 G-12 j l
SL-2-3-25 A/C 2 G-191267 I-04 -
SL-2-3-27 A/C 2 G-191267 J-04 .
I SL-2-3-31A A/C 1 G-191267 G-04 )
~
SL-2-3-31B A/C 1 G-191267 G-04 SL-2-3-31C A/C 1 G-191267 G-04 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 i
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-191207 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 I
\
SL-2-3-31N A/C 1 G-191267 H-12 j SL-2-3-31P A/C 1 G-191267 H-12 Revision 16 5-87
4 REFUELING OUTAGE JUSTIFICATION Number: - ROJ-V01, Revision 1 (Sheet 4 of 4) i OM Safety Dwg Valve Number Cat Class Drawing Number Coor 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 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 t
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:
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 i 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 f testing performed in accordance with Paragraph 4.2.2.3 of Part 10 of the !
Code. i i
i i
r
. Revision 16 5-88 w s- , ,.e-- w 4.w. m.- w w .> . - c
REFUELING OUTAGE JUSTIFICATION Number: ROJ-V02, Revision 1 (Sheet 1 of 2)
SYSTEM: Nuclear Boiler COMPONENTS:
OM Safety Dwg ;
Valve Number Cat Class Drawing Number Coor {
RV-2-71A C 1 G-191167 D-08 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
_yngg ~ n cmm. yppy ,
w wnm,ngwmy -n m n,m OI4JA#MM/2MG d+#.4MJi!.id%s4LdanN&;; 7:Et U.d.ss?;zk <. 'iksN0%ii;1w:! Ah5AMJA8.RJ46 d$2didlific::i,s 3,4-J adhd
?xr'wm:Cr"rm"vm*$?x+3MtPSym%Mn=rm:"mm;:' vmiv4?Earp&tvrymyrrm myg ety*!i;4MW.M kNuG WS.LJA%%Gnack&&d%2MuaL&inhucs.unk51R k%L%A%dh%&MGskakia&%%%5snAslg A gwypepp:W'MQEre ?gypiwtt+v',::qg?j{o Tr*99"y:?*femg?"mSvefeS^77735?N!4Mi^;rg?ggyjY.;3*w mg$
eve i.sAdkubSd6Es0$$d5l$d:NhthA%5k%;C2MMN: L:$id\dSL I!cikkdGMkksAsdNY55% YEA $kdUIiskonl%b r+PY:W eypWp0"+2mm?*r"?MMTetWt"%+ve~v IF:rW5tM*T?i?!Q3:1 N W M P 73:MtM*2 @ M 9 " BR y k@dM4Nb;:2Nb5$2S &LMsbisMA:dualGD$.6LINSMM5DS[siss$$?h0$'3*bONNM bAiOdd0 ids 5sdsNJAWO4h !$
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.
.-.y. m ,;w g _ , m.,
u
,n nn~ g+, .n:, .- ,-
,y
< ~
' +
+
, umas m&'
L ,
, 4 >
lbsk&T> aw libidu.a ~ kubMu% 23;.Ndiach :,uS&idedhsaw2:.ueunau6c:.edkh562ndb JUSTIPICATION:
Stroke testing!cf these valves quarterly during power operation is not recommended. As recommended by NUREG-0737 and the corresponding study by the BWF. Owners Group (BWR Owners Group Evaluation of NUREG-0737, Item II.K.3.16, " Reduction of Challenges and Failures of Relief Valves"), the exercising of these valves sl. mld be minimized to reduce the number of challenges to safety / relief ve'res.
Revision 16 5-89
1 REFUELING OUTAGE JUSTIFICATION j Number: ROJ-V02, Revision i (Sheet 2 of 2) l JUSTIFICATION (con't)- l The failure of any relief valve to close during stroking at power 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 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.
Revision 16 5-90
REFUELING OUTAGE JUSTIFICATION Number: ROJ-V03, Revision 1 (Sheet 1 of 2)
SYSTEM: Nuclear Boiler COMPONENTS:
CM 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 V2-28B A/C 2 G-191167 H-05 ,
V2-96A A/C 2 G-191167 H-03 V2-96B C 2 G-191167 F-03 4
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 isolation check valves for the "B" Feedwater Line, respectively. They '
. have a safety function in the. closed position to provide primary containment isolation, and in the open position to pass Reactor Core Isolation Cooling flow to the reactor.
Valve V2-96B is the second outboard check valve in the "A" Feedwater Line.
The valve has a safety function in the closed position to prevent diversion of High Pressure Coolant Injection flow in the "A" Feedwater Line.
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. ;
)
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l Revision 16 5-91
1 i
REFUELING OUTAGE JUSTIFICATION l Number: ROJ-V03, Revision 1 (Sheet 2 of 2) ,
l I
JUSTIFICATION: , ,
/
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 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. -
~
Revision 16 5-92
REFUELING OUTAGE JUSTIFICATION Number: ROJ-V04, Revision 0 (Sheet 1 of 1)
EXETEM: 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 posit.'.on to ensure automatic depressurization a;atem (ADS) capability is maintained via the MSRV accumulators on a loss of the instrument nitrogen supply.
4 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.
Revision 16 5-93
t l
REFUELING OUTAGE JUSTIFICATION Number: ROJ-V05, Revision 0 (Sheet 1 of 1) ;
i SYSTEM: Nuclear Boiler l 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 oi 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, Revision 1 (Sheet 1 of 2)
SYSTEM: Control Rod Drive Hydraulic COMPONENTS: (Typical of 89)
OM Safety Dwg Valve Number Cat Class Drawing Number Coor CV-3-126 B 2 G-191170 C-16 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 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.
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.
Valves SE-3-121 & 122 are the manual control exhaust and withdrawal valves, respectively, for the CRD 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.
l valve V3-114 is the scram exhaust to the discharge volume check valve. I This valve has a safety function in the open position to pass scram i exhaust flow to the discharge volume. l Revision 16 5-95 I
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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.
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 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 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 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 result in an increase in safety or quality. All control rods drives are verified operable in accordance with Technical Specifications 4.3.B.1 each Refueling Outage, thus stroke testing of these valves for control rods that remained fully inserted throughout the operating cycle will occur each Refueling Outage.
These valves will be exercised as a minimum each Refueling Outage in accordance with Paragraphs 4.2.1.2 (h) and 4.3. 2. 2 (h) of Part 10 of the Code.
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Revision 16 5-96 l
REFUELING OUTAGE JUSTIFICATION Numbers. ROJ-V07, Revision 1 (Sheet 1 of 1)
SYSTEM: Control Rod Drive Hydraulic COMPONENTS:
OM Safety Dwg Valve Number Cat Class Drawing Number Coor V3-412A A/C 2 G-191170 E-12 V3-412B A/C 2 G-191170 E-12 V3-413A A/C 2 G-191170 E-12 V3-413B A/C 2 G-191170 ,
E-12 These valves are the recirculation pump seal purge supply check valves. .
They have a safety function in the closed position to provide primary containment isolation.
4 JUSTIFICATION:
These valves can only be backflow tested via a leak type or non-intrusive test which would require isolating 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. ,
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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.
Revision 16 5-97 l
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REFUELING OUTAGE JUSTIFICATION Number: ROJ-V08, Revision 1 (Sheet 1 of 1)
SYSTEM: Standby Liquid Control-COMPONENTS:
OM Safety Dwg Valve Number Cat Class Drawing Number Coor 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 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 l
REFUELING OUTAGE JUSTIFICATION Number ROJ-VOS, Revision 0 (Sheet 1 of 1)
SYSTEM: Reactor Core Isolation Cooling COMPONENTS:
OM Safety Dwg Valve Number Cat Class Drawing Number Coor V13-70 C 3 G-191174 Sh 2 K-13 V13-133 C 2 G-191174 Sh 2 K-10 These valves are the Reactor Core Isolation Cooling (RCIC) barometric condenser condensate pump discharge check valves. They have a safety 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.,
Revision 16 5-99
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REFUELING OUTAGE JUSTIFICATION Number: ROJ-V10, Revision 0 (Sheet 1 of 2)
SYSTEM: Reactor Water Clean Up 9.9MF_QHEHTal.
OM Safety Dwg Valve Number Cat Class Drawing Number Coor V12-28A C 3 G-191178 Sh 1 D-08 i 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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l REFUELING OUTAGE JUSTIFICATION l l
Number: ROJ-V10, Revision 0 (Sheet 2 of 2) l TNTS?PAGE.TWAB]INTENTI
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REFUELING OUTAGE JUSTIFICATION Number: ROJ-Vil, Revision 1 (Sheet 1 of 1)
SYSTEM 1 Neutron Monitoring System COMPONENTS:
l OM Safety Dwg Valve Number Cat Class Drawing Number 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 close.d position to provide primary containment isolation.
JUSTIFICATION:
This valve can only be tested via a leak type or non-intrusive test that requires securing of the nitrogen purge to the NMS Tip system. The nitrogen purge is required during operation and Cold Shutdown to prevent condensation and corrosion in the NMS Tip system.
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 5-102 1
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REFUELING OUTAGE JUSTIFICATION Number: ROJ-V12, Revision 0 (Sheet 1 of 1)
SYSTEM: Control Rod Drive Hydraulic 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 j
~
These valves are the Control Rod Drive (CRD) scram discharge volume vent check valves. They have a safety function in the closed position to isolate the scram discharge volume during a scram condition, thereby preventing reactor coolant inventory loss. ;
' JUSTIFICATION:
These valves cannot be exercised during normal (power) operation since this would require taking the CRD system out of service.
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. l 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 5-103 w g -- - 'w--, p+
REFUELING OUTAGE' JUSTIFICATION Number: 3ROJ-V13k'(Revision"17]Shdet Y Of?1)
SYSTEMi ~ R.5si'dudlL Heat: Rem. ovsl i COMPONENTS:
OM1 Sahety:- ._ __ . _ . . . __ _-Dwg
- Valve Num.ber Cat 1: Class ; Drawing Number; Coor V10146A- C::: -2~ fG-191172l :-E007 V10-46B' :C; L2 i; GL1l91172 ' 'E210 This' refueling :.outisgeDjustificist' ion ~:hssibsen:TwithdraWn. iThessWsives 'hre now Stested;on alcold shutdown.and--refuelingioutage' basis. i Re_fer: to LCSJ4 V14. :This. item': Nas1; changed-:in2 Revision ~:c16.c o f theHInservice Test 3 Program Plan.
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l Revision 16 5-104 !
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REFUELING OUTAGE JUSTIFICATION
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l REFUELING OUTAGE: JUSTIFICATION l Ntj6hb'eFi[~IROJ4Vi47[ ReVis165[0[(S hssdi}2i:[3fS 2 )]
JUSTIFICATION?
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I Revision 16 5-106 i
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REFUELING OUTAGE JUSTIFICATION '
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REFUELING OUTAGE JUSTIFICATION Nuinb[eiMROJ. -V1. 6 ; 7ReViiissiTO LT(S. h_sd.E176f fi. )l.
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JUSTIFICATION:
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1 Revision 16 5-108
REFUELING OUTAGE W STIFICATION Number: ' ROJ-V17 j .' Revision L0f(Sheet i of11)-
SYSTEM: Service Watsr OM Safety. .
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!3 7 1B-07
. V70215B(
'E( LG219.1159
- Sh 1" f.y s- A y-These^: valves 'sre l'the ~: Service'^ Water Systehi: Header Supply. IsolationFValvs~s; The safety function of these: valves:;is1to closeJin order eliminate the'of Alternate Cooling Flow from bypassing the' cooling.. tower whileftheiServide '
Water System.is in the? Alternate: Cooling mode y ~of. operation.
UUSTIFICATIONi ItEis":inipracti'calftol f 011;;OEpsrtir tifoksTbMrciseTtheseWalvest:'6Kis s
quarterly': basis:or during;; cold shutdowns C1bsure Lof?either:-Lo.fithese valves Reactor;could Buildinginterrupt cooling:.
Closed Cooling flow z iiltheirflrsspectivei Waterysystem trainst tol thsoEIES heat 3:exchangers!?(Eh8/1Af 8-1B):. The LRBCCWi systeinstprovidsJco611ngsflowjtofcomponentsysuch?asEthe~ ^~'~ "
. RHR' pumoicoo_lersi.fthellCRD pump'. cool'erikand::thed:spentT7 fuel! pooljheat sxchangers 9(E9-1Af and ;E9-1B) /whichLare3' required?forf theJsafesoperati6iW6'f the: plant 'atspower cand:icold1 shut-downTperiodsi The se~/ valves : shal-1:.:Lbedfull-
~
stroke; exercised'during refueling;-outagesiwhen these cooling'loadsicanibe" safely' isolated.
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I 1
Revision 16 5-109
REFUELING.. OUTAGE JUSTIFICATION 1
Nun. nssII'[ROJ1V18,?Revi'sion!0?(Shs5h?1Mo_
x.- ~ - . fit,
~
I l
SYSTEMi t'Seis/[cE[Watsr
. , , , , , ,. . , , .n . , , . ~
< 4
?OM' iSafety :. . ;Dwg" l Valve? Niimb.er.i TCat'?Cl; ass.;- lDrawingjNumber? / Coos
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7V7001 87Ki 1'
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% t. + y ,, .wa,e y-v.s-. , v N .y,fA ,; v;. .y. .; y n ;.w.qqre. ,ym
. . u > ~ a . .' , 1 TheseV valVesV;areT;th67SsEvlhe?Wst'enPsihfGishd?;.Sfal7Supp1pfIddistiied Valves, ! Thei s af ety:! fahctidn ! 6fi theselvulves $i sj to rclose finf:; ordsrlFtd l leakage}bariier for; thEssrVideVWat er$ Supply? Header provide Isolation;;'ai (Valvesbadkup'h(V70 2 13Atand?.V70-13B) P;whilestheiservicelWater LSy'stshiTi's " ~ ^ ^ ' ' * ~~~
in(thetAlternatejCo,dlin (m[odeldf2bperation( "
4 JUSTIFICATION:
7 rsd61~ddlT Ed $f dll! ors partils tiokelsxe r'ci s e ;[E hssEWhlVes TbiBa ItFis ;-l imp quarterly /ba' sis!losiduring? cold 7 shutdowns c. (Closure tpf61thssdoff Eheu valves icosid Eint ersupt[ cooling 7 f lows to s ths;? s ervise iWat er!Pumpi gland;V!ssiliL Interrdption06fl.glandisealsflostostheselpumpsicould/danse me chanical i s ealst whichicould s prevestSiEdrom p psrfortninglit ~
s/ damagsVtM ninteiided" safetylfudstion-. ' s Ths7 Service s Water!! Pumps f arsirequirsdythi!bskopesabls during:1powerkopssationThndscoldkshutdownsifor$coolingito?6thskgibsdsi '
Thes e valVesi,shalM, ben
. . ~ ful19 st roke Lexerdissd?durihg ?refus,lihga760tasess , - - - - -
Revision 16 5-110
-- =- .
_. __ _ . .m .. . . _ _
BEE H KING... OUTAGE" JUSTIFICATION NumbeEIROJ-V19{ Rsvisi6nT Og JShesE3fI6f}11 SYSTEMi Servibe Watsr -
. . . ,. 50MF Safety . . . .
EDwg i Valvel Number .- CatllClassJ ! Drawing [ Number [ iCoor ,
4 , . . _ . 1 m . s m ,
',>/Tv70;171
~ .',- a TBS 13L P"
. v . s.r' % s TG2 191159ESli T *
%.n.,. -f -
s
'F DIO6 dif. 6% g y MV70 M 1 ! i911597ShT212 P,.9DV,D7
[ ' " , OBT ~^ ? 3'J. #m ~ 1,G c c - ~
. w ESB 2 76 %
LB] T ^~"7G?i91159f;f$10 %) d
- WO9 a.. .
, . a . m., , a Valve?v70-11%henTopen~ proVidesTWsher?tidTcheFCooliuMT6WeriBss1E7tfa preventEtheldevelopmentfofdiceiih5thsibasihi..svalvs2V70 17fwhenXspen 2 providssi flowJt o;1:thej CoolingiToweh.spiay/headerf to?pr' 6videsad?a1Eeinstis.
cooling? path for;the.LServicel Water > System. EThe Mainicondensbr?:Dischsrs5 2 BlockiValvel(SBb. 7041)Swhensopenfprovidesla::lflowL pathsto?thesriVer'b (Thess valves Lhave?anJa6tiVedfunctionf to changej p6sition?inforderstiofpf6 fide l[d" i hath;for0flowitoftheiccolingl TowerLwhenitheyServidesWaterisystem$1s' required': to;be ;in]the Alternatejcocaingj modeyofioperstionf ~
JUSTIFICATION I tEislitip'rac ticalTtio7f 61RofipafEFs E roks .isxsidis 67 thss'sTiFilishidHElds power.operstion:forfduringfcoldsshutdowns. sThs4desi"gn[of j the ?ServidelWsEsi System 1 requires J thatiwheneversthe-l$ConnectiEUtdRiverstsmp&.tolthe' eratdis[is.3 ' "~~ " 'grest thanH45'F , .ithe i Servich iWateh/Systenidischargsjist aliyhsd Circulating? WaterTDis6hargeEto : the(river [ lWhens9erithefriverstiemperaEUFs WaterESystem jisf aligneditoithe7 cooling ~~~~~
is tower 51sss"than;;L45'FN basinsofensure;that'the, .
th@ Service (/ba, 7 sin wats &+ n- dos,s,3h,otEfruszed
.n VsivssEV.7 Oill?and TSB:70;1"sh6uldTh6Eib6?bpensd55imul5EshsB6slpMsR66phsf 6E ths4 minimum;timetrequired:0forKsvatem;1ineuplchangesM becauseithsipotentisl
'ejcis tsiforf thEt ower ; basin: toLbeTdrsissd MA i rdinimumilevellisirequiredQ6" the. cool,in.g to_wer.3 basins forf. theWalt._ ernst_ef_ cooling s 6_de3.m-o_fiop_ m erat _ ion
_. i.-
s ~ .
V70l i7iwill[bsIf6111stidkeTexdfdissd?!6E75"IiEsSisily;libislMshinW70?i1Yis l opentduringsthey colder montihsibfsplsntiV6peratisin.kTlieiopsnidg $fSV70417" )
when $BL70-1EisiopenLcouldIcadssithsipipeworkinpstrismXofhv70417% ofdrWiE7's Thef draining 16f f thelups t! re am ! pipewoiM6ouldsdauss?/atprss sures transishtiyand~
potentially; damage 7pipework;if F,flswWsreNiniti,a_tsM_to_fthei_spfayahshds_ry.
- - -- - :.-~ n . .- . -~- .~ , "~
Va We s 1 V7661 Qshd] SBf 70913 shsll7hs?f Ull2EEf6ksTsMs r6issdjihsn3EsTE~66 fins configuratientoff the' Services WaterESystem?is?chanyedidualt60t-heichangelin river-watekitsmpersture. ~ iv701-17?shallsbe$fullfstroke ;
q'u arterlyibasisiwhenSSB-7071/isiclosed.: lAsia minitriuttd(exercisedionXa each/valveIwillibs '
~"I full.istroksfexercisedLatlleast[oncelperfiefuelingfcpclei ~ ~ ~~
Revision 16 5-111 l
1 I
REFUELING' OUTAGE" JUSTIFICATION Number:'?ROJ-V20p; Revision"lO':lShssQ flof^1{
fYSTEMi lServidetWate9
..: ,,y.
OM; .Safstyi: , '
- Dwg
.,' Valvsl Number Cati: Classy Drawing (Numberi jCoor
- V7 0 418.' ,
'Bi 13: "G-1911597Sh?2l: 2Ei07 5
Thisi: valve:!i'stheTservics WateFHeadeMDiscsEge?iIsb1'atilonivalvs tThs safety functioniof these valves is;:'to:close in' order:to contain?invenEhry of vital cooling: water when the-:. Service Water SystemL isjinithe Alternate'
~"
Cooling t mode' 'ofj operation..
JUSTIFICATIONi It:L is' 'i'mprabticsif to T full 'di$ psrtrstfoke7eisrcissithiiiWalVesToh's quarterly basis.or~during cold shutdowns.ix.JClosurefof:this #alveic6uld interrupt cooling l flow. from planti componentelsuch!:asythe LReactor;. .Biiildid@
Clo' sed'. Cooling L Water 'systemtheat exchangers ? (E-8-1A;or Et 8 1B) ? andithe' emergency ' diesel;-l generators;.whitch?are:: required. for' the5::Lsafef.operationJof the plant lat! power;ani cold'Tshutdownfperiodsa Thesel: valves Jshalls be:1 fulli stroke exercis6d-Lduring:{refuelingioutages /when these(coolingl:-lloadsicanibe.
safely isolatedt l
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Revision 16 5-112 j
RELIEF REQUEST Number: RR-V01, Revision {(Sh;sjQ^jf[1)]
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-in the open position to provide cooling for the RHRSW pump motor during operation.
EXAM OR TEST CATEGORY:
Category B.
T.H,IST RELIEFm..m
~R_EQU_ EST~'
m...WAST m _MIT_HDRA..h.W...
. . . a.m, INS R.EVIS_
s ~ ION?lMOFI.THE,
-.. m-. . TIS'"7#RO, GR.AC m
Revision 16 5-113 J
i RELIEF REQUEST Number: RR-V02, Revision 1]{(jf((f M Q J}
SYSTEM: Service-Water ,
COMPONENTS:
OM Safety 'Dwg 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 '
V70-1C C 3 G-191159 Sh 1 I-03 E
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 i diversion of cooling water through an idle station Service Water pump.
t EXAM OR TEST CATEGORY: ;
Category C. !
THIS ZRELIEFIREQ'UESTINASIWITHD'RAWNTINFREVISbN!fffdFETHEZISTIPRdGRA%eLANI] '
REFERMTO/REF
+- - a-u ._UELI, NGTOU_
. - - TAG.E . .u- - - - -
4V ->
n - a . 5JUSTIFIC.ATI,ON2~R.OJ.w 14 f.7 ""~~*^ " ^^**""" "*~ ^~~ ;
e E
t Revision 16 5-114 3 l
RELIEF REQUEST
!- Number: RR-V03, Revision 1 (Sheet 1 of 3)
SYSTEM: Diesel Generator Starting Air COMPONENTS: .
I l
OM Safety Dwg l
Valve Number Cat Class Drawing Number Coor AS-24-1A B 3 G-191160 Sh 7 B-16 I AS-24-1B B 3 G-191160 Sh 7 B-03 I'
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 I
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."
1
=
Revision 16 5-115
t l
RELIEF REQUEST i
N' umber: RR-V03, Revision { (Sheet 2 of 3)
CODE REQUIREMENT (con' t) : Part 10 Para. 4.2.1.3 " Valve Obturator Movement" "The-necessary valve obturator movement shall be determined j
' 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 f obturator position."
i REQUEST FOR RELIEF: ;
i
. 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 i requirements would be an overall decrease in plant safety. Furthermore, since~the air start system is not totally, redundant (e.g. they share r common piping, components and initiating logic), testing of these valves !
individually on a quarterly basis would not increase the quality and i 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 cpens, and :
the vent valve closes, will be performed by ensuring the EDG starts.
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Revision 16 5-116 ,
c- . w - -n-e, r -,- --v- , ,, , , w
RELIEF REQUEST Number: RR-V03, Revision 1 (Sheet 3 of 3)
ALTERNATE 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 signiff. cant 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:
Relief was granted in the March 1994 SER (Reference (u)] for Relief Request RR-V03, Revision 1.
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l Revision 16 5-117 i
~
RELIEF... REQUEST F
Number: RR-V04, Revision fM.S_li_E5BiV~6_f5fm)]
e--mm ame i
SYSTEM. Fue1 Oil Transfer 1
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 position to ensure fuel oil system, integrity upon loss of the non-safety related fill line piping. I EXAM OR TEST CATEGORY:
Category C.
$ $ bbb$Nbbbs N YLT jj M Q % @ (( N N N N [p] ((QE][Sj[P j o] Q j :
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4 t
L b
I 1
Revision 16 5-118 '
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RELIEF REQUEST Number: RR-V05, Revision {(' .S jiEd5%~oQ1))
SYSTEM: Nuclear Boiler COMPONENTS:
OM Safety Dwg Valve Number Cat Class Drawing Number Coor 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 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 d
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.
Valves RV-2-71A through D are the main steam dual function relief valves. 1 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 THIS.JREL, I.EF 7 R.E-QUEST,7;.~~
N I.-..
WASE.w.. TH. .DRANN.
~. - TIN. 5REVISIOICf6TOFITHE
- . TIST "PR'OGRAt4 f 1
l Revision 16 5-119 I
.~ - .-. . .
RELIEF REQUEST Number RR-V06, Revision 0 (Sheet l'of 2)
SYSTEM: P'gh Pressure Coolant Injection COMPONENTS:
OM Safety Dwg Valve Number Cat Class Drawing Number Coor J 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.
t EXAM OR TEST CATEGORY:
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 sec 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 for.' 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. !
d Revision 16 5-120 t
RELIEF REQUEST Number: RR-V06, Revision 0 (Sheet 2 of 2)
REOUEST FOR RELIEF (con' t) :
To minimize the amount of 'ariability 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 tim' 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 acceptance criteria of 25% of the reference value.
ALTERNATE METHOD:
The acceptance criteria for the HPCI turbine Control valves will be expanded to 1 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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Revision 16 5-121 1
\l FE IEF REQUEST Number: RR-V07, Revision {(S{ {t}1Sj,Q )]
SYSTEN: ~ Control Rod Drive Hydraulic 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 These valves are the Control Rod Drive (CRD) scram discharge volume vent check valves. They have a safety function in the closed position to isolate the scram discharge volume during a scram condition, thereby preventing reactor coolant inventory loss.
THIS RELIEF REQUEST WAS DELETED IN REVISION 15 OF THE IST PROGRAM. NsFis TOKREFUEIJINGTOUTnGE730STIFICATIDNJROJAVf2TINTHESEEVAINESTMAVEFNOQ~PENING'"
~~
g g]ONygg g jgRJjk g gjp f[CpNpSjQEREg[{ ASS p i g gSj[ ~ ~**
1 Revision 16 5-122 I
J
.]
~
l RELIEF REQUEST l
Number: RR-V08, Revision 0 (Sheet 1 of 2) U SYSTEM: Standby Liquid Control -
f&HPONENTS:
OM Safety Dwg Valve Number Cat Class Drawing Number Coor SR-11-39A C 2 G-191171 G-08 l
SR-11-39B- C 2 G-191171 K-08 Valves SR-11-39A & B are the Standby Liquid Control (SLC) pu.p discharge ,
relief valves. They have a safety function to operate to prevent '
overpressurization of the SLC system.
. EXAM OR TEST CATEGORY:
Category C CODE REQUIREMENT: Part 1 L 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 i valve shall successfully pass a retest before it is returned to service.
Revision 16 5-123
RELIEF REQUEST Number: RR-V08, Revision 0 (Sheet 2 of 2)
REQUEST FOR RELIEF:
Relief is requested on the basis that the prenosed alternatives would provide an acceptable level of quality and e% ety.
Vermont Yankee Technical Specifications 4.4 t requires testing of valves SR-11-39A & B at least once every operating fcle. This testing frequency represents a six-fold increase over the tete ing frequency required by Part 1 of the Code and, as such, yields more accurate valve degradation trending data. The testing is currently perforued at the Vermont Yankee plant site.
The acceptable range of relief valve actuation given in Technical Specifications 4.4.A is 1400 psig to 1490 psig. The 1400 psig value ensur s that a sufficient injection pressure can be established prior to lifting of the relief valve. The 1490 psig value ensures relief valve actuation prior to reaching the system design pressure of 1500 psig. 1490 psig translates into a maximum relief valve setpoint of 99% of system design pressure as opposed to 110% allowable by the piping code. Applying the Part 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).
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:
In accordance with Vermont Yankee Technical Specifications 4.4.A, valves SR-11-39A & B shall be tested at least once every operating cycle. The setting of the valves shall be between 1400 and 1490 psig.
USNRC EVALUATION STATUS:
Relief was granted in the September 1993 SER (Reference (s)] for Relief Request RR-V08, Revision O.
Revision 16 5-124 L J
RELIEF REOtFEST Number: RR-V09, Revision 1]SQQ6f])j SYSTEM: Residual Heat Removal 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 RER pump suction during shutdown cooling operation.
Valves V'10-27A & B are the RHR system low presoure" coolant injection primary containment isolation valves. These valves have a safety function in the closed position to provide primary containment and pressure isolation, and in the open position to pass low pressure coolant injection water to the reactor.
USNRC EVALUATION STATUS:
T6fds'fEREf?fslish~5F'wIs(isfEKdfaElsi?REYl~sf6ERfsC6fGEs?tiissi~fissEtesE
-~v-~~~..--~~~u-n-----w r- - ~=.-- n~~~~
yygm s~yy3g;- . .,~ .
ll
,, t Revision 16 5-125 I
_