ML20064H910
| ML20064H910 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 03/11/1994 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20064H899 | List: |
| References | |
| PROC-940311-01, NUDOCS 9403180199 | |
| Download: ML20064H910 (150) | |
Text
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SECTION 4.0 INSERVICE TESTING PROGRAM PLAN FOR VALVES 9403180199 940311
{DR ADOCK 05000454 PDR
Rev. 12 TABLE OF CONTENTS 4.0 Inservice Testing Program Plan for Valves 4.1 Program Description 4.2 Program References 4.3 Program Tables - Units 1 and 2 4.4 Notes Note 1 Main Steam Isolation Valves Note 2 CV Emergency Boration System Flowpath Valves Note 3 Main Feedwater Isolation Valves Note 4 CV System Letdown and Make-up Isolation Valves Note 5 RHR Pump Suction Isolation Valves Note 6 Intersystem LOCA Valves Note 7 Reactor Vessel Head Vent Valves Note 8 CV, RHR Pump Discharge Check Valves Note 9 RHR ECCS Check Valves Note 10 Main Feedwater Waterhammer Prevention Valves Note 11 VQ Purge Supply and Exhaust Isolation Valves Note 12 AF Suction and Steam Generator Check Valves Note 13 CV High Head Injection Isolation Valves Note 14 SVAG Valves Note 15
" Deleted" Note 16 Main Feedwater Regulating Valves Note 17 Main Feedwater Regulating Bypass Valves Note 18
" Deleted" Note 19
" Deleted" (Incorporated into Note 14)
Note 20 Position Indication Testing of Solenoid Valves Note 21 Main Feedwater Tempering Flow Isolation Valves Note 22 Hydrogen Monitoring System Check Valves Note 23 Event V Check Valves Note 24 Pressure Relief Check Valves Note 25 SI Pump Suction Check Valve (1/2 SI8926)
Note 26 CV Pump Suction Check Valve (1/2 CV8546)
Note 27 RH Pump Suction Check Valves (1/2 SI8958A/B)
Note 28 VCT Outlet Check Valve (1/2 CV8440)
Note 29 Emergency Boration Check Valve (1/2 CV8442)
Note 30 AF Check Valve Leak Checks (1/2 AF014A-H)
Note 31 CV/SI Mini-Flow Recirculation Line Check Valve Full Flow Testing (1/2 CV8480A/B and 1/2 SI8919A/B)
Note 32
" Deleted" Note 33 SX Make-Up Pump Discharge Check Valves (OSX028A/B)
Note 34 SD Containment Isolation Valves (1/2 SD002A-H, 1/2 SD005A-D)
Note 35 RH Containment Isolation Valves (1/2 RH8705A/B)
Note 36 RY PORV's and Block Valves Note 37 Process Radiation Check Valves (1/2 PR032)
Note 38 Process Sampling Check Valves (1/2 PS231A,B)
(9998D/WPF/021694) 4.0 - page 1 of 3
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Rev. 12 4.4 (Cont.).
l Note 39 Nitrogen Supply to SI Accumulator Check Valves (1/2 SI8968)
Note 40 Safety Injection Check Valves (1/2'SI8815, 1/2 SIB 900A-D, 1/2 SI8818A-D, 1/2 SI8819A D, 1/2 SI8841A,B, 1/2 SI8905A-D, 1/2 SI8949A-D)
Note 41 RH Hot Leg Suction Pressure Relief Check Valves (1/2 RH8705A,B)
Note 42 Safety Injection Cold Iag Pressure Isolation Valves (1/2 SI8948A-D)
Neto 43 RH Crosstie Valves (1/2 RH8716A, B)
Note 44 Component Cooling Non-Essential Load Isolation Valves (1/2CC9415)
Note 45 Feedwater Tempering Flow Check Valves.(1/2FWO36A-D)
Note 46 Main Feedwater Header Flow Check Valves (1/2FWO79A-D) 4.5 Technical Approaches and Positions VA-01 Method of Stroke Timing Valves VA-02 Method of Fail Safe Testing Valves VA-03 Method of Exercising Check Valves VA-04 Determining Limiting Values of Full-Stroke Times for Power-Operated Valves.
(reference stroke time $10 seconds)
VA-05 Justification for Exercising the U-0 CC Heat Exchanger and Pump Isolation Valves on a U-2 Cold Shutdown Frequency VA-06 Stroke Time Corrective Actions 4.6 Relief Requests VR-1 Appendix J Valves VR-2 Containment Spray NaOH Additive Check Valves Draft VR-2A Containment Spray NaOH Additive' Check Valves
]
VR-3 Safety Injection ECCS Check Valves VR-4 Containment Spray Discharge and Ring Header Check Valves I
VR-5 Accumulator Discharge Check Valves Testing Frequency VR-6 SI Pump Suction Check Valve VR-7
" Deleted" (Incorporated into VR-12 and VR-17)
VR-8 Component Cooling RC Pump Thermal Barrier Valves VR-9 RC Pump Seal Injection CV Check Valves VR-10 Instrument Air Containment Isolation Valves VR-11
" Deleted" (per EG & G recommendation)
VR-12 Trending of Fast Actuating Valves VR-13 Diesel Generator Air Start Valves VR-14
" Deleted" (using ASME method instead of requesting exemption from position indication testing of scienoid operated valves)
VR-15 Safety Injection ECCS Check Valve Testing during Refueling Outage
'j (999BD/WPF/021694) 4.0 - page 2 of 3 l
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Rev. 12 4.6 (Cont.)
DRAFT VR-15A CV Injection Related Check Valves DRAFT VR-15B RH Suction Isolation Thermal / Pressure Relief Check Valves DRAFT VR-15C SI Injection Related Check Valves
-]
DRAFT VR-15D RH/SI Hot Leg Injection Related Check Valves VR-16 Containment Sump Outlet Isolation Valve Testing.During Refueling VR-17 Motor Driven Auxiliary Feedwater Pump L.O. Cooler Solenoid Valve Stroke Testing VR-18
" Deleted" re-organized into several relief requests VR-19 Auxiliary Feedwater Check Valves i
VR-20 Trending of Power-Operated Valve Stroke Times
-l (reference stroke times >10 seconds)
VR-21 Draft " Withdrawn" per SER 9/14/90 VR-22
" Withdrawn" VR-23 Primary Water Supply to PRT Check Valves and Nitrogen-Supply to PRT Check Valves i
VR-24 Chilled Water to RCFC Coils Check Valves VR-25 Containment Spray Eductor Discharge Check Valves l
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(9998D/WPF/021694) 4.0 - page 3 of 3 U
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SECTION 4.1 PROGRAM DESCRIPTION I
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Rev. 12 PROGRAM DE1CRIPTION The Inservice Testing (IST) Program for Class 1, 2,
& 3' valves meets the requirements of Subsection IWV of the ASME Section XI Code, 1983 Edition, through the Summer of 1983 Addenda. Where code requirements are determined to be impractical, specific requests for relief are written, referenced, and included with the tables. Additional valve relief. requests may be necessary and these will be identified and submitted during subsequent program revisions. Byron Station received a Safety Evaluation Report (SER) on September 15, 1988 and is listed in Table 2 of NRC Generic Letter 89-04 as a plant with a reviewed IST Program and SER issued.
Per NRC Generic Letter 89-04, the status of relief requests as stated in the SER is unchanged. Any modifications to Byron Station relief requests approved in the SER (VR-1 through VR-17) which are covered by one of the eleven positions discussed in NRC Generic Letter 89-04, Attachment 1, must.be performed in accordance with the guidelines given in the Generic Letter.
Pre-approval is granted for all relief requests submitted which are consistent with the eleven positions given. New relief requests dealing with a position D21 covered by NRC Generic Letter 89-04, Attachment 1, must receive NRC dpproval prior to implementation. The table lists all code Class 1, 2,
& 3 valves which have been assigned a specific code category as directed by Subsection IWV of Section XI.
The table is organized according to operating system and listed in valve number order using P&ID references to further categorize.
The valves subject to ISI testing are those valves which are identified in accordance with the scope of ASME Section XI, subsection IWV-1100:
"This Subsection provides the rules and requirements for inservice testing to assess operational readiness of certain Class 1, 2,
and 3 valves (and their actuating and position indicating systems) in light-water cooled nuclear power plants, which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident."
Exceptions to this scope are those valves which are exempt, but added to the program based on NRC mandates. These valves are identified in the program notes and relief requests.
After installation and prior to service, all valves identified in this program were tested as required by Subsection IWV-3100 of Section XI of the ASME Code. These tests were conducted under conditions similar to those to be experienced during subsequent inservice tests. When a valve or its control system has been replaced or undergone maintenance that could affect its performance, it will be retested prior to its raturn to service, to demonstrate that all performance parameters are within acceptable limits.
1 (9998D/WPF/021694) 4.1 - page 1 of 2 i
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Rev. 12 As required by NRC Generic Letter 89-04, Attachment 1, Position 5, the limiting value of full-stroke time will be based on the valve reference or average stroke time of the valve when it is known to be in good
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condition and operating properly. This limiting value is based on a reasonable deviation from this reference stroke time based on valve size, valve type, actuator type, system design, dual unit / dual train design,-etc.
The deviation should not be so restrictive that it results in a valve being declared inoperable due to reasonable stroke time variations. However, the deviation used to establish the limit should be such that corrective action would be taken for a valve that may not perform its intended function. New or additional reference values may be required if:
1)
A valve has been replaced, 2)
When a reference value or set of values may have been affected by repair or routine servicing of a valve, or 3)
If it is necessary or desirable for some reason other I
than 1) or 2) above.
NRC Generic Letter 89-04, Attachment 1, Positions 1-3 discuss full stroke, alternatives to full stroke, and backflow testing of check valves, respectively. A valid full stroke test is one in which verification of maximum required accident condition flow through the valve is obtained. The minimum acceptable flow value for a specific valve is determined from Technical Specifications, UFSAR, manufacturers data, engineering calculations, etc. _An alternative to full stroke testing includes, but is not limited to, a sample disassembly and inspection program of valves grouped by similarity of design (manufacturer, size, model number, materials of construction, etc.) and service conditions (including valve orientation)
This sample disassembly and inspection program will be performed during refueling outages. A backflow test verifies that the disc travels to the seat promptly on cessation or reversal of flow, for check valves which perform a safety function in the closed direction, for category 3/C check valves (valves that have a specified leak rate limit and are self-actuated in response to a system characteristic), the backflow test is satisfied by performing the leak-rate test.
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Per NRC Generic Letter 89-04, Attachment 1, Position #8, whenever valve i
data is determined to be within the Required Action Range, the valve is inoperable, and the Technical Specification LCO Action Statement time starts.
In the event a valve must be declared inoperable as a result of inservice testing, limitations on plant operations will be as stated in the Technical Specifications.
Section XI of the ASME Boiler and Pressure Vessel Code shall not be construed to supersede the requirements of the Technical Specifications.
(9998D/WPF/021694) 4.1 - page 2 of 2
a SECTION 4.2 PROGRAM REFERENCES J
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Rav. 12 PROGRAM REFERENCES 1.
Title 10, Code of Federal Regulations, Part 50, Domestic Licensing of Production and Utilization Facilities, particularly Section 50.55a, Codes and Standards.
2.
ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1983 Edition, Summer 1983
- Addenda, i
3.
ASME/ ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants, including 1988 Addenda, Part 10, Inservice Testing of Valves in Light Water Reactor Power Plants.
4.
U.
S.
Nuclear Regulatory Commission, Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs, 5.
Byron Station UFSAR, Section 3.9.6.2, Inservice Testing of Valves.
6.
Byron Station Technical Specification 3/4.0.5, Generic ASME Program Requirement.
7, Byron Station Technical Staff Procedure, BVP 200-2, ISI Requirements for Valves.
8.
NRC Safety Evaluation Reports (SER's),
a.
09/15/88 (Initial Program Plan Review) b.
09/14/90 (Supplemental Program Plan Review) c.
09/14/90 (Relief Requests VR-21 and VR-22 Review) d.
08/16/91 (Relief kequest VR 4 Review) e.
01/31/92 (Relief Requests VR-2, VR-18, VR-19, VR-20 Reveiw) f.
01/25/93 (Relief Requests VR-4 Review) 9.
Byron Station IST Valve Program Plan Responses (file: 3.11.0240) a.
Byron Letter 88-1321 (Initial Program Plan Review Response) 10.
Minutes of the Public Meeting on Generic Letter 89-04, dated October 25, 1989, Question 40' I
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(9998D/WPF/021694) 4.2 - page 1 of 1 l
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f SECTION 4.3 PROGRAM TABLES I
Rev. 12 TABLE DESCRIPTION The following information is included in the summary tables:
A.
REVTSION The revision corresponds to the current revision of the program.
B.
PAGE The pages are numbered sequentially and show the total number of tables.
C.
VALVE NUMP""
The valve number references the unique Byron Station equipment piece number (EPN).
This specific valve number identifies the unit and system.
D.
P&ID The P&ID column references the specific P&ID number which the valves are located on.
The Unit 2 P&ID number is given directly underneath the Unit 1 P&ID number.
E.
CLASS 1
The class refers to the ASME class assigned to the specific valve.
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VALVE CATEGORY i
The valve category identifies the valve category defined in subarticle IWV-2200 of ASME Section XI.
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G.
VALVE SIZE The valve size lists the nominal pipe size of each valve in inches.
(9998D/WPF/021694 )
4.3 - page 1 of 5 i
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Rav. 12 f
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VALVE TYPE t
The valve type categorizes the valve as to its valve design. The following abbreviations will be used to identify specific valve types:
Gate GA Globe GL Butterfly BTF Check CK Safety Valve SV Relief Valve RV Power Operated Relief Valve PORV Diaphragm Seated D
Plug P
Angle AN I.
ACT. TYPE The actuator type identifies the valve actuator.
The following abbreviations will be used to designate specific types of valve actuators:
Motor Operated M.O.
Air Operated A.O.
Hydraulic Operated H.O.
Self Actuated S.A.
Manual M
Solenoid Operated S.O.
I J.
NORMAL POSITION
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Normal position identifies the normal operating position of a specific valve. Q for open and f for closed.
K.
STROKE DIRECT.
The stroke direction identifies the direction the valve actuator moves a specific valve stem to place the valve disc in a position to perform its designed safety function (s). Q for open, and g for closed.
This identifies the direction (s) the valve stem will move when tested.
Note: Exercising of a power operated valve will involve stroking the.
I valve to both'its open and closed position.
The valve will only be timed, however, in the direction (s) designated to perform its safety function (s). Therefore, the program plan specifies only the direction (s) in which valves must be stroke' timed.
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4.3 - page 2 of 5 1
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TEST METHOD 4
The test method column identifies specific tests which will be performed on specific valves to fulfill the requirements of Subsection IWV of ASME Section XI.
The test and abbreviations used are as follows:
U l.
(Bt) Check Valve Back Flow Test The check valve disc will be exercised to the closed position-required to fulfill its safety function by verifying that the disc travels to the seat promptly on cessation or reversal of flow.
2.
(Ct) Check Valve Full Stroke Test The check valve disc will be exercised to the open position required to fulfill its safety function by verifying the maximum required accident flow through the valve or alternatives to full flow testing, per NRC Generic Letter 89-04, Attachment 1, Positions 1 and 2.
3.
(Ft) Fail Safe Test Valves with fail safe actuators will be tested to verify the valve operator moves the valve stem to the required fail safe position upon loss of actuating power, in accordance with IWV-3415.
This will be accomplished during the normal stroking of the valve.
Upon stroking a valve to its fail safe position, the solenoid operator is de-energized causing air to be vented which in turn allows the spring to move the valve to its fail safe position.
This condition simulates loss of actuating power (Electric and/or Air) and hence satisfies the fail safe-test requirements of IWV-3415, 4.
(It) Position Indication Check valves which are identified to require a Position Indication Test will be inspected in accordance with IWV-3300 of ASME Section XI.
5.
(Lt) Seat Leakane Test The seat leakage tests will meet the requirements of IWV-3420 for i
Category A valves.
On these valves, seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their safety function.
(9998D/WPF/021694) 4.3 - page 3 of 5
Rev. 12 6.
JRt) Safety Valve Setnoint Check Safety valve setpoints will be verified in accordance with IWV-3510 of ASME Section XI.
7.
(St) Full Stroke Test Valve exercising tests of Category A and B valves will be performed in accordance with IWV-3410.. The test will include full.
stroke testing to verify operability in the direction required to fulfill the required safety function.
8.
IXt) Part-Stroke Test If only limited operation is practical during plant operation, the valves shall be part-stroke (:Xt) exercised during plant operation and full-stroke exercised during cold shutdowns, in accordance with IWV-3412 or IWV-3522.
M.
TEST MODE Denotes the frequency and plant condition necessary to perform a given test.
The following abbreviations are used:
Normal Ooeration (OP)
J Tests designated "OP" will be performed once every 3 months, except in those modes in which the valve is not required to be operable.
il Semiannual (S)
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Tests with this designation will be conducted once every 6 months, except in those modes in which the valve is not' required to be operable.
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Cold Shutdown (CS)
Valves that cannot be operated during plant operation shall be full stroke exercised during cold shutdowns. Valve testing will commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown, with completion of cold shutdown valve testing not being a prerequisite to plant startup, Valve tests which are not completed during a cold shutdown, shall be completed during subsequent cold shutdowns to meet the Code Specified Testing Frequency.
For planned shutdowns, where ample time is available, and testing all'-
the valves identified for cold shutdown test frequency in the IST Program will be accomplished, exceptions to the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may be taken.
In case of frequent cold shutdowns, valve testing need not be performed more often than once during any three-month period.
I (9998D/WPF/021694) 4.3 - page 4 of'5 e
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Rev. 12 Reactor Refuelino (RR)
Tests with this designation will be conducted during reactor refueling outages only.
N.
RELIEF REOUEST Relief requests reference a specific request for relief from code requirements. All relief requests are included in Section 4.6.
e O.
NOTES Notes provide a short explanation concerning a particular IST valve.
All notes are included in Section 4.4.
P.
TEQiNICAL APPROACHES AND POSITIONS Technical approaches and positions provide detailed discussions on a particular IST topic. All technical approaches and positions are included in Section 4.5.
Q.
REMARKS Remarks reference other information useful in determining valve testing requirements or methods.
(9998D/WPF/021694) 4.3 - page 5 of 5
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DISERVICE TEST 1NG PROGRAM PLAN CIASS 1,2,3 AND AUGMENTED VALVES BYRON NUCLEAR POWTR STATtON UNtTS O,1,2 Reves on 12 VALVE 3
VALVE VALVE VALVE
- ACT, NORFA4.
STROKE
. TEST TEST ftUEF TECH.
NUMBER
'-4 CLASS CATEGORY SIZE TYPE TYF1E POSITION OtPECT.
RKTHOO MCOE REQ'KST NOTES POS.
REMAPKS
(!N )
NP1 (VA)
I 1/2AFOO1A 4 37 3
C 6.0 CK S.A.
C O
Xt/Ci OPtCS 12 3
M122 C
Bt RR VR.19 3
1/2AFOO18 4 37 3
C B.O CK S.A.
C O
Xt/C1 OP/CS 12 3
M122 C
Be M
VR19 3
1/2AFOO3A M37 3
C 6.0 CK S.A.
C O
Xt/Ct CP/CS 12 3
4 122 112AFOO3B M37 3
C 6.0 CK S. A.
C O
XtlCt OP CS 12 3
M-122 1 ** %FOO6A M37 3
8 S.0 GA M.O.
C O
St OP 1
M122 it PR ll2AFOOCB M37 3
8 S.0 GA M.O.
C O
St OP 1
4122 It M
1/2AFC13A M37 2
8 40 GL M.O.
O C
St OP 1
4 122 ft RR 1/2AF0138 M37 2
8 4.0 GL M.O.
O C
St OP 1
M122 ft M
1/2AF013C M37 2
B 4.0
. GL M.O.
O C
St OP 1
M172 ft RR 1/2AF0130 M37 2
B 4O GL M O.
O C
St OP 1
4 122 H
RR It2AF013E M37 2
B 4.0 GL M O.
O C
St OP 1
M122 ft RR ll2AFC13F M37 2
B 40 GL FA O.
O C
St OP 1
M122 h
RR 1/2AF013G M-3 7 2
B 4.0 GL M.O.
O C.
St OP 1
M122 it RR 1/2AF013H M37 2
8 4.0 GL M.O.
O C
St OP 1
4 122 It FlR 1/2AF014A M37 2
C 4.0 CK S.A C
O Ct CS 12 3
M.122 C
Bt CS 12.30 3
1/2AF014B M37 2
C 4.0 CK S.A.
C 0
Ct CS 12 3
4 122 C
Bt CS 12,30 3
4.3 VALVE TABLES - PAGE 1 of 42
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INSERVICE TESTING PROGRAM Pt.AN CLASS 1. 2. 3 AND AUGMENTED VALVE 5 BYRON NUCLEAR POWER STAT 10N LFNITS 0.1,2 Rewssort 12 VALVE VALVE VALVE VALVE ACT.
NOFEuL STROKE TEST TEST
- EUEF TEC!L I
NUMBER P&O CLASS CATEGORY StZE TM TYPE POSITION DmECT.
METHOD MODE REQUEST NOTES POS REMARKS (IN )
{V3U g,
il2AF014C M37 2
C 4.0 CK S.A.
C O
Ct CS 12
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4122 C
8t CS 12,30 3
1!2AF0140 M37 2
C 4.0 CK S.A.
C O
C1 CS 12 3
M122 C
Bt CS 12,30 3
1/2AF014E M37 2
C 4.0 CK S.A.
C O
Ct CS 12 3
4 122 C
Bt CS 12,30 3
Il2AF014F M37 2
C 4.0 CK S.A.
C O
Ct CS 12 3
4 122 C
Bt CS 12,30 3
1/2AF014G M3 7 2
C 4.0 CK S.A.
C O
Ct CS 12 3
N4122 C
Bt CS 12,30 3
Il2AF014H M37 2
C 4.0 CK S.A.
C O
Ct CS 12 3
4 122 C
Bt CS 12,30 3
li2Af317A M37 3
8 6.0 GA M.O.
C O
St OP 1
M122 It RR ll2AF017B M37 3
8 6.0 GA M O.
C 0
St OP 1
M-122 It RR 1/2AF029A 4 37 3
C 6.0 CK S.A.
C O
Ct CS 12 3
M122 If2AF0298 4 37 3
C 6.0 CK S.A.
C O
Ct OS 12 3
M122 4.3 VALVE TABLES PAGE 2 of 42 i
p3wpWocemtd\\vahres.sts
FdSERVICE TESTr4G PROGf%M PLAN CLASS 1, 2, 3 AND AUGtKNTED VALVES BYRON NUCLEAR POWIR STATION UNITS O,1, 2 Rwoon 12 VALVE VALVE VALVE VALVE ACT.
fv0PMAL STROKE TEST TEST PELIEF TECR NUMBER P&lD CLASS CATEGORY SIZE TYPE TYPE POSITION DRECY.
METHOD MODE MOVEST NOTES
- PCs, MMARirS fRJ l (VR)
(val ll2CC3486 FA06-1 A 2
AC 6.0 CK S.A.
O O
Lt. Bt MtCS VR 1, 8 3
FA 139-1 O
Ct OP 3
1/2CC9518 PA 661 A 2
AC O.75 CK SJL C
41391 0
Ct M
VR8 24 3
ll2CC3534 PA66-1 A 2
AC-0.75 CK S.A.
C C
Lts et MR/CS VR 1, 8 3
M1391 0
Ct CS VR8 24 3
4.3 VALVE TABLES - PAGE 4 of 42 p:\\wp\\docrmWwafwee.mle -
I PdSERVICE TESTING PROGRAM PLAN i
CLASS 1,2,3 AfD AUGMENTED VALVES l-BYRON NUCLEAR POAYR ST ATION l
LRATSO.1,2 Reeson 12 l
VALVE VALVE VAVE VALVE ACT.
NORMAL STROKE TEST T F ', T REUEF IECH.
MJMPER P&4D CLASS CATEGORY SIZE TYPE N
POSITION DIRECT.
METHOO WODE REQUEST NOTES POS.
REMARKS bN I (VR)
NA) 1/2CCS85 M661A 2
A 4.0 GA M.D.
O C
St C5 Vf4 8 1
M139-1 It RR Lt RR VR1 1/2CC9412A M 66-2 3
8 12.0 GA M.O.
C O
St OP 1
M139-2 ft RR II2CC34128 M66-2 3
8 12.0 GA M.O.
C O
St OP 1
M139-2 h
RR 1/2CC9413A MSS 1 A 2
A 6.0 GA M.O.
O C
St CS VR8 1
M139-1 h
RR tt RR VR1 1/2CC9414 M 66-1 A 2
A 6.0 GA M.O.
O C
St CS VR8 1
M139-1 et M
Lt RR VR1 l
1/2CC2415 M66-4D 3
8 16.0 GA M.O.
O CO St CS 44 1
h 8Wt g
1/2CC9416 M66-1 A 2
A 6.0 GA M.O.
O C
St CS VR8 1
41391 M
PR tt RR VR1 1/2CC9437A M66-1 A 2
8 3.0 GL A.O.
C C;O StJt OP 1,2 M139-1 h
PR 112CCS437B M66-1 A 2
8 3.0 GL A.O.
O CIO St. F t OP 1,2 M139-1 It RR 1/2CC9438 M66-1 A 2
A 4.0 GA M.O.
O C
Lt RR VR1 M 139-1 h
1CC94598 M 66-3A 3
8 16.0 GA M
O O/C St CS 5
2CCS459B M66-3A 3
8 16.0 GA M
C OiC St CS S
li2CC9463A M-66-38 3
C 12.0 CK SA C
O CVBt OP 32 3
C 1/2CCS4S3B M66-38 3
C 12.0 CK S.A.
C O
Ct/Bi OP 32 3
C OCC9464 M66-3B 3
C 12.0 CK S.A.
C O
CCBt CP 32 3
C 1CC9467B M6640 3
8 16.0 GA M
O O!C St CS 5
2CCS4678 M66-4D 3
8 16.0 GA M
C O!C 5:
CS 5
1/2CC3473A M 60-3B 3
B 16.0 GA M.O.
C C/O St OP 1
tt PR 1/2CC94738 M 66-3B 3
9 16.0 GA M.O.
C C/O St OP 1
ft RR 4.3 VALVE TABLES - PAGE 3 of 42 p.hopWocrmtdwahree.xfe
MSERVICE TESTING PROGRAM PLAN CLASS 1, 2. 3 AND AUGMENTED VALVES BYRON M)CLIAM POWTR STATION UNITS O,1, 2 Revieron 12 VALVE VALVE VALVE VALVE ACT.
NOht&t.
STROKE TEST TEST REUEF TECH.
NVP.EER P&O CLASS CATEGORY SIZE TYPE TYPE POSITION DsRECT.
METHOD MODE REQUEST NOTES POS.
REMARKS ON )
IVR)
(VA) 1/2CSOO1 A M 61 -4 2
B 14.0 GA M O.
O C
St OP 1
M136-4 It RR 1/2CSOO18 M 61 -4 2
8 14 0 GA M.O.
O C
St OP 1
M136-4 It RR 1/2CSOO3A 446-1 A 2
C 10.0 CK S.A.
C 0
Xt/C1 OP/RR VR4 3
M129-1 A II2CSOO3B M461 A 2
C 10.0 CK S.A.
C O
Xt/Ct OP/M VR4 3
M 129-1 A 1/2CSOO7A M 4 5-1 C 2
A Ido GA M O.
C OiC Lt M
VR-1 M1291C St OP 1
H RR 1/2CSOC78 M46-1C 2
A 10.0 GA M O.
C O/C Lt PR VR1 M 129-1 C St OP 1
It RR 1/2CSOO8A M 46-1 C 2
AC 10.0 CK S.A.
C O
Ct Bt RR VR4 3
M 129-1 C C
Lt RR VR-1 3
If 2CSOOSB M4S-1C 2
AC 10.0 CK S.A.
C O
Ct/Bt HR VR4 3
M 129-1 C C
L?
RR VR1 3
ll2CSOOSA M 61 -4 2
8 16.0 GA M.O.
C O
St OP 1
M136-4 M
RR 1/2CSOOSB MSI 4 2
B 16.0 GA M O.
C O
St OP 1
M136-4 ft RR 1/2CSO11 A M46-1 A 2
C 6.0 CK SA.
C O
Xt OP 3
M129-1 A Ct M
VR25 3
1/2CSO118 M461 A 2
C 6.0 CK S A.
C O
Xt OP 3
M129-1 A Ct RR VR 25 3
1/2CSO19A M 46-1 B 2
B 3.0 GA M O.
C O/C St OP 1
M12918 le RR 1/2CSO198 M451B 2
B 3.0 GA M.D.
C O/C St OP 1
M129-1 B se RR 1/2CSO20A M46-1B 2
C 3.0 CK S.A.
C O
Ct RR VR-2 3
M129-1 A C
Bt OP 3
1/2CSO208 M 46-1 B 2
C 3.0 CK S.A.
C O
Ct RR VR 2 3
M129-1 A C
Bt CP 3
4 3 VALVE TABt.ES-PAGE 5 of 42 s
p:\\wpwocrmtevadves.xte
GVSERVICE TESTING FROGRAM PLAN CLASS 1,2,3 AND AUGMENTED VALVES BYRON NUCLEAR POWER STATIOtt UNITS 0.1, 2 Reymon 12 VALVE VALVE VALVE VALVE ACT.
NOBA%L STROKE TEST TEST REUEF TECH.
NUMBER POD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
METHOD MODE REQUF.e7 NOTES POS.
REMAFUCS MJl
{\\ R)
(VA}
1/2CV1128 M644A 2
B 4.0 GA M.O.
O C
St CS 4.28 1
M.138-4 It RR ll2CV112C M64-4A 2
8 4.0 GA M O.
O C
St CS
- 4. 28 1
4 138-4 ft RR 1/2CV112D M64 48 2
B 8.0 GA M.O.
C O/C St CS 2
1 M 138-4 ft AR 1/2CV112E M64-48 2
8 8.0 GA M.O.
C OiC St CS 2
1 M138-4 h
RR 1/2CV8100 M 64-2 2
A 2.0 GL M.O.
O C
St CS VR9 1
M138 2 ft RR Lt RR VR1 1!2CV8104 M64-48 2
8 3.0 GL M.O.
C O
St CS 2
1 M 138-4 it RR 1/2CV8105 M 64-39 2
B 3.0 GA M.O.
O C
St CS 4
1 M138-38 ft RR 1/2CV8106 4 64-38 2
B 30 GA M.O.
O C
St CS 4
1 4138-3B tt RR 1/2CV8110 M64-3A 2
B 2.0 GL M O.
O CIO St OP 1
4 138-3 ft RR 1/2CV8111 M 64-3A 2
B 2.0 GL M O.
O C/O St OP 1
M138 3 h
RR 1/2CV8112 M64 2 2
A 2.0 GL M.O O
C St E.S VR9 1
M138-2 ft RR Lt RR VR.1 1/2CV8113 M 64-2 2
AC O.75 CK S.A.
C C
LtlSt futCS VR.1. 9 3
4 138-2 O
Ct RR VR-9 24 3
II2CV8114 M 64-3A 2
8 2.0 GL S 0.
O C/O St OP 1
M138-3 ft RR 20 1/2CV8116 M64-3A 2
8 2.0 GL S 0.
O CIO St OP 1
M.138-3 l'
RR 20 4.3 VALVE TABLES. PAGE e of 42 pnwpWocmnt$welves. mis
INSERVICE TESTING PROGRAM PLAN CLASS 1, 2. 3 AND AUGMENTED VALVES BYRON NUCLEAR POWER STAT!ON UNtTS O,1. 2 Rewmon 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST REUEF TECH.
NUMBER P&iD r1 ASS CATEGORY SIZE TYPE TYDE POSITION Dl8tECT.
METHOD MODE REOtKST NOTES PCS.
REMARKS f!N )
(VR1 (VA)
It2CV8152 M 64-5 2
A 3.0 GL A.O.
O CtO St CS 4
2 lt RR VR1 1/2CV81SO M 64-5 2
A 3.0 GL A.O.
O CIO St CS 4
2 it RR VR-1 1/2CVB440 454-4B 2
C 4.0 CK S.A.
O C
Bt CS 28 3
M138-4B O
Ct OP 3
1/2CV8442 464-4r 2
C 2.0 CK S.A.
C O
Ct CS 2,23 3
M137. '
'}'
1/2CV8480A M 64-3*
C 2.0 CK SA C
O Ct OP 31 3
M 138-3 C
Bt OP 3
112CV84800 M 64-3A 2
C 2.0 CK S A.
C O
Ct OP 31 3
M138-3 C
Bt OP 3
1/2CV8481 A M 64-3A 2
C 4.0 CK -
S.A.
C O
Ct!Kt CS/OP VR15 3
M138 3A C
Bt OP 3
1/2CV8481 B M64-3A 2
C 4.0 CK S.A, C
O Ct!Xt CS/OP VR15 3
M138-3A C
Bt OP 3
1(2CVB540 M 64-4B 2
C 8.0 CK S.A C
0 Ct CS VR15
- 2. 26 3
M138-4 1!2CV8804A M 64-48 2
B 8.0 GA M.O.
C O
St CS 2
1 M-138-4 ft RR 4.3 VALVE TABLES - PAGE 7 of 42 pdwpWocmntci\\ valves.xis
INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3 AND AUGMENTED VALVES BYRON NUCLIAR POWER STATION UNITS 0,1,2 Revemon 12 VALVE -
VALVE VALVE VALVE ACT.
NORMAL STfKAE TEST TEST MLIEF TECH.
NUMBER P&O CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
hETHOD MODE REQUEST NOTES POS.
REMARKS (IN )
(VR1 (VA)
II2DG5182A M152-20 NONE B
3.0 GA S.O.
C O
St OP VR13 (TYPtCAU EOG51828 4 152-20 NONE B
3.0 GA S.O.
C O
St OP Vf413 (TYPtCAU 112DG5183A M152-20 NONE B
3.0 GA S.O.
C O
St OP VR13 (TYPICAO 1120G51838 M152-20 NONE B
3.0 GA S.O.
C O
St OP VR13 (TYRCAO 1/2DG5184A M152-20 NONE C
3.0 CK
$ A.
C O
Ct OP VR13 3
(TYMCAU 1/2DG51848 M152 20 NONE C
3.0 CK S.A.
C O
Ct OP VR13 3
(TYPtCAU 1/2DG5185A M152 20 NONE C
3.0 CK S.A.
C O
Ct.
OP VR-13 3
(TYPICAU 1/2DG51858 M 152-20 NONE C
3.0 CK S A.
C O
Ct OP VR.13 3
(TYPfCAO 4.3 VALVE TABLIS PAGE 8 ef 42 pdwpWocmntdWafves.nle
LTSERVICE TESTPdG PROGRAM PLAN QASS 1,2,3 AND AUCMENTED VALVES BYRON NUCLEAR POWIR STATION UMTS 0.1,2 Revison 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST MLIEF TECH.
NUMBER P&tD CLASS CATEGORY SIZE TYPE TYPE POSITION OfRECT.
METHOD MODE REQUEST NOTES POS MMARKS (N.)
C 1.5 CK SA C
0 C1 OP a
M130-1 A C
Bt OP 3
11200003B M501A 3
C 1.5 CK SA C
O Ct OP 3
413418 C
Bt OP 3
1/2DOOO3C 4 50-18 3
C 1.5 CK SA C
0 Ct OP 3
M1341A C
Bt OP 3
1/2000030 4501 A 3
C 1.5 CK SA C
O Ct OP 3
M1341B C
8t OP 3
4.3 VALVE TABLES.PAGE 9 cf 42 p:\\wpWocrew*td\\ valves.nle
.*.a m
INSERVICE TESTNG PROGRAM PLE2s CLASS 1. 2,3 AND AUGMENTED VALVES.
- BYRON NOCLEAR POWER STATION UNITS 0.1,2 Revision 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST RLuff TEOt NUMBER PMD CLASS CATEGORY SIZE TWT TYPE POSITION DIRECT.
LETHOD MODE REQUEST NOTES POS.
REMARKS ON )
(VR)
(VA)
Il2FC009 M631 A 2
A 4.0 P
M C
C Lt RR VR1 PASSt%1E It?FC010 M631 A 2
A 4.0 P
M C
C Lt RR VR1 PASSIVE 1/2FC011 4 63-18 2
A 3.0 P
M C
C Lt RR VR1 PASSNE M6 3-1C 1/2FC012 463-1 B 2
A 3.0 P
M C
C Lt RR VR-1 PASSIVE M631C 4.3 VALVE TABLES - PAGE to of 42 pdwpWocmntdivalves.xte
INSERVICE TESTING PROGCAM PULN CLASS 1. 2. 3 AND AUCRENTED VALVES BYRON NUC11AR POWT.R STATON UNfTS 0,1, 2 Revinson 12 VALVE VALVE VALVE VALVE ACT.
NOFS4AL STROKE TEST TEST RELIEF TECH.
NUEEER P&O CLASS CATEGORY SIZE TYPE TYPE POSITION DRECT.
METHOD MODE REQUEST NOTES POS.
REn4 ARKS (tN )
(VP4 (VA)
II2FP010 MS 2-1 2
8 4.0 GA A.O.
O C
St OP 1
ft PR Ft OP 2
4.3 VALVE TABLES - PAGE 11 of 42 p:\\wpWocemttP, valves.mte
- NSERVlCE TESTING AOGRAM R.AN CLASS 1,2. 3 AND AUGMENTED VALVES SYRON NUCLEAR POWER STATION UNITS 0.1. 2 Revison 12 VALVE VALVE VALVE VALVE ACT.
NOMMAL STROKE TEST TEST RittEF TECH.
NUMBER P&lD C1 ASS CATEGORY SCE TYPE TYPE POSITION DE CT.
METHOO MODE REQUEST NOTES PCS.
REn%PXS HN )
WPJ (VA) 1/2FWOO9A M 36-1 C 2
8 16.0 GA H.O.
O C
StiXt CS/OP 3
1 4 121-18 It RR II2FWOO98 M36-1 A 2
8 10.0 GA H.O.
O C
StiXt C5.'OP 3
1 M121-10 h
RR If 2FWOOSC M36-1D 2
8 15.0 GA H.O.
O C
StlAt CS/OP 3
1 M121-1 A et RR 1/2FWOO90 M 36-18 2
8 16.0 GA H.O.
O C
StlXt CS/OP 3
1 M 121-1C ft RR 112FWO34A M 3 S-1 C Not4 8
2O GL A_O.
O C
Ft RR 21 2
M 121 18 f t2fWO348 439-1 A Nord 8
2.0 GL A.O.
O C
Ft PR 21 2
4121-1 D 1/2FWO34C 1A 36-1D NONE 8
2.0 GL A.O.
O C
Ft RR 21 2
- A 121-1 A If 2FWO34D M 36-18 NONE 8
2.0 GL A.C.
O C
Ft RR 21 2
M121 1C 1/2FWO35A M 35-1 C 2
8 3.0 GL A.O.
O C
St OP 1
M121-18 it PR Ft OP 2
112FWO358 M 36-1 A 2
8 3.0 GL A.O.
O C
St OP 1
M121-1D tt PR Fe OP 2
1(2FWO35C M35-1D 2
8 3.0 GL A.O.
O C
St OP 1
Il2FWO35D 84 36 18 2
8 3.0 GL A.O.
O C
St OP 1
1/2fwC36A M 3 S-1 C 2
C 3.0 CK SA O
C Bt CS 45 3
M 121 18 1/2FWO368 M 36-1 A 2
C 3.0 CK S.A-O C
81 CS 45 3
M 121-1 A 1/2FWO3SC M3S-10 2
C 3.0 CK SA O
C 8t CS 45 3
M 121-1 C 1/2FWO3eD M 36-18 2
C 3.0 CF-SA O
C 8t CS 45 3
M121-1C 4.3 VALVE TABLES - PAGE 12 of 42 a
p:\\wp\\docremtd\\walves.mte
INSERV1CE TESTING PROGRAM F1.AN CLASS 1,2,3 AND AUGMENTED VALVES BYRON NUCLEAR POWER SYATION UNITS O,1, 2 Revssion 12 VALVE VALVE VALVE VALVE ACT.
NOMAAL STROKE TEST TEST RELIEF TECH.
NUMBER P&O CLASS CATEGORY SIZE TYPE TYTT POSITION DIRECT.
METHOO MODE REQUEST NOTES POS.
IVR)
NA) 1/2FWO39A M 36-I C 2
B Sf GA A 0.
O C
St CS 10 1
1/2FWO398 M36-1 A 2
8 0.0 GA A.O.
O C
St CS 10 1
1/2FWO39C M36-1D 2
B 6.0 GA A.O.
O C
St CS 10 1
It2FWO3SO M 36-18 2
B 5.0 GA A.O.
O C
St CS 10 1
II2FWO43A M36-1C 2
B 3.0 GL A.O.
C C
St OP 1
1/2f WO438 M 36-1 A 2
B 3.0 GL A.O.
C C
S1 OP 1
1/2FWO43C M 36-1 D 2
B 3.0 GL A.O.
C C
St OP 1
1/2FWO430 M 36-18 2
B 3.0 GL A.O.
C C
St OP 1
1/2FWO 79A M361C 2
C 16.0 CK
& A.
O C
Bt CS 46 3
M 121-1B 1/2FWO798 M361 A 2
C 16.0 CK S.A.
O C
Bt CS 46 3
M121-10 1/2FWO79C M36-1 D 2
C 16.0 CK S.A.
O C
Bt CS 46 3
M121-1 A 1/2FWO79D M36-1 B 2
C 16.0 CK S.A.
O C
Bt CS 46 3
4121-1 C 1/2FW510 M36-1 C NONE B
16 0 AN A.O.
O C
Ft RR 16 2
M121-1 1/2FW510A M36-1C NONE B
4.0 GA A.O.
C C
Ft RR 17 2
4 121-1 4.3 VALVE TABus - PAGE 13 of 42 I
l i
l l
P:s Pse.e,-tos..n,..i.
l l
DsSEfMCE TESTING PROGRAM FLAN CLASS 1,2. 3 AND AUGMENTED VALVES SYRON NUCLEAR POWER STATKW UNITS O.1. 2 Reveen 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST REUEF TECH.
MJMBER P&O Q. ASS CATEGORY SIZE TYPE TYPE POSITION DtHECT.
METHOD MODE REQUEST NOTES POS.
REMARKS WI (V'll (VA) 1/2FW520 436-1 A NONE 8
16.0 AN A.O.
O C
Ft RR 15 2
4 121-1 112FW520A M 3S-1 A NONE 8
4.0 GA A.O.
C C
Ft RR 17 2
M121-1 1/2FW530 430-1D NCreE 8
16.0 AN A.O.
O C
Ft RR to 2
M 121 -1 Il2FW530A M 36-10 NONE 8
4.0 GA A.O.
C C
Ft RR 17 2
M 121-1 II2FW540 M36-18 NONE 8
10.0 AN A.O.
O C
Ft BR 16 2
41211 1/2FW540A M36-18 NONE 8
4.0 GA A.O.
C C
Ft RR 17 2
M121-1 4.3 VALVE TABLES - PAGE 14 of 42 pSwp'usocmnteveNea.nle
i OtSERVICE TESTNG AOGRAM PLAN CLASS 1. 2,3 AND AUGMENTED VALVES BYRON NUCLEAR PCMTR STATION UNITS 0.1. 2 Rowman 12 VALVE VALVE VALVE VALVE ACT.
NOPJAAL 51ROKE TEST TEST H UEF T ECH.
NUMBER P&lO CLASS CATEGORY SIZE TYPE TE POSITION CtRECT.
ATTHOO MODE FIEQUEST NOTES POS.
REMAfUt3 UN 1 (VRI (VA)
It21AOe5 M 554 2
A 3.0 GL A,0.
O C
Lt M
VR1 M 55-5 St M
VR10 1
Ft RR VR10 2
ft M
1/25AOe6 M 55-4 2
A 3.0 GL A.O.
O Cio Lt RR VR1 M 55-5 St RR VRIO 1
Ft PR VR 10 2
ft RR II2tA091 M55 4 2
C C
Lt/Bt RR VR1.10 3
M55-5 O
Ct RR V410 3
4.3 VALVE TABLES. PAGE 15 of 42 I
e I
I p:ivepWocmritevahree.wis
=
CESERV1CE TESTING P90 GRAM FL40 CLASS 1. 2. 3 AND AUGnENTED VALVES I
BYRON NUCLEAR POWER STATION UNITS 0.1. 2 -
Rewrmon 12 VALVE VALVE VALVE VALVE
- ACT, NORMAL STROKE TEST TEST REl.lEF TECH.
NUMER P&O CLASS.
CATEGORY' SIZE TYPE TYPE POSCION DIRECT.
AETHOD MODE REQUEST NOTES POS.
REMARKS 11N i (V39 (VA)
Il4W1 A M352 2
8 30.25 GA H O.
O C
StiXt CS/OP 1
1 M 12S2A It RR 1/2MSOO18 M 351 2
8 32.75 GA H.O O
C StiXt CS/OP 1
1 M12S1 ft RR II2MSOO1 C M35-2 2
8 32.75 GA H.O.
O C
StiXI CS/OP 1
1 M 120-29 te M
i II2MSOQ1 D M351 2
8 30.25 GA H O.
O C
StXt CS:OP 1
1 M120-1 h
RR 1/2MSO13A M 35-2 2
C 6.0 X SV
$ A.
C OiC Rt RR M12S2A 10 0 112MSO138 M 351 2
C 6.0 X SV S.A.
C O.C Rt RR M1201 10.0 1/2MSO13C M 35-2 2
O/C Rt RR M 120-2B 10.0 1/2MSO130 M 351 2'
OIC Rt RR M120-1 10.0 II2MSO14A M 35-2 2
O/C Rt RR M120 2A 10 0 1/2MSO140 M35-1 2
O!C Rt RR M1201 10 0 142MSO14C M 35-2 2
O!C Rt RR 4 120 25 to O t/2MSO140 M351 2
O/C Rt RR M1201 10 0 1/2MSO15A M352 2
C 60X SV S.A.
C 0;C Rt RR M1232A 10 0 112MSO158 M341 2
0;C Rt RR M1201 10 0 1/2MSO15C M352 2
C
. 6.0 X SV S.A.
C 0:C Rt RR M12S29 10.0 if 2MSC150 M 351 2
Orc Rt RR M 120-1 10 0 4.3 VALVE TABLES - PAGE 16 of 42 L
l pnwpWecnet@. valves mss i
INSERVICE TESTING PROGMM RN4 CLASS 1. 2. 3 AND AUG8ENTED VALVES BYFtDN NUCLEAR POWER STATlON UNITS 0. t. 2 Reveen 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STRCKE TEST TEST N UEF TECH.
NUMBER P&lD CLASS CATEGORY SIZE TYPE TYFT POSITION DIRECT.
fMTHOD MODE REQUEST NOTES POS.
REA%RKS 41N )
(VRi FVA)
It2MSO16A M 352 2
C 6.0 X SV S.A.
O 0;C Rt M
M120 2A 10 0 I t2MSOl68 M351 2
C 6.0 X SV S.A.
O OtC Rt RR M1241 10 0 1/2MSOl6C M352 2
O O/C Rt ftR 4 12428 10.0 1/2MSO160 M35-1 2
C 6.O X SV S.A.
O O/C Rt RR 41201 10.0 1/2MSO17A M352 2
C 6.0 X SV S A.
O O/C Rt RR M12424 10 0
- 11. w 178 4351 2
C 6.0 X SV S.A.
O OfC Rt RR M125.i 10 0 112MSO17C M352 2
C 6.0 X SV SJL C
0;C Rt RR M12428 10 0 1/2MSO170 M351 2
O/C Rt RR M1201 10 0 1/2MSOlBA M 352 2
8 6.0 X PORY H.O.
C CIO St OP VR 12 1
II2MSO188 M351 2
6 60X PO**V H.O.
C C;O St OP VR12 1
M1241 6.0 ft PR Ft OP 2
It2MSO18C M352 2
8 6.0 X PORV H.O.
C CIO St OP VR12 1
II2MSO18D M351 2
8 6.0 X PORV H.O.
C C;O St OP VR12 1
4.3 VALVE TABLES - PAGE 17 of 42 p:\\wpWocmntevalves.co
INSERVICE TESTING fwAAM PLAN CIASS 1, 2. 3 AND AUGBANTED VALVES BYRON NUCLEAR POWER STATION UMTS O.1, 2 Remoon 12 VALVE VALVE VALVE VALVE ACT.
NOf%%L SIROKE TEST TEST REUEF TECH.
NUMBER P8JD CLASS CATEGORY SIZE TYPE TYPE POSITtON DdECT.
LETHOO MODE REQUEST P40TES POS.
REMARKS ftN I (VR)
(VA)
It2MSO19A M352 2
8 8.0 GA M
O C
St OP M1242A 112MSO198 4351 2
8 8.0 GA M
O C
St OP M120-1 t/2MSO13C M352 2
B 0.0 GA M
O C
St CP M12428 1/2MSO19D M351 2
8 8.0 GA M
O C
St OP M1201 1/2MS101 A M352 2
8 4.0 GA A.O.
C C
St OP 1
II2MS1018 M351 2
B 4.0 GA A.O.
C C
St.
II2MS101C M 351 2
8 4.0 GA AO.
C C
St OP 1
Il2MS1010 M351 2
8
- 4. 0 GA A.O.
C C
fit OP 1
4.3 VALVE TABLES - PAGE 18 of 42
.I p iwpWocmnt&veeves. mis a
j 1
d HSERVICE TESTpdG N FIAN Q. ASS 1, 2, 3 APO AUG04NTED VALVES BYRON NUCLEAR POWIR STAT 40N UNITS 0.1,2 Revemon 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST REUEF TEO4.
NUMBER P&O CLASS CATEGORY SIZE TY'E TYFT POSITICN DIRECT.
AETHOD MODE ftEQUEST NOTES POS.
FIEMARKS (IN I (VR)
O/A) tt20GO57A 4472 2
A 3.0 BIF M.O.
C ClO Lt M
VR1 St OP 1
M1542 ft RR 1!2OGO79 M4 7-2 2
A 3.0 BIF M O.
N RR 1/2OGO90 M 47-2 2
A 3.0 BTF MO.
C Cs 0 Lt RR V41 M150 2 St OP 1
it RR 1/20GO81 M4 7-2 2
A 30 BIF M.O.
C C/O Lt RR Vf41 M1542 St OP 1
ft RR 1120GO62 M4 7-2 2
A 3.0 BYF M O.
A 3.0 BTF M 0.
It RR 1/20GO64 M47-2 2
A 3.0 BTF M O.
ft RR 1120GOe5 4472 2
A 3.0 8TF M.O.
C ClO Lt PR V41 M1542 St OP 1
le RR 4.3 VALVE TABLES - PAGE 19 of 42 2
)
9 pdwp%3cmntsveNoe sie
EMSERVICE TESTCOG PROGRAM FQ.AN CLASS 1,2,3 AND AUGMENTED VALVES BYRON MJCLEAR POWER STATION UMTS O,1, 2 Revison 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST RELJEF TECH.
NUMBER P&lO CLASS CATEGORY StZE TYFE TYPE POSITION DIRECT.
METHOD MODE REQUEST NOTES POS.
REMARKS IIN )
(VR)
(val II2PMOO1 A M 7810 2
A 1.0 GL A.O.
O C
St OP 1
h RR 1/2PROO18 M 78-10 2
A 1.0 GL A.O.
O C
St OP 1
it RR 112 MOO 2E M 78-6 2
A 2.0 GL M
C C
Lt M
VR1 PASStVE 1/2PROO2F M 78-6 2
A 2.0 GL M
C C
Lt RR VR1 PASSIVE 1/2PROO2G M78 6 2
AC 2.0 CK S.A.
C C
Lt RR VR1 3
PASSIVE II2PHOO2H M 78-6 2
C Lt RR VR-1 3
PASSIVE 1/2 PRO 32 M 78-10 2
C Lt.'8t MVCS V41 37 3
PASSIVE M151-1 1/2 PRO 33A M 78-6 2
A 2.0 GL M
C C
Lt ftR VR 1 PASSIVE 5
112 PRO 338 M 78-6 2
A 2.0 GL M
C C
Lt RR VH1 PASSIVE 112 PRO 33C M 7 8-6 2
A 2.0 GL M
C C
Lt fir VR1 PASSIVE 112 PRO 33D M78 6 2
A 2.0 GL M
C C
Lt RR VR1 PASSIVE 112PR066 M 78-10 2
A 1.0 GL A.O.
O C
It RR St OP VR.12 1
4.3 VALVE TABLES-PAGE 20 of 42 e
pavvpWocmntd\\wenres.mte
W4 SERVICE TESTueG mOGPAJA PLAN C1. ASS 1,2,3 AND AUGLENTED VALVES SYRON NUCLEAR POWTR STATION UNITS 0.1,2 Revean 12 VALVE VALVE VA'.ii VALVE ACT.
NCf9AAL STROKE TEST TEST fELJEF TECH.
N1.%EER P8JD CIASS CATEGORY ICE TYPE TYPE POSITION DIRECT.
fETHOD MODE REQUEST NOTES POS.
REMARKS (VR)
(VA)
It2PS228A Lt RR VR1 M 68-7 2
A O.5 CL 5,0.
O C/O St OP VR12 1
41446 Ft OP 2
ft RR 20 1/2PS2288 Lt RR V41 4 68-7 2
A O.5 GL S.O.
O Cto St OP VR-12 1
M1446 Ft OP 2
It RR 20 I
1/2PS229A Lt im VR1 M 68-7 2
A O.5 GL S.O.
O C/O St OP VR12 1
[
M140-6 Ft OP 2
tt RR 20 ti2PS2298 Lt AR V41 M68-7 2
A O.5 GL S O.
O CIO St OP VR12 1
M1446 Ft OP 2
M 68-7 2
A 1.0 GL S 0.
C C/O St OP VR12 1
M1446 Ft CP 2
ft RR 20 1/2PS2308 Lt RR VR 1 M 68-7 2
A 1.0 GL S. O.
C CIO St OP VR12 1
41446 Ft OP 2
ft RR 20 1/2PS231 A 4 08-7 2
A
.75 CK S A.
C C
Lt!Bt FWVCS V41 38 3
41446 O
Ct OP 22 3
1/2PS2318 M 68-7 2
A
.75 CK S.A.
C C
Lt,8t fWVCS VR 1 38 3
M1446 O
Ct OP 22 3
4.3 VALVE TABLES-PAGE 21 of 42 r
pnwph,vahres.xis
int 1RVICE TESTING PROGPAM FLAN CLASS 1,2. 3 AND AUGDENTED VALVES
. BYRON NUCLEAR PO%TR STATION UMTS 0.1. 2 Revisen 12 VALVE VALVE VALVE VALVE ACT.
NOPMAL J T ROs.E IEST TEST MLIEF 1ECH.
NUMBER P&iD CLASS CATEGORY StIE TYPE TYPE POSJTION Dh'CT.
METHOD MODE REQUEST NOTES POS.
REMLRKS ON )
NRI (vat 112PSS354A St OP 1
M 68-18 2
A O.375 GL A.O.
C C
Lt M
VR1 M 1441 M
Il2PS93548 St OP 1
4 08-18 2
A C.375 GL A.O.
C C
Lt RR VR-1 M1441 ft PR Ft OP 2
Il2PS9355A St OP 1
M68-18 2
A O.375 GL A.O.
C C
Lt M
VR1 M1441 it PR Ft OP 2
Il2PSS355B St OP 1
M6818 2
A O.375 GL A.O.
C C
Lt M
VR1 M1401 ft PR Ft OP 2
1/2PS9356A St OP 1
M68-1 A 2
A O.375 GL A.O.
C C
Lt M
VR1 M1441 ft PR Ft OP 2
11"PS93568 St OP 1
468-1 A 2
A O.375 GL A.O.
C C
1/2PS9357A St OP 1
M68-1 B 2
A O.375 GL A.O.
C C
Lt RR VR1 41441 ft M
Ft OP 2
112PS93578 St OP 1
4 08-18 2
A O.375 GL A.O.
C C
4 3 VALVE TABLES-PAGE 22 of 42 4
NMMDbSG.EN
I WSERVICE TESTING PROGRAM PLAN CLASS 1,2,3 AND AUGMENTED VALVES BYRON fd) CLEAR POWYR STATION UNITS O,1, 2 Reviecri 12 VALVE VALVE VALVE VALVE ACT.
NOfh. 4 STROKE TEST TEST RLUEF TECH.
NUMBER P&lO CLASS CATEGORY Sf2E TYPE TYPE POSITION ' DIRECT.
AETHCO MODE REQUEST NOTES POS.
REMARKS (tN )
Nf4 (VA)
It2RC014A M6018 1
8 1.O GL S O.
C O/C St CS Vf412 7
1 M13518 Ft CS 7
2 ft RR 20 1(2RC0148 M60wi 8 1
8 1.0 GL S.O.
C O/C St CS Vf412 7
1 M1351B Ft CS 7
2 ft RR 20 II2RC014C 4 60-18 1
8 1.0 GL S.0.
C O/C St CS Vf&I 2 7
1 M13518 Ft CS 7
2 ft RR 20 1/2RC014D M60-18 1
8 1.0 GL S.O.
C OtC St CS VR-12 7
1 M13518 Ft CS 7
2 ft RR 20 4.3 VALVE TABLIS. PAGE 23 of 42 l
i i
{
L t
pdwpWecmntssvalves.xis
INSERVtG TESTING PROGRAM PLAN CLAS$ 1,2. 3 AND AUGPANTED VALVES BYRON NUCLEAR POWTR STATION UNITS 0.1. 2 Revwon 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST REUEF YECH.
NUMBER P&ID CLASS CATEGORY StZE TYPE TYPE POSITION DIRECT.
METHOD MODE REOUEST NOTES POS.
RD4 ARKS (IN t (VRt IVA) 1/2RLIOC3 M70-1 2
A 3.0 D
A.O.
C C
St OP 1
4 141-1 Lt RR VR-1 ft RR Ft OP 2
112f%9157 M701 2
A 1.0 D
A.O.
O C
St OP VR12 1
M 141-1 Lt BR VR1 ft M
Ft OP 2
II2RE9159A M 701 2
A
.75 D
A.O.
O C
St OP VR-12 1
4 141-1 Lt RR VR1 ft M
Ft OP 2
1/2RE91598 M701 2
A
.75 O
A.O.
C C
St OP VR12 1
41411 Lt RR VR-1 ft RR Ft OP 2
1/2fE 91 SOA M701 2
A 1.0 D
A.O.
O C
St OP VR12 1
4 141-1 Lt RR VR1 h
M Ft OP 2
1/2RE916CB M 701 2
A 1.0 O
A O.
O C
St OP VR-12 1
If2Rf9170 M 70-1 2
A 30 D
A.O.
O C
St OP VR12 1
4.3 VALVE TABLE $ PAGE 24 of 42 t
p:1wpWocmntdhalves.mte
24 SERVICE TESTING PROGRAM PLAN CLASS 1, 2. 3 AND At>GMENTED VALVES BYRON NLWR POWER STATION UNI 1S O,1, 2 Revson 12 VALVE VALVE VALVE VALV E ACT.
NORA%L STROKE TEST 1EST RE11EF TEC2t NUMBER P&to CLASS CATEGORY SIZE TYPE TYPE POSITION DtMCT.
METHOD MODE REQUEST NOTES
- POS, REA%RKS (tN l (VR)
(VA) 112HF026 M48 6B 2
A 2.0 P
A.O.
O C
li2HFC27 M48-6A 2
A 2.0 P
A.O.
O C
4.3 VALVE TABdS-PAGE 25 of 42 p:\\wpWocmntd\\ valves. mis
INSERVICE TESTNdG PROGRAM PLAN CLASS 1,2. 3 AND AUGSAENTED VALVES D'RON NUC11AR POWER STAT 10N tPdTS0.1.2 Peesson 12 VALVE VALVE VAlb E VALVE ACT.
NORMAL STROKE TEST TEST REUEF TECH.
i NUMBER P&fD CLASS CATEGORY SCE TYPE TYPE POSITION DIRECT.
METHOD MODE NOVEST NOTES POS.
REMARKS 4
UN 1 WR}
(val 1/2f#t510 4 62 2
8 3.0 GA M O.
O C/O St OP 1.4 4137 N
RR It2fM611 M62 2
B 3.0 GA M O.
O CO St OP 1.4 M137 N
RR 1121WtS 701 A M62 1
A 12.0 GA M O.
C O/C St CS 5
1/2fM8 7018 M62 1
A 12.0 GA M O.
C O/C St CS 5
1 M137 ft RR Lt PR 6
1/2RH8702A M 62 1
.A 12.0 GA M O.
C OiC St CS S
1/2RH87028 M62 1
A 12.0 GA M O.
C O/C St CS S
1/2RH8 7CSA M62 2
.75 CK SA.
C C
Lt;Bt CS
- 6. 41 3
M137 0
Ct CS 24,35.41 3
1/2RH87058 M62 2
.75 CK SA.
C C
LtSt CS 6,41 3
4137 O
Ct CS 24.35,41 3
1/2RH8 706A M62 2
C 3.0 X RV S.A.
C O
Rt RR M137 4.0 C
112RH87008 M62 2
C 3.0 X RV SA.
C O
Rt RR 4137 4O C
1/2fM8716A M62 2
8 8.0 GA M O.
O CO St CS 43
- 1. 4 M137 et RR II2fM8 7168 M62 2
B 8.0 GA M O.
O C/O St CS 43 1, 4 4137 ft RR It2fN8730A M62 2
C 8.0 CK SA.
C O
CtlXt C1'OP e
3 4137 C
Bt CS 3
II2RH87308 4 62 2
C 8.0 CK SA.
C O
Cr/Xt CS/OP e
3 4137 C
Bt CS 3
4.3 VALVE TA8 TIS PAGE 26 of 42 l
I l'
l I
l l
l-p:hvpMoermtdtwaives.m!s t
INSERVICE TESTh'G F7K)GFmM PLAN CLASS 1,2,3 AND AUGMENTED VALVES BYRON NUCLEAR POVJR STATION UMTS 0.1, 2 Revs >on 12 VALVE VAlbE VALVE VALVE ACT.
NORMAL STROKE TESI IEST REUEF T E Ct.
NUMBER -
PILIO CLASS CATEGORY SIZE TYPE TYTT POSITION OtRECT.
METHOO MODE REQUEST NOTES POS.
REMARKS t*N i fvR)
NA) 1/2RYO75 M 206GS 2
A O.5 GL M
C C
Lt RR VR1 PASSIVE M21356 1/2RY455A M605 1
9 3.0 PORY A_O.
C O< C St CS 36 1
1/2RY456 M605 1
S 3.0 PORV A,0.
C OiC St CS 3S 1
41355 h
IIIRY BOOCA M645 1
9 3.0 GA M O.
O C
St OP 1
M1355 h
RR 36 1/2Rv 80008 M 60-5 1
8 3.0 GA M.O.
O C
St OP 1
M1355 h
M 36 1/2RY8010A M605 1
C 6.0 SV S A.
C O/C Rt BR M1355 te mR 36 1/2RYSC10B M645 1
C 6.0 SV S.A.
C Orc Rt RR M135-5 ft RR 36 1/2RYSO10C M605 1
C 6.0 SV S.A.
C O.C Rt RR 41355 ft RR 36 1/2RY8025 4006 St CP 1
u1356 2
A
.375 GL A.O.
C C
Lt RR VR1 PASSfvE it RR 36 Ft (P
2 1/2RY 8026 4646 St OP 1
M135-0 2
A
.375 GL A.O.
O C
II2RY8028 M646 St OP 1
41356 2
A
.75 D
A 0.
O C
Lt M
VR1 ft RR 36 Ft 09 2
1/28Y8033 M 6' 6 St OP VR12 1
J M1356 2
A O.8 D
A.O.
O C
4,3 VALVE TA8 tis PAGE 27 of 42 pdowpWocprna hee.mde
DdSERVICE TESTHG PROGRAM PLAN CLASS 1,2. 3 AND AUGNENTED VALVES BYRON NUCLEAR POWER STATION UMTS 0.1,2 Rwsm 12 VALVE VALVE VALVE VALVE ACT.
NOPMAL STROKE TEST TEST NEttEF TECH.
NUME,tR P&lO CLASS CATEGORY SIZE TYPE TYPE PoslTION D: RECT.
METHOD MODE PLOUEST NOTES POS.
REMARKS ON l (VR)
(VA) f 1/2RYBO46 PA600 2
AC 3.0 CK
$_A.
C C
Lt Bt RH/CS VR t, 23 3
PASSVE M-135-6 3
?/28YSO47 L4646 2
AC O.75 CK S.A.
C C
LtBt RH VR 1, 23 3
PASSVE
.4 135-6 3
4.3 VALVE TABLES - PAGE 28 of 42 l
t pAwp\\docrvuehwa*wesAs
. l i
i INSERVICE TESTING PRC3f%M RAN CLASS 1. 2. 3 AND AUGRENTED VALVES BYRON NUCLEAR POWER STATlON UNITS 0.1,2 Rommon 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST i RELiff TECH.
NUhSER P&O CLASS CATEGORY SIZE TYPE TYPE POSITION OtRECT.
aETHOD MODE,.50t>EST NOTES POS.
REMARKS IN $
TVRt WA)
It2SA032 4 54-2 2
A 1.5 GA A.O.
O C
II2SA033 M54-2 2
A 1.5 GA A.O.
O C
Lt PR VA1 St OP 1
4.3 VALVE TABLES-PAGE 29 of 42 i
pdvupWocmn4thwahree.xis
m INSERVICE TESTING FP3 GRAM PLAN CLASS 1, 2, 3 AND AUGAENTED VALVES BYRON NUCLEAR POWER STAftON l
UNITS 0.1. 2 Revieson 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST REllEF TECH.
NUMBER P&O CLASS CATEGORY SIZE TYPE TYPE POStilON OtRECT.
METHOD MODE REQUEST NOTES POS.
REMARKS UNI (VR)
(VA) 1/2SD002A M48-5A!B 2
A 2.0 GL A.O.
O C
h M
Ft OP 2
112500028 4 48-5AiB 2
A 20 GL A O.
O C
It M
Ft OP 2
1/2SD002C M48-5A/B 2
A 2_O GL A.O.
O C
Lt M
VR.12(U-2) 34 St OP 1
It M
Ft OP 2
1/250002D M 48-5A/B 2
A 2.0 GL A O.
O C
Lt RR VR121U-2) 34
{
St OP 1
It M
Ft OP 2
1!2SD002E M48-5A/B 2
A 2.0 GL A.O.
O C
ft M
Ft OP 2
Il250002F M 48-5A/B 2
A 2.0 GL A.O.
O C
Lt M
VR121U-2) 34 St OP 1
It RR Ft Op 2
l 1/250002G 4 48-5A/B 2
A 2.0 GL A.O.
O C
Lt M
VR 12(U-2) 34 St CP 1
1/250002H M48-5A.15 2
A 2.0 GL A.O.
O C
Lt M
VR12(U-2) 34 St OP 1
ft M
F1 OP 2
4.3 VALVE TABLES PAGE 30 of 42 p3wpWocrmtdivehres.mts
. - ~ =
L CWSERVICE TESTING Pf:DGRAM PLAN CLASS 1. 2,3 AND AUGENTED VALVES BVBON NUC1 EAR PW'ER STATION UNITS O.1,2 Rwom 12 VALVE WALVE VALVE VALVE ACT.
NOFW4%
STROKE TEST TEST MLgF Ysrw 1 NUMBER P&O CLASS CATEGORY SIZE TYPE TYTT POSITION DtRECT.
WTHOD MODE REQUEST h0TES POS.
KW'*.S FN1 NR)
{VA)
II2SDOOSA M48-5AlB 2
A O.375 GL A.O.
O C
St OP 1
1/2500056 448 & B 2
A O375 GL A.O.
O C
St OP 1
1/2SDOO5C M48-5A/B 2
A O.375 GL A.O.
O C
St OP 1
1/2S00050 M48 5A/S 2
A O.375 GL A.O.
O C
St OP 1
l Lt M
4.3 VALVE TABLES. PAGE 31 of 42 p:\\wp\\docrmtd\\ valves.xte -
m
-s
INSERVICE TESTING P'OGRAM F1AN -
CLASS 1. 2,3 AND AUGMENTED VALVES BYRON NUCLEAR POWER STAT 10N UMTS 0,1, 2 Revison 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST Hell [F TECH.
NUMBER P&lD CLASS CATEGORY SIZE TYPE TYPE POSITION E2 RECT.
METHOD MODE PEQUEST NOTES POS.
F1EMARKS (IN )
(VR)
(VA)
II2Sl8801 A M612 2
8 4.0 GA M 0.
C OiC St CS 13 1
41362 h
RR 1/2S888018 M 612 2
8 4.0 GA M O.
C O/C St CS 13 1
M136 2 h
M II2Sl8802A M613 2
8 4.0 GA M.D.
C Orc St CS 14 1
M136 3 ft RR II2518802B M-61 3 2
8 4.0 GA M.O.
C OiC St CS 14 1
M1363 ft RR 1/25188048 M611A 2
8
- 8.0 GA M O.
C O
St OP 1
M1361 ft PR l
1/2538800 M61+' A 2
B 8.0 GA M.O.
O 01C St CS 14 1
M136-1 ft RR l
It2Si8807A M611A 2
8 0.0 GA M.O.
C O
St OP 1
4 136-1 h
RR 1/25188078 M61-1 A 2
B 6.0 GA M O.
C O
St OP 1
M136-1 ft M
1/2Sl8809A M 61 -4 2
8 8.0 GA M O.
O OIC St CS 14 1
M136 4 ft PR 1/2$189099 M61-4 2
B 8.0 GA M O.
O O/C St CS 14 1
41364 it BR II2 SIS 811 A M614 2
5 24.0 GA M O.
C O/C St RR VR-16 1
M1364 ft RR 1125488118 4 61-4 2
B 24.0 GA M.D.
C 04C St HR VR-16 1
M 136-4 h
RR 112588812A M 61 -4 2
B 12.0 GA M O.
O C
St OP 1
M136 4 ft M
1/25488128 M 61 -4 2
8 12.0 GA M O.
O C
St OP 1
M1364 h
M li2S!8813 M61 18 2
9 2.0 GL M.O.
O C
St CS 14 1
M136-1 ft M
1/2510814 M61-1A 2
8 1.5 GL M.O.
O C
St OP 1
M136-1 It M
4.3 VALVE TABLIS.PAGE 32 of 42 pdwpwocmntd\\ valves.mte
INSERVtCE TESTING PROGRAM PLAN CLASS 1,2,3 AND AUGMENTED VALVES BYRON NUCLEAR POW 1B STATION UNITS O,.1, 2 Resion 12 VALVE VALVE VALVE VALVE ACT.
NORMAL ST RC*.E TEST TEST REUEF TECH.
NUMBfR P&fD CLASS CATEGORY StZE TYFT TYPF POSITION OfRECT.
METHOO MODE REQUEST NOTES POS.
REP.uRKS (IN.)
(V59
{VA) 1/2St9815 M61-2 1
AC 3.0 CK S. A.
C 0
Ct CS VR 15 3
M136-2 C
ttBt RR/CS 6.40 3
1/2 stb 818A M614 1
AC 6.0 CK S.A.
C O
Ct/Bt CS 6,9.23.40 3
M1364 C
Lt RR 1/25188188 M 61 -4 1
AC 6.0 CK S.A.
C O
Ct'Bt CS 6.9.23.40 3
M 136-4 C
Lt RR 1/2518818C M 61 -4 1
AC 6.0 CK S.A.
C O
Ct'Bt CS 6.9.23,40 3
M1364 C
Lt RR 1/CS68818D M 61 -4 AC 6.0 CK S. A.
C O
Ct Bt CS 6,9,23,40 3
M 136-4 C
Lt RR 1/2Sl8819A M 61 3 1
AC 2.0 CK S.A.
C O
Lt/Bt PJ1iCS 6,23.40 3
Mt 36-3 C
Ct RR VR-15 3
1/2 stb 819B M 61-3 1
AC 2.0 CK S.A.
C 0
LttBt FWCS 6.23.40 3
41363 C
Ct RR VR-15 3
1/2S18819C M 613 1
AC 2.0 CK S.A.
C O
Lt Bt FRCS 6.23,40 3
M136 3 C
Ct RR VR-15 3
1/2S18818D M 613 1
AC 2.0 CK S.A.
C O
Lt/Bt RRICS 6,23,40 3
M 136-3 C
Ct RR VR-15 3
1/2Sl8821 A M613 2
8 4.0 GA M.O.
O C/O St OP 1
M 136-3 ft RR 1/25188218 M 61-3 2
B 4.0 GA M.O.
O C/O St OP 1
4 136-3 ft RR 1/2518835 M-61 -3 2
B 4.0 GA M.O.
O C/O St CS 14 1
4 136-3 it M
1/2 sis 840 M 61 3 2
8 12.0 GA M.O.
C C/O St CS 14 1
M 136-3 ft RR 1/2St8841 A M613 1
AC 8.0 CK S.A.
C C
Lt AR M 136-3 O
CtPt CS VR 15 6.40 3
1/2Sl8841 B M 61-3 1
AC B.O CK S.A.
C C
Lt M
M136-3 O
Ct/Bt CS VR-15 6.40 3
4,3 VALVE TABLIS. PAGE 33 ef 42 pnvrpidocrmtd\\vaeves.ris
s 4
$NSERVICE TESTING PROGRAM PLAN CLASS 1. 2,3 AND AUGMENTED VALVES BYRON NUCLEAR POWER ST ATION UNITS O.1. 2 Reveen 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST RELIEF TECH.
NUMBER Pato CLASS CA TEGORY SIZE TYPE TYPE POSITION DIRECT.
METHOD MODE REQUEST NOTES POS.
REMARKS ONP (VR; (VA) 1/2Sl88 71 M 61-6 2
A
.75 GL A.O.
C C
St OP VR-12 1
M-136-6 Lt RR VR-1 PASSIVE It RR Ft OP 2
1/2Sf 8880 M 61-6 2
A 1.0 GL A.O.
C C
St OP 1
M 136-6 Lt RR VR-1 PASSIVE tt RR Ft OP 2
1/2 SIB 888 M 61-3 2
A
.75 GL A.O.
C C
St OP 1
M-136-3 Lt RR VR 1 PASSIVE lt RR Ft
'OP 2
1/2S18900A M 612 1
AC 1.5 CK S.A.
C O
Ct CS VR-15 3
M-136-2 C
Lt!Bt RR/CS 6.40 3
1/2S18900S M-61 -2 1
AC 1.5 CK S. A.
C O
Ct CS VM 15 3
M 136-2 C
Lt/Bt RR/CS 6.40 3
112S!8900C M 61 -2 1
AC 1.5 CK S.A.
C O
Ct CS VR-15 3
M-136-2 C
Lt.'Bt RR/CS 6.40 3
Il2 SIS 9000 M 612 1
AC 1.5 CK S.A.
C 0
Ct CS VR-15 3
M-136-2 C
t t.'9f RR/CS 6.40 3
1/2St8905A M 61-3 1
AC 2.0 CK S. A.
C O
Ct RR VR-15 3
M 136-3 C
Lt!Bt RR/CS
- 6. 40 3
1/2S189058 M 61-3 1
AC 2O CK S. A.
C O
Ct RR VR-15 3
M-136-3 C
Lt!Bt RRTS 6.40 3
1/2Sl8905C M 61-3 1
AC 2O CK S.A.
C O
Ct RR Vf&l 5 3
M-136-3 C
Lt/9t RR/CS 6.40 3
1/2S18905D M 613 1
AC 2.0 CK S. A.
C O
Ct RR VR-15 3
M 136-3 C
Lt/Bt RR/CS 6.40 3
1/2St0319A M 61 1 A 2
C 1.5 CK.
S. A.
C O
Ct OP 3
M 138-1 C
Bt C#
31 3
1/25t89199 M 61-1 A 2
C 1.5 CK S. A.
O O
Ct OP 3
M-136-1 C
Bt OP 31 3
4.3 VALVE TABLES - PAGE 34 of 42 i
p:1=pt.docmntavalves. sis m
m 3
E k
3 INSERVICE TESTING PROGRAM PLAN CLASS 1,2. 3 AND AUGMENTED VALVES BYRON NUCLEAR POWER STATtOM tJNITS O,1. 2
]
Revesson 12 VALVE VALVE VALVE
. VALVE ACT.
NORMAL STROKE TEST TEST RELIET 1ECH.
NUMBER P&lO CLASS CAT EGORY SIZE TYPE TYPE POSITION DIRECT.
METHOD MODE REQUEST NOTES POS.
REMARKS t
f tN )
(VR) tVA) 112S18920 M-61 1 A 2
B 15 GL M.O.
O-C St OP 1
M-136-1 ft RR 1/2S18922A M-61 1 A 2
C 4.0 CK S. A.
C.
O Ct RR VR 3 3
M-136-1 C
Bt
-OP 3
1/2S58922 B M-61-1 A 2
C 4O CK S.A.
C O
C1 RR VR-3 3
M 136-1 C
B1 OP 3
1/2516924 M-61 1 A 2
8 6.0 GA M.O.
O C/O St OP 1
M 136-1 R
RR 1/2S!8326 M-61-1 A 2
C-8.0 CK S.A.
C O
Ct/Xt C$iOP VR 6 25 3
M-136-1 1/2St8948A M 61-5 1-AC 10 0 CK S. A.
C C
M-136-5 0
Xt/Ct CS 42 3
1/25I83488 M-61 -5 1
AC 10.0 CK S.A.
C C
'3 M-136 5 0
xt/Ct CS 42 3
1/2S18948C M 61-6 t
AC 10.0 CK S. A.
C C
M 136-6 0
Xt/Ct CS 42 3
112S189480 M-61-6 1
AC 10 0 CK S. A.
C C
M-136 6 O
Xt'Cf CS 42 3
i 1/2518949A M-61-3 1
AC 60 CK S.A.
C C
Lt!81 RR/CS 6.40 3
M-136-3 O
Cr RR VR-15 3
112S189498 M 613 1
AC 6.0 CK S.A.
C C
Lt/8t RR/CS 6.40 3
M-136-3 O
Ct RR VR-15 3
1/2 SIS 949C M-61-3 1
AC 6.0 CK S. A.
C C
Lt/Bt RR/CS 6.40 3
M-136-3 O
Ct RR VR-15 3
1/2Sl89490 M 613 1
AC 6.0 CK S. A.
C C
Lt/8t RR/CS 6.40 3
M-138-3 O
Ct RR VR-15 3
112 SIB 956 A M-61-5 i
AC 10.0 CK S. A.
C C
Lt/8t CS VR-5 6
3 M 136-5 O
Ct RR VR5 3
1/2S183568 M-61-5 1
. 10 0 CK S. A.
C C
Lt:St CS VR-5 6
3 M-136-5 O
Ct RR VR5 3
1/2 stb 956C M-61-6 1
AC 10.0 CK S. A.
C
.C Lt/Bt CS VR-5 6
3 M-136-6 0
Ct RR V45 3
4.3 VALVE TABLES - PAGE 35 of 42 pSwgAdocmritd\\ valves.xis
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MsERVICE TESTING PROGRAM PtJG4 Q. ASS 1,2,3 AND AUGMENTED VALVES 8YRON NUCLEAR POWER STATION UNITS 0,1,2 hsien 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TEST REL2EF TECH.
NUMBER PMD CLASS CATEGORY SIZE TYPE TYPE POSITION DERECT.
METHOD MODE REQUEST NOTES POS.
REMARKS flN )
fVRi OfA) 1/2St99500 4510 1
C Lt/Bt CS VR-S 6
3 M136-6 O
Ct PR VR 5 3
1/2SI8958A MS) 4 2
C-12.0 CK S.A.
C O
Ct CS 9
3 4 136-4 C
8t OP 27 3
1/25889588 4 61-4 2
C 12.0 CK SA C
O Ct CS 9
3 4 136-4 C
Bt OP 27 3
112S88964 M 61-0 2
A
.75 GL A O.
C C
St OP 1
M 136-6 Lt RR VR)
1/2588968 M 61-6 2
AC 1.0 CK S.A.
C C
Lt/Bt RR/CS VR-1 39 3
PASSIVE M136 6 4.3 VALVE TABLES-PAGE 36 of 42 p:\\wpWocrmtevefwee.mte
2 W
tNSERVICE TESTING PROGRAM PLAN CLASS 1,2, 3 AND AUGMENTEO VALVES BYRON NUCLEAR POWER STATtON UNITS 0,1, 2 Revisen 12 VALVE VALVE VALVE VALVE ACT NORMAL STROKE TEST TEST REttEF NOTES TECH.
RLMARKS NUMBER P&tD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
METHOD MODE REQUEST POS.
IIN l (VR)
(VA) 1/2SXOO2A 4 42-1 B 3
C 36.0 CK S.A.
C O
Ct OP 3
C Bt OP 3
1/2SXOO2B M4 2-1 A 3
C 3S O CK S A.
C O
C Bt OP 3
OSXOO7 M42-2A 3
8 24.0 BIF M.O.
C 0
St OP 1
It RR 1/2SX016A M 42-SB 2
B 16_O BTF M.O.
O O!C St OP 1
41263 ft RR 112SX0168 M4 2-5A 2
B 16.0 BIF M.O.
O 0, C St OP 1
M 126 3 It RR 1/2SX027A M 42-5B 2
8 16.0 BTF M 0.
O O/C St OP 1
41263 ft RR 1/2SXO278 M42 5A 2
8 16.0 BIF M O.
O O/C St OP 1
41263 ft RR CSXO2BA M 42-6 3
C B.O CK S.A.
C 0
C1 OP 3
C Bt OP 3
OSX0288 M42-6 3
C 8.0 CK S.A.
C 0
Ct OP 3
C Bt OP 3
II2SX101 A M-4 2-3 3
8 1.5 GL S.O C
O St OP VR-17 M-1281 Ft OP 2
1/2SX112A M4 2-3 3
8 12.0 BTF A.O.
O C
St OP 1
41261 ft RR Ft Op 2
II2SX1128 4 42-3 3
B 12.0 BIF A.O.
O C
St OP 1
1/2SX114A M42-3 3
B 12.0 BIF A.O.
O C
St OP 1
1/2SX114B M4 2-3 3
8 12.0 BIF A.O.
O C
St OP 1
1/2SX116A M42-28 3
C 3.0 CK S.A.
O O
Ct OP 3
M42-2B 1/2SX1168 442-2A 3
C 3.0 CK.
S.A.
O O
Ct OP 3
442-2A OSX146 M 42 2A 3
8 30.0 81F M.O.
C O
St OP 1
It RR OSX147 M4 2-2A 3
8 30.0 BIF M O.
C O
St OP 1
ft RR 4.3 VALVE TABLES - PAGE 37 of 42 pawpWocmr.Mwelves.x!s
I.
' QNSERVICE TESTING FAOGRAM Pl.AN C1. ASS 1,2. 3 AND AUGMENTED VALVES BYRON NUCLEAR POWER STATON UNITS 0.1. 2 Receion 12 VALVE VALVE VALVE VALVE ACT.
f40RMAL 61ROKE TEST TEST REUEF NOTES TECH.
REMARKS NUMBER P&O CLASS CATEGORY St?E TYPE TYM POSITION DIRECT.
METHOD MODE REQUEST POS.
(fN )
(VR)
(VA) 1/2SA14 7 A M4 2-3 3
8 16.0 BIF S. O.
N/A O
Ft OP M126-1 1/2SX1478 4 42-3 3
8 16.0 BTF S.O.
N/A O
Ft OP M126-1 Il2SX189A M42-3 3
8 10.0 STF A.O.
C O
St OP 1
Il2SX1698 M 42-3 3
8 10.0 STF A.O.
C O
St OP 1
1/2SX173 M42 3 3
8 6.0 GA A.O.
C O
St OP 1
M126-1 Ft 09 2
If2SA174 4423 3
C 6.0 CK S.A.
C 0
Ct OP 3
M 126-1 1/2SK178 M42-3 3
B S.O GA A.O.
C O
St OP 1
M126-1 Ft OP 2
4.3 VALVE TABLES - PAGE 38 of 42 pdwpWocrr stAwelves.xle
INSERVICE TESTING PROGRAM PLAN CLASS 1. 2. 3 AND AUGMENTED VALVES BYRON NUCLEAR POMR STATION UNITS O,1, 2 Reeseen 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST TESI REUEF NOTES TECH.
REMARKS NUMBER P&tD CLASS CATEGORY St2E TYPE TYPE POSITION DIRECT.
METHOD MODE REOUEST
- POS, ON }
(VR1
{VA) 1/2VOOO1A M 105-1 2
A 48.0 BTF H.O.
C C
Lt S
VR1 11 M106-1 St CS 11 1
PASSIVE ft RR If 2VOOO1 B M 105-1 2
A 48.0 BIF H O.
C C
Lt S
VR1 11 84106 1 St CS 11 1
PASSNE tt RR 112VOOO2A M 1041 2
A 48.0 BIF H.O.
C C
Lt S
VR1 11 M106-1 St CS 11 1
PAS $1VE tt RR 1/2VOOO28 M 105-1 2
A 48.0 BIF H.O.
C C
Lt S
VR1 11 M1061 St CS 11 1
PASSIVE lt RR 1/2VQOO3 fA 105-1 2
A 8.0 BIF A.O.
C C
Lt OP VR 1 11 M106-1 St OP 1
PASSIVE tt RR 1/2VOOO4A M 105-1 2
A S.O BIF A.O.
C C
Lt OP VR1 11 M1061 St OP 1
PASSIVE It PR 1/2VQOO4B M 105-1 2
A 8.0 BIF A.O.
C C
Lt OP VR-1 11 M106-1 St OP 1
PASSIVE tt m
1/2VOOO5A M 105-1 2
A 8.0 BTF A.O.
C C
PASSIVE lt RR 1/2VOOO58 PA 105-1 2
A B.O BTF A.O.
C C
Lt OP VR1 11 4 106-1 St OP 1
PASSIVE lt RR 1/2VOOOSC M 105-1 2
A 8.0 BTF A.O.
C C
Lt OP VR1 11 M 106-1 St OP 1
PASStVE tt M
4.3 VALVE TABLES - PAGE 39 of 42 pdwpWocnntdivalves.xts
INSER%1CE TESTO3G PROGRAM PLAN CLASS 1. 2,3 AND AUGMENTED VALVES BYRON NUCLEAR POWIR STAT!ON UNITS O,1. 2 R.woon 12 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE TEST 1EST fEUEF NOTES TECM.
REMARKS NUMBER P&tD CLASS CATEGORY SCE TYPE TYPE POSITION DIRECT.
METHOD MODE REQUEST POS.
ftN )
WR)
NA) 1/2VQO10 M 105-3 2
A C.5 GL M
C C
Lt RR VR1 PAS $fVE 1/2VOC17 M-105-3 2
A O.5 GL M
C C
Lt RR VR1 PASSIVE II2VO318 M 105-3 2
A 0.5 GL M
C C
Lt RR VR1 PASSIVE 1/2VQO19 4 105-3 2
A 0.5 GL M
C C
Lt RR VR1 PASSIVE 4.3 VALVE TABLES. PAGE 40 of 42 t
l l
i
[
p:\\w,w crentav hr ici.
EeSERVICE TESTC#G PROGRAM PUWI CLASS 1,2. 3 AND AUGAENTED VALVES BYBON NUCLEAR POWER STATION UNITS O,1, 2 Rev ean 12 VALVE VALVE VALVE VALVE ACT.
NO60AAL S1ROKE TEST TEST RE1JEF NOTES
- TECH, REMARKS NUMBER P&lD CIASS CATEGORY SIZE TYPE TYPE POStTION
- DIRECT, WTHOD MODE REQUEST POS.
[1N )
(VR)
(VA) 1/2WM190 M4 9-1 A 2
A 20 GL M
C C
Lt RR VR1 PASSfvE M49-1B f
Il2WM191 M 49-1 A 2
C Lt RR VRr1 3
PASStVE i
M 49-1 B l
4.3 VALVE TABLES-PAGE 41 of 42 p:twpWocnydd\\ valves.mte
NSEENICE TESTNG fHOGl%M PLAN CLASS 1. 2. 3 AND AUGMENTED VALVES BYRON M> CLEAR POWER STAT 10N UNITS 0.1. 2 Revimon 12 VALVE VALVE VALVE VALVE ACT.
NOHP.%L STROKE 1EST TEST REUEF NOTES TECH.
REMAfES NtAEER P8 eld CLASS CATEGORY SIZE TYPE TYYY POSITION DIRECT.
METHOD MODE REQUEST POS.
(tN 1 (VR)
(val 1/2WOOOSA St OP 1
M 118-5 2
A 10 0 GA M O.
O C
Lt RR VR1 41187 ft PR 1/2WOOO58 St OP 1
M118 5 2
A 10.0 GA MO.
O C
Lt P!R VRr1 M.118-7 ft RR 1/2WOOO7A M118-5 2
C C
Lt/81 RR VRI. 24 3
PAS $1VE M 118-7 It2WOOO78 4 118-5 2
AC 10.0 CK S.A.
C C
Lt/8t RR VR 1, 24 3
PASStVE M 118-7 1/2 WOO 20A St OP 1
M 118-5 2
A 10 0 GA M.O.
O C
Lt RR VS1 4118-7 it RR If 2 WOO 206 St OP 1
M118-5 2
A 10.0 GA M O.
O C
Lt RR VR1 M118 7 N
M 112 WOO 50A St OP 1
M-118 5 2
A 10.0 GA M O.
O C
Lt RR VR1 M118 7 it RR II2 WOO 5SS St OP 1
M118-5 2
A 10.0 GA M O.
O C
Lt RR V41 4 118-7 h
RR 4.3 VALVE TABLES-Page 42 of 42 p:twptdocrmtd\\vahreexa
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.s a a 2.._2.s 4.a s1 SECTION 4.4 NOTES 4
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- - - - - -- _______ _ - - _ _ -. _ _, -.i_
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Rev. 12 NOTE 1 Closure of the Main Steam isolation valves 1MS001A-D or 2MS001A-D during unit operation would result in reactor trip and safety. injection actuation. To avoid this transient, these valves will be partially stroked every'three months.
Full stroke testing will be done during Modes 4, 5, or 6 as plaat conditions allow, per 1WV-3412.
NOTE.2 The testing of any emergency boration flowpath valves during unit operation is not practical.
Stroke testing the Boric Acid injection isolation valve ICV 8104/2CV8104 and check valve 1CV8442/2CV8442, the RH to CV pump suction isolation valve ICV 8804A/2CV8804A, or the RWST to CV pump suction isolation i
valves 1CV112D,E/2CV112D,E, - could result in boration of the RCS, resulting-in a cooldown transient. Aligning the system in this configuration even for a short duration is, therefore, unacceptable. These valves will be stroked tested during cold shutdown, in accordance with IWV-3412.
HQTE 3 These valves are the Main Feedwater isolation valves:
1FWOO9A-D/2FWOO9A-D, and cannot be fully stroked during operation as feedwater would be terminated-causing a reactor trip. They will, however, be partially stoke tested during
)
operation as well as full stroke tested during cold shutdown, per the requirements of IWV-3412.
NOTE 4 Closure of these letdown and makeup valves 1CV112B,C/2CV112B,C, ICV 8105/2CV8105, ICV 8106/2 CV8106, ICV 8152/2CV8152 and ICV 8160/2CV8160 during j
normal unit operation would cause a loss of charging flow which would result I
in a reactor coolant inventory transient, and possibly, a subsequent reactor trip. These valves will be fully stroke / fail safe exercised during cold
]
shutdown as required by IWV-3412.
NOTE 5 The 1RH8701A/B, 1RH8702A/B, 2 RH8701A/B, and 2RH8702A/B valves are the isolation boundary between the Residual Heat Removal pumps and the' Reactor Coolant System.
Opening one of these valves during unit operation will_ leave j
only one valve isolating RHR from the high RCS pressure. This would place the
)
plant in an undesirable condition. Therefore, these valves will be full stroke tested during cold shutdown, per IWV-3522.
J
)
' l
-(9998D/WPF/022194) 4.4 page 1 of 10 i
m
Rev. 12 NOTE 6 The following valves have been identified as intersystem LOCA valves. They form a pressure boundary between the RCS and other essential components in order to protect these components from damage. These valves will be leak tested in accordance with the Byron Technical specifications.
Performance of the leak test on these valves also satisfies the back-flow test required for.
check valves by NRC Generic Letter 89-04.
Byron Unit 1 and Unit 2 Intersystem LOCA Valves 1RH8701A/B 1RH8702A/B 2RH8701A/B 2RH8702A/B 1RH8705A/B*
1SI8815 2RH8705A/B*
2SI8815 ISI8818A-D ISI8905A-D 2SI8818A-D 2SI8905A-D-1SI8819A-D 1SI8948A-D 2SI8819A-D 29IB948A-D ISI8841A/B 1SI8949A-D 2SI8841A/B PSI 8949A-D ISI8900A-D 1 SIB 956A-D 2SI8900A-D 2SI8956A-D
- Not true pressure isolation valves - not listed in Tech Specs.-
FOTE 7 The Reactor Pressure' Vessel Vent Valves 1RC014A-D and 2ROO14A D cannot be stroked during unit operation, as they provide a pressure' boundary between the Reactor Coolant system and containment atmosphere.
Failure of one of these valves in the open position would result in leaving only one valve as the high pressure boundary. These valves will be full stroke / fail safe exercised when the RCS pressure is at a minimum during cold shutdown, per IWV-3412.
NOTE 8 The Residual Heat Removal Pump discharge check valves 1RH8730A/B and 2RH8730A/B cannot be full stroke exercised during unit operation due to the high RCS pressure. These check valves will be partial stroke tested, however, on a quarterly basis and full stroke exercised during cold shutdown. This is in accordance with IWV-3522.
NOTE 9 Due to the RCS pressure, the check valves listed below cannot be full stroke exercised during unit operation:
ISI8818A-D 2SI8818A-D RHR Cold Ieg Injection 1SI8958A/B 2SI8958A/B RWST to RHR Pump Suction These valves will be full stroke exercised during cold shutdown, in accordance with IWV-3522.
(9998D/WPF/022194) 4.4 - page 2 of 10
Rev. 12'
?
NOTE 10 The 1FWO39A-D and 2FWO39A-D valves cannot be stroke tested during unit operation as closure of these valves would result in termination of the waterhammer prevention feedwater flow.
This would result in undesirable affects on the System Generators.
These valves will be full stroke / fail safe tested during cold shutdown, per IWV-3412.
NOTE 11 The Primary Containment Purge Supply and Exhaust Valves IVQ001A/B, IVQ002A/B, 2VQ001A/B, and 2VQ002A/B cannot be stroke timed during unit operation. These 48-inch valves are the only isolation points between the containment atmosphere and the environment. Stroking these valves at any time other than mode 5 or 6 would be a violation of the Byron Technical Specifications. These valves will be full stroke tested during cold shutdown, in accordance with IWV-3412.
These valves will be leak tested semiannually, in accordance with Byron Station Technical Specifications.
The Primary Containment Mini-Purge and Fxhaust Valves IVQ004A/B, IVQ005A/B/C, 2VQ004A/B, and 2VQ005A/B/C, and the Post LOCA Purge Exhaust Valves IVQOO3/2VQOO3 will be leak tested every 3 months, in accordance with Byron Station Technical Specifications.
NOTE 12 The Auxiliary'Feedwater check valves 1AF001A/B, 1AF003A/B, 1AF014A-H, 1AF029A/B, 2AF001A/B, 2AF003A/B, 2AF014A-H, and 2AF029A/B cannot be. full stroke tested during unit operation, as this would induce potentially damaging thermal stresses in the upper feedwater nozzle piping.
The 1AF001A/B, 1AF003A/B, and 2AF003A/B valves will be partially stroke tested during operation, and all valves full stroke tested during cold shutdown. This will be performed per Tech Spec 4.7.1.2.2 and is in accordance with 1WV-3522.
NOTE 11 The High Head Injection Isolation Valves ISI8801A/B and 2 SIB 801A/B cannot be stroke tested during unit opezation.
These valves isolate the CV system from the RCS.
Opening them during operation would enable charging flow to pass directly into the RCS, bypassing the regenerative heat exchanger.
The temperature difference of the charging flow and the RCS could result in damaging thermal stresses to the cold leg nozzles as well as cause'a reactivity change which would, in turn, cause a plant transient. These valves-will be full stroke tested during cold shutdown in accordance with IWV-3412.
4 (9998D/WPF/022194) 4.4 - page 3 of 10
~
.Rev. 12 NOTE 14 The safety injection system SVAG (Spurious Valve Actuation Group) valves ISI8802A/B, 1 SIB 806, 1SI8809A/B, ISIB813, 1SI8835, 1SI8840, 2SI8802A/B, 2SI8806, 2SI8809A/B, 2SI8813, 2SI8835, and 2SI8840 cannot be stroke testen during unit operation..These valves are required by the Technical Specifications to be dc-energized in their proper positions during unit operation. Stroking them would be a violation of the Technical Specifications as well as-defeating the de-energized SVAG valve principle. These valves will be stroke tested during cold shutdown when they are not required to be de-energized. This is in accordance with IWV-3412 NVTE 15
" DELETED" NOTE 16 These feedwater valves are exempt from all ASME Section XI testing requirements per IWV 1100 and 1WV-1200.
They are included in the program for operability tracking purposes only. The closure of the Main Feedwater Regulating Valves 1FW510, 1FW520, 1FW530, 1FW540, 2FW510, 2FW520, 2FW530, and 2FW540 during unit operation would cause a loss of feedwater to the steam generators, resulting in a plant transient with a possible reactor trip as a result. These valves will be fail safe (Ft) tested pursuant to the Byron Station Technical Specifications.
NOTE 17 These feedwater valves are exempt from all ASME Section XI testing requirements per IWV-1100 and IWV-1200.
They are included in the program for operability tracking purposes only.
The closure of the Main Feedwater Regulating Bypass Valves 1FW510A, 1FW520A, 1FW530A, 1FW540A, 2FW510A, 2FW520A, 2FW530A, and 2FW540A during unit operation would require the Main Feedwater Regulating Valves to correct for bypassed flow and could result in a plant transient with a possible reactor trip as a result. These valves will be fail safe (Ft) tested pursuant to the Byron Station Technical Specifications, NOTE 18
" DELETED" NOTE 19
" DELETED" (Incorporated into NOTE 14)
(9998D/WPF/022194) 4.4 - page 4 of 10
. - ~
l Rev.-12 NOTE 20
-l The remote position indicator for these valves'cannot be observed'directly due to the encapsulated design of the solenoid valve body.
During the indication.
test, indirect evidence of the necessary valve disk movement shall~be used, in accordance with IWV-3412 (b).
These valves affected are listed below:
1CV8114 1PS230A/B 2PS228A/B 1CV8116 1RC014A-D 2PS229A/B 1PS228A/B 2CV8114 2PS230A/B 1PS229A/B 2CV8116 2RC014A-D NOTE 21 The Main Feedwater Tempering Flow Isolation Valves 1/2FWO34A-D are exempt..from all ASME Section XI testing requirements per IWV-1100 and'IWV1200.
They are included in the program for operability tracking purposes only, and will be fail safe (Ft) tested pursuant to the Byron Station Technical Specifications.
NOTE 22 Per NRC request, the post-accident hydrogen monitoring system check valves 1/2PS231A and 1/2PS231B will be stroke exercised open on a quarterly frequency to verify operability.
NOTE 23 1/2SI8818A-D, 1/2SI8819A-D, and 1/2SI8948A/B are Ev'ent V check valves, which are defined as two check valves in series at a low pressure /RCS interface whose failure may result in a LOCA that bypasses containment. They are individually leak-tested in accordance with NRC generic letter 89-04,. position
- 4b.
NOTE 24 1/2CC9518, 1/2CC9534, 1/2CV8113, and 1/2RH8705A/B are check valves designed-to relieve pressure between two containment isolation valves..The full flow limiting value is zero, since the safety function of these valves in the open direction is to relieve pressure only.
(9998D/WPF/022194 )
4,4. page 5 of 10
Rev. 12 NOTE 25 Check valve 1/2SI8926 prevents flow from the Safety Injection (SI) pump suction line to the Refueling Water. Storage Tank (RWST).
The SI pumps are normally lined up in the INJECTION MODE to take suction f rom the RWST.
This check valve would stop reverse flow when the SI pumps are transferred to HOT / COLD LEG RECIRCULATION MODE to prevent contamination of the RWST.
However, the 1/2SI8806 M.O.V.
is in series with this check valve and would be closed to prevent reverse flow as directed by the emergency procedures.
Therefore, no backflow test (:Bt) is required for 1/2SI8926.
NOTE 26 Check valve 1/2CV8546 prevents flow from the Chemical and Volume Control (CV) pump suction line to the Refueling Water Storage Tank (RWST). The CV pumps are normally lined up in the INJECTION MODE to take suction from the RWST.
This check valve would stop reverse flow when the CV pumps are transferred to HOT / COLD LEG INJECTION MODE to prevent contamination of the RWST.
- However, the 1/2CV112D and 1/2CV112E M.O.V.'s are in series with this check valve and would be closed to prevent reverse flow as directed by the emergency procedures. Therefore, no back flow test (Bt) is required for 1/2CV8546.
NOTE 27 Check valves 1/2SI8958A/B prevent flow from the Residual Heat (RH) Removal pump suction line to the Refueling Water Storage Tank (RWST). The RH pumps are normally lined up in the_ INJECTION MODE to take suction from the RWST.
These check valves would stop reverse flow when the RH pumps are transferred to HOT / COLD LEG RECIRCULATION MODE to prevent contamination of the RWST.
The 1/2SI8812A/B M.O.V 's are in series with these check valves and would be closed to prevent reverse flow as directed by the emergency procedures.
In addition, the RH suction valves 1/2SI8812A/B, 1/2RH8701A/B or 1/2RH8702A/B, and 1/2 SIS 811A/B are electrically interlocked to prevent the backflow to the RWST when the RH system is in a RECIRCULATION MODE.
However, during the injection mode, if a pump fails to start, these values are relied upon to prevent diversionary flow back to the RWST.
NOTE 28 The 1/2CV8440 check valves allow seal water return to the suction of the.CV pumps. During the hot leg recirculation phase of an SI, the VCT. outlet check valve prevents diversionary flow back to'the VCT via the seal water heat exchanger relief valve, which could potentially lead to an unfiltered release of radioactivity to the environment. These valves can only be tested in cold shutdown, when all 4 RCPS and charging pumps are off.
Refer to CHRON
- 0117821, dated November 23, 1992.
9998D/WPF/022194) 4.4. page 6 of-10
(
- ~.
.~
Rev. 12 NOTE 29 Check valve 1/2CV8442 prevents flow from the Chemical and Volume Control.(CV) pump suction header to the boric acid transfer pump. This line is normally isolated by-the 1/2CV8104 emergency boration valve. This valve would only be opened during an emergency with the boric acid transfer pump running. This check valve is unnecessary with the current system operation, and thus, no back flow testing of 1/2CV8442 is required.
NOTE 30 Check valves 1/2AF014A-H are verified to be closed each shift by the Operating Department, by verifying that the temperature at 1/2AF005A-H is s 130*F, per l
BOP 199-A40 (U-1) and BOP 199-A61 (U-2).
If the temperature is > 130 F at any 1/2AF005 valve, then abnormal operating procedure 1/2 BOA SEC-7, " Auxiliary Feedwater Check Valve Leakage", is entered to isolate and cool down the affected lines. This shiftly monitoring of 1/2AF014A-H in the closed position adequately monitors the status of these valves during unit operation.
i NOTE 31 Check valves 1/2CV8480A/B and 1/2SI8919A/B are the Centrifugal Charging Pump and Safety Injection Pump mini-flow recirculation line valves which open to prevent full recirculation flow during IST Surveillances.
Since full stroke for these valves will depend on the reference point of testing, acceptable full stroke will be verified whenever the recorded mini-recirculation flowrate is within the " acceptable" or " alert" ranges given in the IST Pump Surveillance.
EOTE 32
" Deleted" NOTE 33 The Essential Service Water (SX) and Make-Up Pump discharge' check valves (OSX028A/B) open to permit make-up water flow from the Rock River to the SX System Basin. These check valves are downstream at the pump discharge tap-off to the SX Make Up Jacket Water Heat Exchanger and Gear Oil Cooler. Since this tap off line is orificed, the.flowrate through this line, and therefore.the flowrate through pump discharge check valves OSX028A/B, will depend on the reference point of testing. Acceptable OSX028A/B full stroke will be verified whenever the recorded total pump flow minus the tap-off line flow is within
" Acceptable" range contained in the ASNB pump surveillance.
(999 8D/WPF/022194 )
4.4 - page 7.of 10
Rev. 12 NOTE 34 Per Byron Technical Specifications Amendment valves 1/2SD002A-H, 1/2SD005A-D have been removed from the list of valves to be tested under 10CFR50 Appendix J and will now be tested per ASNE Code Section XI, IWV-3420.
NOTE 35 The 1/2RH8705A/B check' valves will operability tested by verifying that there is depressurization in line 1/2RH26AA-3/4 and 1/2RH26AB-3/4 when they are
~
opened. This is a test method which was approved by the NRC in SER 09/14/90.
NOTE 36 PORV's 1/2RY455A and 1/2RY456 will be stroke tested on a cold shutdown frequency and valves 1/2RY8025, 1/2RY8026, 1/2RY8028, 1/2RY8010A, 1/2RY8010B, 1/2RY8010C, 1/2RY8033, 1/2RY8000A, 1/2RY8000B, 1/2RY455A and 1/2RY456 will receive position indication tests on a refuel frequency per Generic Letter 90-06.
e NOTE 37 The Process Radiation Containment Isolation check valves 1PR032 and 2PR032 cannot be back flow tested during unit operation due to their' location. The test method used to backflow test these valves requires' containment entry.
These valves will be backflow tested during cold shutdown.
NOTE 38 The Process Sampling Hydrogen Monitor Containment Isolation check valves
'1PS231A, B and 2PS231A, B cannot be back flow tested during unit operation due to their location. The test method used to backflow test these valves requires containment entry. These valves will be backflow tested during cold
' shutdown.
i NOTE 39 The Nitrogen Supply to the SI Accumulator Containment Isolation check valves 1SI8968 and 2SI8968 cannot be backflow tested during unit operation due to their location. The test method used to backflow test these valves requires containment entry. These valves will be backflow tested during cold shutdown.
(9998D/WPF/022194 )
4.4 - page 8 of 10
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Rev. 12
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NOTE 40 The following valves are backflow tested.by way of a seat leakage test.
These valves are inside containment and cannot be tested without entering containment, Since it is not radiologically prudent to make containment entries for routine testing, these valves will be backflow tested during cold
- shutdown, i
1/2SI8815 1/2SI8900A-D 1/2SI8818A-D 1/2SI8905A-D
~
1/2SI8819A-D 1/2SI8949A-D i
1/2SI8841A,B NOTE 41 The RH Hot Leg Suction Pressure Relief Check Valves (1/2RH8705A,B) are full stroke and backflow tested using a method which requires containment entry.
Since it is not radiologically prudent to make containment entries for routine testing, these valves will be full stroke and backflow tested during cold shutdown.
NOTE 42 The 1/2SI8948A-D Safety Injection Cold Leg Pressure Isolation Valves cannot be tested during plant operation due to the high pressure of the RCS system relative to the pressures attainable through the RH and SI pumps.
They will be full flow and backflow tested at cold shutdown, i
NOTE 43 The 1/2RH8716A/B "RHR Cross Tie" valves are out-of-service open per Technical Specifications and can only be exercised during cold shutdown or refuel.
NOTE 44 The 1/2CC9415 valves are motor operated 16" Gate valves and are in the supply.
line to the RCPs and other non-essential Component Cooling Water loads. They close to isolate non-essential loads from essential loads during accident conditions. These valves may only be closed with all 4 RCPs off.
Therefore, these valves will be tested at Cold Shutdown with all 4 RCPs off.
Refer to VR-8 for additional information.
(9998D/WPF/022194) 4.4 - page 9 of 10
Rev. 19 NOTE 45 The feedwater tempering flow check valves (1/2FWO36A-D) are open during
- full /high power operation to ensure the S/G upper nozzle subcooled margin is maintained above the 75'F minimum. They also open to allow tempering flow during shutdown and startup. The close to provide an immediate isolation function during a feedwater line break accident to mitagate a loss of i
secondary make-up and/or inventory.
^
These are 3 inch swing type check valves with no position indication. Flow through this line at full /high power cannot be stopped for longer than one minute while in Mode 1.
Also, flow / pressure is always toward the Steam Generators (S/Gs) during operation, making it impractical to perform a back.
leakage or back pressure test to prove valve closure. Theses check valves' will be tested during cold shutdowns using non-intrusive techniques to prove.
valve closure.
NOTE 4 6 These valves (1/2FWO79A-D) are the main feedwater header flow check valves.
They open to allow main feedwater flow during power operation. They close to provide an immediate (2 to 3 second) isolation function during a feedwater line break accident to mitigate a loss of secondary make-up and/or inventory.
The safety function in the close position is to provide pressure integrity of l
the piping between the safety related portion and the non-safety related portion. They are 16 inch tilting disc type check valves utilizing a piston
')
and rod assembly as an anti-slam mechanism..These check valves have no j
external position indicators to provide disc position. Also, flow / pressure is j
always toward the Steam Generators (S/Gs) during normal operation, making it.
{
impractical and unsafe to perform a back leakage or back pressure test to j
prove valve closure on a quarterly basis. The main feedwater flow check j
valves cannot be stroked closed during power operation without causing a i
reactor trip due to low S/G 1evel.
These check valves will be tested during cold shutdowns when bonnet
_)
temperature is less than 100 F using ultrasonic techniques to prove closure.
Closure is determined by the piston rod height as measured using an ultrasonic straight beam technique, similar to that used for measuring the height of sediment in a pipe. A transducer is placed on the piston cylinder and the backwall is brought up (range / depth and amplitude) on the scope above the
}
piston. As the transduce is lowered, the backwall signal will decrease, while the top of the piston rod signal starts to appear. This transition zone is used to give the disc position, since the piston rod is connected to the disc.
1 (9998D/WPF/022194) 4.4 - page 10 of 10
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SECTION 4.5
)
TECHNICAL APPROACHES AND POSITIONS 1
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1 1
1 1
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Rev. 12 VA-01 IST Technical Approach and Position A.
Comoonent Identification:
1.
==
Description:==
Method of Stroke Timing Valves - Timing using control board position indication lights (St).
2.
Component Numbers:
See IST Valve Tables.
3.
References:
ASME Code,Section XI, Subsection IWV, paragraph IWV-3413 (a).
4.
Code Class:
1, 2,
and 3.
5.
Examination Category (s)
N/A.
6.
Item Number (s) :
N/A.
B.
Reauirement:
Use of the control board open and closed lights to determine the stroke time of power-operated valves has recently become an issue for liscussion in the industry.
Paragraph IWV-3413 of ASME XI defines
' full-stroke time" as "that time interval from initiation of the actuating signal to the end of the actuating cycle."
It is common industry practice to measure stroke time as the time interval between placing the operator switch on the control board in the "close" or "open" position and indication that the valve is open or closed on the control board (switch to light).
C.
Position:
It is required that the way in which the limit switch that operates the remote position indicator lights is set may result in " closed";or "open" indication before the valve obturator has actually completed its travel, this is not considered to be a problem, as the purpose of the test is to determine if degradation of the valve operator system is occurring, which is determined by observing changes in stroke time relative to the reference stroke time.
Stroke time measurements should be rounded to the nearest tenth (0.1) of a second, except that stroke times less than one half (0.5) second may be rounded to 0.5 second, if appropriate.
Standard rounding techniques are to be used when rounding stop watch readings during valve stroke time testing (e.g.,
10:45 rounds to 10.5 and 10.44 rounds to 10.4).
Rounding to the nearest second for stroke
{
' times of 10 seconds of less, for 10% of the specified limiting stroke i
time for stroke times longer than 10 seconds, as allowed by-ASME Section.
XI subparagraph IWV-3413 (b), should not be used.
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(9998D/WPF/021694) 4.5 - page 1 of 14
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Rev. 12
+
VA-02 IST Technical Approach and Position A.
Comoonent Identification 1 1.
==
Description:==
Method of Fail Safe Testing Valves.
2.
Component Numbers:
See IST Valve Tables (Ft).
3.
References:
ASME Code,Section XI, Subsection IWV, paragraph IWV-3413.
4 Code Class:
1, 2,
and 3.
S.
Examination Category (s) :
N/A, 6.
Item Number (s) 1 N/A.
B.
Recuirement:
Paragraph IWV-3415 of ASME XI states that "When practical, valves with fail-safe actuators shall be tested by observing the operation of the valves upon loss of actuator power."
Most valves with a fail-safe mechanism to stroke the valve to the fail-safe position during normal operation.
For example, an air-operated valve that. fails-closed may use air to open the valve against spring pressure.
When the actuator is placed in the closed position, air is vented from the diaphragm and the spring moves the obturator to the closed position.
C.
Position:
In the cases where normal valve operator action moves the valve to the 4
closed position by de-energizing the operator electrically, by venting air or both (e.g., an electric solenoid in-the air system of a valve operator moves to the vent position on loss of power), no additional fail-safe testing is required. Valves with fail-safe actuators.that do not operate as part of normal actuator operation must be tested by other This may be accomplished for motor-operated valves by opening means.
the circuit breaker supplying operator power and observing.that the valve moves to its fail-safe position. Lifting leads is not required unless it is the only method.of de-energizing the actuator.
Using a valve remote position indicator as verification of proper fail-safe operation is acceptable, provided.the' indicator is periodically verified to be operating properly as required by ASNE Code,Section XI, Subsection IWV, paragraph IWV-3300.
(9998D/WPF/021694) 4.5 - page 2'of 14
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Rsv. 12-VA-03 IST Technical Approach and Position-A.
Cgmoonent Identification:
1.
==
Description:==
Method of Full Stroke (Ct) and Back Flow (Bt)
Exercising of Check Valves.
2.
Component Numbers:
See IST Valve Tests (Ct and Bt).
~
3.
References:
(a) NRC Generic Letter 89 04, Guidance on Developing Acceptable Inservice Testing Programs, Attachment 1, Positions.1, 2, and 3; (b) ASME Code,Section XI, Subsection IWV, paragraph IWV-3522.
4.
Code Class:
1, 2,
and 3.
5.
Examination Category (s). N/A.
6.
Item Number (s) : N/A.
B.
Recuirement:
Paragraph IWV-3522 of Article XI states
" check valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation.
If only limited operation is practical during plant operation, the check valve.shall be part-stroke exercised during plant operation and full-stroke exercised during cold shutdowns." For check valves'with no' external position indication devices, the determination of when they are in full;open position has proven difficult to detennine. The verification of when a valve is in the full open position affects the determination of which valves are only part stroked and thus require additional full-stroke testing during cold shutdown or refuelings.
]
C.
Position 1 Valid full stroke exercising to the full-open or full closed position
-j may be accomplished by observing an external position indicator which is considered to be a positive means of determining obturator position.
Where external position indicators are not provided, manual stroking of-the valve is acceptable.
Where a mechanical exerciser is used, the torque required to move the obturator must be recorded and meet the acceptance standards of subparagraph IWV-3522 (b).
Per the requirements of the NRC Generic Letter 89-04, Attachment 1, Position 1, the other acceptable method of full-stroke exercising a check valve to the open position is to verify that the valve passes the maximum required accident condition flow. Any flow less than this is considered as a part-stroke exercise.
Flow through the valve must be determined by.
positive means such as permanently installed flow instruments, temporary flow instruments, or by measuring the pressure drop across the valve or other in-line component. Measuring total flow through multiple parallel lines does not provide verification of flow through individual valves.
(9998D/WPF/021694) 4.5 - page 3 of 14
Rev. 12 C.
Position: (continued)
One exception to the " maximum required accident flow requirement is the a
methodology used to verify full-stroke exercising ~of the Safety Injection (SI) Accumulator Back-up Check Valves, 1/2SI8956A-D. Becauce of the high maximum design flowrate of the valves, a maximum design accident flowrate test is physically impossible to perform.
For those valves, an Engineering calculation has been performed to determine the minimum flowrate for full dise lift. An acceptable full stroke exercise of these valves will be performed each refueling outage by measuring the accumulator level decrease over time, converting these parameters to a flowrate through the valve, and verifying this value is greater-than or equal to the engineering calculated minimum flowrate for full disc' lift.
This method is superior to sample disassembly and inspection of one valve per outage which would require unusual system line-ups, freeze seals, radiation exposure, and possible plant transients.
Other alternatives to measuring full design accident flow or disassembly an6 inspection of check valves to satisfy full stroke requirements is allowed as long as the requirements of NRC Generic Letter 89-04,,
Positions 1, 2,
and 3 are utilized QR specific relief requests are approved by the NRC.
Stroking a valve to the full closed position for valves without a manual exerciser or position indicator must be verified using indirect means.
These include, but are not limited to, (1) observing pressure indications on both sidas of the valve to determine if the differential pressure expected with the valve shut is obtained, or (2) opening a drain connection on the upstream side cf the valve to detect leakage rates in excess of that expected with the valve. shut.
valves that cannot be full-stroke tested or where full-stroking cannot be verified, shall be disassembled, inspected, and manually exercised.
Valves that require disassembly for full-stroke testing during cold shutdowns or refueling still require quarterly part-stroke testing, where possible.
Testing of check valves by disassembly.shall-comply with the following:
a.
During valve testing by disassembly, the valve internals ~
j shall'be visually inspected for worn or corroded parts, and-the valve disk shall be manually exercised, b.
Due to the scope of this testing, the personnel hazards I
involved, and system operating restrictions,' valve disassembly and-inspection may be performed during reactor refueling outages.
Since this frequency differs from.the
' Code required f requency, this deviation must be specifically.
i
'noted in the IST program.
(9998D/WPF/021694 )
- 4. 5 z
. page 4 of 14
Rev. 12 c.
Where it is burdensome to disassemble and inspect all applicable. valves each refueling outage, a sample-disassembly and inspection plant for groups of identical I
valves in similar applications may be employed. The NRC Generic Letter 89-04 guidelines for this plan are explained below:
The sample disassembly and inspaction program involves grouping similar valves and te9 ting one valve in each group during each refueling outage. The sampling technique requires that-each valve in the group be the same design (manafacturer, size, model number, and materials of construction) and have the same service conditions including valve orientation.
Additionally, at'each disassembly the licensee must verify that the disassembled valve is capable of full-stroking and that the internals of the valve are structurally sound (no loose or corroded parts). Also, if the disassembly is to verify the full-stroke capability of the. valve, the disk should be manually exercised.
A different valve of each group is required to be disassembled, inspected, and manually full-stroke exercised at each successive refueling outage, until the entire group has been tested.
If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in that group must also be disassembled, inspected, and manually full-stroke exercised during the same outage. 'Once this is. completed, the sequence of disassembly must be repeated unless extension of the interval can be justified.
Extending the valve sample disassembly and inspection-interval from dinassembly of one valve in the group every refueling outage or expanding the group size would increase the time between testing of any particular valve.in'the group. With four valves in a group and an 18-month reactor cycle, each valve would be disassembled-and inspected every six years.
If the fuel cycle is increased to 24 months,-
each valve in a four-valve sample group would be disassembled and inspected only once every eight years.
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(9998D/WPF/021694) 4.5 -'page 5 of 14 1
Rev. 12 C.
Position: (continued)
Extension of the valve disassembly / inspection interval from-that allowed by the Code (quarterly or cold shutdown frequency) to longer than once every 6 years is a substantial change which may not be justified by the valve failure. rate data for all valve groupings.
When disassembly / inspection data for a valve. group show a greater than 25% failure rate, the ststion should determine whether group show a greater than 25% failure rate, the station should determine whether the group size should be decreased or whether more valves from the group should be disassembled during every refueling outage.
Extensions of the group size will be.done on a' case by case basis.
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(9998D/WPF/021694 )
4.5 - page 6 of 14
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Rev. 12 VA-04 IST Technical Approach and Position A.
Comoonent Identification:
1.
==
Description:==
Determining limiting values of full-stroke times for.
2.
Component Numbers:
See IST Valve Tables (St),
3.
References:
r a.
ASME Code,Section XI, Subsection IWV, Sub Article IWV-3413.
b.
NRC Generic Letter 89-04, Attachment A, Position 5.
c.
ANSI /ASME OM-1987 through OMb-1989 Addenda,-Part 10, Section 4.2.
4, Code Class:
1, 2,
and 3.
5.
Examination Category (s).
N/A.
B.
Reauirement:
The IST program originally assigned a limiting value of full-stroke time based on the most conservative value from plant Technical Specifications i
(TS) or Updated Final Safety Analysis-Report (UFSAR).
For valves not having a specified value of full-stroke, a limiting value was assigned based on manufacturers design input,. engineering input, or initial valve preoperational testing.
This methodology is contrary to NRC' Generic Letter 89-04.
According to NRC Generic Letter 89-04 the' limiting value of full-stroke should be based on an average reference stroke time of a valve when it is known to be operating properly.
The. limiting value should be a reasonable deviation from this reference stroke time. based on the valve size, valve type, and actuator type. The deviation should not be so restrictive that it results in a valve being declared' inoperable due to reasonable stroke time variations. However, the deviation used to establish the limit should be such that corrective action would be taken for a valve that may not perform its intended. function.
When the calculated limiting value for a full-stroke is greater than a TS or safety analysis limit the TS or safety analysis limit should be used as the limiting value of full-stroke. time.
Based on this,'a review of each valve operating history was performed and an average / reference value of full-stroke determined.
In addition, valves were grouped together by system, train, unit, valve type, and actuator type to provide for a more thorough review in determining what would be a " reasonable" deviation from the average / reference full-stroke value.
(999 BD/WPF/021694 )
4.5 - page 7 of 14-
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Rev. 12 B.
Feauirement:
(continued)
The 1983 Edition through Summer 1983 Addenda of ASME Section XI does not provide. guidance for determining values of full-stroke. However, it' does provide requirements for when to. start monitoring a valves performance on a more frequent basis, also known as alert range testing.
If a valve strokes in 10 seconds or less, a 50% increase over the previous value requires it to be put on a monthly test frequency, and for valves stroking in greater than 10 seconds, a 25% increase over the-previous value requires it to be put on a monthly test frequency (see VR-20).
Trending stroke times, based on the percent change from.
the previous test, as ASME Section XI requires, allows gradual.
degradation to occur over a long period of time without triggering the additional trending attention that increased testing frequency requires.
Therefore, an improved method of component performance monitoring is employed which requires a valve to be placed on increased test frequency based on the percent change from the fixed reference value established' via NRC Generic Letter 89-04, Attachment 1, Position 5.
This criteria, in conjunction with establishing reference / average values of full-stroke, should allow for reasonable deviations in stroke time _
measurements without declaring a valve inoperable. The corrective actions specified in IWV-3417 (b) of Section XI and as described in IST Program Relief Request VR-20 will be taken when a valve exceeds its limiting value of full stroke.
C.
Position:
The following criteria will be used as general guidance to establish ALERT and REQUIRED ACTION ranges for power-operated valves:
SOV's/HOV's/AOV's - Less than or eaual to 10 seconds:
ALERT RANGE:
(1.50) (Tref) - (2.0) (Tref)
REQUIRED ACTION VALUE:
> (2.0) (Tref)
MOV's - Less than or eaual'to 10 seconds:
ALERT RANGE:
(1.25) (Tref) - (1.50) (Tref}
REQUIRED ACTION VALUE:
> II.50) (Tref)
MOV's/SOV's/HOV's/AOV's - Greater than 10 second.gi See VR-20; this technical approach and position will not be put into application until relief request VR-20 is approved.
(9998D/WPF/021694) 4.5' page 8 of 14
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Rev. 12 NOTES:
1.
Tref is the reference or average stroke value in seconds of an individual valve or valve grouping established when the valve is known to be operating acceptable.
2.
Standard rounding techniques are to be used when rounding off stopwatch readings during valve stroke timing (e.g. 10.45 rounds to 10.5, and 10.44 is rounded to 10.4 seconds).
Round-off all i
measured stroke time to the nearest tenth of a second.
3.
When reference stroke values or average stroke values are affected by other parameters or conditions, then these parameters or conditions must be analyzed and the above-factors adjusted.
4.
If the above calculated values exceed a Technical Specification or FSAR value, then the TS or FSAR must be used for the limiting value of full-stroke.
5.
Fast acting valves (vales which normally stroke in less than 2 seconds consistently).are included in Relief Request.VR-12.
These valves are HQI assigned ALERT RANGES and are HQI trended.
6.
The above criteria is a guide and cannot cover all valves. The ALERT RANGES and REQUIRED ACTION VALUES are selected based on comparison between the REFERENCE VALUE, LIMITING VALUE given'in Technical Specifications /UFSAR, operating history, and calculated values using the above criteria.
7.
Valves which serve the same function on dual trains (i.e.,
ICC9473A and 1CC9473B) and dual units (i.e. ICC9473A and 2CC9473A) are assigned the same REQUIRED ACTION / ALERT RANGE VALUES based on human factors considerations, unless valve or system design differences exist between the trains / units.
8.
Refer to Relief Request VR-20 for related information.
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4.5 - page 9 of 14 l
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Rev. 12 VA-05 IST Technical Approach and Position A.
Comoonent Identification:
1.
==
Description:==
Justification for exercising the U 0 heat exchanger-and pump isolation valves on a U-2 Cold Shutdown frequency per.OM-10, paragraph 4.2.1.2.c.
2.
Component Numbers:
1/2CC9459B, CC Pump Suction Header Crosstie
~
Manual Isolation Valves; 1/2CC9467B, CC Heat Exchanger Outlet Header Crosstie Isolation Valves.
3.
References:
(a) ASME Code,Section XI, Subsection IWV, paragraphs lWV-3411, 3412; (b) Draft NUREG-1482, Section 3.1.1; (c) OM-10, paragraphs 4.2.1.1, 4.2.1.2.
i 4.
Code Class:
3.
5.
Category:
B.
B.
Reauirement:
Per OM 10, paragraph 4.2.1.1, 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.
Per section 4.2.1.2.c, if exercising is not practicable during plant operation, it may be limited to full stroke 1
exercising during cold shutdowns. Per draft NUREG 1482, section'3.1.1.,
testing at Cold Shutdown is'an allowable deferral of testing' required by.
OM 10.
Hence, Byron will use OM-10 for -justifying the impracticality of exercising these Component Cooling Water' valves quarterly.
t (9998D/WPF/021694) 4.3. page 10 of 14
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Rev. 12 C.
Position:
These manual valves are used to provide for train separation and/or isolation of the Component Cooling Water System.
They are aligned to place the U-0 Heat Exchanger and pump on the U-1 or U-2 side of CCW to ensure adequate cooling during Shutdowns and/or Post-Accident.
Stroking these valves quarterly or during U 1 cold shutdowns would be a considerable burden and potential safety concern. The CC system is a delicately balanced system that has the potential for becoming upset upon swapping the Unit 0 Heat Exchanger and pump from one unit to the other. History has shown that stroking these valves will cause oscillations in the lines, disrupt flow balancing due to D/P differences throughout the system, and would place the normal loads at risk for adequate cooling. For instance, the CC685 valve, which is the Reactor Coolant Pump thermal barrier Component Cooling Water return valve, auto-closes on high flow, which would result ^in a loss of flow to the RCP thermal barriers.
This valve could potentially close during the CC stroke tests due to the upset flow conditions.
In addition, the CC surge tanks will be at risk of draining, resulting in possible pump trips on low-low level.
The potential problems would only be compounded by stroking these valves during a U-1 cold shutdown since the U-0 heat exchanger and pump will be in use on the U-1 train. Fence, Byron considers it impractical to perform this testing quarterly or during a U-1 cold shutdown.
UFSAR " active valve" table 3.9.16 does not list these valves as
" active" and Section 9.2.2.4 gives justification that these valves are not required in the short term following an accident. Al t.o, the UFSAR states that if there was a single failure of a valve in the long term, making it undesirable to use a particular pump and heat exchanger, sufficient cooling would be provided with a different subsystem. Hence,-
l testing these valves is conservative on Byron's part, and quarterly testing is less significant than in other cases due to the design of the system.
(9998D/WPF/021694 )
4.5 - page II of 14
Rev. 12 C.
Position (continued)-
A minimum eighteen month frequency will reduce the likelihood os a CC system malfunction caused by stroking these manual valves.
In addition, a review of maintenance history dating back to 1983, shows there has been no evidence of valve exercising malfunctions from that time to the i
present. These valves are normally aligned such that the U-0 CC heat exchanger and pump are on the U-1 side.
The valves normally stay in this position until U-2 is shutdown and put on RHR cooldown.
When this is done, the U-0 heat exchanger and pump are aligned to U-2, which includes stroking open the 2CC9459B and 2CC9467B valves, and closing the U-1 respective valves.
Following the U-2 Cold Shutdown or Refueling Outage, the lineup will be re-set to the original lineup which involves stroking the CC9459B and CC9467B valves in the opposite direction than before the shutdown. This would complete the necessary stroking of the manual valves listed. Since these valves are not often manipulated, they experience minimal wear and a minimum eighteen month stroke frequency should be sufficient to detect a problem.
These manual valves will be stroke exercised in one direction prior to each U 2' Cold Shutdown, or a minimum of once every 18 months during a U-2 Refueling Outage. This is when the U-0 heat exchanger and pump are normally swapped to U-2.
The CC9467B and CC9459B valves will be stroked in the opposite direction when the U-0 heat exchanger and pump are re-aligned to the U-1 side following the U-2 Cold Shutdown or Refueling Outage. The testing will occur under carefully controlled conditions to minimize the consequences of exercising these valves.
1 (9998D/WPF/021694) 4.5 - page 12 of 14
Rev. 13 VA-06 IST Technical Approach and Position A.
Comoonent Identification:
1.
==
Description:==
Stroke Time Corrective Actions.
2.
Component Numbers: All Power Operated Valves, except those identified in VR-12 (rapid-acting valves).
3.
References:
(a) Subarticle IWV-3417 (a) ; (b) OM-10, Section 4.2.1.9.
4.
Category: A and B.
B.
Recuirement:
Per IWV-3417 (a), if, for power operated valves, an increase in stroke time of 25% or more from the previous test for valves with full-stroke times greater than 10 seconds, or 50% or more for valves with full-stroke times less than or equal to 10 seconds is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed.
In any case, any abnormality or erratic action shall be reported.
C.
Position:
The Code requirement for increased frequency testing is based.on a comparison between the current stroke time and the previous stroke time.
Depending on the stroke duration and the percentage increase, monthly testing may be required. This approach, if not checked by trending, allows for the threshold for more frequent testing to slowly creep up over time.
For example, an increase of 10% at each quarterly test could take place over a period of one year without any action being required.
This variable limit is also difficult to administer because the limit is not a permanent entry in the test procedure.
A more appropriate method to be used should be based on an empirically derived fixed limit using. valve operating history, valve condition and comparison with other valves of similar design (valve size,-valve type, and actuator type). This allows for a more thorough review in determining what the " reasonable deviation" from the average / reference stroke value should be for an individual or group of valves (Seo VR-20 and VA 4).
For those valves that are identified for stroke testing in cold shutdown or refueling only, these valves cannot be placed on a monthly testing frequency for the reasons already presented in the valve test program.
Since the Code does not provide any direction for these frequencies of test, it is unclear if these valves are even to be included in the context of IWV-3417 (a).
(9998D/WPF/021694) 4.5 - page 13 of 14
Rav. 12 i
C.
Position:
(continued)
For all power operated valves which normally strc~e in greater than two seconds, an alert range will be established based on reaching a given percent increase from the reference average value. The maximum limiting value of full stroke is established per Technical Approach and Position, VA-04 and Relief Request VR-20.
The reference value used to determine the alert range will be reconfirmed following maintenance activities that could affect valve stroke time, or a new limit will be established based on the new stroke time.
For valves that can only be stroke timed in cold shutdown or refueling, once the valve (s) enter the alert range, they will be retested.
If the retest is acceptable, then an evaluation will be performed to determine the cause.
If the retest is unacceptable, then the valve will be declared inoperable until corrective actions are taken or an evaluation is completed justifying continued operability.
For valves that are stroke timed quarterly, when the alert range is exceeded, the valve will be immediately retested.
If the retest is acceptable, then an evaluation will document this deviation.
If the retest is unacceptable, the valve will be placed on a monthly testing frequency until corrective action is taken or an evaluation is completed, justifying continued operability providing the limiting valve or full stroke is not exceeded.
Using fixed alert ranges based on the reference value established when a valve is known to be operating acceptably will ensure that gradual valve performance degradation is monitored and evaluated, by placing the valve on an increased testing frequency when the stroke time exceeds a fixed multiple of the reference value. This method is superior to that I
required by the Code in that the point of reference used to evaluate the performance trend on a valve remains fixed. The alternate test method uses the same percentage increase as the Code, except that it is applied to the reference value.
Performing an engineering evaluation / investigation when a cold shutdown / refueling valve enters the alert range, providing the retest is acceptable, is adequate to monitor the valve for degradation.
This position will be gradually incorporated to support Byron's ten year update in 1995.
(9998D/WPF/021694) 4.5 - page 14 of 14
=.
a M
SECTION 4.6 RELIEF REQUESTS 4
I r
. +.. -. -, --, -
--e i
a
,-l--,
Rev. 12 RELIEF REOUEST VR-1 1.
Valve Number:
All primary containment isolation valves in this program are listed as Category A:
VALVE #
VALVE #
VALVE J 1) 1CC685 41)
IPR 033B 81)
ISI8888 2) 1CC9413A 42) 1PR033C 82)
ISI8964 3) 1CC9414 43) 1PR033D 83)
ISI8968 4) 1CC9416 44) 1PR066 84) 1VQ001A 5)
ICC9438 45) 1PS228A 85) 1VQ001B 6) 1CC9486 46) 1PS228B 86) 1VQ002A 7) 1CC9518 47) 1PS229A 87) 1VQOO2B 8) 1CC9534 48) 1PS229B 88) 1VQOO3 9) 1CS007A 49) 1PS230A 89) 1VQOO4A 10)
ICS007B 50) 1PS230B 90) 1VQ004B 11) 1CS008A 51)
IPS231A 91) 1VQ005A 12) 1CS008B 52) 1PS231B 92) 1VQ005B 13) 1CV8100 53) 1PS9354A 93) 1VQ005C 14) 1CV8112 54) 1PS9354B 94) 1VQOl6 15) 1CV8113 55) 1PS9355A 95) 1VQ017 16)
ICV 8152 56) 1PS9355B 96) 1VQO18 17) 1CV8160 57) 1PS9356A 97) 1VQ019 18)
IFC009 58) 1PS9356B 98) 1WM190 19) 1FC010 59) 1PS9357A 99)
IWM191 20) 1FC011 60) 1PS9357B 100) 1WOOO6.A 21) 1FC012
,1) 1RE1003 101) 1WOOO6B 22)
IIA 065 62) 1RE9157 102) 1WOOO7A 23)
IIA 066 63) 1RE9159A 103) 1WOOO7B 24)
IIA 091 64) 1RE9159B 104) 1 WOO 20A 25) 10G057A 65) 1RE9160A 105)
IW3020B 26) 10G079 66) 1RE91608 106) 1VOO56A 27) 10G080 67) 1RE9170 107) 1110056B 28) 10G081 68) 1RF026 29) 10G082 69) 1RF027' g
30) 10G083 70) 1RYO75 1
31) 10G084 71) 1RY8025 32) 10G085 72) 1RY8026 33) 1PR001A 73) 1RY8028 34) 1PR001B 74) 1RY8033 35) 1PR002E 75) 1RY8046 36)
IPR 002F 76) 1RY8047 37) 1PR002G 77) 1SA032 38) 1PR002H 78) 1SA033 39) 1PR032 79)
ISI8871 40) 1PR033A 80)
ISI8880 (9998D/WPF/021694) 4.6 - page 1 of 70
Rev. 12 RELIEF REOUEST VR-1 (continued) 1.
Valve Numbert (continued)
VALVE #
VALVE _1 VALVE #
{
108) 2CC685 148) 2PR033B-189) 2 SIB 964 109) 2CC9413A 149) 2PR033C 190) 2 SIB 968 110) 2CC9514 150) 2PR033D 191) 2VQ001A-111) 2CC9416 151) 2PR066 192) 2VQ001B 112) 2CC9438 152) 2PS228A 193) 2VQOO2A 113) 2CC9486 153) 2PS228B 194) 2VQ002B 114) 2CC9518 154) 2PS229A 195) 2VQOO3 115) 2CC9534 155) 2PS229B 196) 2VQ004A 116) 2CS007A 156) 2PS230A 197) 2VQOO4B 117) 2CS007B 157) 2PS230B 198) 2VQ005A 118) 2CS008A 158) 2PS231A 199) 2VQ005B 119) 2CS008B 159) 2PS231B 200) 2VQ005C 120) 2CV8100 160) 2PS9354A 201) 2VQOl6 121) 2CV8112 161) 2PS9354B 202) 2VQ017 122) 2CV8113
~~ 162) 2PS9355A 203) 2VQO18 123) 2CV8152 163) 2PS9355B 204) 2VQ019 124) 2CV8160 164) 2PS9356A 205) 2WM190 125) 2FC009 165) 2PS9356B 206) 2WM191 126) 2FC010 166) 2PS9357A 207) 2WOOO6A 127) 2FC011 167) 2PS9357B 208) 2WOOO6B 128) 2FC012 168) 2RE1003 209) 2WOOO7A 129) 2IA065 169) 2RE9157 210) 2WOOO7B 130) 2IA066 170) 2RE9159A 211) 2 WOO 20A 131) 2IA091 171) 2RE9159B 212) 2 WOO 20B 132) 2OG057A 172) 2RE9160A 213) 2 WOOS 6A 133) 20G079 173) 2RE9160B 214) 2 WOOS 6B 134)- 20G080 174) 2RE9170 135) 20G081 175) 2RF026 136) 20G082 176) 2RF027 137) 20G083 177) 2RYO75 138) 20G004 178) 2RY8025 139) 20G085 179) 2RY8026 140) 2PR001A 180) 2RY8028 141) 2PR001B 181) 2RY8033 142) 2PR002E 182) 2RY8046 143) 2PR002F 183) 2RY8047 144) 2PR002G 184) 2SA032 145) 2PR002H 185) 2SA033 146) 2PR032 186) 2SI8871 147) 2PR033A 187) 2SI8880 188) 2SI8888 d
(9998D/WPF/021694 )
4.6 - page 2 of 70
Rev. 12 1
BELIEF REOUEST VR-1 (continued) 2.
Number of Items:
212 3.
ASME Code Cateoorv A
4.
ASME Code.Section XI Recuirements:
Seat Leakage Measurement per IWV-3420.
S.
Basis for Relief:
Primary containment isolation valves will be set sk tested in accordance with 10CFR50, Appendix J.
For thes. s
'es, Section.XI testing requirements are essentially equivalent to those of Appendix J.
4 6.
Alternate Testino:
Primary containment isolation valves shall be set leak rate tested in accordance with the requirements of 10CFR50, Appendix J.
The results of such leak rate measurements shall be analyzed and corrected, as necessary, in accordance with the guidance set forth in ASME Code Section XI, Subsection IWV, paragraphs IWV-3426 and IWV-3427 (a). The trending requirements of IWV-3427 (b) will D2% be utilized.
7.
Justification:
No additional information concerning valve leakage would be gained by_
performing separate tests to both Section XI and Appendix J.
Therefore, overall plant safety is not affected. As specified per NRC Generic Letter 89-04, Attachment 1, position 10, the usefulness of IWV 3427 (b) does not justify the burden of complying with this. requirement.
8.
Aonlicable Time Period:
This relief is requested once per two years during the first inspection.
interval.
9.
Anoroval Status:
Relief granted per'SER.9/15/88 contingent upon compliance with
{
a ASME Section XI IWV-3426, 27.
-j b.
Revised to comply with ASME Section XI'IWV-3426, 27 in Byron SER Response 12/16/88 (Byron Station Letter 88 1321).
c.
Relief granted per NRC Generic Letter 89-04 d.
Deleted SD valves per Technical Specification Amendment #39, e.
Relief granted per SER 9/14/90.
f.
1/2RYO75 Valve added to relief.
Relief granted for same reasons as noted in SER 9/14/90 (9998D/WPF/021694) 4.6 - page 3 of 70
Rev. 12 4
RELIEF REOUEST VR-2 1.
Valve Number:
ICS020A 2CS020A 1CS020B 2CS020B 2.
Number of Items:
4 3.
ASME Code Catecorv: C 4.
ASME Code.Section XI Recuirements:
Exercise check valves to the position required to fulfill their function (open = CT; closed = BT) unless such operation is not practical during plant operation, per IWV-3522.
5.
Basis for Relief:
The check valves in the spray additive system cannot be stroked without introducing NaOH into the CS system.
6.
Alternate Testina:
The A train and B train valves are of the same design (manufacturer, size, model number, and materials construction) and have the same service conditions, including orientation, therefore they form a sample disassembly group.
Group 1 Group 2 1CS020A 2CS020A 1CS020B 2CS020B One valve from each group, on a per unit basis, will be tested e'ach
+
refueling outage.
If the disassembled valve.is not capable of being full-stroke exercised or if there is binding or failure of valve inte rnals, the remaining valve on the affected unit will be inspected.
7 qustificationi Full flow testing of these valves can not be accomplished without posing a serious threat to the safety of equipment and personnel, It is impractical to either full or part stroke exercise these valves since flow through these valves would result in'the introduction lof_NaOH into the CS system. Full-flow testing would require a special test hook-up and necessitate flushing the system.
(9998D/WPF/021694) 4.6 - page 4 of 70
.,~
]
Rev. 12 j
BELIEF REOUEST VR-2 (continued) 7.
Justification:
(continued)
The alternate test frequency is justifiable in that maintenance history and previous inspections of these valves at Byron and Braidwood stations has shown no evidence of degradation or physical impairment (this is to be expected since the valves see very limited operation).
Industry experience, as documented in NPRDS, showed no history-of problems with these valves. A company wide check valve evaluation addressing the "EPRI Applications guidelines for Check Valves in Nuclear Power Plants" revealed that the location, orientation and application of these valves are not conducive to the type of wear or degradation correlated with SOER 86-03 type problems, but these valves still require some level of monitoring to detect hidden problems.
The wafer type design of the valve body for these valves make their removal a simple process, with little chance of damage to their internals. Also, there is no disassembly of internal parts required; all wear surfaces are accessible by visual examination. After inspection and stroke testing, the valve is reinstalled into the line and post maintenance testing is performed. The valve inspection procedure requires post-inspection visual examination of the check valve to insure that the pin is oriented properly and that the flow direction is correct.
The alternate test method is sufficient to insure operability of these valves and is consistent with Generic Letter 89-04.
8.
Anolicable Time Periodi l
This relief is requested once per quarter during the first inspection
.{
interval.
9.
Acoroval Status:
- \\
Relief to disassemble in place of full flow testing granted per a.
SER 9/15/88.
b.
Relief to disassemble in place of full flow testing granted per Generic Letter 89-04.
Relief to disassemble in place of full flow testing granted per c.
SER 9/14/90.
d.
Revised to include both full flow (CT) test and back flow (BT) test; relief granted per Generic Letter 89-04.
Relief granted per SER 1/31/92 provided licensee complies with e.
GL 89-04, position 2.
j (9998D/WPF/021694) 4.6 - page 5 of 70 1
__m Rev. 12 DRAFT BEMEE_BXQUEST VR-2.n 4
1.
Valve Number:
ICS020A 2CS020A 1CS020B 2CS020B 2.
Number of Items:
4 i
3.
ASME Code Cateoorv:
C 4.
ASME Code.Section XI Reauirements:
Exercise check valves to the position required to fulfill their function-(CT/Open; BT/ Closed) quarterly, unless such operation is not practical during plant operation per IWV-3521, or exercise during cold shutdown per IWV-3522, 5.
Basis for Relief:
These check valves in the spray additive system (CS) cannot be stroked without introducing NaOH into the CS system, unless the piping between the NaOH storage tank and the injection isolation valves, 1/2CS021A/B, is drained into containers. This amounts to almost two 55 gallon drums of potentially (radioactive / toxic) mixed waste that requires either recycling or disposal. Then, primary water is connected to the CS system via special test connections and is used to flow test the.line to ensure that the proper Technical Specification eductor flow rate can be passed.
The problem with disposal stems from the caustic being slightly contaminated, as well as having a high pH.
Recycling (pouring the contents of the drums back into the NaOH tank)' is not always a viable option either, considering the caustic has been contained in a stagnant line (up to five years) and may not meet chemistry requirements.
- Thus, storage of hazardous mixed waste can become very costly. This is due to the non-existence of commercial disposal facilities for mixed waste, which means that any mixed waste generated would have to be stored on-f site. Also, the draining and handling of this highly caustic material l
poses a significant hazard to personnel, and can result in. loss'of eye j
sight and/or chemical burns, if splashed or spilled.
(9998D/WPF/021694 )
4.6 - page 6 of 70
_J
-, ~.
Rev, 12 DRAFT REMEEEQUESLyp-lg 6.
Alternate Testinql Group 1 Group 2 1CS020A 2CS020A 1CS020B 2CS020B The A and B train valves are of the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions, including orientation. This forms an acceptable sample disassembly group per Generic Letter 89-04, Position 2c.
Each group will be disassembled and visually inspected at the same frequency as the Technical Specification eductor flow test, conducted at least once every five years. The visual inspection of internals will precede the eductor flow test.
7.
Justification:
If the disassembled valve is not capable of being manually full-stroked exercised or there is binding or failure of internals, the remaining valve on the affected unit will be evaluated for further action as well.
Full flow testing of these valves cannot be accomplished without posing a serious threat to the safety of equipment and personnel.
It is impractical to either full or partial stroke exercise these valves since
]
flow through them requires draining and' flushing the piping to prevent-the introduction of caustic effluent into the CS system. The problem of l
mixed waste disposal or recycling created by system draining of approximately two 55 gallon drums is considered an undue hardship, if i
the Code requirements are imposed.
The alternate test frequency (same f requency as the Technical Specification eductor flow test of at 'least once every five years).
-l is justifiable in that maintenance history and previous inspections of these valves at both Byron and Braidwood stations have'shown no evidence of degradation or physical impairments (i.e. corrosion, chemical buildup, wear). This is to be expected since these valves see limited operation (flow in line during eductor flow test only).
Industry experience, as documented in NPRDS, shows no history of problems with these valves. A company wide check. valve evaluation J
addressing the "EPRI Application Guidelines for Check Valves in Nuclear' Power Plants" revealed that the location, orientation and application of these valves are not conducive to the type of wear or degradation correlated with SOER BC-03 type failures, i
(9998D/WPF/021694 )
4.6 - page 7 of 70
-. _ -..... ~...
. - -.~
l
-Rev. 12 i
i DRAFT EF1IE F_. REQUEST _,VR-2 a 7
Justification:
(continued)
The alternate test method, visual inspection of internals followed by the Technical Specification eductor flow test, at least once every.five years, is sufficient to ensure operability of these valves and is consistent with Generic Letter 89-04 guidelines. The hardship involved with the hazardous mixed waste, disposal and handling caustic material with regards to personnel safety does not provide a compensated increase in safety of the CS system equipment.
8.
Anolicable Time Period:
This relief is requested for the first inspection interval.
9.
Aonroval Status:
Since this relief le a new submittal and is not specifically a.
addressed in NRC Generic Letter 89-04, it-is HQI approved for use.
Formal written approval from the NRC is required prior to -
implementation.
Review and approval are requested by 8/20/94, prior to Byron's next refueling outage.
(9998D/WPF/021694) 4.6 - page 8Lof 70
... ~.
Rev. 12 l
RELIEF REOUEST VR 1.
Yalve Number:
1SI8922A-2SI8922A ISI8922B 2SI8922B 2.
Number of Items:
4 3.
ASME Code Catecorv:
C 4.
&$M3 Code.Section XI Reauirements:
Exercise check valves to the position required to fulfill their function-(open = CT; closed = BT) unless such operation is not practical during plant operation, per IWV-3522.
5.
Basis for Relief:
These check valves cannot be full flow tested during operation as the-shut-off head of the Safety Injection pumps is lower than the reactor:
coolant system pressure.
Performance of this test with the RCS depressurized, but intact, could lead to inadvertent'over-pressurization of the system. The alternate method of protecting against over-pressurization by partially draining the RCS to provide a surge volume is not considered a safe practice Jue to concerns of maintaining adequate water level above the reactor core.
6.
Alternate Testino:
These valves will be full stroke tested during refueling outages as a' minimum, but no more frequently than once per quarter.
7.
Justificat;1gnt This alternative will adequately maintain the system in-a statelof operational readiness, while not sacrificing the safety'of the_ plant, ty
^
testing the valves as often as safely possible.
8.
Acolicable Time Period:
This relief is requested once'per quarter during the first inspection interval.
~
9.
Anoroval Status:
a.
Relief granted per SER-9/15/88.
b.
Relief granted per NRC Generic Letter 89-04, c'.
Relief < granted per SER 9/14/90.
(9998D/WPF/021694 )
4.6'- page 9 of 70
Rev, 12 F
RELIEF REOUEST VR-4 1.
Valve Number:
'lCS003A 2CS003A 1CS003B 2CS003B 1CS008A 2CS008A 1CS008B 2CS008B 2.
Number of Items:
8 l
3.
ASME Code,Section XI Reouirements:
i a.
Exercise check valves to the position required to fulfill their function (open = CT; closed = BT), unless such operation is not practical during plant operation, per IWV-3522.
b.
Exercise check valves at least once every 3 months, per IWV-3521, c.
Exercise check valves at least once every 3 months to the~ position required to fulfill their function, unless such operation is not practical during plant operation, per IWV-3412 (for.1/2CS008A,.B only),
t d.
When a valve has been repaired, replaced, or has undergone maintenance that'could affect its performance and prior to the time it.is returned to service, it shall be tested to demonstrate that the performance parameters, which could have been affected by the replacement, repair, or maintenance, are within acceptable-limits, per IWV-3200~.
1 5.
Basis for Relief:
These valves cannot be full flow tested as a matter of course during unit operation or cold' shutdown as water from the CS pumps would be' discharged through the CS ring headers causing undesirable effects on system components inside containment.
Additionally, the full flow testing of these check valves during periods' of cold shutdown, using the CS pumps, would fill the reactor refueling cavity with contaminated water from the refueling water storage tank.-
The filling of the cavity, via temporarily installed large bore piping, would require the removal of the reactor. vessel head so as to preclude equipment damage from borated water.
The erection of temporary piping' from the CS line to the reactor cavity would take an estimated nine to twelve shifts, or longer compared to one to two shifts for valve inspection.
This estimate does not take into account the time. required to drain and remove the piping from containment.
(9998D/WPF/021694) 4.6
-page 10 of 70
Rev. 12 EELIEF REOUEST VR-4 (continued)_
5.
Basis for Relief:
(continued)
Currently, full flow recirculation flow paths do not exist from the discharge of the CS pumps through these check valves to the refueling water storage tank.
The addition of such flow paths would require extensive plant modifications to existing plant designs, including penetration of containment integrity.
Partial stroking of the 1/2CS008A, B valves using air does not provide adequate assurance of valve operability and may be detrimental for the following reasons:
a.
There is no correlation between air flow and angle of disc movement.
b.
Venting and draining the appropriate piping quarterly may cause deposition of boric acid residue which could in turn promorc binding of the check valve internals.
6 Alternate Testino:
The A and B train valves are of the same design (manufacturer, size, model number, and materials construction) and have the same service conditions, including orientation, therefore they form a sample disassembly group.
Group 1 Group 1 1CS003A 2CS003A 1CS003B 2CS003B Group 2 Group 2 1CS008A 2CS008A 1CS008B 2CS008B one valve from each two valve groups, on a per unit basis, will be tested each refueling outage.
If the disassembled valve is not capable of_being full-stroke exercised or if there is binding or failure of valve internals, the remaining valve on the affected unit will be inspected.
(9998D/WPF/021694) 4.6 - page 11 of 70
Rev. 12 l
RELIEF REOUEST VR-4 (continuedl 7.
Justification:
The 1/2CS008A,B and 1/2CS003A,B valves are removed from the system and visually examined per the strict detailed inspection requirements of the Station Check Valve Program. This inspection adequately verifies that the valves are maintained in a state of operational readiness. The valves are verified to be functional by performing a thorough visual inspection of the valve internals and by performing a full stroke-test exercise of each disc.
Previous inspections of these particular. valves at both Byron and Braidwood have repeatedly shown them to be in good condition.
The wafer type design of the valve body for these valves make their removal a simple process, with little chance of damage to their internals. Also, there is no disassembly of internal parts required; all wear surfaces are accessible by visual examination. After
)
inspection and stroke testing, the valve is reinstalled into the line and post maintenance testing is performed.
The 1/2CS008A, B valves receive a containment leakage test, and the 1/2CS003A, B valves are partial flow tested. These tests verify proper installation of the check valves, and the valve inspection procedure requires post-inspection visual examination of the check valve to insure that the pin is oriented properly and that the flow direction is correct.
The alternate test frequency is justifiable in that maintenance history and previous inspections of these valves at Byron and Braidwood stations has shown no evidence of degradation or impairment.
Industry experience, as documented in NPRDS, showed no history of problems with these valves. A company wide check valve evaluation addressing the "EPRI Applications Guidelines for Check Valves in Nuclear Power Plants" revealed that the location, orientation and application of these valves are not conductive to the type of wear or degradation correlated with SOER 86-03 type problems.
However, they require some-level of monitoring to detect hidden problems.
8.
Acolicable Time Period:
This relief is requested once per quarter during the first inspection interval.
(9998D/WPF/021694) 4.6 - page 12 of 70 i
I Rc . 12 RELIEF REOUEST VR-4 (continaed) 9.
Acoroval Status; a.
Relief-to disassemble in place of full flow testing granted per SER 9/15/88 for 1/2CS003A, B; relief denied per SER 9/15/88 for 1/2CS008A.
b.
Revised to address NRC concerns in Byron SER response 12/16/88 (Byron Station-Letter 88-1321).
c.
Relief to disassemble in place of full flow testing granted per Generic Letter 89-04.
d.
Revised to address NRC concerns in Byron SER 9/14/90 and to include both full flow (CT) and backflow (BT) test; relief granted per Generic Letter 89-04.
e.
Relief granted per SER 01/25/93.
1 i
l i
I j
(9998D/WPF/021694) 4.6 - page 13 of 70
- ~ - - -
Rev. 12 EgJJ_EF REOUEST VR-5 1.
Valve Number (ASME Code Class)
- 1 SIB 956A D(1) 2SI8956A-D(1) 2.
Number of Valves:
8 3.
ASME Code.Section XI Recuirements:
Relief is requested from the 3 month' test frequency for. the full stroke (CT) and backflow
(. T) test as stated in ASME Section II, IWV-3521:
B
" Check Valves shall be exercised at least once every 3 months, except as l
provided by IWV-3522".
IWV-3522 states that valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full-stroked exercised during cold shutdowns, i
5.
Basis for Relief:
The 1/2SI8956A-D check valves are located inside the containment building missile barrier on the-lines from the accumulator tanks to the Reactor Coolant System (RCS) cold legs.
These 8 check valves have safety functions in both the open and closed directions:
1/2SI8956A-D Closed The 1/2SI8956A-D check valves' safety function in the closed direction is to maintain the Reactor Coolant Pressure Boundary (RCPB).
Open The 1/2SI8956A-D check valves' safety function in the open direction is to permit the injection of borated water into the reactor vessel cold legs during the passive injection ~
l phase of a safety injection.
Check valves 1/2SI8956A-D'cannot be-tested during unit operation due to the pressure differential between the accumulators (650 psig)~ and the reactor coolant system (2235 psig).
Full stroke exercising of these valves could occur only with a rapid depressurization of the reactor coolant system.
l (9998D/WPF/021694) 4.6 - page 14 of 70
,_4
Rev. 12 2
RELIEF REOUEST VR-5 (continuedt 6.
Alternate Testina:
These valves will be backflow tested (BT) on the same schedule as the Byron Station Technical Specifications leakage test as follows:
a.
At least once per 18 months, b.
Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months, c.
Prior to returning the valve to service following maintenance, repair or replacement work on the valve, or d.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to manual action or flow through the valve.
These check valves will be full stroke exercised (CT) during refueling outages when the accumulators are discharged into the reactor vessel.
7.
Justification:
These eight valves are part of the Passive Injection subsystem portion of the safety injection system.
This subsystem is designed to inject borated water into the reactor cold legs only after Reactor Coolant System (RCS) pressure has decreased below the accumulator nitrogen' gas pressure. Under normal plant conditions the RCS system pressure is 2235 psig and the accumulator pressure is 650 psig. Therefore, it is not possible to full stroke these valves unless there is rapid depressurization of the Reactor Coolant System.
Full stroke testing (CT) of these valves during operation or at cold shutdown would require depressurization of the RCS.
Additionally, full stroking these valves during cold shutdowns, routine or forced, would impose hardship with no compensating increase in plant safety.
To perform this test, the reactor coolant system (RCS) must be at approximately 40 psi with all 4 reactor purps (RCPs) off and accumulator pressure at 100 psi over RCS pressure. The RCS boron concentration is low compared to the 2000 ppm concentration of the accumulators.
This injection test requires that approximately 8 thousand gallons of this boron concentrated water be injected into the RCS.
This would result in a considerable increase in the boron concentration of the RCS.
The feed and bleed process required to restore desired RCS boron concentration would result in considerable increases in restoration time and in amounts of radioactive water rejected from the site.
(9998D/WPF/021694 )
4.6 - page 15 of 70
Rev. 12 RELTEF REOUEST VR-5 (continuedl 7.
Justification:
(continued)
Successful completion of the seat leakage test will provide positive verification of closure (BT)
Therefore, backflow testing thene valves on the same schedule as their required Technical Specification leak rate testing will adequately maintain the system in a. state of operational readiness.
8, Apolicable Status:
This relief is requested once per quarter during the first inspection interval.
9.
Anoroval Statual 09/15/88 - Relief for full stroke test granted per SER.
09/14/91 Relief for full stroke test granted per SER.
01/23/92 Reorganized to indicate safety function of the 1/2SI8956A D-valves and to add backflow test.
l (9998D/WPF/021694 )
4.6 page 16 of 70 I
T'W P
e T
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Rev. 12 RELIEF REOUEST VR-6 l
1.
Valve Number:
1SI8926 2SI8926 J
2.
Number of Items: 2 P
3.
ASME Code Cateoorv:
C 4.
ASME Code,Section XI Reauirements:
Exercise for operability (CT) of check valves'every 3 months, per 1
IWV-3521.
5.
Basie for Relief 1 Full stroke exercising of the Safety Injection pump suction check valves, 1SI8926 and 2SI8926 cannot be demonstrated during unit operation as the reactor coolant system pressure prevents the pumps from reaching full flow injection conditions.
Performance of this test with the.
reactor coolant system intact could lead to an inadvertent.
over-pressurization of the system. The alternate method of protecting i
against over-pressurization by partial draining of the reactor coolant.
system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
6.
Alternate Testino:
i J
The ISIS 926 and 2 SIB 926 valves will be partial stroke tested during periodic inservice tests with.the SI pumps in'the recirculation. mode.
Full stroke exercising for the valves will be done during refueling l
outages as a minimum, but no more frequently than once per quarter.
7 dystificatlp_ryl This alternative will adequately maintain the system in a state of.
operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible.
8.
Apolicable Time Period:
This relief is requested once per quarter during the first inspection interval.
9.
Aporoval Status:
l a.
Relief granted per SER 9/15/88.
b.
Relief granted per NRC Generic Letter 89-04.
1 i
c.
Relief granted per SER 9/14/90.
)
(9998D/WPF/021694) 4.6 - page 17 of 70 m,
... ~ _.
Rev. 12 t
f RELIEF REOUEST VR-7
- DELETED" Deleted relief request VR-7, Incorporated valves formerly covered by VR-7 into VR-12 and VR-17 Added maximum stroke times to the valve' tables.
I for all valves in VR-12 per EG & G request.
I i
i 3
(9998D/WPF/021694 )
4.6 - page 18 of 70
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Rev. 12 t
i RELIEF REOUEST VR:1 1.
Valve Number LASME Code ' Class) :
ICC685 (2) 2CC685 (2) 1CC9413A (2) 2CC9413A : (2)
ICC9414 - (2 )
2CC9414 (2)
ICC9416 ' (2) '
2CC9416 (2)
ICC9438 (2) 2CC9438 (2)
ICC9486 (2) 2CC9486 - (2)
.)
1CC9518 (2) 2CC9518 ' (2) 1CC9534 ~ (2) 2CC9534 (2) j 2.
Number of Valves:
16 3.
ASME Code Cateoorv:
A, B,
C l
J 4.
ASME Code.Section XI Reauirements:
a.
Motor operated valves:
1/2CC685, 1/2CC9413A, 1/2CC9414, 1/2CC9416, 1/2CC9438 Relief is requested from the 3 month test frequency for the stroke (ST) test as stated in ASME Section II IWV-3521, " Category A and B valves shall be exercised at least once every 3 months, except.as provided by IWV 3412 (a), IWV-3415, and IWV-3416".
IWV-3412 states that valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full-stroke exercised during cold shutdowns, b.
1/2CC9486, 1/2CC9518, 1/2CC9534 Relief is requested for check valves 1/2CC9518 and 1/2CC9534 from the 3 month test frequency for the full stroke (CT) test and j
backflow (BT) test as stated in ASNS Section XI IWV-3521:
" Check valves shall be exercised at least once every'3 months, except as
{
provided by IWV-3522".
IWV 3522 states that valves-that cannot be' exercised during plant operation shall be specifically identified' by the owner and shall be full-stroke exercised during cold' shutdowns.
Relief is requested for the 1/2CC9486'from the 3 month test frequency for the backflow (.T) test as stated-in ASME Section XI B
~
IWV-3521:
" Check valves shall be exercised at least once every 3 months,'except as.provided by IWV-3522".
IWV-3522 states that valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke' exercised during cold shutdowns.
i 1
(9998D/WPF/021694 )
4.6 - page 19.of 70
Rev. 12 i
RELIEF REOUEST VR-8 (continued) 5.
Basis for Relief:
a.
Motor operated valves:
1/2CC685,~1/2CC9413A, 1/2CC9414, 1/2CC9416, 1/2CC9438 1/2CC685, 1/2CC9438 Closed These valves are located on the Component Cooling return line from the Reactor Coolant Pump (RCP) thermal barrier cooling coils. The safety function of these valves in the closed direction.is to provide a leak-tight barrier between the containment atmosphere and the environment during post accident conditions after a' postulated rupture of the thermal barrier heat exchanger.
Open The fuaction of these valves in the open direction is to provide Component Cooling water return from the Reactor Coolant Pump thennal barriers.
1/2CC9413A Closed l
These valves are located on the Component Cooling supply line to the Reactor Coolant Pumps (RCP's).
The safety function of these valves in the closed direction is to provide a leak tight barrier between the containment atmosphere.and the environment during accident conditions.
i Open The function of thene valves in.the open direction.is to supply Component Cooling water to the Reactor Coolant Pumps.
h 4
4 (9998D/WPF/021694) 4.6 - page 20 of 70
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Rev. 12 RELIEF F,EDUEST VR-8 (continued) 1/2CC9414, 1/2CC9416 Closed These valves are located on the Component Cooling return line from the Reactor Coolant Pump (RCP) upper and lower motor bearing coolers.
The safety function of these valves in the closed direction is to provide a leak-tight barrier between the containment atmosphere and the environment during accident conditions.
Open The function of these valves in the open direction is to provide Component Cooling water return from the Reactor Coolant Pumps upper and lower motor bearing coolers.
Component Cooling water flow to the reactor coolant pumps is required at all times while the pumps are in operation and for an-extended period of time while in cold shutdown.
Failure of one of these valves in a closed position during an exercise test would result in a loss of cooling flow to the pumps and eventual pump damage and/or trip.
b.
1/2CC9486, 1/2CC9518, 1/2CC9534 1/2CC9486 Closed These check valves are located on the Component Cooling supply line to the Reactor Coolant Pump motor bearings and thermal barrier. The safety function of these valves in the' closed direction is to provide a leak-tight barrier between the containment atmosphere and the environment during accident conditions.
Open The function of these. valves in the open direction is to supply Component Cooling water to the Reactor Coolant Pump motor bearings and thermal barriers.
1 l
Component Cooling water flow to the reactor coolant pumps is-
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required at all times while the pumps are in operation'and after an extended period of time while in cold shutdown.
Failure of 1/2CC9486 in a closed position during an exercise test would result in a loss of cooling flow to the pumps and eventual pump damage and/or trip.
(9998D/WPF/021694) 4.6'- page 21 of 70
s Rev. 12 z
s RELIEF REOUEST VR-8 (continued) i 1/2CC9518 Closed I
These valves are located on the. Component Cooling water return line from the Reactor Coolant Pump thermal barrier. The safety function of these valves in the closed direction is to provide a leak-tight i
barrier between the containment' atmosphere and the environment during accident conditions.
Open The function of these valves in the open direction is to provide pressure equalization between inside containment isolation valves 1/2CC9438 and outside containment isolation valves 1/2CC685.
1/2CC9534 Closed These valves are located on the Component Cooling water return line from the-Reactor Coolant Pump motor-bearings. The safety function of these valves in the closed direction is to provide a leak-tight barrier between the containment atmosphere and the environment during accident' conditions.
Open The function of these valves in the open direction is to provide pressure equalization between piping inside and outside containment.
Full stroke (CT) and backflow (BT) testing of check valves 1/2CC9516 and 1/2CC9534 would interrupt flow from the RCP thermal barrier and motor bearings. Therefore, full flow testing of the 1/2CC9518 and 1/2CC9534 is only possible with the RCP's shut down.
6.
blternate Testino:
a.
Motor operated valves:
1/2CC685, 1/2CC9413A, 1/2CC9414, 1/2CC9416, 1/2CC9438 These valves will be stroke tested (see VR-1 for leak testing frequency) during cold shutdowns, provided all of the RCP's are not in operation (RCP's will not. necessarily be secured for the sole purpose of performing this test).
This testing period will be each refueling outage as a minimum, but no more frequently than 1
once per quarter.
(9998D/WPF/021694) 4.6 - page 22 of.70
'l
Rev. 12 RELIEF REOUEST VR-8 (continued) b.
1/2CC9486, 1/2CC9518, 1/2CC9534 Check valves 1/2CC9518 and 1/2CC9534 will be full stroke tested (CT) and backflow (BT) tested and 1/2CC9486 will be backflow (:BT) tested during cold shutdowns provided all of the reactor coolant pumps are not in operation (RCP's will not necessarily be secured for the sole purpose of performing this test). This testing period will be each refueling outage as a minimum, but not more frequently than once per quarter. Both these tests will be l
performed in conjunction with the seat leakage test.
7.
Justification:
This alternate test frequency has been previously approved for the motor operated valves contained in this relief request. Check valves 1/2CC9486 were previously approved for the backflow test to be performed at refueling frequency.
This alternate frequency will adequately maintain the system in a state of op= rational readinesn by testing these valves as often as safely possible. Shutting down the RCP's and the subsequent restarting incurs a reactor vessel overpressurization risk.
In addition, it is operationally undesirable due to the time and manpower involved in starting an RCP.
Also, an operator is required to observe the RCP shaft rotation upon starting.
Stopping and starting RCPs would add unnecessary radiation exposure (approximately 20 mrem).
8.
Acolicable Status:
This relief is requested once per quarter during the first inspection ~
interval.
-i 9.
Acoroval Status:
09/15/88 Relief granted for motor operated valves and 1/2CC9486 back
+
flow test 01/23/92 - Reorganized to:
1.
Add safety function of all valves.
j 2.
Add full stroke (CT) and backflow (BT) for check
)
valves 1/2CC9518 and 1/2CC9534 3.
Change from refuel frequency to cold shutdown with all RCPs off for the backflow (BT) test of 1/2CC9486 (9998D/WPF/021694) 4.6 - page 23 of 70 1
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CC SUPPLY WATER RCP MOTOR BEARINGS
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THERMAL BAPAIER BRNGS EXCESS LO PETURN INSIDE s'
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1 Rev. 12 RELIEF REOUEST VR-9 1.
Valve Number (ASME Code Class) -
1CV8100 (2) 2CV8100 '(2) 1CV8112 '(2) 2CV8112 (2) 1CV8113 ' ( 2 ).
2CV8113 (2) l 2.
Number of Valves 6
3.
ASME Code Cateaory:
A, AC 4.
ASME Code.Section XI Recuirements:
a.
Motor operated valves:
1/2CV8100 and 1/2CV8112 Relief is requested for these four (4) valves from the 3 month test frequency for the stroke (ST) test as stated in.ASNE.Section XI IWV-3521, " Category A and B valves shall be exercised at least once every 3 months, except as provided by. IWV-3412 (a), IWV-3415, and IWV-3416".
IWV-3412 (a) states that valves that cannot be.
exercised during plant operation shall be specifically'identif'ied' by the owner and shall be full stroke exercised during. cold shutdowns.
b.
Check valves: 1/2CV8113 Relief is requested for these two (2) valves from the 3 month test-frequency for the full stroke (CT) and backflow (BT) test as stated in ASME Section XI IWV-3521, " Check valves shall be exercised at least once every 3 months, except as provided lby IWV-3522".
IWV-3522 states that valves'thaticannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised during cold shutdowns.
5.
Basis for Relief:
^
a.
Motor operated valves:
1/2CV8100 and 1/2CVB112 Open These motor operated globe valves are located in the Reactor Coolant Pump seal water return lines.
Their function in the open direction is to permit seal water return flow from the Reactor Coolant Pumps to the seal water heat exchanger.
t (9998D/WPF/021694) 4.6 - page 24 of 70 T
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Rev. 12
'j RELIEF REOUEST VR-9 (continued)
Closed The safety function in the closed direction is to provide a leak-tight barrier between the containment atmosphere and the environment during accident conditions.
These valves cannot be tested during unit operation as seal flow from the reactor coolant pumps is required at all times while the pumps are in operation.
Failure of one of these valves in'the closed position during an exercise test.would result in an abnormal seal water return flow being diverted to the Pressurizer Relief Tank (PRT) by lifting a relief' valve (1/2CV8121) upstream sf the isolation valves.
b.
1/2CV8113 Closed These are normally closed check valves located across containment isolation valves 1/2CV8112 inside containment. Their safety function in the closed direction is to maintain the integrity of the Reactor Coolant Pressure Boundary and to provide a leak-tight barrier between the containment atmosphere and the environment during accident conditions.
Open The safety function of these valves in thelopen direction is to relieve any pressure that may buildup between containment isolation valves 1/2CV8100 and 1/2CV8112.
These check valves function only when both the associated containment isolation valves are closed. Therefore, they cannot be full stroke tested without closing the 1/2CV8100 and 1/2CV8112 valves.
6.
Alternate Testino:
a.
Motor operated valves:
1/2CV8100 and 1/2CV8112 These valves will be full stroke exercised during cold shutdown, provided all reactor coolant pumps are not in operation and seal leak-off can be isolated (RCP's will not' necessarily be secured for the sole purpose of performing this test). This testing period will be each refueling outage as a minimum, but no more frequently than once per quarter,
- (9998D/WPF/021694 )
4.6 - page 25 of 70
Rev. 12 RELIEF REOUEST VR-9 (continued) d b.
1/2CV8113 Since the 1/2CV8113 valves cannot be full stroke tested without closing the 1/2CV8100 and 1/2CV8112, they will also be full stroke tested and backflow tested during cold shutdown provided'all reactor coolant pumps are not in operation and seal-leak-off can be isolated. This test frequency'is the same as that of the 1/2CV8100 and 1/2CV8112.
7.
dyptification:
This alternate frequency will adequately maintain the system in a state of operational readiness, by testing these valves as-often as safely possible.
Shutting down the RCP's and the subsequent restarting incurs a reactor vessel overpressurization risk.
In addition, it is operationally undesirable due to the time and manpower involved in starting an RCP.
Also, two operators are required to observe the RCP shaft rotation upon starting.
Stopping and re-starting RCPs would add unnecessary radiation exposure (approximately 20 mrem).
8.
Aeolicable Status:
This relief is requested once per quarter during the first inspection interval.
9.
Acoroval Statug; 09/15/88 - Relief granted per SER for valves 1/2CV8100 and 1/2CV8112 09/14/90 Relief granted per SER for valves 1/2CV8100 and 1/2CV8112 01/23/92 - Reorganized to indicate safety function of all valves and to add full stroke test and backflow test of check valves 1/2CV8113 r
(9998D/WPF/021694) 4.6 - page 26 of 70 i
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CV8100 CV8112
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GENERAL DIAGRAM J
FOR INFORMATION ONE MG4-2
Rev. 12' RELIEF REOUEST VR-10 1.
yalve Number (ASME Code Clapal;.
11A066 (2) 2IA066 (2)
IIA 065 (2) 2IA065 (2)
IIA 091 (2) 2IA091 (2) 2.
Number of Valves:
6 3.
ASME Code Catecory: A and AC 4.
ASME Code.Section XI Recuirements:
a.
Air operated valves:
1/2IA065 and 1/2IA066 Relief is requested from the 3 month test frequency for the stroke test (ST) and fail safe test (PT) as stated in ASME Section XI IWV-3411, " Category A and B valves shall be exercised at least once every 3 months, except as provided by IWV-3412 (a), IWV-3415, and IWV-3416".
IWV 3412 (a) states that valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised during cold shutdown.
b.
1/2IA091 Relief is requested from the 3 month test frequency for the backflow (BT) test as stated in ASME Section XI, IWV-3521, " Check valves shall be exercised at least once every 3 months, except as.
provided by IWV-3522".
IWV-3522 states that valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised during cold shutdown.
5.
Basis for Relief:
a.
Air operated valves:
1/2IA065 and 1/2IA066 The 1/2IA065 and 1/2IA066 valves are the outboard and inboard (respectively) containment isolation valves for Instrument Air supply lincs to containment. The closed safety function of these valves is to provide a leak-tight barrier between the containment atmosphere and the environment during accident conditions.
Stroke testing of the 1/2IA065 and 1/2IA066 valves during plant operation or cold shutdown would, by design, isolate the air to air operated instruments inside the containment building.
(9998D/WPF/021694)
'4.6 - page 27 of 70 i
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Rev. 12 RELIEF REQUEST VR-19 (continued) b.
1/2IA091 The 1/2IA091. valves are located on the air supply lines to the 1/2IA066 valves. The 1/2IA066 valves are the inboard containment isolation valves for the Instrument Air supply lines-to containment. The safety function of the 1/2IA091 valves in the closed direction is to provide a leak-tight barrier between the containment atmosphere and the environment during ' accident conditions. The function in the open direction is to supply-control air to the 1/2IA066 valves.
Stroke testing of the 1/2IA091 valves cannot be performed without actuating the 1/2IA066 which would result in the isolation of all Instrument Air to containment.
6.
Alternate Testino:
a.
Air operated valves:
1/2IA065 and 1/2IA066 The 1/2IA065 and 1/2IA066 valves will be stroke tested (ST) and fail safe tested (PT) during refueling outages, b.
1/2IA091 The 1/2IA091 valves will be backflow tested (BT) during refueling outages. This backflow test will be done in conjunction with the seat leakage test.
7.
Justification:
a.
Air operator valves: 1/2IA065 and 1/2IA066 The full stroke exercising of the 1/2IA065 and 1/2IA066 Instrument Air containment isolation valves during unit power operations.or cold shutdowns, would introduce the possibility of major operating perturbations and/or. personnel safety concerns should these valves fail to re-open during testing activities.
The failure of these valves in the closed position, as a result of testing activities during plant operation or cold shutdown, would subsequently isolate the air operated instruments inside the containment building thus resulting in scenarios such as:
1.
Loss of Pressurizer Pressure Control -
The pressurizer spray valves 1/2RY455B & C and the pressurizer auxiliary spray valve 1/2CV8145 would fail
-l closed and not be available for pressurizer pressure control.
(9998D/WPF/021694) 4.6 - page 28 of 70
=..
Rev. 12 EELIEF REOUEST VR-10 (continuedl 2.
Loss of Chemical Volume Control System Letdown Flow (both normal and excess) and Charging Flow -
4 The loss of instrument air would cause a disruption in the unit letdown flow paths resulting in pressurizer level' increases. Such valves as the letdown orifice containment outlet header isolation valve 1/2CV8160, the letdown line isolation valves 1/2CV459 and 1/2CV460,- the letdown orifice outlet isolation valves 1/2CV8149A, B & C, the excess letdown heat exchanger inlet isolation valves 1/2CV8153A &
B, and the regenerative heat exchanger letdown inlet isolation valves 1/2CV8389A & B would go to their fail-closed positions. Additionally, the ability to normally make up reactor coolant inventory and adjust the reactor chemical shim (i.e. normal boration/ dilution) would also be lost as the regenerative heat exchanger inlet isolation valves 1/2CV8324A & B would fail to their respective closed positions.
3.
Loss of Component Cooling to Containment Penetrations -
The loss of instrument air supply would cause the penetration cooling supply flow control valve 1/2CC053.to go to its fail closed position. The loss of penetration cooling would result in elevated' temperatures.being imposed on the penetrations being supported by the component cooling system.
4.
Loss of Personnel Breathing Air.
The loss of Instrument Air supply to the Service Air downstream isolation valve 1/2SA033 would cause this valve to go to its fail close position.
This loss of Service Air in the containment building would eliminate the normal source of supplied breathing air needed to support numerous maintenance and component inspection activities in a contaminated environment, b.
1/2IA091 Check valves 1/2IA091 provide the air supply to maintain the 1/2IA066 valves in the open position. Testing of the 1/2IA091 valves in the closed position would force the 1/2IA066 valves to' their fail closed position, by design, causing loss of instrument air to containment. Loss of Instrument' Air would result in scenarios such as those previously listed.
(9998D/WPF/021694) 4.6 - page 29 of 70 1
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Rev. 12 RELIEF REOUEST VR-10 (continuedl 8.
Aeolicable Status:
d l
This relief is request once per quarter during the first inspection interval.
9.
Anoroval Statual 09/15/88 Relief' denied per SER 12/16/88 - Revised (to address NRC concerns) in Byron response to SER (Byron Station Letter 88-1321) 09/14/90 - Relief for Part A granted per SER 01/23/92 - Reorganized to indicate safety function of all valves and to add backflow test (. T) of check valves 1/2IA091 B
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I (9998D/WPF/021694 )
4.6 - page 30 of 70 y
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l GENERAL DIAGRAM 4F FOR INFORMATION ONLY M55-4
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.I Rev. 12 i
RELIEF REOUEST VR-11 1
" DELETED" Deleted relief request VR-11 per EG & G recommendation. This was a request for extension of position indication tests from every two years to every three years.
d (9998D/WPF/021694 )
4.6 - page 31 of-70 e
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Rev. 12 RELIEF REQUEST VR-12 1.
yp1ve Number: Valves that normally stroke in 2 seconds or less:
I VALVE #
VALVE #
VALVE #
VALVE #
1MS018A-D 2MS018A-D 1PR066 2PR066 1RE9157 2RE9157 1PS228A, B 2PS228A, B 1RE9159A, B 2RE9159A, B
~
1PS229A, B 2PS229A, B 1RE9160A, B 2RE9160A, B 1PS230A, B 2PS230A, B 1RY8033 2RY8033.
1RC014A-D 2RC014A-D ISI8871-
.2SI8871 2SD002A H 2.
Number of Items:
52 3,
ASME Code Cateuorv A&B 4.
ASME Code.Section XI Reauirements:
Verification, by trending of power operated valve times, that'an increase in stroke time of 50% or more, from the previous. test, does not-occur, per IWV-3417 (a) 5.
Basis for Relief:
Minor timing inaccuracies, with small stroke times can lead to substantial increases (percent wise) in stroke times.
For example, a
~
valve with a stroke time of 1 second in an initial test,:and 1.6 seconds in the subsequent test, has experienced an apparent 60% increase in stroke time.
If the accuracy requirements of IWV-3413 (b) are utilized, it could be argued that stroke times between 1 and 2 seconds could constitute as much as a 100% increase in stroke. time when, in fact,.only a 0.2 second increase occurred.
For instance, if the initial time was 1.4 seconds, (measured to the nearest second is 1,0 second) ' and'If the next time is then 1.6 seconds, (measured to the nearest second is 2.0 seconds) the percent increase is 100%.
2 1
(9998D/WPF/021694 )
.4.6
- page 32 of 70
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d Rav, 12 RELIEF REDUEST VR-12 (continued
'l 6.
Alternate Testino:
i II Fast acting valves can be defined as those valves that normally stroke in 2 seconds or less.
No trending of stroke time will be required, and upon exceeding 2 seconds, corrective action shall be taken-immediately in accordance with IWV-3417 (b).
7.
Justification:
For small stroke times, the trending requirements are too stringent for the accuracies specified in the Code. The alternative specified.will adequately maintain the system in a state of operational readiness, while not imposing undue hardships or sacrificing the safety of the plant.
8.
Aonlicable Time Period:
This relief is requested once per quarter, during the first inspection-interval.
9.
Anoroval Status a.
Relief denied per SER 9/15/88.
b.
Revised (to address NRC concerns) in. Byron response to SER 12/16/88 (Byron Station Letter 88-1321).
c.
Relief granted per SER 9/14/90, l
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I (9998D/WPF/021694) 4.6 - page 33 of 70 i
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Rev. 12
.I' RELIEF REOUEST VR-13 1.
Valve Numbers:
1DG5182A,B 2DG5182A,B 1DG5183A,B 2DG5183A,B 1DG5184A,B 2DG5184A,B 1DG5185A,B 2DG5185A,B 2.
Number of Itemat 16 3.
ASME Code Catecorv: B&C 4.
ASME Code Section XI Recuirements:
These valves are not within the scope of ASME Code,Section XI, Subsection IWV requirements. However, the requirements for stroke timing and trending of the. valves associated with the Diesel Air Start System are being mandated by the NRC as an augmented testing requirement pursuant to 10CFR50.55 (a) (g).
Therefore, valves associated with the Diesel Air Start System shall be exercised to the position required to fulfill their function during plant operation per IWV-3412 and IWV-3522.
Additionally, the stroke'-
testing.of power operated valves shall be measured to the nearest second-and such stroke times trended to document continued valve operational readiness per IWV-3413 (b) and IWV-3417.
i 5.
Rasis for Relief:
y I
The monthly Diesel Generator testing program, outlined in Byron Station's Technical Specifications and implemented by station operating procedures, exceeds the intent of the quarterly valve testing program which would be required by ASME Code,.Section XI.
Additionally, the stroke timing of solenoid operated valves associated with the Diesel Air Start System is impractical due to the fact actuation of these valves.
6.
Alj;,,ernate Testing 1 The performance of Byron Station's Diesel Generator operability monthly surveillance will verify the operational readiness of the valves associated with the Diesel Air Start System.
This surveillance testing will require the recording of the air pressures contained in both trains A & B of the Diesel' Generator Air Start Receiver Tanks both before and immediately after diesel generator start.
By the comparison of these valves between trains, the satisfactory 4
operation of the power operated and self-actuated check valves
~
associated with the Diesel Air Start System can be adequately' demonstrated.
(9998D/WPF/021694 )
4.6 - page 34 of 70 l
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Justification:
Proper valve operation will be demonstrated on a monthly basis by the verification of diesel generator air start capability.
Such verification will compare the air pressures contained in the receiver tanks both before and after the diesel generator start, thus verifying
.the operability of the air start control valves. The proposed testing-methodology at the increased frequency satisfies the intent of the Section XI requirements without posing undue hardships or difficulties.
8.
Aonlicable Time Period!
This relief is requested once per quarter during the first inspection interval.
9.
ADoroval Status:
a.
Relief granted per SER 9/15/88.
b.
Relief granted per NRC Generic Letter 89-04, c.
Relief granted per SER 9/14/90.
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(9998D/WPF/021694) 4.6 - page 35 of 70
.. - ~.
Rev. 12 RELIEF REOUEST VR-14 I
" DELETED" Deleted relief request VR-14.
This was a request for exemption for position indicating tests for solenoid operated valves. Alternate testing allowed by the ASME Code will be used instead.
(9998D/WPF/021694) 4.6 - page 36 of 70
_ ~
i Rev. 12' l
RELIEF REQUEST VR-15
+
1.
Valve Numbergi 1CV8481A, B 2CV8481A, B 1CV8546 2CV8546 ISI8815 2 SIB 815 ISI8819A-D 2SI8819A-D ISI8841A, B 2 SIB 841A, B 1SI8900A-D 2SI8900A-D ISI8905A-D 2SI8905A-D ISI8949A-D 2SI8949A-D 2.
Number of Valves:
44 3.
ASME Code,Section XI Recuirements:
Check valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised during cold shutdowns per IWV-3412 and IWV-3522.
5.
Basis for Relief:
The full stroke exercising of check valves not stroked quarterly is required to be performed during cold shutdowns.
However, the stroking' of check valves 1/2SI8815, 1/2SI8900A-D, 1/2SI8949A-D,-and 1/2SI8841A, B, associated with Emergency Core Cooling System, during cold shutdowns will induce thermal stresses on their respective reactor vessel nozzles as the Reactor Coolant System (maintained approximately 180*F) is injected with water from the Refueling Water Storage Tank (maintained approximately 65'F.
This also applies to the stroking of check valves 1/2CV8546 and 1/2CV8481A,B because the full stroke of these check valves causes stroking of 1/2SI8815 and 1/2SI8900A-D located in the full flow path.
Additionally, Byron Station Technical Specifications require all Safety.
Injection Pumps and all but one Charging Pump to be inoperable during Modes 4, 5, and 6, except when the reactor vessel head is removed. This requirement minimizes the possibility of low temperature over-pressurization of the Reactor Coolant System. Therefore, check valves 1/2SI8819A-D, 1/2SI8905A-D, and 1/2SI8949A-D, cannot be full stroke exercised during routine Mode 5' cold shutdowns as required by IWV-3412 and IWV-3522 In addition to the stroke test exercise used to verify operational readiness of these check valves, the act of such stroking cause the necessity for Technical Specification required leak rate testing of these valves prior to unit criticality. This testing, in conjunction with the stroke exercising of these check valves, adds approximately one week to the duration of any outage and additional radiation exposure to workers who must connect flowmeters and differential pressure gauges:
I directly to pipes containing radioactive fluids.
(9998D/WPF/021694 )
4.6 - page 37 of 70
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4 Rav. 12 RELIEF REOUEST VR-15 (continued) i 6.
Alternate Testino:
Byron Station's Technical Specifications require routine leak rate testing to be performed on these Reactor Coolant System Boundary Isolation check valves if the unit is in Cold Shutdown for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and such leak rate testing has not been performed within the previous nine months. Therefore, Byron Station will stroke exercise check valves 1/2SI8815, 1/2SI8900A-D, andz1/2SI8841A,'B on the same l
schedule. To prevent unnecessary stroking of check valves 1/2 SIB 815 and 1/2SI8900A D. check valves 1/2CV8546~and 1/2CV8481A, B will be stroke exercised on the same schedule as check valves 1/2SI8815, 1/2SI8900A-D and 1/2SI8841A, B.
Additionally, stroke exercising of check valves 1/2 SIB 819A-D, 1/2SI8949A-D, and 1/2SI8905A-D can'only be safely performed in Mode 6 with the Reactor Vessel head removed.
Full. stroke exercising of these check valves will be performed at a minimum frequency of once each refueling outage.
7.
hstificasion:
Stroke exercising the 1/2CV8481A, B,
1/2CV8546, and 1/2 SIB 815 1/2SI8900A D, and 1/2SI8841A, B check valves on the same schedule as.
their required Technical Specification Reactor Coolant System boundary Isolation leak rate testing will allow the coordination of testing activities without. imposing additional check valve. leak rate testing.
requirements.
Such activity coordination will optimize testing efforts and resources.while adequately maintaining the system in a state of operational-readiness. Valves 1/2SI8949A-D,,1/2SI8905A-D and 1/2SI8819A-D can not be stroked during cold' shutdown without exceeding Technical Specification limiting condition for operation-(LCO 3/4.5.3) t since stroking these valves requires starting a SI pump..
Stroke exercising check valves 1/2SIA819A-D, 1/2SI8905A-D and 1/2SI8949A-D at least once per Reactor Refueling mode of operation, will insure compliance with Byron Station Technical Specifications and' minimize the possibility of low temperature over pressurization of the reactor Coolant System.
+
8.
boolicable Time Period:
This relief in requested once per quarter during the first inspection interval.
(9998D/WPF/021694 )
4.G - page 38 of 70 i
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I Rev. 12 I
RELIEF REQUEST VR-15 (continued) 9.
ADoroval Status:
1 a.
Relief granted per SER 9/15/88 for valves 1/2 SIB 819A-D, 1/2 SIB 905A-D, and 1/2SI8949A-D; relief denied per SER 9/15/88 for valves 1/2SI8815,.1/2 SIB 841A, B, and 1/2SI8900A-D.
b.
Revised (to address NRC concerns) in Byron response to SER 12/16/90 (Byron Station Letter 88 1321).
c.
Relief granted per NRC Generic Letter 89-04.
d.
Relief granted per SER 9/14/90.
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(9998D/WPF/021694 )
4.6-- page 39 of 70
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Rev. 12 l
DRAFT RELIEF REQtJERT VR-15A 1.
Vglve Numbers:
ICV 8481A,B 2 CV84 81A, B CV Pmp Dsch ICV 8546 2CV8546 CV Pmp Comb Suction 1 SIB 815 2SI8815 CV Inject Comb Hdr 1SI8900A D 2 SIB 900A-D CV Cold Leg. Inject.
2.
Egmber of Valves: 16 P
3.
ASME Code Cateoorv:
AC.
4.
ASME Code.Section XI Recuirements:
Relief is requested from both the quarterly and cold shutdown exercise frequencies for the full stroke (Ct) and backflow (Bt) tests for the above check valves as required by paragraphs IWV-3521 and IWV-3522.
i 5.
Basis for Relief:
Safety Function 1/2SI8P3; Open This valve is in the line from the Chemical and Volume Control (CV) Centrifugal Charging pump.
Its safety function in the open direction is to permit flow of coolant from the centrifugal charging pump to the 'four lines which branch off and provide flow to the reactor cold legs during the high pressure injection phase of a safety injection, Closed The safety function of this valve in the closed direction is to provide a redundant. (back up to the 1/2SI8900A-D check valves) reactor coolant system pressure boundary (PIV),
i 1/2SI8900A-D Open These-valves are in the four lines which branch off from the lines containing the 1/2SI8815 valves mentioned above.
Their safety function in the open direction is to permit flow of coolant from the chemical and volume control
~
centrifugal charging pumps to the reactor cold legs during the high pressure injection phase of a safety injection.
closed The safety function of these valves in the closed direction is to provide a reactor coolant pressure boundary.
(9998D/WPF/021694) 4.6 page 40 of 70
m Rev. 12 DRAFT REREF REOUEST VR-15_A (continued) l 1/2CV8481A,B Open These check valves are located at'the discharge of the Chemical and Volume Control charging pump. 'Their function is to prevent reverse flow from the charging header when the pump is not in operation. The safety function in the open position is to permit flow of coolant during a safety injection.
1/2CV8546 Open This check valve is the cambined suction of the charging pumps f rom the Refueling Water Storage Tank (RWST). Their.
function is to prevent flow from the suction header. The safety function in the open position is to permit flow of
. coolant when the charging pumps tak.e suction from the RWST during a safety injection.
Basis The full stroke exercising of check valves.1/2SI8815 and 1/2SI8900A-D associated with the Emergency Core Cooling System during-operation would induce thermal stresses on their respective reactor vessel nozzles as the Reac;cr Coolant System (maintained at greater than 500
- F) is.
injected with water from the Refueling Water StorsQe Tank (maintained at approximately 65
- F).
The 1/2CV8481A,B and 1/2CV8546 check valves are in series and cannot be full stroke exercised without causing stroking of 1/2 SIB 815 and 1/2SI8900A-D.
These valves cannot be exercised during cold shutdowns without increasing the possibility of low temperature over-pressurization (LTOP) of the Reactor Coolant System. The Byron Station Technical specifications require that all Safety Injection Pumps and.all but one l
Charging Pump be inoperable during Modes 4, 5 and 6, except when the reactor vessel head is removed to prevent this over-pressurization occurring while at low temperatures. 'In addition, injecting large quantities of highly borated water from the RWST would likely; delay
-l reactor start up and the cost of processing the reactor coolant to i
restore the optimum boron concentration is consequential.
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(9998D/WPF/021694 )
4.6 - page 41 of 70 F
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Rev. 12 DRAFT
_RELIEl.REOUEST VR-154 (continued)
The 1/2SI8900A-D and 1/2SI8815 check valves can only be verified closed by performance of an individual leakage' test on each valve. These valves are simple lift check. valves and are not equipped with an-external operator or disk position indication.
It is impractical to verify them closed during power operation or during cold shutdowns.
System reconfiguration'and connecting and disconnecting leak testing equipment during cold shutdowns would likely delay the return to power.
This would be costly and burdensome to the station.
System redesign and modification would be necessary to allow testing these valves closed quarterly, which would also be costly and burdensome. Both of these alternatives would provide no compensating increase in plant safety.
6.
Alternate Testing 1 Byron Station will full stroke exercise (open--Ct; close--Bt) the 1/2 SIB 815 and 1/2SI8900A-D on a refueling frequency test schedule.
These valves are verified closed in conjunction with the Technical Specification pressure isolation valve leakage test.
Check valves 1/2CV8481A, B; 1/2CV8546 cannot be full stroke exercised without causing stroking of 1/2SI8815 and 1/2SI8900A-D, therefore they will be full stroke exercised on the same schedule (refueling frequency) as the 1/2SI8815 and 1/2SI8900A-D valves.
7.
Jystification Based on the guidance provided in question 24 of the "Public Meeting notes on Generic Letter 89 04":
check valves possessing safety functions in both the open and closed direction should be stroked to the open position and then tested in the closed position.
For the 1/2 SIB 815 and 1/2SI8900A-D valves, it is best to perform the backflow - (Bt) test, which in this case is accomplished in conjunction with the leakage test (Lt), on the same frequency as the full flow (Ct) test, thus stroking them to their open position and then testing in their closed position.
Check valves 1/2CV8481A, B and 1/2CV8546 cannot be full stroke exercised without causing stroking of 1/2SI8815 and 1/2SI8900A-D because of the system configuration. Therefore, 1/2CV8481A/B will be full flow (Ct) and backflow (Bt) tested in conjunction with the 1/2SI8815 and 1/2SI8900A-D full flow test (B train backflow tested during A train full flow and vice versa). The 1/2CV8546 will also be full flow (Ct) - tested in conjunction with the full flow test of the 1/2SI8815 and 1/2SI8900s.
(9998D/WPF/021694) 4.6 - page 42 of 70
Rev. 12 DRAFT RELIEF REAQEST VR-15A (continued) 7 Justification:
(continued)
In addition, the high pressure (from CV pumps) safety injection _ check i
valves will have their seat tightness demonstrated during the Byron Station Technical Specification testing required to verify the pressure isolation capability of these valves under the following conditions:
a.
At least once per 18 months.
b.
Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months.
c.
Prior to returning the valve to service following maintenance, repair or replacement work on the valve, and i
d.
Within the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to manual action or flow through the valve.
t The alternate test frequency will adequately maintain this portion of the safety injection system in a state of operational. readiness, while not sacrificing the safety of the plant, by testing these check valves at each refueling outage, when the safety risks are minimal.
S.
Aeolicable Status:
This relief is requested for the first inspection interval.
9.
Anoroval Status:
i a.
Braidwood has approval. Byron is submitting the same relief request anticipating a combined Byron /Braidwood program submittal in 1995.
However, this is a new submittal for Byron and is not specifically approved for Byron. Approved VR-15 will be used in the interim.
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Rev. 12 s
DRAFT RELIEF REOUEST VR-15]l 1.
Valve Number:
1RH8705A,B 2RH8705A, B RH Suction Isolation Thermal / Pressure Relief 2.
Number of Valves, 4 r
3.
ASME Code Catecorv:
AC 4.
ASME Code,Section XI Recuirements:
Relief is requested from both the quarterly and cold shutdown exercise frequencies for the full stroke (Ct) and backflow (Bt) tests for the above check valves as required by paragraphs IWV-3521 and IWV-3522.
5.
Basis for Relief:
Safety Function 1/RHB705A, B Open These valves are located on the 3/4" branch line between the 1/2RH8701A, B and 1/2RHB702A, B RH suction isolation valves.
Their safety function in the open direction is to relieve excess pressure due to thermal expansion back to the RCS when both suction isolation valves are closed in order to prevent over pressurization of the piping.
Closed The safety function of these valves in the closed direction' j
is to maintain the integrity of the reactor coolant pressure boundary.
The 1/2RH8705A, B and 1/2RH8705A, B thermal / pressure relief check valves can only be verified closed by performance of an individual i
leakage test on each valve.
These valves are simple' spring loaded q
lift check valves and are not equipped with an external operator or disk position indication.
It is impractical to verify them i
closed during power operation or during cold shutdowns.
System reconfiguration and connecting and disconnecting leak testing equipment in conjunction with depressurizing the RCS during cold
)
shutdowns would delay the return to power. This would be costly' and burdensome to the station. System redesign and modification would be necessary to allow testing these valves closed quarterly, which would also be costly and burdensome.
(9998D/WPF/021694) 4.6 - page 44 of 70
l Rev. 12 DRAFT RELIEF REQUEST VR-15B (continued) 6.
Alternate Testino:
The 1/2RH8705A/B check valves will be operability tested in the open-direction by verifying that the piping between the suction isolation.
valves is able to be depressurized through the applicable valve. The PIV leakage test will be used to verify valve closure and seat tightness. Both of these (Ct-open, Bt-closed) tests will be perfonmed at each reactor refueling outage.
7.
Justification Performing the exercise test requires placing the standby train of residual heat removal (RHR) in an inoperable condition and that the RCS be depressurized (requires all four reactor coolant pumps to be stopped).
This will delay reactor start up and return to power.
In addition, taking away the back/ redundant train of RHR reduces both'the
[
plant decay removal capability and the available safety margin regarding shutdown risk assessment.
Furthermore, these valves are also given.
specific exemption from being leakage tested (no closure test required) following flow through the suction isolations per Technical Specifications (regarding PIV testing).
This alternate test frequency is adequate to maintain this portion of RHR in a state of operational readiness,-while not sacrificing the safety of the plant, or causing undue hardship in returning to power with no compensated increase in' safety.
I 8.
ADolicable Status:
This relief is requested for the first inspection interval.
1 9.
Acoroval Status:
a.
Braidwood has approval. Byron is submitting the same Relief request anticipating a combined Byron /Braidwood's.
a submittal in 1995.
However, this is a new submittal and is not specifically I
approved for Byron.
4 (999 BD/WPF/021694 )
4.6 - page 45 of 70
Rev. 12 DRAFT t
RELIEF REOUEST VR-15C 1.
yglve Number:
1 SIB 819A-D 2SI8819A-D SI Cold Leg Inj 1SI8905A-D 2SI8905A-D SI Hot Leg Inj 1 SIB 949B,D 2SI8949B,D SI/RH Hot Leg Inj 2.
Number of Valves:
20 3.
ASME Code Catecorv:
AC 4.
ASME Code,Section XI Reauireinents:
Relief is requested from both the quarterly and cold shutdown exercise frequencies for the full stroke (CT) test and backflow (:BT) test as-stated in ASNE Section XI IWV 3521:
" Check Valves shall be exercised at least once every 3 months, except as provided by IWV-3522."
5.
Basis for Relief Safety Function 1/2 SIB 819A-D Open These valves are located in the lines going from the Safety Injection pumps to the reactor vessel cold legs. Their safety function in the open direction is to permit flow of coolant to the reactor cold legs'during a safety injection.
Closed The' safety. function of these valves in the closed direction is to maintain the reactor coolant system pressure boundary (PIV).
1/2SI8905A-D Open The safety function of this valve in the open direction is.
to permit flow of coolant from the Safety Injection pump to the reactor vessel hot legs during.the Hot Leg-Recirculation portion of a safety injection.
Closed The closed safety function of this valve'is to maintain the reactor coolant pressure boundary.
(9998D/WPF/021694) 4,6 - page 46.of 70
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Rev. 12 DRAFT RELIEF REOUEST VR-15C (continued) 5.
Basis for Relief:
Safety Function (continued) 1/2SI8949B,D Open The safety function of this valve in the open direction is-to permit flow of coolant from the Safety Injection pumps to the reactor vessel hot legs during the Hot Leg Recirculation portion of a safety injection.
Closed The closed safety function of these valves is to maintain the reactor coolant pressure boundary.
These valves cannot be full stroke exercised during operation or during_
routine Mode 5 cold shutdowns due to Byron Station Technical Specifications requirement that all Safety Injection Pumps and all but one Charging Pump be inoperable during modes 4, 5,'and 6 (temperature less then - 350' F), except when the reactor vessel head is removed (the reactor head is only removed during refueling outages). This requirement minimizes the possibility of low temperature over--
pressurizatien (LTOP) of the Reactor Coolant System (RCS).
6, Alternate Testino:
Full stroke exercising of these valves can only be safely performed in Mode 6 with the Reactor vessel head removed. Therefore, full stroke exercising and backflow testing of these valves will be performed at each. refueling outage.
7.
Justification:
These check valves cannot be stroked during cold shutdown without exceeding Technical Specification limiting condition for operation (LCO 3/4.5.3).
Since stroking these valves' requires starting an SI pump.
't Stroke exercising check valves 1/2SI8819A-D, 1/2SI8905A-D,'and 1/2SI8949B,D during each reactor refueling outage, will insure compliance with Byron Station Technical Specification and will reduce the risk of low temperature over-pressurization of the. Reactor Coolant System.
8 Apolicable Status:
This relief is requested for the first inspection interval.
(9998D/WFF/021694) 4.6 - page 47 of 70
Rev. 12 DRAFT RELIEF REQUEST VR-15C (continued) 9.
Acoroval Status:
a.
Braidwood has approval. Byron is submittin the same Relief request anticipating a combined Byron /Braidwood program submittal.
in 1995.
However, this is a new submittal and is not specifically approved for Byron, Approved VR 15 will be used in the interim; l
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.i (9998D/WPF/021694) 4.6 - page 48 of 70
Rev. 12 DRAFT PELIEF REQUEST VR-1.1Q 1.
Valve Number:
ISI8841A,B 2SI8841A,B Mi Hot Leg Inj ISI8949A,C 2SI8949A,C SI/RH Hot Leg Inj 2.
Number of Valves: 8 3.
ASME Code Category:
AC 4.
ASME Coder Section XI RecuirementSi Relief is requested from both the quarterly and cold shutdown exercise frequencies for the full' stroke (Ct) test and backlow (Bt) tests as stated in ASME Section XI IWV-3521:
" Check Valves shall be exercised at least once every 3 months, except as provided by IWV-3522."
5.
Basis for Relief:
ggfety Function 1/2 SIB 841A,B Open The safety function of the 1/2SI8841A,B check valves in the open direction is to permit flow of coolant from'the RHR Pumps to the reactor vessel hot legs during the Hot Leg Recirculation phase of a safety injection.
Closed The safety function of these valves'in the closed direction is to maintain the reactor coolant system pressure boundary (PIV).
1/2SI8949A,C Open The. safety-function of the 1/2SI8949A,C check-valves in the open direction is to permit flow of makup water'upon a safety injection from: -(1) the' Safety Injection Pumps during the high pressure safety injection phase, or (2) the RHR Pumps during the Hot Leg Recirculation phase, to the reactor vessel hot legs.
Closed The closed safety function of these valves is to maintain.
the reactor coolant pressure boundary.
(9998D/WPF/021694) 4.6.- page 49 of 70
'Rev. 12 1
DNAFT REkIELEELUEST "R-JE continued 5.
Basis for Relief:
Eg{ety Function (continued)
Basis The full stroke exercising of check valves 1/2 SIB 841A,B and 1/2SI8949A,C, associated with the Emergency Core Cooling System (ECCS)-
and the Residual Heat Removal (RHR) System cannot be accomplished'during normal reactor operation because of the low head developed by the RHR pumps (less than 250 psi) is not great enough to-inject water into the RCS (2235 psi).
In addition, the SI Pumps cannot be used to full stroke the 1/2SI8949A,C check valves at power due to:
(1) the high thermal stresses imposed on the reactor vessel nozzles, (2) the margin of safety is reduced for brittle fracture prevention, and (3) an unacceptable reactivity excursion would be created (high boron concentration and low temperature-water).
Exercising these check valves in cold shutdowns is not practical, full or partial, because they are required by Technical Specifications to be leak tested if there has been flow through them.
This leak rate testing will cause a delay in returning the plant to power.
Flow testing and the resultant leak rate testing would cause unnecessary radiation exposure to test personnel.
6.
Alternate Testino:
j These check valves will be exercised-(CT-open), Bt-closed) during each refueling outage and is consistent with_AMSE/ ANSI Part 10, 4.3.2.2 regarding deferral of check valve exercising until refueling outages, which was approved in rulemaking to 10CFR 50.55a effective September 8, 1992.
The closure test is done in conjunction with the leak test.
P
- (999 aD/WPF/ 021694 )
4.6 - page 50 of 70
Rev. 12 DRAFT RELIEF REQQEST VR-1ED continued 7
Justification:
Based on the guidance provided in question 24 of the "Public Meeting notes on Generic Letter 89-04":
" Check valves possessing safety functions in both the open and closed direction should be stroked to the open position and then tested in the closed position.
For the 1/2SI8841A,B and 1/2SI8949A,C valves, it is best to perform the backflow (Bt) test, which in this case is accomplished in conjunction with the leakage test (Lt), on the same frequency as the full flow (Ct) test, thus testing them to their open position and then to their closed position.
The alternate test frequency is adequate to maintain this portion of RHR in a state of operation readiness, while not sacrificing the safety of the plant, or causing undue hardship in returning to power with no compensating increase in safety.
8.
Acolicable Status:
This relief is requested for the first inspection interval.
l 9.
Angroval Status:
I a,
Braidwood has approval.
Byron is submitting the same Relief request anticipating a combined Byron /Braidwood program submittal-in 1995. However, this is a new submittal'and is not specifically approved for Byron. Approved VR-15 will be used in the interim.
i
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(9998D/WPF/021694) 4.6 - page 51.of 70
.i
l Rev. 12
. RELIEF REOUEST VR-16 1.
Valve Numbers:
1SI8811A, B 2SI8811A, B 2.
Number of Valves:
4 3.
ASME Code Catecorv: B 4.
ASME Code.Section XI Reouirementsi Valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised-during cold shutdowns per IWV-3412.
5.
Basis for Relief:
The full stroke exercising of valves not stroked quarterly is required to be performed during cold shutdowns. However, the stroking of the Containment Sump Outlet Isolation valves, 1/2SI8811A, B requires the suction of the Residual Heat Removal Pumps to be drained, thus rendering.
one train of the system inoperable.
For Cold Shutdown operations with the Reactor Coolant Loops filled and one train of Residual Heat Removal declared inoperable, Byron Station's Technical Specifications require two steam generators with a secondary side narrow range water level greater than 41% (Unit 1) and greater than 18% (Unit 2).
However, if the cold shutdown was necessitated by a problem requiring draining of the secondary side of the Steam Generators (i.e. tube leaks), Byron Station's Technical Specification 3.4.1.4.l' would preclude the testing of the containment sump outlet isolation valves until such time as the affected' steam' generators had been refilled.
For Cold Shutdown operations with the Reactor Coolant Loops not filled (i.e. drained down to support Reactor Vessel Incore-Seal Table, Loop Stop Valve, Reactor Coolant Pump and Seal Maintenance or primary leakage), Byron Station's Technical Specification 3.4.1.4.2 would
. preclude the. testing of the Containment Sump Outlet ~ Isolation Valves as it mandates that "two residual heat removal (RHR) Loops shall be operable and at least one RHR Loop shall be in operation".
6.
Alternate Testino:
Byron Station will full stroke exercise the Containment Sump Outlet Isolation Valves, 1/2SI8811A, B during refueling outages vice' cold shutdown.
(9998D/WPF/021694) 4.6 - page 52 of 70:
l I
j r--
Rev. 12 RELIEF REOUEST VR-16 (continued) i l
)
7.
Justification:
The full stroke testing of the 1/2SI8811A, B valves; in conjunction with system draining, filling and venting of each train, accounts for'an additional six days (3 days per train) of scheduling requirements and increased radiation dose to operators and radiological control personnel.
Processing of thousands of gallons of containment water, and
~
subsequent required liquid effluent discharges would also result from the draining, refilling and venting of the RHR system. This time duration required to perform the surveillance testing of the Containment Sump Outlet Isolation Valves during Cold Shutdown activities, could, as a result, cause a violation of the action requirements for Byron Station's Technical Specifications 3.4.1.4.1 and 3.4.1.4.2.
The violations would occur since these action statements require (as_noted in their respective foot note sections) the return of the inoperable residual heat removal loop to service within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, if such loop was removed for surveillance testing provided the other RHR Loop'is operable and in operation.
In addition, NRC Generic Letter 88-17, Loss of Decay Heat Removal, highlights the consequences of.a loss of RH during reduced Reactor Coolant System inventory (below three feet below the reactor vessel flange).
If the operating RH pump is lost due to air entertainment, and the other train is inoperable for the stroke test, then the " operable" train must be vented to restore decay heat removal. Under worst conditions, boiling in the core would occur in approximately 10 minutes, the core would be uncovered in approximately 30 minutes, and fuel damage would occur in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Given the apparent disparity,between the Technical Specification time requirements for an inoperable RHR Loop return to service (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and the time required to perform surveillance stroke testing of the Containment Sump Outlet Isolation valves (3 days) during Cold Shutdown, the proposed alternate testing frequency of refueling outage periodicity.
will adequately maintain the system-in a state of operational readiness, while not imposing undue hardships or sacrificing the safety of the plant.
8.
Acolicable Time Period:
This relief is requested once per quarter, during the first' inspection interval.
9.
Acoroval Status:
a.
Relief denied per SER 9/15/88.
b.
Revised (to address NRC concerns) in Byron response to SER 12/16/90.
c.
Relief granted per SER 9/14/90.
(9998D/WPF/021694 )
4.6 - page 53 of 70 p
4 4
m
Rev. 12 RELIEF REOUEST VR-17 1.
Valve Numbers:
1SX101A 2SX101A 2.
Number of Valves:
2 3.
ASME Code Catecorv:
B 4.
ASME Code.Section XI Reauirements:
Stroke time and trend the stroke time for power operated valves per IWV-3413 and IWV-3417.
5.
Basis for Relief; 1/2SX101A are the essential service water outlet isolation valves for the Unit 1/2 motor driven auxiliary feedwater pump lube oil coolers.
These valves are completely encapsulated per design and do not have local or remote position indicators which could be used to time the valve stroke.
6.
Alternate Testino:
1/2SX101A-will be verified to open during each quarterly ASME surveillance of the motor driven auxiliary feedwater pumps.
In addition, these valves are stroked monthly during auxiliary feedwater pump surveillance required by Byron Station Technical Specifications.
7 Justification:
These valves will be stroke exercised to their required safety positions each month during the motor driven auxiliary feedwater pump surveillances. This testing will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant.
8.
Acolicable Time Period:
This relief is requested once per quarter during'the first inspection interval.
9.
Acoroval Status:
a.
Relief granted per SER 9/15/88.
b.
Relief granted per NRC Generic Letter 89-04.
c.
Relief granted per SER 9/14/90.
(9998D/WPF/021694) 4.6 - page 54 of 70 i
, -., ~,,..
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. ~ _ _., _.
Rev.'12 RELIEF REOUEST VR-18
" DELETED" Deleted relief request VR-18 and re organized into several new and existing relief requests per NRC suggestion:
VR*5, VR-8, VR-9, VR 10, VR-23, and VR-24.
(9998D/WPF/021694) 4.6 - page 55 of 70
s m,
Rev. 12 RELIEF REOUEST VR-19 1.
Yalve Numbers:
1AF001A 2AF031A 1AF001B 2AF001B 2.
Number of Valves:
4 3.
ASME Code Cateaory:
C 4.
ASME Code.Section XI Reauirement:
Exercise check valves to the position required to fulfill their function (Bt/ Closed, Ct/Open), unless such operation is not practical'during plant operation, per IWV-3522.
5.
Basis for Relief:
The 1/2AF001A/B valves are the suction check valves to the AFW pumps from the condensate storage tanks, and function to prevent backflow of essential service water if that suction source is required.
It is undesirable to full stroke open these valves quarterly due to the transients placed en the feedwater system and the thermal stresses imposed on the steam generator (S/G) nozzles (refer to program note 12).
With respect to acoustically testing these valves to prove closure, versus disassembly, the operating surveillance procedure used for the auxiliary feedwater (AFW) check valve cold shutdown full stroke test is written to test a single train of AFW at a time.
With an AFW pump running on mini-flow recirculation, flow is. initiated to'each S/G on a gradual basis, while simultaneously reducing feedwater flow. As soon as the required flow data is obtained, AFW flow is gradually reduced, while simultaneously increasing feedwater flow, to minimize feedwater flow perturbations to the S/Gs. Due to this gradual change in flow, the open and close acoustical impacts cannot be observed from that of the flow noise.
However, the acoustic data taken during the 18 month dual pump injection test, has provided sufficient data to determine valve disk closure (refer to SMAD Report M-6479-91, dated 10-28-91).
This test is scheduled during the shutdown process, preceding reactor refueling, due to the large transient placed on feedwater flow and the thermal stresses imposed on the S/Gs.
The application of RCM (Reliability Centered Maintenance) to the AF system has both concluded and recommended that performing acoustic monitoring on a 3 year frequency is sufficient to detect if the check valves fail to close..The failure analysis process required that the functional failures identified be evaluated using the failure modes and effects analysis (FMEA). The FMEA provides a format for identifying the dominant failure modes of component failures leading to a functional failure and the impact of each component failure locally at the component, on the system, and on the plant.
(9998D/WPF/021694) 4.6 - page 56 of 70
Rev. 12 I
RELIEF REOUEST VR-19 (continued) 5.
Dagis for Relieft (continued)
Additionally, the closure capability of these valves cannot.be verified adequately by performing a back pressure test due to the multiple boundary isolation points. The system configuration makes it. impossible to assign any observed leakage to any individual valve or component using standard mass make-up or pressure decay techniques.
6.
Alternate Testino:
The 1/2AF001A and 1/2AF001B suction check valves will be acoustically tested for closure (Bt) at each refuel outage in conjunction with the AFW full flow test and equipment response time of the AFW pumps. The open stroke (Ct) test will be tested during cold shutdowns, or at least once during each refueling cycle (approximately 18 months).
7.
Justification:
Performing a pressure test to verify closure is impractical due to the system configuration. To perform this test it would be necessary to attach a pump or some other type of pressure scurce to a test counection and pressurize the line contain4ng the valve. However,.this lL a also contains many potential leskage paths (valves, pump seals, and instruments).
It is not possible to assign a leakage value '. any specific path using available methods of seat leakage testenp Maintenance history and previous inspections of these valves at both Byron and Braidwood stations has shown no evidence of degradation cnr physical impairments.
Industry experience,.as documented in NPRDS, has shown no history of problems with these valves. A company wide check valve evaluation addressing the "EPRI Application Guidelines for Check Valves in Nuclear Power Plants" revealed that the location, orientation and application of these valves are not conducive to the type,of wear or degradation correlated with SOER 86-03 type problems.
Acoustic testing provides ample information relative to valve condition, without physically taking the valve apart for visual inspection to prove-
)
-ralve closure. These valves are of the same design (manufacturer, size,.
j madel, and materials of construction) and have the same service conditions, including orientation. Upon abnormal'or questionable acoustic test results, the valve will be scheduled for disassembly and-internal visual inspection.
The results of this inspection will be used to further evaluate the standby train valve as well, for possible-action. This type of' alternate testing provides more than adequate assurance of both valve functional and operational requirements.
The alternate test method is sufficient to ensure both functional'and operational requirements are met based on RCM failure mode and effect analysis for these valves, j
(9998D/WPF/021694 )
4.6 - page 57 of 70
{
1 Rev. 12 I
i RELIEF REOUEST VR-19 (continued) 8.
Acolicable Time Period:
This relief is requested once per quarter during the first inspection interval.
9.
Acoroval Status:
a.
Relief granted per NRC Generic Letter 89-04.
b.
Revised to include more detail on only AF valves in response to j
5/7/91 NRC teleconference; relief _ granted per Generic' Letter 89-04.
c.
Relief granted per SER dated-01/31/92, provided licensee complies with Generic Letter 89-04, Position 2.
J d.
Per the NRCs recommendations in SER 01/31/92, non-intrusive diagnostic techniques have been' incorporated in Revision 12, along with more descriptive information. Braidwood also has this j
relief. Relief granted per Generic Letter 89-04.
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(9998D/WPF/021694) 4.6 - page 58Jof 70
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Rev. 12 l
RELIEF REOUEST VR-20 1.
Valve Numbers:
1/2AF006A 1/2CV8116 1/2PS9357A,B
.1/2FI8813 1/2AF006B 1/2CV8152 1/2RE1003
'1/20I8814 1/2AF013A-H 1/2CV8160 1/2 RE9170 1/2SI8821A,B 1/2AF017A,B 1/2CV8804A 1/2RF026 1/2SI8835.
1/2CC685 1/2FP010 1/2RF027 1/2SI8840 1/2CC9412A,B 1/2FWOO9A-D 1/2RH8701A,B 1/2SI8880 1/2CC9413A 1/2FWO35A-D 1/2RH8702A,B 1/2SI8888 1/2CC9414 1/2FWO39A-D 1/2RY455A-1/2SI8920 1/2CC9416 1/2FWO43A-D 1/2RY456 1/2SI8924 1/2CC9437A,B 1/2IA065 1/2RY8000A,B 1/2SI8964 1/2CC9438 1/21A066 1/2RY8025 1/2SX016A,B 1/2CC9473A,B 1/2MS001A-D 1/2RY8026 1/2SX027A,B 1/2CS001A,B 1/2NG101A-D 1/2RY8028 1/2SX112A,B 1/2CS007A,B 1/20G057A
.1/2SA032 1/2SI114A,B 1/2CS009A,B 1/2OG079 1/2SA033 1/2SX169A,B 1/2CS019A,B 1/20G080 1SD002A-H 1/2SX173 1/2CV112B-E 1/20G081 1/2SD005A-D 1/2SX178 1/2CV8100 1/20G082 1/2SI8801A,B 1/2VQ001A,B 1/2CV8104 1/20G083 1/2SI8802A,B 1/2VQ002A,B 1/2CV8105 1/20G084 1/2SI8804B 1/2VQ003 1/2CV8106 1/2OG085 1/2 SIB 806 1/2VQ004A,B 1/2CV8110 1/2PR001A,B 1/2 SIB 807A,B 1/2VQ005A-C 1/2CV8111 1/2PS9354A,B 1/2SI8809A,B 1/2WOOO6A,B 1/2CV8112 1/2PS9355A,B 1/2SI8811A,B 1/2 WOO 20A,B 1/2CVB114 1/2PS9356A,B 1/2SI8812A,B 1/2 WOO 56A,B 2.
Number of Items:
340 3.
ASME Code Cateoorv: A and B
{
4.
ASME Code,Section XI Reauirements:
Verification, by trending of power-operated valve stroke times, that an increase in stroke time of 25% or more from the previous test (for valves with full stroke times greater than 10 seconds), or 50% or more (for valves with full stroke times less than or equal to 10 seconds).
does not occur, per IWV-3417 (a) (see Technical Approach.and Position VA-04).
(9998D/WPF/021694) 4.6
.page 59 of 70
.. ~ ~
Rev. 12 9
RELIEF REOUEST VR-20 (continued) 5.
Basis for Relief:
Trending stroke times, based on the percent change from the nrevious test, as ASME_Section XI requires, allows gradual degradation to occur over a long period of time without triggering the additional trending attention that increased testing frequency requires. An improved method of component performance monitoring is proposed, which'will require.a valve to be placed on increased test frequency based on the percent change from the fixed reference value established via NRC Generic Letter 89-04, Attachment 1.,
Position 5.
6.
Alternate Testing 1-For all power-operated valves which normally stroke in greater than two seconds, an ALERT RANGE will be established based on reaching a given percent change from the reference value established via NRC Generic letter 89-04.
.The following table will be used as-a startina coint in evaluation of this fixed ALERT RANGE:
VALUE REFERENCE REQUIRED ACTION TYPE STROKE TIME ALERT RANGE VALUE (TREF)
SOV's
> 10 sec.
(1. 2 5 ) (Tref) - (1. 75) ' (Tref)
> (1.75) (Tref).
HOV's or or.
AOV's (Tref +10 sec)-(Tref +20 see)
> (Tref + 20 see)
MOV's
> 10 sec.
(1.15) (Tref) - (1. 25) (Tref)
> (1.25) (Tref) or or (Tref +10 sec) - (Tref +20 sec)
> (Tref + 20 sec)
Notes:
A.
Fast acting valves (valves which normally stroke in less than 2 seconds consistently) are included in Relief Request VR-12.
These valves are agt' assigned ALERT RANGES and are E21 trended.
B.
In all cases, the REQUIRED ACTION VALUE cannot exceed Technical Specification or UFSAR values, regardless of calculated values.
1
-)
(9998D/WPF/021694) 4.6 - page 60 of 70
Rev. 12' RELIEF REOUEST VR-20 (continued)
C.
The above Table is a guideline and cannot cover all valves.
The ALERT RANGES and REQUIRED ACTION VALUES are selected based on the comparison between the REFERENCE VALUE, limiting value given in Technical Specifications /UFSAR, and calculated values using the table above:
- 1).
All values are rounded to the nearest whole second,
~
2).
Valves which serve the smne function on dual trains (i.e.,
ICC9473A and ICC9473B) and dual units (i.e.,
1CC9473A and 2CC9473A) are assigned the same REQUIRED ACTION / ALERT RANGE VALUES based on human factors considerations, unless valve or system design difference exist between the trains / units.
Refer to IST Technical Approach and Position VA-04 for related information.
7.
Justificatigni Using fixed ALERT RANGES based on the valve REFERENCE VALUE established when the valve was known to be operating acceptable will ensure that gradual valve performance degradation is monitored and evaluated, by placing the valve on increased testing frequency when the stroke time exceeds a fixed multiple of the REFERENCE VALUE.
This method is superior to that required by the ASME Code in that the point of reference used to evaluate the performance trend on a valve remains fixed. This alternative utilizes the same stroke time percentage change values as required by the ASME Code to place a valve on. increased frequency testing.
8.
Aonlicable Time Period:
This relief is requested once per quarter, during the_first inspection interval.
9.
Acoroval Status:
a.
Since this relief request is a new submittal and is not specifically addressed in NRC Generic 89-04, it is HQI approved for use.
Formal written approval from the NRC is required prior to implementation.
Expeditious review and approval are requested, l
b.
Relief granted per SER 1/31/92.
.?
I (999 BD/WPF/021694) 4.6 - page 61 of 70
Rev. 12 DRAFT BELIEF REQUEST VR-21
" WITHDRAWN"
. l This relief request was in draft form and was later withdrawn per'SER 9/14/90.
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4.6 - page 62 of 70 i
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i Rev., 12 l
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INTERIM j
RELIEF REQMEST VR-U i
The relief request was in interim form and was later withdrawn, x
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- (9998D/WPF/021694 )
4.6 page 63 of 70 M
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i R@v. 12 RELIEF REOUEST VR-23 1.
Valve Number (ASME Code Class)*
1RY8046 (2) 2RY8046 (2) (Primary Water supply to PRT) 1RY8047 (2) 2RY8047 (2) (Nitrogen supply to PRT) 2.
Number of Valves:
4.
ASME Code,Section XI Reauirements:
Relief requested from the 3 month test frequency for. the backflow (BT) test as stated in ASME'Section XI IWV-3521:
" Check Valves shall be exercised at least onco every 3 months, except as provided by IWV-3522".
IWV-3522 states that valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised durIng cold shutdowns.
5.
Basis for Relief:
a.
1/2RY8046 These valves are located on the Primary Water (PW) supply line to the Pressurizer Relief Tank (PRT) and to the Reactor Coolant Pump (RCP) standpipes. Their safety function in the closed direction is to provide a leak-tight barrier between the containment atmosphere and the environment during accident conditions..Their function'in the open direction is to provide PW to the PRT and RCP standpipes.
Testing these valves to the closed position while the Reactor Coolant Pumps are in operation could result in a loss of seal flow to the pumps and eventual pump damage and/or trip, b.
1/2RY8047 These valves are located on.the nitrogen supply line to the Pressurizer Relief T&nk. (PRT).
Their safety function in the closed direction is to provide a leak-tight barrier between the containment atmosphere and the environment during accident conditions.
Testing _these valves to the closed position could cause'the loss of the Nitrogen blanket maintained in the Pressurizer Relief Tank to prevent the creation of an explosive atmosphere.
3 i
I (9998D/WPF/021694) 4.6 - page 64 of 70
Rev. 12 EELIFF REOUEST VR-23 (continued) 6.
Alternate Testino:
a.
1RY8046 These valves will be backflow tested (BT) at cold shutdown provided all of the Reactor Coolant Pumps are not in operation (RCP's will not necessarily be secured for the sole purpose of the performing this test). The testing period will be each refueling outage as a minimum, but no more frequently than once per quarter.
The backflow test will be performed in conjunction with their leakage test.
b.
1/2RY8047 These valves will be backflow tested (" ) each refueling outage.
The backflow test will be performed in conjunction with their leakage test.
7.
Justification:
a.
1/2RY8046 This alternate frequency will adequately maintain the system in a state of operational readiness, by testing these valves as often as safely possible.
Shutting down the RCP's and the subsequent restarting incurs a reactor vessel overpressurization risk.
In addition, it is operationally undesirable due to the time and manpower involved in starting an RCP.
Also, an operator is required to observe the RCP shaft rotation upon starting.
Stopping and starting RCP's would add unnecessary radiation exposure (approximately 20 mrem).
b.
1/2RY8047 This alternate frequency will adequately maintain the system in a state of operational readiness, by testing these valves as often as safely possible.
This frequency will avoid placing the plant in the unsafe condition which would result from removing the protective Nitrogen blanket from the Pressurizer Relief Tank, Removal of this blanket could result'in the creation-of an explosive mixture of Hydrogen and Oxygen.
8.
Anolicable Status:
This relief is requested once per quarter during the first' inspection interval.
9.
Acoroval Status:
l.
Relief pending.
(9998D/WPF/021694)
.4.6 - page 65 of 70
B 1/2RY8046, 8047 D
d is O
1 1
NITROGEN iN SUPPLY RY8091 RY8034 RY8047
((
RY8033 O
h PRIMARY VN d
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MAKEUP m
WATER 5j PUMP RY8028 RY8030 RY8046 Es DISCHARGE J
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STANDPIPES 4
GENERAL DIAGRAM FOR INFORMATION ONLY M60-6
Rev. 12 l
RELIEF REOUEST VR-24 1.
Valve Number (Asme Code Class)-
1WOOO7A, B (2) 2WOOO7A, B (2) 2.
Number of Valves: 4
+
3.
ASME Code.Section XI Recuirements:
Relief requested from the 3 month test frequency for the backflow
(. T)
B test as stated in ASME Section XI IWV-3521:
" Check Valves shall be exercised at least once every 3 months, except as provided by IWV-3522".
IWV-3522 states that valves that cannot be exercised during plant operation shall be specifically identified by the owner ind shall be full stroke exercised during cold shutdowns.
l 5.
Basis for Relief:
These valves are located inside containment on the Chilled Water supply lines to the Reactor Containment Fan Coolers (RCFC) chilled water coils.
Their safety function in the closed direction is to provide a leak-tight barrier between the containment atmosphere and the environment during accident conditions.
Testing these valves to the closed position on either a quarterly or cold. shutdown frequency would cause undue hardship with no compensating return i.. plant safety.
6.
Alternate Testino:
These valves will be backflow tested
(. T) each refueling outage. The B
backflow test will be performed in conjunction-with their leakage test.
7.
Justificationt This alternate frequency will adequately maintain the system in a state of operational readiness, by testing these valves as often as is practical. Backflow testing of these valves during operation or at cold shutdown would involve removing this system from service for approximately three (3) days per valve to complete. ~ This includes approximately two (2) days to drain approximately 3000 gallons of Chilled Water from the RCFC coils and approximately one (1) day to fill and vent the isolated portions of the piping. Therefore, the time required for test execution and preparation and the processing of such a ~
large quantity of water make it impractical to perform this test on anything other than a refueling f requency, i
(9998D/WPF/021694) 4.6 - page 66 of 70
i Rev.' 12' PfLIEF REOUEST VR-24 (continued) 8.
Aeolicable Status:
I This relief is requested once per quarter during the first inspection interval.
9.
Acoroval Status:
Relief pending.
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i (9998D/WPF/021694 )
4.6 - page.67 of 70
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WOOOGA(B) 4 3
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4ll WOOS 6A(B)
WOO 20A(B) fu GENERAL DIAGRAM FOR INFORMATION ONLY M118-5 i
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i Rev. 12.
RELIEF REOUEST VR-25 1.
Valve Number:
1CS011A/B 2CS011A/B 2.
Number of Items: 4 3.
ASN3 Code Cateoorv: C 4.
ASME Code.Section XI Recuirements:
Exercise check valves to the position required to fulfill their function (open = Ct; closed = Bt), unless such operation is not practical during plant operation, per IWV-3522, 5.
Basis for Relief:
The 1/2CS011A/B check valves are on the discharge of the eductor and the safety function in the open direction is to allow flow from the discharge of the CS pump and the spray additive tank back to the suction of the CS pump. They function in the closed direction to prevent backflow into the eductor from the CS pump suction side. These valves cannot be full or design flow (185 gpm is the design flow rate - 130 gpm eductor flow plus 55 gpm NaOH flow) tested as a matter of course during unit operation or cold shutdown as NaOH.from the spray additive' tank would be discharged throughout the CS system causing undesirable chemical ef fects on the reactor make-up supply (RWST) and associated systems.
Non-intrusive techniques (NIT) using acoustics and magnetics have not been successful in proving full stroke of the disk plates. The reason is that the critical flow rate is 10 feet per second (the mmount of flow which is required to full-stroke the disks) and cannot be obtained based on current system design.
It is considered to be impractical and burdensome to attempt to disassemble valves in both trains every outage. Large amounts of reactor grade water needs to be reprocessed due to the need to drain the entire system before removing the valve from the system.
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(9998D/WPF/021694) 4.6 - page 68 of 70 i
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r-i Rev. 12 RELIEF REOUEST VR-21 1
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Alternate Testino:
The A and B train valves are of the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions, including orientation, therefore they form a sample disassembly group.
One valve from each group, on a per unit basis, will be examined each refueling outage.
If the disassembled valve is not capable.of being manually full stroked exercised or if there is binding or failure of internals, the remaining valve on the affected unit will be inspected.
In addition to the above, the 1/2CS011A, B valves will be partial stroke tested during the quarterly pump surveillance and after maintenance in order to verify that it was installed correctly.
7.
Justification:
The 1/2CS011A, B valves are removed from the system and visually examined per the strict detailed inspection requirements of the Station Check Valve Program. This inspection adequately verifies that the valves are maintained in a state of operational readiness and that their performance parameters are adequately assessed.
The valves are verified to be functional'by performing a thorough visual inspection of the internals and by performing a manual full-stroke exercise of each disc.
The wafer type design of the valve body for these valves makes their removal a simple process, with little chance of damage'to their internals. Also, there is no disassembly of internal' parts required; all wear surfaces are accessible to visual examination. After inspection and stroke testing, the valve is reinstalled into the line and post maintenance testing is performed.
The alternate test frequency is justifiable in that maintenance history and previous inspections of these valves at both Byron and Braidwood stations has shown no evidence of degradation or physical impairments.
In addition, industry experience, as documented in NPRDS, show no history of problems with these types of valves in this service. This data indicates that there is no significant decrease in plant safety by
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performing sample disassembly.
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The alternate test method is sufficient to ensure operability of these valves and is consistent with Generic Letter 89-04, Position 2.
The hardship involved with full' stroke exercising these check valves,'ifLthe Code requirements were imposed, does not provide a compensated increase in safety of these CS system check valves.
(9998D/WPF/021694) 4.6 - page 69 of 70 ~
Rev. 12 RELIEF REOUEST VR-25 8.
ADolicable Time Period:
This relief is requested once per quarter during the first inspection
- interval, 9.
ADoroval Status:
Relief is granted based on NRC Generic Letter 89-04, Position 2.
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