ML20090A854
| ML20090A854 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/27/1992 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20090A841 | List: |
| References | |
| PROC-920227, NUDOCS 9203030121 | |
| Download: ML20090A854 (134) | |
Text
ATTACHMENT B SECTION 4.0 INSERVICE TESTING PROGRAM PLAN FOR VALVES
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i ReV. Il TABLE._Or._ CONTENTS
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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
,j Note 2 CV Emergency Boration System Flowpath Valves i
l Note 3 Main reedwater Isolation Valves Note 4 CV System Letdown and Make-up Isolation Valves i
Note 5 RHR Pump Suction Isolation Valves Note 6 Intersystem LOCA Valves l
Note 7 Reactor Vessel Head Vent Valves Note 8 CV, RHR Pump Discharge Check Valves Note 9 RHR ECCS Check Valves Note 10 Maln reedwater Waterhammer Prevention Valves Note 11 VQ Purge Supply and Exhaust Isolation Valves Note 12 Ar Suction and Stenm 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 Teedwater Regulating Bypass Valves Note 18 " Deleted" Note 19 " Deleted" (Incorporated into Note 14)
Note 20 Position Indication Testing of Solenoid Valves Note 21 Main reedwater Tempering Flow Isolation Valves Note 22 Hydrogen Moultoring System Check Valves Note 23 Event V Check Valves Note 24 Pressure Relief Check Valves Note 25 51 Pump Suction Check Valve (1/2 S18926)
Note 26 CV Pump Suction Check Valve (1/2 CV8546)
Note 27 RH Pump Suction Check Valves (1/2 SIB 958A/B)
Note 28 VCT Outlet Check Valve (1/2 CV8440)
Note 29 Emergency Boration Check Valve (1/2 CVB442)
Note 30 AT Check Valve Lesk Checks (1/2 AF014A-H)
Note 31 CV/SI Minl-Flow Recirculation Line Check Valve Full Flow Testing (1/2 CV8480A/B and 4
1/2 SIB 919A/B)
Note 32 CC Pump Discharge Check Valves (1/2 CC9463A, 1/2 CC9463B, OCC9464)
Note 33 SK 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)
Note 39 Nitrogen Supply to SI Accumulator Check Valvas (1/2 SI8968)
(0092D/0034D/022192) 4.0 - page 1 of 2 f
Rev. 11 4.4 (Cont.)
Note 40 Safety Injection Check Valves (1/2 S18815, 1/2 SIB 900A D, 1/2 S!8818A-D, 1/2 S!8819A-D, 1/2 S!8841A,B, 1/2 S!8905A.D, 1/2 518949A-D)
Note 41 RH Hot Leg Suction Pressure Relief Check Valves (1/2 RH8705A,5)
Note 42 Safety Injection Cold Leg Pressure Isolation Valves (1/2-$18948A-D) 4.5 Technical Approaches and Positions VA-01 Method of Stroke Timing Valves VA-02 Hethod of rail Safe Testing Valves VA-03 Method of Esercising Check Valves VA-04 Determining Limiting Values of Full-Stroke Times for Power-operated V' 1ves.
(reference stroke time A10 seconds) 4.6 Rollef Requests VR-1 Appendia J Valves VR-2 Containment Spray NaOH Additive Check Valves VR-3 Safety injection ECCS Check Valves VR-4 Containment Spray Discharge and Ring Hender Check Valves 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 Coollag RC Pung Thermal Barrier Valves VR-9 RC Pump Seal Injection CV Check Valves VR-10 Instrument Air Containment Isolation Valves VR-11
" Deleted" (per EG & C recommendation)
VH-12 Trending of Test Actuating Valves VR-13 Diesel Generator Air Start Valves VR-14
" Deleted" (using ASME method instead of requesting esemption from position indication testing of soledoid operated valves)
VR-15 Safety Injection ECCS Check Valve Testing during Refueling Outage VR-16
- Containment Sump Outlet Isolation Valve Testing During Refueling VR-17 Notor Driven Auxiliary feedwater Pump L.O. Cooler Solenoid Valve Stroke Testing VR-18
" Deleted" re-organised into several relief requests l
VR-19 Auxiliary Teedwater Check Valves 7
Draft VR-20 Trending of Power-Operated Valve Stroke Times (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 l
Supply to PRT Check Valves i
VR-24 Chilled Water to RCrc Coils Check Valves l
l l
l (0092D/0034D/022192) 4.0 - page 2 of 2 L
SECTION 4.1 PROGRAM DESCRIPTION
i i
Rev, 11 b
PROGRAM _DESCR1ET10N r
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 selief are r
written,-referenced, and included with the tables.
Additional valve relief. requests may be necessary and these vill be identified and submitted during subsequent program revlaions.
Dyron Station received l
a Safety Evaluation Peport (SER) on September 15, 1988 and is listed in Table 2 of HRC Generle Letter 89-04 as a plant with a reviewed IST Program and SER lasued.
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 j
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 no.t covered by HRC Generic Letter 89-04, Attachment 1, must receive NRC approval prior to implementation. 7he table lists all code Class 1, 2,
-G 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 categorire, The valves subject to ISE testing are those valves which are identified in accordance with the scope of ASME Section XI, Subsection IWV-11001 i
"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 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.
l r
After installation and prior to service, all valves identified ir. 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 return to service, to demonstrate that all performance parameters are within acceptable.11mits.
L
I Rev. 11 i
i l
1 As required by NRC Generic Letter 89-04, Attachment 1, Position 5, the
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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 condition and operating properly. This limiting value is based on a reasonable deviation from this reference stroke time based on valve sise, 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
,e may not perform its intended function. New or edditional reference values may be required ift 1)
A valve has been replaced,
- 2) When a reference value or set of values way have been affected by repair or routine servicing of a valve, or 7
3)
If it is necessary or desirable for some reason other 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 1
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 i
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 i
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 verifles 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 A/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.
Per NRC Generic Letter 89-04, Attachment 1, Position 18, whenever valve 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 en plant operations will be as stated in the Technical Specifications.
Section XI of the ASME Boller and Pressure Vessel Code shall not be construed to supersede the requirements of the Technical Specifications.
i.
1 (0092D/0034D/022192) 4.1 - page 2 of 2
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9 SECTION 4.2 PROGRAM REFERENCES
(
i
1 Rov. 11 EEDGRAM_ REFERENCES 1
1.
Title 10, Code of Pederal Regulations, Part 50, Domestic Licensing of Production and Utilization Pac 111 ties, particularly Section 50.55a, codes I
and Standards.
l 2.
ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components,1983 Edition, S umme r 1983 Addenda.
3.
ASME/ ANSI OH-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, Guliance on Developing-Acceptable Inservice Testing Programs.
5.
Byron Station UPSAR, 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 S,taff Procedure, BVP 200-2, 151 Requirements for Valves.
8.
NRC Safety Evalvation 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) 9.
Dvr " Statiet IST Valve Program Plan Responses (files 3.11.0240) t, on Lstter 88-1321 (Initial Program Plan Review Response)
- 10. Min.tes of the Public Meeting on Generic Letter 89-04, dated-October 25, 1989, Question 40-4
L 4
SECTION 11.3 PROGRAM TABLES b
T 1
Rev. 11 IABLE DISCRIEIl06 The following information is included in the summary tables A.
REELS 10tl The revision corresponds to the current revision of the program.
D.
EASE-The pages are numbered sequentially and show the total number of tables.
C.
VALVE NUMP.12 The valve number references the unique Byron Station er;ulpment piece number (EPN).
This specific valve number identifies the unit and system.
D.
E61D The P&ID column references the specific P&1D number which the valves are located on.
The Unit 2 P&1D number is given directly underneath the Unit'l P&lD number.
E.
CLASS The class refers to the'ASME class assigned to the specific valve.
F.
VALVE CATEGORY The valve category identitles the valve category defined in subarticle IWV-2200 of ASME Section XI.
G.
VALVE E1IE The-valve _ size lists the nominal pipe sise of each valve in inches.
f I'
(0092D/0034D/022192) 4.3 - Page 1 of 5 L
L-
i Rev. 11 H.
VALVE TYEE 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 BT!
Check CK Safety Valve SV Relief Valve RV Power Operated Relief Valve PORV Diaphragm Seated D
Plug p
Angle AH r
1.
ACT. TYPE The actuator type identifies the valve actuator. The following abbreviations will be used to designate spec 3fic 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.
J.
RQP. MAL POSITICH Normal position identifies the normal operating position of a specific valve.
O for open and C for closed.
K.
"tTEDELDIRECL.
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.
O for open, and C for closed. This identifies the direction the valve stem will move when tested.
Notes Exercising of a power operated valve will involve stroking the valve to both its open and closed position.
The valve will only be timed, however, in the direction designated to perform its safety function. Therefore, the program plan specifies only the l
direction in which valves must be stroked to be timed.
(
,1
)
(0092D/0034D/022192) 4.3 - page 2 of 5 1
l
i Rev. 11 L.
II11_METERD The test method column identifies speelfle tests which will be performed on specific valves to fulfill the requirements of Subsection 1WV of ASME Section XI.
The tests and abbreviations used are as follows:
1.
(Bt) Check Valve Back riow Test The check valve disc will be exercised to the closed position 1
required to fulfill its safety function by verifying that the
,I disc travels to the seat promptly on cessation or reversal of j
flow.-
2.
LC1LChec kJAl?;t_Isl.LS t r.u ke_ Inst 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 e
flow testing, per 11RC Generic Letter 89-04, Attachment 1, Positions 1 and 2.-
3.
LE.t ) Fall SalcJ gst Valves with fall safe actuators will be tested to verify the valve operator moves the valve stem to the required fall safe position upon loss of actuating power, in accordance with INV-3415.
This will be accomplished during'the normal stroking of the valve. Upsn stroking a valve to its fall safe position, the solenold operator is de-energized causing air to be vented which in turn allows the spring to move the valve to its fall safe position. This condition simulates loss of actuating power (Electric and/or Alt) and hence satisfles the fall safe test requirements of IWV-3415.
4.
(It) Pos111nn l ndi. cation _Che.ck Valves which are identified to require a Position Indication Test will be inspected in accordance with IWV-3300 of ASME 5ection XI.
5.
ILtLS. cat Lenkagelegt The seat leakage tests sill meet the requirements of IWV-3420 for Category _A valves.
On tl.'se valves, seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their safety function.
j (0092D/0034D/022192) 4.3 - page 3 of S f,
-. ~ -.... -.
Rev. Il ti.
11tLSafety_Yehe_Setroint._fhttk Safety valve setpoints will be verified in accordance with IWV-3510 of ASME Section XI.
7.
11tl,J.nlLE(Init_Ittil R
Valve exercising tests of Category A and D 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.
IXtL1'AthEttokt._Itat If only limited operation is practical during plant operation, the valves shall be part-stroke (Xt) exercised during plant operation ano full-stroke exercised during cold shutdowns, in accordance with IWV-3412 or IWV-3522.
H.
ILSI_hQDE Denotes the frequency and plant condition necessary to perform a given test.
The following abbreviations are used:
+
HnImal_0prIntion_10Pl 3
Tests designated "OP" will be performed once every 3 months, except in those modes in which the valve is not required to be operable.
Etelannual_.Ill 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.
C911 Shutdown ifs 1 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 (0092D/0034D/022192) 4.3 - page 4 of 5
Rev. 11 ERA; tor ReLue11mg_.1RBI Tests with this designation will be conducted during reactor refueling outages only.
N.
EEldI L EL W LEI Relief requests teference a specific request for relief from code requirements. All relief requests are included in Section 4.6.
O.
RQIES Notes provide a short explanation concerning a particular IST valve.
All notes are included in Section 4.4.
P.
IICig11 CAL APPROACHE5 MIILP.QE171WS Technical approaches and positions provide detailed discussions on a particular IST topic.
All technical approaches and positions are included in Section 4.5.
O.
EEMARES Hemarks reference other information useful in determining valve testing requirements or methods.
l l
l l-f, l2 (0092D/0034D/022192) 4.3 - page 5 of 5
1 SECTION li 3 PROGRAM TABLES UNITS 1 AND 2 I
l
1 IF * "CE TESTING PROGRAM
'Rev.'11 e ?'TH EDISON GrM M0 7 7WER STATION l
VALVE l
l l VALVE l VALVE l VALVE l42T.l NORMAL l STROKE l TEST ' l TEST l RE3IEF l
lTECM. ]
'l l
NUMBER l
P&ID l CLASS l CATEGOP.Y l SIZE l TYPE l TYPE l POSITION l DIRECT.l METHOD l MODE l Rl'0! EST l
NOTES l POS..l REMARKS'l-l l
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l (00930/00400/022192) 4.3 - TABLE 1 of 42 l
a.
INSERVICE TESTING PROGRAM Rev. 11 COMMONWEALTH EDISON i
' BYRON NUCLEAR POWER STATION l " VALVE l
l l VALVE. l VALVE l VALVE lACT.l NORMAL 'l STROKE l TEST l TEST l RELIET l
l TECH.'l l
l NUMBER l
P&ID l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION l OIRECT.-l HETHOD l MODE l REQUEST l
NOTES l POS.
l REMARKS l
[
l l
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l l
l l
l l
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l l
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l 1
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l 1
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l l
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{
4.3 - TABLE 2 of 42 (0093D/00400/022192) i
i 4
INSERVICE TESTING PROGRAM Rev. 11 COMMONWEALTH EDISON BYRON NUCLEAR POWER STATION I
l VALVE l
l l VALVE l VALVE l VALVE l ACT. l NORMAL l STROKE l TEST l TEST l RELIEF l
l TECH. l l.
j NUMBER l
P&ID.
l CLASS l CATEGORY l SIZE l TYPE lTYPCl POSITION l DIRECT.lNETH00l HODE l REQUEST l
NOTES l POS. l RCfARKS l l
l 1
l I (IN.) l
~l l
I l
l l
I I
l l
l1/2CC685 lM-66-1A l 2
l A
l 4.0 l GA lM.0.l 0
l C
l St l
CS l
VR-8 l
l 1
l l
l l
lH-139-1 l l
l l
l l
l l
It l
GR l
l j
l l
L l
I I
I I
I I
I I
Lt i
RR I
VR-1 1
I I
l
.l 1/2CC9412A l 566-2
- l. 3 l
B.
l12.0 l GA lM.0.l C
l 0'
l St l
OP l
l l
1 l
l I S139-2 I I
I I
I I
I I
It i
RR l
1 I
I l
I l'1/2CC94128 l W66-2 l
3 l
B l12.0 l GA lM.0.l C-l 0
l St l
OP l
l l
1 l
l~
i l H-139-2
.I I
I I
I I
I I
It' I
RR I
I i
1 l
1 1/2CC9d13A I H-66-1A l 2
l A
l 6.0 l GA l M.0. l 0
l
~
l St l
JS l
VR-8 l
l 1
l l
l l M-139-1 1
l l
l l
l l
l It i
RR l
l l
l l'
l 1
1 1
1 I
I I
I I
Lt i
RR l
VR-1 I
I I
l l 1/2CC9414 l 566-1A l 2
l A
l 6.0 l GA l M.D. l 0
l C
l St l
CS l
VR-8 l
l 1
l l=
I 1
l M-139 l l
l l
l l
l l
It l
RR l
l l
l l
l 1
1 I
I i
l i
i i
tt i
RR I
VR-1 1
I I
l-l1/2CC9416 lM-66-1A l 2
l A
l 6.0. l GA l M.0. l 0
l C
l St l
CS l
VR-8 l
l 1
l l
l l M-139-1 l
l l
l l
l l
l It l
RR l
l l
l l
l l
l l
1 1
I I
I I
Lt i
RR I
VR-1 1
I I
l l 1/2CC9437A l %66-1A l 2
l B
l 3.0 l GL lA.O.l C
l C
l. St l
OP l
l l
1 l Passive l j
i m139-1 1 I
I I
__]
I I
I It i
RR I
I I
I l.
l 1/2CC94378 l N66-1A l 2
l B
l 3.0 l GL j.A.O.l 0
l C
l St l
OP l
l l
1 l
l.
l l M-139-1 l
l l
l l
-l l
l It l
GR l
l l
l 1.
l l
1 1
1 I
I I
I I
I I
I I
I
_l l1/2CC9438 l 566-1A l 2
l A
l 4.0 l GA lM.0.l 0
l C
l Lt l
RR l
VR-1 l
l l
l i
l l M-139-i l
l
'l l
l l
l l
It l
RR-l l
l l
l J
l i
I I
I I
i 1
I st I
CS I
va-a i
I i
I l
l l 1/2CC9463A l W66-3B l 3
l
.C l12.0 l CK l S.A. l C
l 0
l Ct l
CS l
l 32 l
3 l
l l
1 I
i l
i l
l l
C 1
9t i
Or I
I I
3 1
l l
i l 1/2CC9463B l M-66-38 l 3
l C
l12.0 ! CK l 5.A. l C
l 0
l Ct l
CS l
l 32 l
3 l
l l
l 1
1 I
I I
I I
C 1
Bt i
OP l
i I
3 1
l l
lOCC9464 l M-66-3B l 3
l C
l12.0 l CK l S.A. l C
l 0
1 Ct l
CS l
l 32 l
.3 l
l l
l 1
1 1
I I
I I
C 1
Bt i
Op 8
l l
3 l
l i
i l 1/2CC9473A l M-66-3B j ' 3 l
B l.16.0 l GA lN.O.l C
l 0
l St l
OP l
l l
1 l
l l
l l
l l
l 1
1 I
I It i
RR I
I i
1 l
f (0093D/00400/022192) 4.3 - TABLE 3 of 42 1
4 4
.a
+
4 a
4 l
INSERVICE TESTING PROGRAt4 Rev. 11 t
-COMMONWEALTH EDISON-
-[
BYRON NUCLEAR POWEP. STATION I
l VALVE I
l l VALVE l VALVE l VALVE lACT. l NORMAL l STROKE l TEST l IEST l RELIEF l
l TECH. l 1
l NUMBER l
'P&lD l CLASS l CATEGORY l SIZE I TYPE l TYPE l POSITION l DIRECT. l METHOD l MODE I REQUEST l
NOTES 'l P05.
l REMARKS l i
i l
1 1
I i (IN.) l i
l l
l l
l l
1
-l l1/2CC94738iH-66-38 l 3
l 8
l16.0 l GA lM.0.I C
l 0
l St l
OP
[
l l'
I l
l l
1 1
I I
i I
1 1
I It i
RR I
I I
I l'
i 1/2CC9486 l M-66-1A-l 2
l AC l 6.0 l CK l S.A. 1 0
l C
l Lt/Btl CS lVR-1,6 I
l 3
l l
l 1 M-139-1 1
1 1
I
- l 1
i 0
1 Ct i
OP l
l l
3
'l l
i l1/2CC9518 l M-66-1A l 2
l AC l 0.75i CK l S.A. I C
l C
l Lt/Btl RR l VR-1, 8 l
l 3
l Passive l I
I M-139-1 1
I I
I I
I I
o I
Ct I
CS 1 vR-a I
z4 1
3 I
i 4
5, l1/2CC9534 l H-66-1A l 2
l AC l 0.75i CK I S.A. I C
l C
i Lt/Bt i RR I VR-1, 8 l
l 3
l Passive l I
I M-139-1 1
l i
i i
1 1
0 1
Ct I
CS I vR-a i
24 1
3 I
I, i
l i
I I
I I
I I
I I
I I
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l 1
1 1
I I
J_.
I I
I I
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I I
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I I
I I
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I I
I I
I I
I I
l' I
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I I
I I
I I
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i 1
1 1
l l
1 1
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I I
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I I
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1 1
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1 1
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1 1
I I
L 1
I i
1 1
L I
I 4.3 - TABLE 4 of 42
{D0930/00400/022192)
a l-INSERVICE TESTUtG PROGRAM
.Rev. 11 COMMONWEALTH EDISOM BYRON NUCLEAR POWER STATION l
VALVE l
l
'l: VALVE l VALVE-l VALVE.l ACT. l NORMAL l STROKE: l TEST l TEST l RELIEF l
l TECH.'l j'
i l. NUMBER l
.P&lD l CLASS l CATEGORY l SIZE l TYPE-l TYPE l POSITION l DIRECT. lNETH00l MODE l REQUEST l
NOTES l POS. l REMARKS l l
l 1-I
'I (IN.) l l
I I
l 1
l 1
I l
l l 1/2C5001A l M-61-4 l
2 l
B l.14.0 'l GA lM.0.l 0
l C
l St l
OP l
l
.l 3
.l l
l 1 N136-4 l 1
I I
I i
1 1
It I
RR I
I I
I l
l1/2CS001B l.M-61-4 l
2 l
B l14.0'l GA lM.0.l 0
l C
l St l
CP l
l l
1 l
l j
l 1 M-136-4 I I
I I
I I
I I
It i
RR 1
l l
l l
l1/2CS003A lM-46-1A l 2
l C
l10.0 l CK lS.A. l C
l 0
l Xt/Ctl OP/RR l VR-4 l
l 3
l l
l l
l M-129-1A l 1
I l
l l
l l
l l
l l
l l
l1/2CS003B lM-46-1A l 2
l
'C l10.0 l CK lS.A. l C
l 0
l Xt/Ct l ~0P/RR l VR-4 l
l 3
l l
1 l
l W129-1A l 1
1 I
i 1
I I
l 1
I I
I l
l1/2C5007A l M-46-1C l
2 l
A
]10.0 l GA lM.0.l C
l 0
l Lt l
RR l
VR-1 l
l
- l l
l l N 129-1C l l
l-l l
l l
l St l
OP l
l l
1 l
l l
l l
l 1
1 I
I I
I It i
RR l
i I
I l
l1/2C5007B l M 46-1C l 2
l A
l10.0 l GA lM.0.l C
l 0
l Lt l
RR l
VR-1 l
l l
l l
l H-129-1C l l
l l
l l
l l
St l
OP l
l l
1 l
l l
l l
l l
1 1
1 I
I It i
RR I
1 1
1 l
l1/2C5008A l M-46-1C l 2
l AC l10.0 l CK l S.A. l C
l 0
l Ct l
RR l VR-4 l.
l 3-l l'
l l M-129-1C I I
I l
l I
1 C
l Bt/tt 1 RR l VR-1 I
l 3
l l
l1/2CS0088 lM-46-IC l 2
l AC l10.0 l CK lS.A. l C
l 0
l Ct l
RR l VR-4 l
l 3
l l
4 l
1 m129-iC I I
l-1 1
1 1
C 1 st/tt i RR l VR-1 1
1 3
I l
l1/2C5009A lM-61-4 l
2 l
8 l16.0 l GA lM.O.l C
l 0
l St l
OP l
l l
1 l
l j
i M-136-4 l l
l l
l l
l 1
It l
RR l
l I
I l
l l 1/2C50098 l M-61-4 l
2 l
B l16.0 l GA l M.(. l C
l 0
l St l
OP l
l l
1 l
l l
1 5136-4 I I
1 1
I I
I I
It i
RR 1
l I
i l
l l 1/2C5011A lH-46-1A-l 2
l C
l 6.0 l CK l S.A. l C
l 0
l Ct l
OP l
l l
3 l
i l
1 N129-1A I l
l l
l I
l l
l l
1 l
l l
l1/2CS0118 l M-46-1A l 2
l C
l 6.0 l CK lS.A. l C
l 0
l Ct l
OP l
l l
3 l
l' j
i H-129-1A I I
I I
I I
I I
I I
I I
I l
l1/2CS019A l %46-1B l 2
l B
l' 3.0 l GA lM.0.l C
l 0
l St l
OP l
l l
1 l
-l 1
l l S129-1B I I
l' I
l i
i 1
It i
RR l
l I
l
'l l1/2CS0198 l M-46-1B l
2 l
B l
3.0 l GA l M.0. l C
l 0
l St l
OP l
l l-1 l
l l
l S 129-1B-l I
I I
I I
I I
It 1
RR I
I I
I l
l 1/2CS020A lM-46-1B l 2
l C
-l 3.0 l CK lS.A. l C
l 0
l Ct l
RR l VR-2 l
l 3
l l
l l M-129-1A I l
l l
I l
l l
l I
i l
l l
l1/2CS020e l H-46-1B l
2 l
C l' 3.0 l CK lS.A. l C
l 0
l Ct l
RR l VR-2 l
l 3
l l
l l W129-1A l l
l l
l l
l l
1 l
l l
l l
4.3 - TABLE.5 of 42 (0093D/00400/022192)
~~
t INSERVICE TESTING PROGRAM Rev. 11 CONM0 W EALTH EDISON BYRON NUCLEAR POWER STATION l
VALVE l
l l VALVE l VALVE l VALVE l ACT. ] NORMAL i STROKE.l TEST l TEST.l RILIEF
.l l'TECM. l' j'
l NUMBER l
P8.ID l CLASS l CATEGORY l SIZE'l TYPE l TYPE l POSITION l DIRECT.lNETH00l MODE l RE00EST l
NOTES
.l POS.
lPEMARKS l l
1 I
I I (IN.1 1 I
I I
l' 1
I I
I-I-
l l1/2CVH2B l'M-64-4A l
2 l
B l
4.C l GA lM.0.l 0-l C
l St l
CS l
l 4, 28 l
1 l
l l
l M-138-4 l l
l l
l 1
l 1
It i
RR l
l 1
1 l
l 1/2CV112C l N64-4A',l 2
l B
l 4.0 l
GA-l M.0. l 0
[
C l
St l
CS l
l 4, 28 l
1 l
l l
I M-138-4 I
I l-1 I
I I
I It i
RR I
I l
l l
l1/2CV1120 l N64 48 l 2
i B
l 8.0.l GA lM.D.l C
l 0
l St l
CS l
l 2 l
1
.l l
l l N138-4 I I
l i
1 1
1 1
It i
RR I
I I
I l.
l1/2CV112E l 564-48 l 2
l B
l 8.0 l GA l M.0. l C
l 0
l St l ' CS l
l 2 l
1 l
l l
l M-138-4 'l 1-1 i
l i
i 1
It i
RR l
1 l
l l
l 1/2CV8100 l 564-2 l
2 l
A l'20 l GL lM.0.l 0
l C
l St l
CS l
VR-9 l
l.
l l
l l M-138-2 l l
l l
l l
l l
It - l RR l
l l
i l
l l
l I
1 1
I I
I I
I tt 1
RR I
VR-1 1
I I
l l 1/2CV8104 l H-64-48 l
2 l
a l
3.0 l GL lM.0.l C
l 0
l St l
CS l
j 2 l
1 l
l-l l 5138-4 1 1
1 I
I I
I I
It i
RR I
I l
l l
l1/2CV8105 lM-64-38 l 2
l 6
l 3.0 l GA lM.0.l 0
l C
l St l
CS l
l 4 l
1 l
'l, l
1 m138-38 l 1
1 I
1 1
I I
It i
RR I
I I
I l
l1/2CV8106 l M-64-38 j. 2 l
B l
3.0 l GA l M.O. l 0
l C
l St l
CS l
l 4 l
1 l
l l
l M-138-38 1 1
1 I
I i
1 0
I It i
RR l
l l
l l1/2Cv8110 l N64-3A l 2
l B
l 2.0 l GL l M.O.- l 0
l
'C l
St l
OP l
l l
1 l
l l
1 513fi-3 I I
I I
I I
I I
It i
RR I
I I
l l
l1/2CV8111 l N64-3A l 2
l B
l 2.0 l GL lM.0.l 0
l C
l St l
OP l
l l
1 l-l l
1 5138-3' I I
I I
I I
I I
It i
RR l
l I
I l
l1/2CV8112 l M-64-2
- l. 2 l
'A l 2.0 l GL lM.O.l 0
l C
l St l
CS lVR-9 l
l 1
l l
l l +138-2 l
l l-l l
l l
l It l
RR l
l l
l l
l 1
1 1
1 l
l-1 I
I tt i
RR I VR-1 l
I l
l l 1/2CV8113 ' l M-64-2 l
2 l
AC l
.75l CK lS.A. l C
l C
l Bt/Ltl CS lVR-1,VR-9 l l
-3 l Passive l l
l S138-2 I I
I I
I I
O 1
l Ct I
CS I VR-9 1 24 1
3 I
l l1/2CV8H4 l S64-3A l 2
l 8
.l 2.0 l GL iS.0.l
.0 l
C l
St l
OP l
l l
1 l
l l
l S138-3 I I
i i
l I
I I
It i
RR I
l 20 I
l l
l 1/2CVa116 l 564-3A l 2-l B
l 2.0 l GL l S.0. l 0
l C
l St l
OP l
l l
1 l
l l
I m i38-3' I i
1 1
I I
I I
It i
RR I
I 20 1
I l-4.3 - TABLE 6 of 42 (0093D/00400/022192)
+
e INSERVICE TESTING PROGRAM Rev. 11 COMMONWEALTH EDISON-BYROM NUCLEAR POWER STATION l
VALVE l
l l VALVE l VALVE l VALVE lACT.l NORMAL l STROKE l TEST l TEST l RELIEF l
l TECH.l l
l NUMBER l
Pt.ID l CLASS lCATEGORYl' SIZE l TYPE l TYPE l POSITION l DIRECT.lNETH00l MODE l REQUEST l
NOTES lP05. l REMARKS l l__
i i
i I (IN.1 1 I
l l
l l
I I
l l
l l 1/2CV8152 -l M 4-5 l
2 l
A l'3.0 l GL l A.O. l 0
l C
l St l
CS l
l 4 l
1 l
l l
l h-138-5A l '
l l
l l
l l
l It l
RR.
l l
l l
'l l
l 1
1 I
I I
I I
I rt l
CS I
I4 l
2 l
-1:
l l
l l
1 I
i i
i 1
Lt 1
RR I
VR-1 I
l l
l l 1/2CV8160 1 M-64-5 l
.2 l
A l 3.0 l GL l A.O. l 0
l C
l St l
CS l
l 4 l
3 l
l 1
l n-138-5A l l
l l
l l
l l
It l
RR l
l l
l l
1 1
I l
1 I
I l
l rt l
CS I
l 4 I
2 l
l l
1 1
1 1
1 1
I I
I tt i
RR I
VR-1 1
I l
l lI/2CV8442 l w64 48 l 2
l C
l 2.0 l CK l S.A. ]
C l
0 l
Ct l
CS l
l 2, 29 i
3 l
l l
l H-138-4 I I
I I
I I
I I
I I
I I
I l
l 1/2CV8480A l N64-3A l 2
l
.C l 2.0 l CK lS.A. l C
l 0
l Ct l
OP l
l 31 l
3' l
l l
l M-138-3 I
i 1
1 1
I i
C l
st i
OP I
I I
l l
l 1/2CV84808 l M-64-3A l
2 l
C l
2.0 l CK l S.A. l C
l 0
l Ct l
OP l
l 31 l
3 l
l l
l S138-3 I I
i 1
1 I
I C
I Bt i
OP I
I l
3 l
l-l 1/2CV8481A l N64-3A l 2
l C
l 4.0 l CK lS.A. l C
]
O l Ct/Xtl CS/0Pl VR-15 l
l 3
l l
l l Ni38-3A 1 l
l
}
l l
l C
I Bt
-l OP l
1 I
3 l
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4.3 - TABLE 7 of 42 (00930/00400/022192)
INSERVICE TESTING PROGRAM Rev. 11 COMMONWEALTH EDISON SYRON NUCLEAR POWER STATION 1
l VALVE l
l l VALVE l VALVE l VALVE lACT.l NORMAL l STROKE. l TEST l TEST l RELIEF l
l TECH. l
].
l NUMBER l
P&ID l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION lDIRErf.IMETH00l NODE l REQUEST l
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l 1
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l-4.3 - TABLE 8 of 42 (00930/00400/022192)
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INSERVICE TESTING PROGRAM Rev. 11 COMMONWEALTH EDISON BYRON NUCLEAR POWER STATION j
VALVE
-l Ll' l VALVE l VALVE l VALVE l ACT, l NORMAL.l STROKE l TEST l TEST l RELIEF l
. l TECH.l l
.l NUMBER l
.l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION l DIRECT. l METHOD l H0DE l REQUEST. l NOTES lPOS. l REMARKS l l
l l
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i 4.3 - TABLE 12 of 42 (00930/00400/022192)
-~
1 INSERVICE TESTING PROGRAM Rev. 11-COMMONWEALTH EDISON f
BYRON NUCLEAR POWER STATION l
l VALVE l
l l VALVE 1 l VALVE l VALVE lACT.l. NORMAL l STROKE' l TEST l TEST l RELIEr-l l TECH.. l l
l NUMBER l
P&ID l CLASS l' CATEGORY.l SIZE l TYPE l TYPE l POSITION l DIRECT.lNETH00l MODE l.
REQUEST l
NOTES l POS. l REMARKS l l
1 1
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l I
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1 l
l
}
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l C
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I I
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l C
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4 (0093D/00400/022192) 4.3 - TABLE 13 of 42
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l VALVE l
l l VALVE l VALVE l VALVE l ACT. l NORMAL l STROKE l TEST l TEST 'l RELIEF l'
lTECM. l l
l NUtSER l
P&ID l CLASS l CATEGORY. l SIZE l TYPE l TYPE l POSITION l DIRECT. l METHOD l N00E l REQUEST l
NOTES l POS. [ REMARKS l l
l l
l l (IN.1 l l
l' I
l l
l 1
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'l l1/2M5001A l M-35-2 l
2 l
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l l
l H-120-2A l l
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l-B l32.75l GA l H.O. l 0
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l 1
l l
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I l
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l C
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l 5120-1 1-1 I
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l l
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l l S120-2A l I
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l l
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2 l
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l l
l l
l 1 5120-1 1 I
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l 0
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l l
l:
l l
l M-120-ZBj.
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2 l
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l 0
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l l
l 3
l
[H-120-1 1 l
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C l 6.0 x l SV l fi. A l C
l 0
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l l
l l
l 1 H-120-2A I I
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2 l
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l 0
l Rt l
RR l
l l
l' l
l 1 M-12D-1 1
I i 10.0 I I
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l l 1/2NS0 4C l M-35-2 l
2 l
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l 0
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l l
l l
l l H-120-2B 1 1
1 10.0 I'
1 I
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2 l
C l6.0x l SV j!.A.I C
l 0
l Pt l
RR l
l l
l l
I M-120-1 1
I I 10.0 I I
I I
I I
I I
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l l1/2HS015A l M-35-2 l
2 l
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l 0
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l l
l l
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2 l
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l l
l l
l l 5120-1 I I
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2 l
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l 0
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RR l
l l
l l
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l l1/2HS0150 l H-35-1 l
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l 0
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RR l
l j
l l
l l 5120-1 1 I
i 10.0 1 I
i i
l i
i 1
1 I
l (0093D/00400/022192) 4.3 - TABLE 16 of 42
~
n INSERVICE TESTING PROGRAM Rev. 11 COMMONWEALTH EDISON BYRON fAJCLEAR POWER STATION I.
l VALVE
-l l
l VALVE. l VALVE l VALVE l ACT. l NORMAL l STROFE l TEST l TEST l RELIEr l
l TECH. l l
l NUMBER l
P&ID l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION l DIRECT. l NETH00 l MODE l ' REQUEST l
NOTES l POS.
l REMARKS l l
l 1
1 I (IN.)'l l
I i
l I
I I
i l
l 1/2NS016A lM-35-2
-l 2
l C
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l 0
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RR l
l.
l l
l l
1 H-120-2A 1
'l l 10.0 l I
l l
l l
l 1
I I
l l1/2NS0168 l M-35-1 l
2-l C
l6.0x.l SV l S.A. l 0
l 0
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RR l
l l
l l.
.l l M-120-1 l
l 1 10.0 1 I
I I
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2.
l C
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l 0
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itR l
l l
l
.]
j-l l N120-28 I I
i 10.0 l I
l-1 1
I I
I I
I:
l l
l 1/ZHS0160 lM-35-1 l
2 l
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0 l
0 l
Rt l
RR l
l l
l l
l l M-120-1 1
I i 10.0 1 1
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l l
l I'
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2 l
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RR l
l l
l l
l 1 M-120-2A l l
1 10.0 l l
l I
l I
l l
l l
l 1
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2 l
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l 0
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l l
'l l
l 1 M-120-1' I I
i 1020 1 1
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l i
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l l 1/2MS017c l m35-2 l
2 l
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l 0
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RR l
l l
l l
l l M-120-2B_1 I
l_10 0 1 I
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l l 1/2MS017D lM-35-1 l
2 l
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l l
l l
l 1 M-120-1 1
I 12 0 1 I
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l 1/2MS018A l M-35-2 l
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l,
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l 1
l l
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l 6.0 l
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l l
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l 1
.]
l l
l M-120-1 l
l l6.0 l
l l
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l l
l l
l l
l 1
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l l1/2M5018C l M-35-2 l
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l C
l St l
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l 1
l l
l l M-120-2B I l
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l l
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l-l j -
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l 1
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l.
l 4.3 - TABLE 17 of 42 (0093D/00400/022192)
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l VALVE l
l l-VALVE l V/LVE l VALVE l ACT. l NORMAL l STROKE l TEST l TEST l.
RELIEF
.]
l TECH. l-l l-NUMBER l
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NOTES l POS.
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l
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l l
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l
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l C
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l l
l 1
l lM-150-2 l l
l l
l l
l l
St l
OP l
l l
1 l
l j
i i
i l
1 I
I i
i It i
RR I
I I
I l
l 1/20G085 l M-47-2 l
2 l
A l 3.0 l BTF l M.0. l C
l C
l Lt l
RR l
VR-1 l
l l
l l
l M-150-2 l l
l 1
l l
l l
St i
OP l
l l
1 l
l l
l l
l l
1 1
1 1
I It 1
RR I
I I
I l
4 l
l i
l l
l l
l l
l l
l l
l 1
l l
l 1
1 1
1 1
I I
i 1
1 I
I I
l l
l l
l l
l l
l 1
l l
l l
l l
l l
1 1
I I
I I
I i
1 1
I I
I I
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l 1
I i
i i
I i
i 1
1 I
I l
i l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l 1
1 I
i 1
I l
i i
1 I
l t
4.3 - TABLE 19 of 42 l
(0093D/00400/022192)
~
~
.m
'i i
INSERVICE TESTING PROGRAM Rev. 11 COMMONWEALTH EDISDN BYRON NUCLEAR POWER STATION l
VALVE l
l l VAL %E l VALVE l VALVE l ACT. l NORMAL l STROKE l TEST l TEST l RELIEr l
l TECM. l' l
l NUMBER l
P&ID l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION l DIRECT. lNETH00l MODE l REQUEST l
NOTES
.l POS.
l REMARKS l l
l 1
I I (IN.) l I
l 1
l l
I I
I I
'l l1/2PR001A l N78-10 l 2
l A
l 1.0 l GL lA.O.l 0
l C
l Lt l
RR l
VR-1 l
l l-l.
i lM-151-1 l l
l l
l l
l l
rt l
OP l
l l
2 l
l l
1 l
l l
l l
l l
l St l
OP l
l l
i l
l'.
l I
I I
I I
I I
I I
It i
RR I
I I
l j
l1/2PR001B l S78-10 l 2
l A
l 1.0 l GL l A.O. l 0
l C
l Lt l
RR l
VR-1 l
l l
l l
lM-isi-1 l l
l l
l l
l l-rt l
OF l
l l
2 l
l-l l
l 1
l l
l l
l l
St
]
OP l
l l
i l
l
-l l
l I
I I
I l
I I
It i
RR I
l l
l l
4 l1/2PR002E l M-78-6 l
2 l
A l 2.0 l GL lM l
C l
C l
Lt l
RR l
VR-1 l
l l Passive l l
l 1
1 1
I I
I I
I I
I I
I I
l
'l1/2PR002f l M-78-6 l
2 l
A l
2.0 l GL lM l
C l
C l
Lt l
RR l
VR-1 l
l l Passive l l
1 1
1 1
1 I
I I
I I
I i
i 1
l 1
l1/2PR002G l M-78-6 l
2 l
AC l
2.0 l CK lS.A. l C
l C
l Lt l
RR l
VR-1 l
l 3
l Passive l l
l l
1 1
I I
I I
i 1
1 I
l 1
l
.i j1/2PR002tt jM-78-6 l
2 l
AC l 2.0 l CK lS.A. l C
l C
l Lt l
RR l
VR-1 l
l 3
l Passive l l
1 I
I l'
I I
I I
I I
I I
I 1
l l1/2PR032 l M-78-10 l
2 l
AC l
1.0 l CK lS.A l C
l C
lLt/Bt lRR/CS l VR-1 l
37 l
3 l Passive l l
l M-Ist-1 1 I
I I
I I
I I
I I
I i
1 l.
L l1/2PR033A l %78-6' l
2 l
.A-l 2.0 l GL lM l
C l
C l
Lt l
RR l
VR-1 l
l l Passive l l
1 1
I I
I I
I I
I I
I I
I I
l l1/2PR0338 l M-78-6 l
2 l
A l 2.0 l GL lM l
C l
C l
Lt l
RR l
VR-1 l
l l Passive l l
l 1
1 1
1 1
I I
i 1
1 I
l-l l
j 1/2PR033C l M-78-6 l
2 l
A l
2.0 l GL lM l
C l
C l
Lt l
2R l
VR-1 l
l
.l Passive l.
l 1
I I
I I
I I
I I
I I
I 1
l l
l 1/2PR0330 l M-78-6 l
2 l
A l 2.0 l -GL lM l
C l
C l
Lt l
RR l
VR-1
}
l l Passive l l
l 1
1 I
I I
I i
l I
I i
l I
l l1/2PR066 l M-78-10 l
2 l
A l
1.0 l GL lA.0 l 0
l C
l Lt l
RR l
VR-1 l
l 1
'l i
-l l M-is1-1 l
.l l
l l
l l
l rt l
OP l
l l
2 l
l l
l l
l l
l l
l l
l It i
RR l
l l.
l l
l l
l l
l l
l l
1 1
1 St i
OP l
VR-12 I
i 1
l l
l l
l l
l l
l l
l l
l l
l l
1 l
l t
i I
I 1
1 1
1 1
1 1
1 1
I
-l 4.3 - TABLE 20 of 42 (00930/00400/022192)
'W
}
n INSERVICE TESTING PROGRAM Rev. 11' COMMONWEALTH EDISON BYRON NUCLEAR POWER STATION l
VALVE l
l l VALVE l VALVE l VALVE lACT.l NORMAL l STROKE l TEST l TEST l RELIEr l
l TECH. l' l
l NUMBER l
P&ID l CLASS l CATEGORY l SIZE l TYPE l TYPE lPOSITiOHl DIRECT.l METHOD l MODE l REQUEST l
NOTES lPOS.,l REMARKS..l' l
1 I
I I (IN.) i I
I I
I I
l l
l 1
l 4
l 1/2PS228A l-l
. l
-l l
l l
l l
Lt l
RR l
VR-1 l
l l
-l' l
l M-68-7 l
2 l
A l 0.50 l-GL l 5.0. l -
0
-l C
l St l
OP l
VR-12 l'
l 1
l l:
I l
l M-14-6 l
l l
l-l l
l l
r(
l OP l
l l
2 l
.]
l l
l l
l l-i I
i 1
It i
RR I
I 20 l
l l
l l1/2PS2289 l l
l l
l l
l l
l Lt l
RR l
VR-1 l
l-l l
l l M-68-7 l
2 l
'A
'l 0.50 l GL lS.0.l 0
l C
l St l
OP l
VR-12 l
l 1
l l:'
l l M-te-6 l-l l
l l
l 1
l rt l
OP l
l l
2
-l l
j__
l I
I I
I I
I I
I It i
RR I
l' 20 1
I l
l 1/2PS229A l l
.l l
l l
'l l
l Lt
]
RR l
VR-1 l
l l
l
[
]
-l M-68-7 l
2 l
A l 0.50 l GL l 5.0. l 0
l C
l St l
OP l
VR-12 l
l 1
l l
l l M-ie-6 l l
l l
l l
l l
rt l
OP l
l l
2 l
l l
l l
l l
l l
1 l
1 It l
RR I
I 20 1
1 l
l 1/2PS2298 l l
l l
l
.]
l l
l tt l
RR l
VR-1 l
l l
l-l lM-68-7 l
2 l
A l 0.50l GL l5.0.l 0
l C
l St l
OP l
VR-12 l
l 1
l l
l 1 M-140-6 l l
l l
l l
l l
rt l
OP l
l l
2 l
l-l l
l 1
1 I
I I
I I
It i
RR I
I 20 l
l
-j.
l1/2PS230A l l
l~
l l
l l
l l
Lt l
RR l
VR-1 l
l l
l l
lM-68-7 l
2 l
A l 1.00l GL lS.C.l C-l C
l St l
OP l
VR-12 l
l I
l l
l l
l M-140-6 l l
-l l
l l
l l
rt l
OP l
l l
2 l
l l
1 1
1 l
l l
l 1
I It i
RR l'
l 20 1
I l
l 1/2PS2308 l l
l l
l l
l l
l Lt l
RR l
VR-1 l
l
'l l
l lM-68-7 l'
2 l
A l 1.00l GL l5.0.l C
l C
l St l
OP l
VR-12 l
l 1
l l
1 l
l M-140-6 l
l l
l l
l l
l rt l - OP l
l l
2 l
l-l 1
1 I
I I
I i
I i
It i
RR I
I 20 1
I l'
.i l 1/2PS231A l M-68-7 l
2 l
A l 0.75l CK lS.A. l C
l C
lLt/Bt lRR/CS'l VW-1 l
38
. l 3
l ll l
l M-140-6 I
I l
i i
1 I
o i
Ct i
OP l
I 22 1
3 I
l l 1/2.PS2318 lM-68-7 l
2 l
A l- 0.75 l CK lS.A. l C
l C
l Lt/Bt lRR/CS l VR-1 l
38 l
3 l
ll f
l l M-140-6 I
I I
I I
I I
O l _. Ct i
OP I
I 22 1
3 1
l
[
l1/2PS9354Al l
l l
l l
l l
l St l
OP l
l l-1 l
l l
lM-6s-1B l 2
l
.A l 0.375l GL lA.O.l C
l C
l Lt l
-l
'VR-1 l
l l
ll l
lM-140-i l
l l
l l
l l
l It l
RR l
l l
.l
.l-l i
i I
i I
I i
1 I
rt i
OP l
l I
2 I
l (0093D/00400/022192) 4.3 - TABLE 21 of 42
Rev --11 INSERVICE TESTING PROGRAM COMMONWEALTH EDISON BYRON NUCLEAR POWER STATION l
VALVE l
.l
.l VALVE l VALVE l VALVE lACT. l NORMAL l STROKE'l TEST l TEST l RELIEF l
l TECH.'l lt l
NUMBER l
P&ID' l CLASS l CATEGORY l SIZE l TYPE.,l TYPE l POSITION { DIRECT.l METHOD l NODE l REQUEST l-NOTES lPOS. lRENARS l=
l l
1 1
I (IN.) !
I I
l l
I l
1 I
I l
l 1/2PS93548 l l
l l"
'l l
l l
l St l
OP
'l l
l.
I l
-l l
' l n-68-18 1 2'
l
'A l0.375l'GL lA.O.l C
l C
l Lt l
RR l
VR-1..
l l
l l
l l M-140-1 I
I I
I I
I I
It - l RR l
l l
l 1
l l
't i
I I
I I
I I
rt i
I I
2 I
'l l
l-l l
l l
St l
OP j
l
.l 1
l l.
l1/2PS9355Al l
l
~ A l0.375l GL lA.O.l C
l C
l ' Lt l,
RR l
VR-1 l
l
-l l
l lM-68-1B l 2
l I
i n-140-1 I
I I
I l
l l
1 It l
RR l
l l
.]
l l
I I
I I
I I
1 I
I rt i
OP i
1 1
2 1
-l.
l 1/2PS93558 l l
l l
l l
l l
l St
]
OP l
l l
1 l
l l
'l M-68-18' l 2
l A
l0.375l.GL l A.O. l C
l C
l Lt l
RR' l
VR-3 l
l l
Il l
1 M-140-1 1
I I
I I
l l
1 It l
RR l
l l
l
-l l
1 1
I I
I I
i l
i Ft i
OP' l
I 1
2 i
'l l1/2PS9356Al l
l l
l l
l l
l St l ' OP l
l l
1 l
l l
l 4 68-1A l 2
l A
l0.375l GL=,lA.O.l C
l C
l Lt l
RR l
VR-l l
l l
l_
l 1 8-140-1.I l
l l
i I
I I
It l
RR 1
l l
l l
I 1
l i
I I
I I
I I
rt i E I
I l-2 I
l l1/2PS93568l l
l l
l l
l l
l St l
09 l
l l
1 l
l.
l l M-68-1A l 2
l A
l0.375l GL l A.O. l C
l C
l Lt l
RR l
VR-1 l
l l
l l
1 M-140-1 I
I I
i l
I I
i It-I RR I
I I
I I
i i
i l
I i
l I
I i
rt i
OP l
l 2
I j.
l1/2PS9357Al l
l l
l l
l l
l St l
OP l
l l
1 l
l l
l H-68-1B l 2
]
A l 0.375] GL l A.O. ]
.C
]
C l
Lt l
RR l
VR-1 l
l l
l l
l n-140-1 I
I I
I I
i l
l It l
RR l
l l
l l_
l l
I i
i l
I I
I i
rt i
OP I
l l
2 l
l l 1/2PS9357B l l
l l
l l.
l l
l St l
OP l
l l
1
.l l
l lM-68-19 l 2
l A
-l 0.375l GL lA.O.l C-l C
l Lt l
RR l
VR-I l
l l
l l
I n-i40-1 l
1 l
'l i
I l
l It i
RR I
l 1
l l-l 1
l 1
1 1
1 1
1 l
rt i
OP l
I I
2 l
l 1
I l
i I
l 1
I I
I I
i l-1 I
I l
l I
i l
'l l
l I
I I
I I
I I
l l
l l-1 I
I I
i l
I I
i l
I.
I l
l l
I I
I I
I I
I I
I I
1 1
1
'l 4.3 - TABLE 22 of 42
-(00930/00400/022192) se.
,a INSERVICE TESTING PROGRAM Rev. 11~
COMMONWEALTH EDISON BYRON NUCLEAR ~ POWER STATION
. ALVE l VALVE l VALVE l ACT. l NORMAL - l STR0kE I TEST l TEST.]
RELIEF l
l TECH.-l l
I VALVE l
l l
V l
NUMBER I
Pt.ID l CLASS I CATEGORY I SIZE" l TYPE ~l TYPE I POSITION l DIRECT. l NETH00 l MODE l REQUEST l
NOTES l POS.,I REMARKS l:
l l
l l
1 (IN.) !
'l l
l 1
l l
l 1
I' l
l1/2RC014A 'l M-60-1B l 1
.l' 8
l 1.0 l GL
- S.0.1 C
l 0
l St I ' CS ll VR l 7
I 1-l l
l l M-135-1B l l
l l
l 1
l C
l-Ft l
CS I
l 7
l 2
l l
r i
I i
i I
I i
1 0
1 It 1
RR I
l 20 l
l 1
i 1/2RC0148 l M-60-18 l 1
l B
i 1.0 l
GL' i S.O. 'l C
.]
O l
St l
CS l
VR-12 l
7 l
1-1 i.
I l M-iss-iB I l
1 l
1 1
1 C
I rt i
CS I
i 7
1 2
l l
l l
l 1
1 I
I I
i
'o i
It i
RR I
I 20 1
l l
j l1/2RC014C l M-60-1B l 1
l B
l 1.0 I'GL l5.0.l C
]
O l'
St I
CS I
VR-12 1
7 l
1
]
I I
IM-135-1Bi 1
1 1
I I
I C
1 n
I CS I
I 7
1 2 - 1 1.
l l
I l-
'l i
i I
i o
l It i
RR I
I 20 I
I l
}
l1/2RC0140 l M-60-1B l 1
l B
li1.0 l GL i 5.0. l C
l 0
l St l
CS I
VR-12 1
7 l
1 l
,1-0 I
lH-135-1Bl l
.l 1
-l l
l C
l rt l
CS I
1.
7 1
2 l
l l
1 1
I I
I I
I l
0 l
It i
RR I
l 20 l
~l l
t 4
I l
i I
I I
.I I
I I
I I
I I
l-I l
l 1
J l
1 1
1 1
1 I
i 1
1 I
I l
1 1
I I
I i
1 1
I I
I I
I I
I l
l 1
1 l'
I I
I I
I I
I I
I I
I 1
l l
l l
l l
l 1
i i
I I
i l
i 1
l-i i
l I
I I
I l
I l
l l
I I
i 1
a; I
I i
i I
I I
I I
I i
l l
1 I
i l
1 1
I I
I i
i I
I I
I i
l 1
l I
I I
I I
I i
1 I
l-1 I
I i
1 1
1 l
l l
l l
1 1
I l
1 I
i I
I I
1 i
i l
l
'l I
.I
'l i
1 1
1 I
l-1 I
I 4
l l
l l
l l
l 1
I I
I l
l l
l 1
I I
I I
I I
I I
I I
I I
I I
l' l
l l
1 1
I I
I I
l 1
I I
i 1
1 I
l-i l
l I
.i
.I l
l l
l l
1
.I I
I l'
I l
l i
i l
i I
I I
I I
I I
I I
1 I
I i
1 1
I I
I I
I I
I I
I I
I l
1 1
_1
- l_
1 1
I I
I I
I I
I i
l
[
i l
l I
i 1
1 I
l' I
i i
i i
1.
I I
I i
i l'
I I
I I
I i
I i
i i
i I
i l'
(00930/00403/022192) 4.3 - TABLE 23 of 42
-~
,e
-INSERVICE TESTING PROGRAM Rev. 11-COMMONWEALTH EDISON BYRON NUCLEAR POWER STATION l
VALVE' l
l l VALVE l VALVE l VALVE l ACT. l NORMAL.l STROKE l TEST l TEST 8 RELIEr l
l TECH. l l
l NUMBER l'
P&ID l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION l DIRECT.lNETH00l MODE l REQUEST l
NOTES lP05. lREMARK$ l l
l l
l 1 (IN.) l l
l l'
I l
i I
I l
l l1/2RE1003 l M-70-1 l
2 l
A l
3.0 l D
l A.O. l C
l C
l St l
OP l
l
-l
'1 l
l l M-141-1 1
I I
I I
I I
I tt.
I RR l
VR-1 l
l l
I i
1 l'
I I
I I
I I
It-l RR 1
l 1.
l l
1 1
I I
I I
I I
I rt i
OP l
I l
2 I
l l1/2RE9157 lM-70-1 l.
2 l
A
-l 1.0 l
D'
.l A.O. l 0
l C
l St l
OP l
VR-12 l
l_
1
.l l
l 1H-141-1 1 I
I I
I I
I I
It l _
l l
l l
l RR l
1 1
I I
I I
I I
I rt i
De l
l l
2 l
l-J l
I I
I I
I I
I I
Lt l
RR l
VR-1 I
I l
l l1/2RE9159AlM-70-1 l
2 l
A
'l 0.75 l D
lA.O.l 0
l C
l St l
OP l
VR l l
1 l
l~
l i M-141-1 l
l l
l l
l l
l
-It l
RR l
l l-l l
l 1
l l
1 I
I I
I I
rt i
De l
l l
2 l
l l
1 1
I I
I I
i 1
l Lt i
RR l
VR-1 I
I l
l l 1/2RE9159B l M-70-1 l
2 l
A l 0.75l D
lA.O.l C
l C
l St l
OP l
VR-12 l
l 1
l l
l 1 M-141-i I
i i
I I
i l
I Lt i
RR l
VR-1 l
l l
l l
1 l
l l
l 1
l l
I It i
RR I
I I
I I
l L
I I
I I
i 1
1 I
rt i
OP l
l l
2 l
l l 1/2RE9160A l M-70-1 l
2 l
A l
1.0 l
D l A.O. l 0
l C
l St l
OP l
VR-12 l
l 1
l l
1 I n-141-1 l l
1 I
i l
l 1
It i
RR I
I I
'l i
i 1
i I
l-1 I
I I
I rt l
OP l
l l
2 l
l 1
I I
I i
1 1
I 1
1 Lt i
RR I
VR-1 I
I 1
l l 1/2RE91608 l M-70-1 l
2 l
A l
1.0 l
D l A.O. l 0
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4.3 - TABLE 24 of 42 (0093D/0040D/022192) w-c
I',
lllllllll1lI1IlIIIiIlIIII!liIilIIIl S
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I lll lllI lliI Il II I!II II II I1
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a Rev. 11 INSERVICE TESTING PROGRAM COMMONWEALTH EDISON BYRON PA' CLEAR POWER STATION l
VALVE l
l l VALVE l VALVE l VALVE lACT,l NORMAL l STROKE l TEST.l TEST I RELIEF l
l TECH.l l
MODE l REQUEST l
NOTES l POS. l REMARKS l l
NUMBER l
P&ID l CLASS l CATEGORY l SIZE l TYPE 'l TYPE l POSITION l DIRECT. l NETH00 l l
i l
l I (IN.) l I
I l
l l
l l
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l l 1/2RH8701A l S62 l
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l 0
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l 0
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8 l
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l I
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l 0
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l l S137 I
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3 l
l I
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l l
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l l
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l l
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l I
l 1
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l l
1 I
l I
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I I
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l-l l
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l 1
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l l
1 1
I I'
l l
4.3 - TABLE 26 of 42 (00930/00400/022192)
_r e.
INSERVIEE TESTING FROGRAM Rev. 11 CCHMONWEALTH EDISON BYRON NUCLEAR POWER STATION l
VALVE l
l l VALVE l VALVE l VALVE lACT.l NORMAL l STROKE l TEST l TEST l RELIEr l
l TECH. l l
l NUMBER l
P&ID l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION l DIRECT. l NETH00 l MODE l REQUEST l
NOTES l P05. l REMARKS l l
l l
1 1 (IN.) l I
l l
l l
l l
l l
l l 1/2RY455A l H-60-5 l
1 l
B l
3.0 l PORV l A.O. l C
l 0
l St l
CS l
l 36 l
1 l
l l
l W135-5 l l
l l
l l
l l
It l
RR l
l 36 l
l l
l l
1 i
l i
I I
i l
rt i
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1 l
2 l
l l1/2RY456 l M-60-5 l
1 l
B l
3.0 lPORV lA.D.l C
l 0
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l 36 l
1 l
l l
l M-135-5 i l
l l
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l 36 l
l l
l l
l l
1 1
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l ll l 1/2RY80008 l %60-5 l
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l 0
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l l
l l
l 1 n-135-5 1 I
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I ll l 1/2RY8010C l W60-5 l
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l 0
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1 I
l l
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1 36 I
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l l
l l
l l
l St l
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l
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l A
l 0.375 l GL l A.O. l C
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l l
l l
l l
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l ll l
l l
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l &l35-6 l l
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l
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l l
l l
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vR-i2 l
l i
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l 11 l
l l
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l i
2 l
l (0093D/00400/022192) 4.3 - TABLE 27 of 42
, ~--
l f
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i l
lI ilIliiI IIIIi I iI il IiI II 1 i lI I I IIl I I S
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INSERVICE TESTING FROGRAM Rev. il
{j COMMOPfWEALTH EDISON BYRCN NUCLEAR POWER STA' ION l
1 VALVE I
I 1 VALVE I VALVE l VALVE I ACT. I NORMAL i STROKE l TEST I TEST I RELIEF i
i TECH. I I
i i
NLPEER I
P&ID ICLASSICATEGORYISIZE I TYPE I TYPE I POSITION l DIRECT. I TTN00 i PODE I RE7 JEST
]
NOTES IPOS. I REMARKS I l
1 1
I I
I IIN.1 1 1
I I
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i I
i 1/25A032 1 554-2 l
2 l
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t-1 1
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l 11/25A033 1 %54-2 1
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j 4.3 - TABLE 29 ef 42 (0093D/00400/022192)
W
INsMVICE TESTING PROGRAM Rev. 11 CCPeortWEALTH EDIs0N BYRON NUCLEAR POWER STATICN l
VALVE I
I l VALVE I VALVE I VALVE I ACT. I NORMAL i STROKE I TEST I TEST I RELIEr I
iTECH. I I
l NUMBER I
P&ID l CLAs3 1 CATEGORY l SIZE I TYPE I TYPE I POSITION l DIPECT. I NET >t0D I MODE I RE0rl5T l
NOTES I POS. I REMAnts i i
i 1
1 I (IN.) 1 I
I I
I I
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1 I
I i 1/25D002A ] 548-sA/B]
2 l
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! 2.0 1 GL iA.O.1 0
i C
i Lt i
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i 14 i
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I I
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i i
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I I
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1 I
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I I v2so002G I m sA/Bi 2
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l 34 I
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st i
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I i
(0108D/0041D/022 92) 4.3 - TABLE 30 of 42
~
i Rev. 11 INSERVICE TESTIP6 FCOGRAM COPHONWEALTH EDISON BYRON N'JCLEAR POWR STATION l
VALVE I
l l VALVE I VALVE l VALVE l ACT. l NORMAL l STR0kE I TEST [ TEST I RELIEF l
l TECH. l l
l NUMBER l
P&ID l CLASS l CATEGORY l SIZE l TYPE I TYPE l FOSITION l DIRECT. ] FETH00 l MODE REQUEST l
NOTES l FOS.
l#EMARK5 l l
l l
1 I
I (IN.) i I
I I
l I
I I
I I
l l 1/250005A l M-48-5A/BI 2
l A
l 0.375 l GL i A.0 1
0 l
C l
St i
CP 1
l l
1 l
l l
I 1
I I
I I
I I
I tt i
pR I
I 34 l
l 1
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]
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1 rt 1
0F 1
1 I
2 I
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l A
i 0.375 i Gt i A.O. (
0 l
C i
St l
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l l
1 l
l I
I i
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I 34 I
I i
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1 0
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1 1.
I I
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1 1
1 I
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1 L_. _ _L L
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1 8
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1
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l_ _L_
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l
_1___ __ I d.3 - TABt.E 31 of 42 (01093/00410/022792)
I
Rev. 11 INSERVICE TESTING F90GEAM Com0NWEALTH EDIs0N ;
BYRON NUCLEAR POWER STATION l
VALVE l
l l VALVE jVALVEl VALVE lACT.l NORMAL l sTR0kE l TEST l TEST l RELIEF l
l TECH. l l
l NUMBER l
Pf.ID l class l CATEGORY l SIZE l TYPE l TYPE l POSITION l DIRECT. l METH00 l KDE l REQUEST l
NOTES l FCs. l REMAX s !
-l l
1 I
I IIN.) i I
I I
I I
I I
i 1
l l 1/2sI8801 A l N61-2 l
2 l
e l
4.0 l GA lM.0.l C
l 0
l st l
C5 l
l 13 l
1 l
l l
1 5136-2 I I
I I
I I
I I
It I
sa i
I I
I l
l 1/2s188018 l 5 61-2 l
2 l
B l
4.0 l GA l M.0. l C
l 0
l st l
Cs l
l 73 l
1 l
l l
1 N136-2 I I
I I
I I
I I
It i
RR 1
I I
I l
l 1/2 SIB 802A l N61-3 l
2 l
s l
4.0 l GA lM.D.l C
l 0
l st l
Cs l
l T4 l
1 l
l l
I m136-3 1 1
I I
I I
I I
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sa i
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I l
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2 l
B 1
4.0 l GA l M.0. l C
l 0
l st l
Cs l
l 14 l
1 l
l l
1 M-136-3 I
I I
I I
I I
I It I
en i
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1 l
l 1/25I88048 l N 61-1A l 2
l e
l 8.0 l GA l M.D. l C
l 0
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l l
1 l
l l
t mi26-1 1 I
I I
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l 1/2518806 l N61 1 A l 2
l B
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l 0
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1 l
l l
l M-136_LJ l
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l B
l 6.0 l GA lM.D.l C
l 0
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07 l
l l
1 l
l l
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l insIss0Ta l 561-i A l 2
l s
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I I
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[
I l
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2 l
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l C
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l 14 l
1 l
l j
l 1 N136-4 I I
I I
I I
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I l
l l 1/2sI8811 A l 561-4 l
2 l
8 l 24.0 l GA l M.0. l C
l 0
l st l
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VR-16 l
l 1
l l
l l 5136-3 1 1
I I
I I
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2 l
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l 0
l St l
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l 1
l l
l l
I M-136 4 1 1
I I
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L I
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2 l
8 l12.0 l GA lM.0.l 0
l C
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l l
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re 1
I I
l l
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l C
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l l
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l J
l 5 136-4 1 1
1 I
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1 1
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l 1/2sI8813 l 561-1B l 2
l 8
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l C
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1 l
l l
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l st l
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l l
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l l
l 1 5136-1 1 I
I i
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n I
RR I
I I
1 l
4.3 TABLE 32 of 42 l
(010B0/0047D/022192) i
^eT l
n Rev. 11 INSERVICE TESTING PROGEM COMMONWEALTH EDISCN BYSON NUCLEAR F0WER STATION f
VALVE l
l l VALVE I VALVE l VALVE l ACT. l NORMAL l STR0kE l TEST l TEST I RELIEF l
l TECH. l l
l NUMBER l
P&ID l class l CATEGORY l SIZE l TYFE j TYPE l PCsITION l DIRECT. l NETH00 l MODE l RE0iXsi l
NOTES l FCs. l FOURKs l l
1 1
I I (IN.) 1 I
i l
i I
I i
i I
l l 1/2518815 l 561-2 l
1 l
AC l 3.0 i tk iS.A.I C
l 0
i Ct I
Cs i
vR-15 l
J 3
l l
l 1 5 136-2 l I
I I
I I
i C
1 tt/st I RR/Cs i I
- 6. 40 1
3 I
ll 1insIB8iBAl ui4 l
i l
AC i
6.0 l Cx i s.A. I C
l o
l Ct i
Cs l
l 9
1 3
l l
l 1 M-136-4 1 I
I I
I I
I C
i Lt/st I se/Cs 1 I 6. 23. 40 1 3
I ij l 1/25188188 l 561 4 l
1 l
AC i 6.0 l CK l S.A. l C
l 0
i Ct l
Cs I
9 l
3 l
l l
I 5136-4 I I
I I
I I
C I Lt/et I sR/Cs !
I 6. 23. 40 1 3
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1 l
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C l
0 i
Ct i
Cs l
l 9
l 3
I I
I I r$-136-4 I I
I I
I I
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I tt/Bt i RR/Cs i I 6. 23. 1 1 3
1 1I i 1/2 SIB 8180 l 561 4 1
1 l
AC 1
6.0 l CK l s.A. I C
l 0
l Ct l
C5 l
l 9
l 3
l
[
ll l
I 5136-4 I I
I I
I I
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1 Ltr
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s 1 I 6. 23_ 40 1 3
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1 l
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l C
l E.3t ' RM.5 l
l 6. 23. 40 1 3
l l
l l 5136-3 I I
I I
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1 0
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i vg ts i
1 3
I l
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1 l
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l C
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1
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FR 1
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I 3
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l l 5136-3 I I
I I
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1 l
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l r
i U'
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i 1
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1 i
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! s.A. I C
l C
l wr ' n/Cs l l 6. 23, 40 1 3
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l l
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l I
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l l
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I I
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.J It I
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6, 40 l
3 l
lI l_
I m11h3 I I
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1 l
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l xtICt_ L C5tRR _I VR-15__]
I 3
I l
l f
4.3 - T ABLE 33 of 42 (01090/00410/022192)
~ - - - - - ' ' -
T
I
i INSERVICE TESTING PROGRAM Rev. 11 CC W EALTM EDIs0N 1
BYRON M) CLEAR POWER STATION l-l VALVE l
1 i VALVE IVALVEIVALVElACT. I NORMAL IsTROKE l TEST I TEST l RELIEF l
1 TECH. l l
l NUPECi l
P&ID l class l CATEGORY l SIZE I TYPE l TYPE i POSITION l DIRECT. l NETH00 l MODE l RE(P1EsT l
NOTES l M.
l REMARKS i I
I i
1 1 (IN.) l I
I I
I I
I I
I I
I l 1/2518871 l 1
2 i
A i 0.75 i GL i A.0 i
C l
C l
st i
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1 1
I l
4 1
I M-61-6 I
I I
I I
i 1
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n I
n-1 1
I lamin 1 1
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i l
1 1
1 1
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n l
1 I
l
[
l
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l C
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l l
1 l
l I
I 561-6 I
l l
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1 3
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1 1/2518900s l 561-2 l
1 l
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l 0
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l 3
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l 1 $136-2 I I
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l 3
i I
4 i
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3 I
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1 AC i
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l 0
i Ct i
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1 3
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l l 5136-2 I I
I i
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_l.
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1 l
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l 0
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I i
1 I
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i i
I i
c 1 Ltret I n/C3 1 1
- 6. 40 3
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i l
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l 1
l 1 513E3 I I
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L 40 1
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l 1/2s189050 l 561-3 1
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l l
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I 31 1
3 I
I i
4.3 - TABLE 34 of 42 (0108D/00410/022192) 4
Rev. II INSERVICE TEsTItG F 0 GRAM CortOf-{ALTH EDIs0N 8YRON NUCLEAR FoWER STATION l
VAtvE l
l l VALVE l VALVE l VAtVE l ACTS I NORMAL I sTRcAE [ TEST { TEST l RELIEF l
l TECH. l l
l NUMBER l
P&ID lCt/.ssl CATEGORY l SIZE l TYPE l TYPE l FosITION l DIRECT. l METHOD l MODE I REQUEST l
MOTES l Pos. l REMARKS l l'
i 1
1 I (IN.1 1 1
- 1 I
I I
I I
I 1
l l t/2sta920 l 561-1A l 2
1 8
l 1.5 i GL l M.o. l 0
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st l
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l l
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[
l I S136-1 1 I
I I
l i
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l C
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l 0
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l l
l 1 m136-1 1 I
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l lI i
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l 4.3 TABLE 35 of 42 (01G80/00410/022192 )
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1 IlI l Il1I]i1III I_i1I!
i IiIlI 1lIjIII liI s
KR i
i A
s s
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'c v.
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2 3
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II iI II iI BA T
S 7
7 E
2 2
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9 6
9 9
2 4
l II ll 11 i I iiII I I I 1 I 1 II iI I I
- I I I II I I Il T
F S E E 5 5 i
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=
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ii T E s
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s cR
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sL L O E AR A I A
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s Fev. Il INSERVICE TESTING PROGRAM COMMONW ALTH EDISON sYWON NUCLEAR F0WER STATIN l
VALVE l
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l TECH. l l
l NUMBER l
P&ID l CLASS l CATEGORY l SIZE lTV'E l TYPE l FOSITION l DIRECT. {.PETHOD I PODE l REfAJEst l
NOTES l FOS. lFEMARKS l l
1 1
I I (IN.) I I
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l l 1/2sx002A l 542-18 l 3
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I 4.3 - 7tBLE 37 of 42 (01060/0041D/022192)
~
[-
y
Pev. 11 INSERVICE TESTING FSoGRAM CCN ONWEALTH EDISON BYRON NUCLEAR POWER STATION l
VALVE l
1 l VALVE l VALVE I VALVE I ACT. I NORMAL i STROKE l TEST I TEST I RELIEF l
l TECH.I l
NUMr>ER I
F&ID'
- CLASS lCATEGORYlSIZE I TYPE ITYPEIPOSITIONIDIRECT.IMETM00l NODE l REQtKST I
NOTES l P05. IGEMAFKS l l
1 I
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I 4.3 - TaSt.E 38 of 42 (01080/0041D/022192) l 1
I m
er Wev. II INSERVICE TESTING PR% RAM C0 6 WEALTH EDISON BYRON NUCLEAR F0WER STATION I
VAtVE I
'l.
l VALVE l V4 VE l VAtVE 1 ACT. I mRm t i STRW E I TEST I TEST I REU Er I
l TECH. I l
l WMBER l
P&ID' lCLASSICATEGORYl SIZE I TYPE I TYPE l POSITION i DIRECT. ] METHOD l M0cE I REQUEST l
NorES l POS.
l REMAFK$ 1 I
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1 I 1/2VQ001A l 5:05-1 -1 2
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l 4.3 TABLE 39 of 42 (0108D/0041D/02'2192)
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ll[Ilil!IilII IIIJIIiIIIIIIliiI1IliI S
e e
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v v
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i (0108D/0041D/022192) 4.3 - TABLE 42 et 42
)
9
-l SECTION 4.4 NOTES i
)
_. -. ~ -
1 Rev. II l
I uQTE 1 Closure of the Main Steam isolation valves 1MS001A-D or 2MS001A-D during unit l
operation would result in reactor trip and safety injection actuation. To i
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 plant conditions allow, per IWV-3412.
KOTE_2 The testing of any emergency boration flowpath valves during unit operation is
.j not practical.
Stroke testing the Boric Acid injection isolation valve ICV 8104/2CV8104 and check valve 1CV8442/2CV8442, the RH to CV pump suction i
isolation valve ICV 8804 A/2CV8804 A, or the RWST to CV pump suction isolation valves ICV 112D,E/2CV112D,E, could result in boration of the RCS, resulting in 5
a cooldown transient.
Aligning the system in this configuration even for a short duration is, therefore, unacceptable.
These valves will be stroke tested during cold shutdown, in accordance with INV-3412.
NOTE,3 l
l These valves are the Main reedvater isolation valves:
IrdOO9A-D/2FWOO9A-D, and cannot be fully stroked during operation as feedwater would be terminated causing a reactor trip. They will, however, be partially stroke tested during operation as well as full stroke tested during cold shutdown, per the requirements of IWV-3412.
uaT u Closure of these letdown and makeup valves 1CV112B,C/2CV112B,C, ICV 8105/
2CV8105, 1CV8106/2CV8106, ICV 8152/2CV8152, and ICV 8160/2CV8160 during normal unit _ operation would cause a loss of charging flow which would result in a reactor coolant inventory transient, and possibly, a subsequent reactor trip.
These valves will be full stroke / fall safe exercised during cold shutdown as required 'oy IWV-3412.
t NOTE 5 The IRH8701A/B. 1RH8702A/B, 2RHB701A/B, and 2RH8702A/B valves are the iroletion bounJary between the Residual Heat Removal pumps and the Reactor Coolt.nt System.
Opening one of these valves during unit operation will leave caly 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 varing cold shutdown, per IWV-3522.
k (0094D/0035D/022192) 4.4 - page 1 of 9 r
~- _. _._._._.,_.. _._ _ __. _ _. _.
Rev. 11 MIL.1 The following valves have been identifled as intersystem LOCA valves. They form a pressure boundary between the RCS and other essential components in order te protect these components f rom damage.
These valves will be leak testJS in accordance with the Byron Technical Specifications.
Performance of j
the leak test on these valves also satisfies the back-flow test required for check valves by HRC Generic Letter 89-04.
Byron Unit 1 and Unit 2 Intersysteu LOCA Valves 1RHB701A/B 1RH8702A/B 2RHB701A/B 2RH8702A/B 1RH8705A/B 1RH8705A/B 2RH8705A/B 2Ril8705A/B ISIB818A-D 181881$
2SatB18A-D 2518815 ISIB819A-D IS18905A-D 2SI8bl9A-D 2SI6905A-D ISIB841A/B 1 SIB 948A D 2 SIB 841A/B 2 SIB 948A-D 1518900A-D 1518949A.D 2518900A-D 2 SIB 949A-D ISIB956A-D 2 SIB 956A-D 11011_1 The Reactor Pressure vessel Vent Valves 1RC014A-D and 2RC014A-D cannot be stroked during unit operation, as they provide a pressure boundary between the Reactor Coolant system and containment atmosphere.
Tailure 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.
IIDIL f 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 4
Due to the RCS pressure, the check valves listed below cannot be full stroke exercised during unit operation 1S18818A-D 2 SIB 818A-D RHR Cold Leg Injection ISIB95BA/B 2518958A/B RWST to RHR Pump Suction These valves will be full stroke exercised during cold shutdown, in accordance with IWV-3522.
(0094D/0035D/022192) 4.4 - page 2 of 9
....... _. ~,. _, - _.
_. -, _ - - - -. _ _ _, _ _,. _.,, _ _ _ _. _ _ _ _. _ _,, - ~, - -
Hev. 11 HQ3E 10 The irWO39A-D and 20WO39A.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 effects on the Stenm Generators. These valves will be full stroke / fall safe tested during colo shutdown, por IWV-3412.
NOIE_ll The Primary Contalnment Purge supply and Exhaust Valves IVQ001A/B, IVQ002A/B, 2VQ001A/D, 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 then mode 5 or 6 would be a violation of the Byron Technical Specifications. 7hese valves wlll be full stroke tested during cold shutdown, in accordance with IWV-3412. These valves will be leak tested semiannually, in accordance with Dyron Station Technical Speeltications.
The Primary Containment Mint-Purge and Exhaust Valves IVQOO4A/B, IVQ005A/B/C, 2VQOO4A/B, and 2VQ005A/B/C, and the Post LOCA Purge Exhaust Valves IVQ003/
2VQOO3 will be leak tested every 3 months, in accordance with Dyron Station Technical Specifications.
tlDitJ2 The Auxillary reedwater check vt:1ves 1Ar001A/B, 1Ar003A/D, 1Ar014A-H, 1Ar029A/B, 2Ar001A/B, 2Ar003A/Ds 2Ar014A-H, and 2Ar029A/D cannot be full stroke tested during unit operation, _ as this would-Induce potentially damaging thermal stresses in the upper feedwater nozzle piping. The 1Ar001A/H, i
1Ar003A/B, 2Ar001A/B, and 2Ar003A/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 IWV-3522.
ROIE_13 The High Head Injection Isolation Valves ISI8801A/B and 2 SIB 801A/B cannot be stroke tested during unit operation.
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 i
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.
Y (0094D/0035D/022192) 4.4 - page 3 of 9
... _ _, _ _ _ _ _.. _. ~. _ _ _ _ _. _
Rev. 11 lE21 Q The safety injection system SVAG (Spurious Valve Actuation Group) valves 1 SIB 802A/D, 1818806, IS18809A/B, 1SI8813, 15I8835, ISIB840, 2 SIB 802A/B, 2518800,-2518809A/B, 2518813, 2518835, and 2 SIB 840 cannot be stroke tested during unit operation. These valves are required by the Technical Specifleations to be de-energized in their proper positions during unit operation.
Ftroking them would be a violation of the Technical Speelfications 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 18 in accordance with IWV-3412.
110T1._11
" DELETE "
llOIE_li
_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 reedwater Regulating Valves IrW510, IrW520, IrW530, IrW540, 2rW510, 2rW520, 2rW530, and 2FW540 during unit _ operation would cause a loss of f eedwater to the steam generators, resulting in a plant transient with a possible reactor trip as a result. These valves will be fall safe (rt) tested pursuant to the Byron Station Technics 1 Specifications, ll0TE_l1 d
These feedwater valves are exempt from all ASME Section XI testing requirements per INVL1100 and IWV-1200.
They are included in the program for
-operability tracking purposes only. The closure of the Main reedwater Regulating Bypass Valves irW510A, IrW520A, IrW530A, IrW540A, 20W510A, 2rW520A, 2FW530A, and 2rW540A during unit operation would require the Maln reedwater 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 fall safe (Ft) tested pursuant to the Byron Station Technical Specifications.
NOTE 18
" DELETE "
UQIE_.LO
" DELETE "
(Incorporated into NOTE 14)
I (0094D/0035D/022192) 4.4 - page 4 of 9 L
i i
Rev. Il llOIL._2D The remote position indicator (or these valves cannot be observed directly due to the encapsulated design of he solerd;d valve body.
During the Indication test, Indirect evidence of the icessary valve disk movement shall be used, in accordance with IWV-3412 (b).
the valves affected are listed below:
ICV 8114 IPS230A/B 2PS228A/B ICV 8116 1RC014A-D 2PS229A/B 1PS228A/B 2CV8114 2PS230A/B IPS229A/B 2CV8116 2RC014A-D NOTE 11 The Main reedwater Tempering riow Isolation Valves 1/2rWO34A-D 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, and will be fall safe (rt) tested pursuant to the Byron Station Technical Specifications.
HQIE_22 Por NRC request, the post-accident hydrogen monitoring system check valves 1/2PS231A and 1/2PS231B will be stroke eserclsed open on a quarterly frequency to verify operability.
NOTE 23 1/2 SIB 818A-D, 1/2SI8819A-D, and 1/2SI894BA/B are Event 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 84-04, position 84b.
NOTE 21 1/2CC9518, 1/2CC9534, 1/2CV8113, and 1RH8705A/B are check valves designed to re11 eve 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 re11 eve pressure only.
UQ15 lh Check valve 1/2 SIB 926 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 INJECTICH MODE to take suction from 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 1/2518806 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 1/2 SIB 926.
j (0094D/003SD/022192) 4.4 - page 5 of 9
)
Rev. 11 IlDTE 26 Check valve 1/2CVB546 prevents flow f rom 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 IHJECTION MODE to take suction f rom the RWST.
This check valve would stop reverse flow when the CV pumps are transferred to HOT / COLD LEG 1HJECT109 HODE 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 (BL) is required for 1/2CV8546.
1107I 21 Check valves 1/2 SIB 958A/B prevent flow from the Residual Heat (RH) Removal
. pump suction line to the Ref ueling Water Storage Tank (RWST).
The RH pumps are norma 12y lined up je the INJECTION MODE to take suction from the RWST.
These check valves woulo stop reverse flow when the RH pumps are transferred to HOT / COLD LEG RECIRCULATION MODE to prevent contamination of the RWST.
However, the 1/2S18812A/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 SIB 811A/B are electrically interlocked to prevent the backflow to the RWST when the RH system is in a RECIRCULATION MODE.
Thus, no back flow testing of 1/2 SIB 958A/B is required.
!!QIIL21 t
NRC Generic Letter 89-04, Attachment 1, Position 3 lists the CVCS Volume Control Tank (VCT) outlet check valve as an example of ASME Code Class check valves that perform a safety function in the closed direction that are frequently not back flow tested.
At Byron Station, check valve 1/2CVB440 prevents flow from the Chemical and Volume Control (CV) pump suction to the VCT.
The VCT is normally aligned to the CV pumps during normal plant operation.
During a Safety Injection signal, the VCT is automatically isolated by closure of the 1/2CV112B and 1/2CV112C M.O.V.'s, which are in series with the 1/2CVB440 check valve.
Closure of either M.O.V. will prevent reverse flow to the VCT.
Thus, no back flow testing of 1/2CVB440 is requited.
IlOIIL12 Check valve 1/2CVB442 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 1/2CVB442 is required.
)
1 (0094D/0035D/022192) 4.4 - page 6 of 9 t,
l l
Rev. II HRTE_JD Check valves 1/2Ar014A-H are verified to be closed each shift by the Operating Department, by verifying that the temperature at 1/2Ar005A-H is 1 130' r, per DOP 199-A40 (U-1) and DOP 199-A61 (U-2).
If the temperature is > 130' r at any 1/2Ar00$ valve, then abnormal operating procedure 1/2DOA SEC-7, " Auxiliary feedwater Check Valve Leakage", is entered to isolate and cool down the affected lines. This shiftly monitoring of 1/2Ar014A-H in the closed position adequately monitors the status of these valves. No additional monitoring /
trending by the IST Group is required.
HDTE_ll Check valves 1/2CVB480A/B and 1/2S18919A/B are the Centrifugal Charging Pwnp 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 wl t depend on the reference point of testing, acceptable full stroke will b. verified whenever the recorded mini-recirculation flowrate is within the " acceptable" or " alert" ranges given in the IST pump Surveillance.
NOTE 32 Check valves 1/2CC9463A/B and OCC9464 are the Component Cooling Water Pump discharge check valves. The full design accident flow through any one pump cannot be obtained during normal operation without causing low flow alarms in adjacent loops and possible equipment damage due to low cooling water flowrates to the Reactor Coolant Pump (RCP) seals.
These valves will be full-stroke exercised during cold shutdowns when plant conditions allow all four RCP's off.
UGTL-.3.1 The Essential Service Water (SX) and Make-Up Pump discharge check valves (OSXO28A/d) 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 Pump 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 pamp 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-of f line flow is within
" Acceptable" range contained in the ASME pump surveillance.
1 (0094D/0035D/022192) 4.4 - page 7 of 9 j
u
Rev. Il ROTE _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 10CTR$0 Appendix J and will now be tested per ASME Code Section XI, INV-3420.
HOIE_15 The 1/2RH870$A/B check valves will be 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 is SER 0/14/90.
HRTE_30 PORV's 1/2RY455A and 1/2RY456 will be stroke tested on a cold shutdown frequency and valves 1/2RYB025, 1/2RYB026, 1/2RYB028, 1/2RY8010A, 1/2RY8010B, 1/2RY8010C, 1/2RYB033, 1/2RY8000A, 1/2RYB000D, 1/2RY455A and 1/2RY456 will receive position indication tests on a refuel frequency per Generic Letter 90-06.
UQ1E 31 The Process Radiation Containment Isolation check valves IPR 032 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.
HQIE_lB The Process Sampling Hydrogen Monitor Containment Isolation check valves IPS231A, B end 2PS231A, B cannot be back flow tested during unit operation due to their-location. The test method used to backflow test these valves requires contairanent entry.
These valves will be backflow tested during cold shutdown.
1101L12 The Nitrogen Supply to the SI Accumulator Containment Isolation check valves 1818968 and 2S18968 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.
j (0094D/0035D/022192) 4.4 - page 8 of 9 1,
Rev. 11 Il0TL40 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 durlng cold shutdown.
1/2518815 1/2S18000A-D 1/2 SIB 818A-D 1/2518905A-D 1/2518819A-D 1/2 SIB 949A-D 1/2S18841A,B ll2ILil The RH Hot Leg Suction Pressure Relief Check Valves (1/2RH8705A,D) 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.
Il0TL42 The 1/251894AA-D Safety injection Cold Leg Pressure Isolation Valves cannot he tested during plant operation due to the high prear.ure 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.
t' (0094D/0035D/022192) 4.4 - page 9 of 9
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SECTION II.5 TECllNICAL APPROACHES AND POSITIONS d
l Rev. 11 1
VA-01
.!ST Technical Approach and Position A.
CQIrpontnt_Ldentificatioll 1.
==
Description:==
Method of Stroke Timing Valves - Timing using control board position indication lights (St).
2.
Component Numbers: See IST Valve Tables.
I 3.
References ASME Code,Section XI, Gubsection INV. paragraph IWV-3413(a).
4.
Code Class 1, 2, and 3.
5.
Examination Category (s): N/A 6.
Item Number (s): N/A B.
Etquirement Use of the control board open and closed lights to determine the stroke time of power-operated valves has recently become an issue for discussion in the industry.
Paragraph IWV-3413 of ASME XI defines " full-stroke tire" 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 th3 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.
ED11Linns It is recognized 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 or less, or 10% of the specified limiting stroke 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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'(0109D/0041D/022192) 4.5 - page 1 of 8
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Rev. 11 VA-02 IST Technical Approach and Position A.
C9Ennent_idRntification s 1.
-Description: Method of rail Safe Testing Valves.
I 2.-
Component Numbers:
See IST Valve Tables (Ft).
l 3.
References ASME Code,Section XI, Subsection IWV, paragraph IWV-3415.
4.
Code Class 1,
2, and 3.
.k 5.
Examination Category (s): N/A 6.
Item Humber(s)s N/A B.
EtqRlLRatnts Paragraph IWV-3415 of ASME XI states that "When practical, valves with fall-safe actostors shall be tested by observing the operation of the valves upon loss af 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 f alls 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.
Ensition:
In the cases where normal valve operator activ moves the valve to the 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 actuetors tnat do not operate as part of normal actuator operation must be tested by other means. This may be accomplished for motor-operated valves by opening the circuit breaker supplying operator power and observing that the valve moves to its fall-safe position, bifting 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 ASME Code,Section XI, Subsection INV,' paragraph INV-3300.
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1-(0109D/0041D/022192) 4.5 - page 2 of 8.
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Rev. Il VA-CJ IST Technical Approach and Position
.A.
Cpmpanent...IfcAtifle ntien t 1.
Descriptions Method of Tull Stroke (Ct) and Back Flow (Bt) Exercising of Check Valves.
2.
Component Numbers: See IST Vala Tests (Ct and Bt).
3.
Referencess (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.
Requirementt Paragraph INV-3522 ef Article XI states " check valves shall be exercisei to the position required to fulfill their function unless such operation is not practical during plant operation.
If only limited operation is practica), 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 determine. The verification of when a valve is the full open position affects the determination of which valves are only part-stroked and thus require additional full-stroke testing during cold shutdowns or refuelings.
C.
Position:
Valid full-stroke exercising to the full-open or full-closed position 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 INV-3522(b).
Per the requirements of 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_vte 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 ' low 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.
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(0109D/0041D/022192) 4.5 - page 3 of 8-1, ]
- _. ~. -
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Rev. 11
.C.' ' Position, continued One exception to the." maximum required accident flow" requirement is the methodology used to verify full-stroke exercising of the Safety 77jection L
(SI) Accumulator Back-up Check Valves, 1/2SI8956A-D.
Because of the high inaximum design flowrate Lof these valves, a maximum design accident flowrate test is physically impossible to perform. For those valves, an Engineering calculation has been performed to determine the m8,ue m flowrate for full disc lift. An acceptable full-stroke exerc n a these valves will be performed each refueling outage by measuring Lae
-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 dice litt.
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 and inspection of check valves to satisfy f ull stroke requiren ents is allowed as long as the requirements of NRC Generic Letter 89-08,, 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 sides of the valve to determine if the differential pressure expected with the valve shut is obtained, or (2)-opening a drain connection on the en stream side of 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 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 involved, and' system operating restrictions, valve disassembly and inspection may be performed during reactor ref ueling outages.
Since this frequency-differs from the Code required frequency, this deviation must be spec 2fically noted in the IST program.
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(0109D/0041D/022192) 4.5 - page 4 of 8 i-
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il Rev. 11 l
Where it is burdensome to disassemtle and inspect all applicable c.
valves each refueling outage, a sample-disassembly and inspection plan for groups of identical' valves in similar applications may be employed. The NRC Generic Letter 89-04 guidelines for this plan are explained belows-The sample disassembly and inspection program-involves grouping similar valves and testing one valve in each group during each refueling outage._ The sampling technique requires that each valve in the group be the same design (manufacturer, size, model number, and materials of construction) and have the same service conditiots includang valve orientation.
Additionally, at each dirassembl ;ts licensee must verify.that the 2
disassen oled 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-valvelof 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 I
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 du.-ing 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 inspecticn interval f rom
-disassembly 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.
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% feiture rate,.the_ station should determine-whether.the group size should te decreased cr.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.
f (0109D/0041D/022192) 4.5 - page 5 of 8 t,
RGv. 11 VA-04 IST Technical Approach and Position A.
-Component IdentificAL1 Qui 1.
Description Determining limiting values of full-stroke times for Power-Operated Valves.
2.
Component Numbers:
See IST Valve Tables (St).
3.
References:
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.
Item Number (s): N/A B.
Requirements-x The IST program originally assigned a limiting value of full-stroke time based on the most conservative value from plant Technical Specifications (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 devi6 tion 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 perf orm its intended f unction. When the calculated limiting value for a full-stroke is greater thar a TS or safety analysis limit, the TS or safety analysis limit should L-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.
(0109D/0041D/022192) 4.5 - page 6 of 8 l
Rev. 11 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 eequirements 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, bE3ed on the percent change from the pityinns 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 refertr,e/ average values of full-stroke, should allow for reasonable deviations sn 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 Pequest VR-20 will be taken when a valve exceeds its limiting value of full stroke.
C.
Ennill2n 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 - Lggi than oI_ equal to 10 seconds:
ALERT RANGE:
(1.50) (Tref) - (2.0) (Tret)
~
REQUIRED ACTION VALUE:
) (2.0) (Tref) tiOV's - Legi_1han or equal _to 10 seconds:
ALERT RANGE:
(1.25) (Tref) - (1.50) (Tref)
REQUIRED ACTION VALUEt
> (1.50) (Tref) llOV's/SOV's/HOV's/AOV's - Greater than 10 seconds:
See VR-20; this technical approach and position will not be put into application until relief request VR-20 is approved.
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(0109D/0041D/022192) 4.5 - page 7 of 8 1,
Rev. 11-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 measured stroke time to the nearest tenth of a second.
3.
When reference stroke valves or average stroke valves are affected by other parameters or conditions, then these parameters or conditions must be analyzed and the above factors adjusted.
l 4.
If the above calculated values exceed a Technical Specification or FSAR value, then the TS or FSAR value must be used for the-limiting value of full-stroke.
5.
Fast acting valves (valves 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 EQI 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 /UTSAR, operating history, and calculated values using the above criteria.
7.
Valves which serve the same function on dual trains (i.e., ICC9473A and ICC94738) and dual units (i.e. ICC9473A and 2CC9473A) are assigned the same REQUIRED ACTION / ALERT RANGE VALUES based on human f actors considerations, unless valve or system design differences exist between the trains / units.
8.
Refer to Relief Request VR-20 for related information.
b A
(0109D/0041D/022192) 4.5 - page 8 of 8 1
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SECTION l.6 i
RELIEF REQUESTS 4
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4
4
'R@v. 11-EELIEL1E0VESI_JPc1
-1.
.o2ve Humbert All primary containment isolation valves'in this Program are listed as Category As YAWLi YRYLt YAWL 1 1)
ICC685 41) 1PR033B 81) 1518964-2) 1CC9413A
- 42)
IPR 033C 82)
IS18968 3)
ICC9434 43)
IPR 033D 83)
IVQ001A 4)
ICC9416 44)
IPR 066 84) 1VQ001B 5)
ICC9438 45) 1PS228A 85) 1VQ002A 6)
ICC9486 46)
IPS22BB 86) 1VQ002B 7)
ICC9518 47) 1PS229A 87)
IV0003 8) 1CC9534 4F) 1PS229B 88) 1V0004A 9) 1CS007A 49)
IPS230A 89)
IV0004B 10)
ICS007B
. 50) 1PS230B 90) 1VQ005A 11)
ICS008A 51) 1PS231A 91)
IV0005B 12)
ICS008B 52) 1PS231B 92)
IVQ005C 13)
ICV 8100 53) 1PS9354A 93) 1V0016 14) 1CV8112 54) 1PS9354B 94)
IVQO17 15)
ICV 8113-55) 1PS9355A 95)
Iv0018 16) 1CV8152 56)
IPS9355B 96)
IVQ019 17) 4CV8160 57) 1PS9356A-97)
IWM190 18).
1FC009 58) 1PS9356B 98)
IWM191
'19) 1FC010 59) 1PS9357A 99)
IWOOO6A 20)
IFC011
- 60) 1PS93578 100)
IWOOO6B 21)
IFC012 61)-
1RE1003 101)
IWOQ07A 22).
IIA 065 62) 1RE9157 102)
IWOOO7B 23).
IIA 066 63) 1RE9159A 103)
IWOO20A 24)
'11A091 64) 1RE9159B 104) 1 WOO 20B 25)
'10G057A 65) 1RE9160A 105) 1HOOS6A 26) 10G079 66) 1RE9160B 106) 3 WOO 56B 27) 10G000 67) 1RE9170
>28) 10G001 68) 1RF026 29) 1CG082 69) 1RF027 30) 10G083 70)
-1RYB025.
31) 10G084 71) 1RY8026 32) 10G085 72) 1RY8028 33) 1PR001A 73) 1RY8033 34) 1PR001B 74) 1RY8046 35)
IPR 002E 75) 1RYB047 36)
IPR 002F 76) 1SA032.
3 7 ) -'
1PR002G-77)
ISA033 38) 1PR002H 78)
ISI8871 39) 1PR032 79) 1518880 40) 1PR033A 80) 1S18888
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1 (0095D/0035D/0221f2) 4.6 - page 1 of 49 L
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-~. - -.~
. -. - ~
Rev. 11 1.
YalyL1hunkn e (Continued)~
YALYE_1 VALYX_1 YALVE_t 107)~
1CC685 147) 2PR033D 187) 2818964 108) 2CC9413A 148) 2PR033C 180) 2S18968 109) 2CC9414 149) 2PR033D 109) 2VQ001A 110) 2CC9416 150) 2PR006 190) 2VQ001B
-111) 2CC9438 151) 2PS228A 191) 2v0002A 112) 2CC9486 152) 2PS228B 192) 2VQ002B 113) 2CC9518 153) 2PS229A 193)
'2VQ003 114) 2CC9534 154) 2PS229B 194) 2VQOO4A 115) 2CS007A 155) 2PS230A 195) 2VQ0048 116) 2CS007B 156) 2PS230B 196) 2VQP05A 117) 2CS000A' 157) 2PS231A 197) 2VQ005B 118) 2CS008B 158) 2PS231B 198) 2VQ005C 119) 2CV8100 159) 2PS9354A 199) 2VQOl6 120) 2CV8112 160) 2PS9354B 200) 2VQ017 121) 2CV8113 161) 2PS9355A 201) 2VQO18
.122) 2CVB152 162) 2PS9355B 202) 2VQO19 123) 2CVB160 163) 2PS9356A 203) 2WM190 124) 270'09 164) 2PS9356B 204) 2NM191 125) 2rC010 165) 2PS9357A 205) 2WOOO6A
.126) 2FC011 166) 2PS9357B 206) 2WOOO6B
'127) 2FC012 167) 2RE1003 207) 2WOOO7A 128) 21A065 168) 2RE9157 208) 2WOOO7B 129)
_2IA066 169) 2RE9159A 209) 2 WOO 20A
.137) 2IA091 170) 2RE9159B 210) 2 WOO 20B 131) 20G057A 171) 2RE9160A 211) 2 WOOS 6A 132) 20G079 172) 2RE9160B 212) 2 WOOS 6B 133) 20G080 173) 2RE9170 134) 20G081 174) 2RF026 135)-
20G082 175) 2RF027 136) 20G0 8 3 -
176) 2RY8025 137)-
20G084 177) 2RY8026 138) 20G085 178) 2RYB028 139) 2PR001A 179) 2RY8033
-- 14 0 )
2PR001B 180) 2RY8046 141) 2PR002E 181) 2RY8047 142)-
2PR002F 182) 2SA032 143) 2PR002G 183).
2SA033 144) 2PR002H 184) 2518871
-- 14 5 )
2PR032 185) 2 SIB 880 146) 2PR033A.
186) 2SI8888 f
1
=(0095D/0035D/022192) 4.6 - page 2 of 49 1
Aev. 11 g
2.
tinabgr of items:
212 A
3.
ASME_fode_Cate. gory: A 4.
ASME Code.Section XI RegttiIcmentat Seat Leakage Measurement per IWV-3420.
5.
Entis for Relieft Primary containment isolation valves will be seat leak tested in accordance with 10 CPR 50, Appendix J.
For these valves.Section XI testing requirements are essentially equivalent to those of Appendix J.
6.
Alternate Testing Primary containment isolation valves shall be seat leak rate tested in accordance with the requirements of 10 CFR 50, 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 nat 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.
Applicable Time Petindt This relief is requested'once per two years during the first inspection interval.
9.
_ Approval Statugs Relief granted per SER 9/15/88 contingent upon compliance with ASME a.
Section XI IWV-3426, 27.
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 939.
e.
Relief granted per SER 9/14/90.
j (0095D/0035D/022192) 4.6 - page 3 of 49
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Rev. 11 RELlEF REOUIST.VR-2
+
I 1.
Yalve Numbei ICSO20A 2CS020A ICS02(lB 2CS020B 2.
' tiumber_nI_ Items :
4 3.
AS11LCode_CatessIy : -
C
'4.
ASMILf94edestinn_XLResu11ements t Exercise check valves to the position required to fulfill their function
.(open= Cts closed =Bt,) unless such operation is not practical during plant operation, per IVW-3522.
5.
Ensis_Inc.Kelini:
The check valves in the spray additive system cannot be stroked without introducing NaOH into the CS' system.
6.
Altern. ale _T.esting:
The A train and B train valves are of the same design (manufacturer, s i r.e,
~
model. number, and materials constre:. tion) and have the same service conditions, including orientation, therefore they form a sample disassembly group.
...... G rnup 1.
.__Grapp 2 1CS020A 2CS020A ICS020B 2CS020B One valve from each group, 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.
7.-
Justification:
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 of NaOH into the CS system.
Full-flow testing would require a special test hook-up and-necessitate flushing the system.
The alternate test frequency is justifiable in that maintenance history and previous inspections of these-valves at Byron and Drnidwood stations has shown no evidence of degradation or physical impairmont (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 j
1 (0095D/0035D/022192) 4.6 - page 4 of 49 1
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.Rev. 11 RELI.EL.P1QLIEST VR-2.
Cont 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 surf aces 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.
Applicable Time Periodt This relief is requested once per quarter during the first inspection interval.
9.
Apptg.yA1_,S t a tu s t a.~
Relief to disassemble in place of full flow testing granted per SER 9/15/88.
b, Relief to disassemble in place of full flow testing granted per Generic Letter 89-04.
c.
Relief to_ disassemble in place of' full flow testing granted per SER
.9/14/90.
-d.
Revised to include both full flow (Ct) test and back flow (Dt) test; relief _ granted per Generic letter 89-04.
)
-(0095D/0035D/022192) 4.6 - page 5.of 49
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'Rev. 11 RELIEr._REQUISI_YPe.1 1.
Valyg._llumkgI t IS18922A 2S18922A-
\\
1513922B
-2S18922B 2.
Humber of Items:
4
-3.
ASME Code Catt9DIy C
4.
ASME CoAtc_Section XI Requirements:
Exercise check valves to the position required to fulfill their function (open-Ct; closed =BL) unless such operation is not practical during' plant operation, per INV-3522.
5.
Engis for Reliti These-check valves cannot be full flow tested during operation as the shut-off head of the Safety Injection pumps.ls 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 enrge volume is not considered a safe practice due to concerns of maintaining adequate water. level above the reactor core.
- 6. _ ' Altar. native-Testing 1 These valves will be full stroke tested during refueling outages as a minimum, but no more frequent 3y than once per quarter.
-7.
Justification 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.
D.-
Applingble Tirie PerlosLt This relief is requested once per quartet during the firnt inspection.
interval.
9.
Approval Statua
.a.
Relief-granted per SER-9/15/88.
b.
Relief granted per NRC Generic Letter 09-04.
c.
Relief granted per SER 9/14/90.
j (0095D/0035D/022192) 4.6 - page 6 of 49 1,
Rev. 11 RELIELEEQUESLYR-3 1.
Yalve NumhgI ICS003A
- 2CS003A ICS003B.
2CS003B ICS00BA 2CS008A 1CS008B 2CS008B 2.
Humher of Items:
8-3.
- AStiLC2de_CattgDIy:- AC & C 4
-ASME_CQdfa Section XI RegglLements :
a.
Exercise check valves to the position required to fulfill their function (open=Ct; closed =BL), unless such operation is not practical during plant operation,-per IWV-3522.
b.
Exercise check valves at least once every 3 months, per INV-3521.
c.
Exercise chec4 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 (fur 3/2CS008A,.B only).
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.
~ 5.
Ensis 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 ntorage tank.
The filling of~the cavity, via temporarily installed lerge 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 ]onger 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.
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 reg / ire extensive plant modifications to existing plant designs, including penetration of containment integrity.
j 1
(0095D/0035D/022192)-
4.6 - page 7 of 49 1,
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Rev. 11 RELI.LE_EERUEST VR-4 conb Partial stroking of the 1/2CS008A, a valves using alt 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 drainir,g the appropriate piping quarterly may cause deposition of. boric acid residue which could in turn promote binding of the check valve internals.
6.
hlietante TeEling:
The A and B train valves are of the same design (manufacturer, size, model number, and materials construction) and have the smne service conditions, including orientation, therefore they form a snmple disassembly group.
Group 1 Group 1 1CS003A 2CS003A ICS003B 2CS003B Group 2 Group 2 ICS00BA 2CS008A ICS008B 2CS008D One valve from each two valve group, 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 unic will be inspected.
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 verifles 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 inter als and by performing a full stroke test. exercise of-each disc.
Previous inspections of these particular valves at'hoth Hyron and Braidwood have repeatedly shown them to be in good condition.
h (0095D/0035D/022192) 4.6 - page 8 of 49
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}tELIEF REOUESI_YR-1, coltt.
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 examinat ion 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 Dyron 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" tevealed that the location, orientation and application.of these valves are not conducive to the type of wear or degradation correlated with SOCR 86-03 type problems.
However, they require some level of monitoring to detect hidden problems.
8.
Applicable _Ilme._ Par 19At This relief is requested once per quarter during the first inspection interval.
. 9.
Apptqyal StatusI 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 flown 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 backflew (Bt) test; relief granted per Generic Letter 89-04.
l J
(0095D/0035D/022192) 4.6 - page 9 of 49 1
RQv. 11 RELIEF REQUEST VR-5 1.
Valve Number ( AStiE_,Cgde CIAss )
ISI8956A-D(1)- 2SI6956A-D(1) 2.
Number of Valves t 8
3.
A$ME Codg& Section XI Requiremental Relief is requested 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 by IWV-3522".
IWV-3522 states that valves tbst cannot be exercised during plant operation shall be specifically identified by the owner and shall be full-stroke exercised during co3d shutdowns.
5.
Basis for Relief '
The 1/2 SIB 956A-D check valves ere 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/iSIB956A-D check valves' safety function in the closed direction is to maintain.the Reactor Coolant pressure Boundary (RCPB).
Open-The 1/2 SIB 956A-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 phase of a safety injection.
Check valves 1/2SI8956A-D cannot be tested during unit operatjun 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.
j (0095D/0035D/022192) 4.6 - page 10 of 49 i,
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Rev. 11 EEllEE._.EEWEST lRd.csitti 6.
A11einnte_Trating1 These valves will be backflow tested (BT) on the s ame schedule as the Byron Station Technical Specifications leakage tost as follows:
a.
At least once por 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.
Jus 11Mratirnt 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 there 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 pumps (RCPs) off and accumulator pr~ssure 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.
Successful completion of the seat Jeakage test will provide positive verification of closure (BT).
Therefore, backflow testing these valves on the same schedule as their required Technical Specification leak tale testing will adequately maintain the system in a state et operational readiness.
1 1
(0095D/0035D/022192) 4.0 - page 11 of 49 1
Rev.:_11 RELIEtlE0VESLYitd_c.cnL 8.
Applicable E nLuu This' relief is requested once per quarter during the first inspection interval.
9.
Approval Sthun 09/15/88 - Relief for full stroke test granted per SER.
09/14/91 - Relief for full stroke test granted per SCH.
01/23/92 - Reorganized to indicate safety function of the 1/2 SIR 956A-D valves and to add backflow test.
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(0095D/0035D/022192) 4.6 - page 12 of 49
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I GENER AL DIAGRAM I/(
l FOR INFORMATION ONLY
Rev. 2?
I EELIIf-REQUESURd 1.
Valve Numbril 1S18926 2 SIB 926 2.
[htmber of Item:
2 3.
ASliEAde._C. ale. gory :
C 4.
A'sME_fm1L._5ec tion XI RagniIrments:
Exercise for operability (Ct) of check valves every 3 monthr, per IWV-3521.
5.
Raals f oI 101121:
Full stroke exercising o' the Safety injectipn pump cuction check valves, 1S18926 and 2 SIB 926 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 against over-pressurization by a surge volume partial draining of the reactor coolant system to provido is not considered a safe practice due to concerns of maintaining adegunte water level above the reactor core.
6.
Alternate Testing:
The ISI8926 and 2SI8926 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 outages as a minimum, but no more frequently than once per quarter.
7.
Justification:
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.
Appllrab.le_Ilme Period:
This relief is requested once per quarter during the first inspection interval.
9.
Approval Statust 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.
b (0095D/0035D/022192) 4.6 - page 13 of 49
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Rev. 11 RELIET_RERUIST_YR-2
" DELETED "
Deleted relief request VR-7 Incorporated valves fortnerly covered by VR-7 into VR-12 and VR-17.
Added maximwn stroke times to the valve tables for all valves-in VR-12 per EG & G regoest.
l (0095D/0035D/022192) 4.6 - page 14 of 49
~
- ~ - -.. -
Rev. 11 RELIEF _RE21EST VR-8 1.
Valve Number (ASME_ Code Class):
ICC685-(2) 2CC685 (2)
-1CCF9413A (2) 2CC9413A (2)
ICC9414 (2) 2CC9414 (2) 1
'1CC9416 (2) 2CC9416 (2)
)
ICC9438 (2) 2CC9438 (2) 1CC9486 (2) 2CC9486 (2)
ICC9518 (2)-
2CC9518 (2) 1CC9534 (2) 2CC9534 (2) 2.
Number of Valven1 16 3.
ASME_Cade_ Category:
A,.B, C
4.
ASME Code.-Sgstion XI RequirementEl A.
Motor operated valves:
1/2CC685,-1/2CC9413A, 1/2CC9414, 1/2CC9416, 1/2CC9430 Relief is. requested from the 3 month test frequency for the stroke (ST) test as stated in ASME 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 states that valves-that cannot be exercised during plant operation shall be specifica)1y 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 menth test frequency for the full stroke (CT) test and backflow (B1) test as stated in ASME Section XI IWV-3521: " Check Valves shall be *aercised at least once every 3 months, except1as provided by IWV-3522".
INV-3522 states that' valves that cannot'be exercised during p1',c' 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 (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 INV-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.
l J
(0095D/00350/022192)-
4.6 - page 15 of 49
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Rev. 11 RELIELREQUESL&fLconta 5.
Il011Lfor Reliell 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 form 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 function of these valves in the open direction is to provide' Component Cooling water return from the Reactor Coolant Pump thermal barriers.
1/2CC9413A Closed 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.
Open The function of these valves in the open direction is to supply Component Cooling water to the Reactor Coolant Pumps.
(0095D/0035D/022192) 4.6 - page 16 of 49 I-
Rev. 11 PILLET._ REQUEST VR-8 conLt 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.
Check valves 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.
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 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.
(0095D/0035D/022192) 4.6 - page 17 of 49
1 Rev. 11 RELIEF REQUEST VR-B cont.
j 1/2CC9518 q
Closed 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 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 irolation 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 prerisure equalization between piping inside and outside containment.
Tull stroke (CT) and backflow (BT) testing of check valves 1/2CC9518 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 chut down.
6.
Al_LeJmttt'[e s tingi 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 j
in operation (RCP's will not necessarily be secured for the sole purpose of performing this test).
This testing period will be each 7
ref ueling outage as a.ainimum, but no more frequently than once per l
quarter.
(0095D/0035D/022192) 4.5 - page 18 of 49 l
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.. _ _ _. _.. _ ~. __
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_.m Rev. 11 RELIEF REOUEST VR-8 conL2 D.
1/2CC9486, 1/2CC9518, 1/2CC9534 Check valves.1/2CC9518 and 1/2CC9534 will be full stroke tested (CT) and backflow (DT) 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 ref ueling outage as a minimum, but not more f requently than once per quarter.
Both these tests will be performed in conjunction with the seat lakage 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 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 RCPs would add unnecessary radiation exposure-(approximately 20 mrem).
8.
Applirabit_.Statu11 This relief is requested once per quarter during the_first inspection
' interval.
9.
Appicyn1 Statu11 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 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 (0095D/003SD/022192) 4.6 - page 19 of 49 I
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EELLELIEQUESLYIL.2 1.
Yalve_IlwebeLI ASMLCodLClas s h ICV 8100 (2) 2CV8100 (2)
ICV 8112 (2) 2Cv8112 (2)
ICV 8113 (2) 2CV8113 (2) 2.
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3.
ABME_fede_ cat.egoryl A,
AC 4.
ASMLC ed e2_S e cil en. XI _Ee gS i t e!!e n t s1 A.
Motor operated valvest 1/2CV8100 and 1/2CV8112 Re11ef is requested for these four (4) valves liom the 3 month test fiequency f or t he stroke (ST) test as stated in ASME Sect.lon XI IWV-3521: " Category A and D valves shall be exercised at Inur.t once every 3 months, except as provided by IWV-3412(n), 1WV-3415, and IWV-3416".
IWV-3412(a) states that valves that cannot be exercised during plant operation shall be specifically identitled by the o
.e and shall be full stroke exercised during cold shutdowns.
11 Check valves:
1/2CV8113 Relief ja requested for these two (2) valves f r om the 3 month t est Irequency for the full stroke (CT) and backflow (137) test as stated in ASME Section XI IWV-3521
" Check Valveu shall be exercised at least once every 3 months, except as provided by IWV-3522".
1WV-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 shutdonna.
5.
Iln. sis _Lardelht A.
Motor opsireted valves:
1/2CV8100 and 1/2CV8112 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.
(0095D/0035D/022192) 4.6 - page 20 of 49
Rev. 11 RELIIf_lW.lLSI llL-LconL Closed
~
7 +.*fety function in the closed direction is to provide a J'
lght barrier between the containment almosphere and
+e vironment during accident conditions.
These valves cannot be tested during unit operatien as seal flow fro.n the reactor coolant pumps is required at all times while the pumps are in operation.
Tallure of one of these valves in the closed position during an exercise test would result in an abnormal seal water return flow being diverte4 to the Pressurizer Relief Tank (PRT) by lifting a.ellet valve (1/2CV8121) upstream of the isolation valves.
i B.
Check valves 1/2CV8113 I
Closed These are normally closed check valves located across containment isolation valves 1/2CVs112 inside containment.
Their safety function in the closed direction is to maintain the integrity of the Reactor Coolant Pressure Doundary and to provide a leak-tfght barrier between the containment atmosphere and the environment during accident conditions.
Open The safety function of these valves in the open direction is to relieve any pressure that may buildup between containment isoaltion valves 1/2CV8100 and 1/2CV8112.
These chevk valves function only when both the associated containment isolation v41ves are closed. Therefore, they cannot be full stroke tested without closing the 1/2CV8100 and 1/2CV8112 valves.
6.
411tinate-Tutingi A.-
Motor operated valves:
1/2CV8100 and 1/2CV8112
(
These valves will be full stroke exercised during cold shutdown, pcovided all reator coolant pumps are not in operation and seal le ak-of f can be isolated (RCP's will not necessarily be secured for the sole purpose of performing this test). This testing period vill I
be each refueling outage as a minimum, but no more frequently than once per quarter.
Rev. II EEL 1ELECWISL&Leont, B.
1/2CV8113 Since the 1/2CV8113 valves cannot be full stroke tested without J
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 18 the same as that of the 1/2CVB100 and 1/2CV8112.
7 2nKLLLLcALLaul 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 AprilCAbit SitLLull This relief is requested once per quarter during the first inspection Interval.
9.
hPSL93A1__ S t a tu gi 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 - Reorganised to indicate safety function of all valves and to add full stroke test and backflov test of check valves 1/2CV8113 1
l (0095D/0035D/022192; 4.6 - page 22 of 49 L
_- ~ _ - _ _
1/2 cv8113 CV8113 a
Q y
!d.
k 44 RCP SEALS CV8100 CV8112 1
0 U
y g,
T 3
6 i
E C
C N
I N
y M
v T
l l
GENERAL DIAGRAM FOR INFORMATION ONLY M64 2 i-l l
1
Rov. 11 RELIELI.rWESLYR.10 1.
Yelve_Humber_LASMLCode Classit 11A066 (2) 21A066 (2) 11A065 (2) 21A065 (2) 11A091 (2) 21A091 (2) 2.
N umbe r_cl _Y.clYe E l 6
3.
ASME.f0dt_CateQOlyl A and AC 4.
ASMLCode _ Section_XLEequirements t A.
Air operated valves:
1/21A065 and 1/21A066 Rellet is requested from the 3 month test frequency for the stroke test (ST) and fall 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-3413, and IWV-3416".
IWV-3412(a) states that valves that cannot be exercised durlug plant operation shall be specifically identified by the owner and shall be full stroke emetelsed during cold shutdowns.
D.
1/21A091 Relief is requested from the 3 month test frequency for the backflow (BT) test as stated in ASME Section XI, IWV-3521: " Check Valver shall be exercised at least once every 3 months, except as provided by IWV-3522".
!WV-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.
Ensis._LoI_Rellei A.
Air operated valves:
1/21A065 and 1/21A066 The 1/21A065 and 1/21A066 valves are the outboard and inboard (respectively) containment isolation valves for Insttument Air supply lines 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 1/21A065 and 1/21A066 valves during plant operation or cold shutdown would, by design, isolate the air to air operated ins' ruments inside the containment building.
(0095D/0035D/022192) 4.6 - page 23 of 49 1
i
~ _ _. _.. _ _ _. _ - _ _. _ _ _ _ _. _. _
1:ev. 11 i
REL1IE_.EmJISLyA-10 cont 4 i
B.
1/2IA091 The 1/21A091 valves are located on the alt supply lines to the 1/21A066 valves.
The 1/2IA066 valves are the inboard containment isolation valves for the Instrument Air supply lines to containment.
The safety function of the 1/21A091 valves in the closed direction is to provide a leak-tight barrier between the containment atmosphere i
and the environment during accident conditions. The function in the open direction is to supply control air to the 1/21A066 valves.
Stroke testing of the 1/21A091 valves cannot be performed without actuating the 1/21A066 which would result in the isoaltion of all Instrisment Air to containment.
6.
41LeInatt_,1cEtingi A.
Air operated valves 1/21A065 and 1/2IA066 The 1/21A065 and 1/21A066 valves will be stroke tested (ST) and fall safe tested (TT) during refueling outages.
H.
1/21A091 The 1/21A091 valves will be backflow tested (BT) during refueling outages. This backflow tost will be done in conjunction with the seat leakage test.
7 du111111Atlong A.
Air operated valves:
1/2IA065 and 1/21A066 The full stroke exercising of the 1/2IA065 and 1/21A066 Instrument Air containment isoaltion valves during unit power operations or cold shutdowns, would introduce the possibility of major operating perturbations and/or personnel safety concerns should thesu valves fail to re-open during testing activities.
The failure of_these valves in the closed position, as a result of testing activities during plar t operation or cold shutdown, would i
subsequently isolate the air operated instruments inside the containment building thus resulting in acenarios such ast 1.
Loss of Pressurizer Pressure Control -
i The pressurizer spray valves 1/2RY455B & C and the pressurizer auxiliary spray valve 1/2CV8145 would fall closed and not be available for pressurizer pressure control.
(0095D/0035D/022192) 4.6 - page 24 of 49
Rev. 11 REldEf, EECUEST VH-f0 cc&
i 2.
Loss of Chemical Volume Control System Letdown Flow (both normal and excess) and Charging Flow -
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 1/2CV8149 A, B & C, the excess letdown heat exchanger inlet isolation valves 1/2CV8153 A &
+
B, and the regenerative heat exchanger letdown inlet isolation valves 1/2CV8389A & B would go to their f all 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 f all to their respective closed positions.
3.
Loss of Component Cooling to Containment Penstrations -
The loss of instrument sir supply would cause the penetration cooling uspply 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.
I 4.
Loss of Personnel Breathing Air -
The locs 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 vf supplied breathing air needed to support numerous i.
maintenance and component inspection activities in a t
contaminated environment.
B.
1/2IA091 Check valves 1/ IIA 091 provide the air supply to maintain the 1/21A066 valves in the open position.
Testing of the 1/2IA091 valves in the closed position would force the 1/2IA066 valves to their fall closed position, by design, causing loss of instrument air to containment.
Loss of Instrument Air would result in scenarious such as those previously listed.
i l'
,-.-.-e.w-y =
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,,,_..mmm,_n.,,.__.
__,,__,.n__,,,m.me_,.,,
w,w._,,m.,~.,,m_.,.,,,-n.m,.y*
Rev. 11 l
EELIIr._ECQUEET VR-10 cnnL 6.
hyglLCAbit ELkLUE1 This relief is request once per quarter during the first inspection interval.
9.
App ti1YA1._S_t atRrd 09/15/88 - Relief denled per SER 12/10/80 - Revised (to address NRC concertis) in Byron response to SER (Dyron Station Letter 80-1321) 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 (DT) of check valves 1/21A091 l
h (0095D/0035D/022192) 4.0- page 26 of 49 L
i
1/2 IA091 1
O N
V, s
I
', S C
,i g'
D E
E L f' N
l' T C cJ N M
o Y
t:
lA091 p,
/
~
l O
k$
f O
L\\ s g-
. g._. _..._ g _
IA066 IA065 Inboard Cnmt Outboard Cnmt Isol Viv
}
lsol Viv y
I"t u'
GENERAL DIAGRAM FOR INFORMATION ONLY M55-4
Hev. Il flELIEF REDL'EST_SR-11
" DELETED "
Deleted relief request VR-11 per EG & G recommendation.
This was a request for extension of position indication teste from every two years to every three years.
l (0095D/0035D/022192)-
4.6 - page 27 of 49 1'
Rev. 11 RELLIr REWEfiT_ YA-12 1.
Yah't 1{nmber t Valves that normally stroke in 2 seconds or lease j
YALYE_i YALYE_t YALY.El YALYEl IM5018A-D 2HS018A-D IPR 060 2PR006 1RE91$7 2RE91b7 IPS228A, B-2PS228A, D 1RE9159A, D 2RE9159A,B IPS229A, D 2PS229A, D 1RE9160A, H 2RE9160A, D 1PS230A, D 2PS230A, B 1RY8033 2RY803) 1RC014A-D 2RC014A-D 1518871 2518871 2SD002A-H 2,
(( umber oLJterans 52 3.
AEME.._C_ ode _.fatego13 :
A&B i
4.
ASME_ Code d esilgn_KI ReguitemRRLEI Verification, by trending of power operated valve times, that an increase in stroke time of $0% or more, Irom the previous test, does not occur, per IWV-3417(a).
5.
Itas_in for Religis Minor timing inaccuracles, with small stroke times can lead to substantial increases (percent wise) in stroke times.
For example, a valve with a stroke time of I second in an initial test, and 1.6 seconds in the subsequent test, has experienced an apparent 60% increase in stroke t.ltne, 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%.
t l
}
(0095D/0035D/022192) 4.6 - page 28 of 49 i
Hov. 11 l
6.
Alternate _,lemiing s fast acting valves can be defined as those valves that nottnally stroke in 2 seconds or less.
No trending of stroke time will be regulred, and upon exceeding 2 seconds, corrective action shall be taken immediately in accordance with IWV-3417(b).
7 Jus.tiLicht19D 8 Tor small stroke tlines, the trending requirements are too stringent for the accuracles speelfled in the Code.
The alternative speelfled will adequately maintain the system in a state of operational readiness, while not Irnposing undue hardships or sacrificing the safety of the plant.
8.
App 11 sable Time Periods' This relief is requested once per quarter, during the first inspection interval.
4.
Approval Sintus a.
Relief denied per SER 9/15/88.
b.
Revised (to address NRC concerns) in Byron response to SER 12/16/88 (Dyron Station Letter 88-1321),
c.
Relief granted per SER 9/14/90.
t-(0095D/0035D/022192) 4.6 - page 29 of 49 i
,, _.. - -.. _. ~.. _ _ _ _
l< e v. 11 EILIEF REDEESI__VPell 1.
Yalyn liumbsts.1 1DG5182A,B 2DG5182A,B 1DG5183A,B 2DG5183A,D 1DG5184A,B 2DGS184A,D 1DG5185A,D 2DG5185A,B 2.
l(Hmbe r_RL.ltenial 16 3.
ASME.Sode_Catego ry.1 B&C 4.
AStit_C oAc_ Sic t io nlLReq u11 cne nta t These valves are not within the scope of ASME Code,Section XI, Subsection IW 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 no an augmented testing requirement pursuant to 10CrR50.55 (a) (g).
Therefore, valves associated with the Diesel Air Star *.>ystem shall be exercised to the position required to fulfill their f>.nction during plant operation per IW-3412 and IW-3522.
Additionally, t.e stroke testing of power operated valves shall be measured to the neares second and such stroke times trended to document continued valve operational readiness per IW-3413 (b) and IW-3417.
5.
11gais f or. Relicit 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 prograra which would be required by ASMC Code,Section XI.
Additionally, the stroke timing of solenoid operated valves associated with the Diesel Air Start System is impractical due to the fast actuation of these valves.
6.
AltcLatte Te.E. Ling 1 The performance of Dyron Station's Diesel Generator operability monthly survell. lance 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 & D of the Diesel Generator Air Start Receiver Tenks both before and immediately after diesel generator ctart.
By the comparison of these valves between trains, the satisfactory operation of.the power operated and self-actuated check valves associated i
with the Diesel Air Start System can be adequately demonutrated.
l l
l t
(0095D/0035D/022192) 4.6 - page 30 of 49 1
~ _ _ _ _. _ _ _.
Rev. 11 7.
Just111rA11gni q
Proper valve operation will be dernonstrated on a monthly basis by the verification of diesel generator air start capability.
Such verification j
will coinpare the air pressures contained in the receiver tanks both before i
and after the diesel generator statt, thus verifying the operability of the alt statt control valves. The proposed testing rnethodology at the increased frequency satisfies the intent of the Section XI requirements without posing undue hardships or difficulties.
8.
Applisabic_IltteleIlod t This relief is requested once per quarter during the firr.t inspection Interval.
9.
Approval Status a.
Nellet granted per SER 9/15/08.
b.
Rollet granted NRC Generic Letter 89-04.
c.
Relief granted per SER 9/14/90.
i r
l.
(0095D/0035D/022192) 4.6 - page 31 of 49 L
Rev. Il i
EILIIf_REQUflT. VF-1.4
" DELETED "
Deleted relief request VR-14.
This was a request for exemption for gonition indicating tests for solenoid operated valves.
Alternate testing allowed by the ASME Code will be used instead.
I t'
b (0095D/0035D/022192) 4.6 - page 32 of 49 i
l.
Rev, 11 i
REL1ELREQUESL%15 1.
Yalyt_11umhetat ICV 8481A, D 2CV8481A, D ICVB546 2CV854 6 1510815 2S1881b ISIB819A-D 2 SIB 819A-D ISI 6841 A,11 2 SIB 841A,11 1518900A-D 2 SIB 900A-D IS18905A-D 2S18905A-D IS18949A-D 2SI8949A-D 2.
[!pmber of ValyeAL 44 3.
ASME_Cudt_ Category 1 AC 4.
A SME_Cuded entiDILX LEnquit. cme ntu Check valves that cannot be exercised during plant operation shall be specifically identifled by-the owner and shall be full stroke exercised during cold chutdowns per INV-3412 and INV-3522.
5.
Ensis - for Relie[1 The full stroke exercising of check valves not stroked quarterly is required to be performed during cold shutdownc.
However, the stroking of check valves 1/2518815, 1/2 SIB 900A-D, 1/2S18949A-D, and 1/2 SIB 843A,D, associated w.
h Emergency Core Cooling System, during cold shutdowns will induce thermal stresses on their respective reactor vessel nozzles as the Reactor Coolant System (maintained approximat.ely-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 1/2CV84DIA,8 because the f ull stroke of these check valves causes stroking of 1/2S18815 and 1/2 SIB 900A-D located in the full flow path.
Additionally, Byron Station Technical Speciflcations require all Safety Injection Pumps and_all but one Charging Pump to be inoperable during Modes 4, 5,
and 6, except when the reactor vescel head is removed. -This requirement minimizes the possibility of Icw temperature over-pressurization of the Reactor Coolant System.
Therefore, check-valves 1/2818819A-D, 1/2SI8905A-D, and 1/2S18949A-D, cannot be full stroke exercised during routine Mode-5 cold st:,tdowns as required by INV-3412 and IWV-3522.
In addition to the stroke test exercise used to verify oye-ational readiness of these check valves, the act of such stroking cause the necessity for Technical Specification required leek rate testing of these valves prior to unit criticality. This testing,-in conjunction with the stroke exercising of those check valves, edds approximately one week to the duration of any outage and additional radiation exposure to workers who must connect flowmeters and differential pressura gauges dliectly to pipes containing radioactive fluids.
(0095D/0035D/022192) 4.6 - page 33 of 49
Rev. 11 Alternate _Iestingi 6.
Dyron Station's Technical Specifications require routine leak rate testing to be performed on these Reactor Coolant System Doundary luolation check
-valves if the unit is in Cold Shutdown fot greate: 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 pievious nine months.
Therefore, Dyron Station will stroke exercise check valves 1/2S18815, 1/2518900A-D, and 1/2S18841A,D on the same schedule. To prevent unnecessary stroking of check valves 1/2518815 and 1/2S18900A-D, check valves 1/2CV8546 and 1/2CVB481A.D will be stroke exercised on the stee schedule as check valves 1/2S18815, 1/2 SIB 900A-D and 1/2818841A,0.
Additionally, stroke exercising of check valves 1/2S18819A-D, 1/2 SIB 949A-D, and 1/2S18905A-D can only be safely performed in Mode 0 with the Reactor Vessel head removed.
Full stroke exercising of these check valves will be perf ormed at a minimum f requency ( f once each ref ueling outage.
7 Jus.tiLLgatipul Stroke exercising the 1/ 2 CV 84 81 A,
B, 1/2CV8546, and 1/2518H15, 1/28900A.D, and 1/2 SIB 841A, B check valves on the same schedule as t heir required Technical Specification Reactor Coolant System Doundary isolation leak rate testing will allow the coordination of testing activities without imposing additional check valve leak rate testing sequirements.
Such activity coordination will optimlee tenting efforts and renources while adequately maintaining the system in a state of operational readiness.
Valves 1/2S18949A-D, 1/2518905A-D and 1/2 SIB 819A-D can not be stroked during cold shutdown without exceeding Technical Specification limiting condition for oper at.lon (LCO llhid). Since stroking theun valves r equires starting an SI p ump.
Stroke exercising check valves 1/2818819A-D, 1/2518905A-D and 1/2SI6949A-D at least once per Reactor Refueling mode of operation, will insure compliance with Dyron Station technical Specifications'and minimize the possibility of low temperature over-pressurization of the reactor Coolant System.
B.
APPlisAhle_._115tiLPRt1Qdi This relinf is requested once per quarter during the firnt inspection interval.
9.
APPIQY ALS.BLUS 8 a.
Relief granted per SER 9/15/88 for valves 1/2518819A-D, 1/2S18905A-D, and 1/2 SIB 949A-D; relief denied per SER 9/15/88 for valves 1/2S18815, 1/2S18841A,L, 1/2SI8900A-D.
b.
Revised (to address NRC concerns) in Byron response t o SER 12/16/90 (Dyron Station Letter 88-1321).
c.
Relief granted per llRC Generic hettes 89-04.
d.
Relief granted per SER 9/14/90.
I h
(0095D/0035D/022192) 4.6 - page 34 of 49 1I
Rev. 11 FILIII_,PlWISI_.YFc10 1.
YalYAJLwnbet.n IS18811A, D 2SI8811A, D 2.
Hmber of valan 4 3.
ASliCA5)e_f.ategory.1. D 4.
ASli[LCpsig. Se ct ion _ XI. Requittatat.R Valves that cannot be exercised during plant operation shall be specifically identitled by the owner and shall be full stroke exorcised during cold shutdowns per IWV-3412.
5.
ItrAls 1.nr Relimit The full stroke exercising of valves not stroked quarterly is required to be performed during cold shutdowns.
Ilowever, the stroking of the Containment Sump outlet Isolation Valves, 1/2S18811A,D requires the suction of the Residual Heat Removal Pump? to be drained, thus rendering one train of_the system inoperable.
For Cold Shutdown operations with the Reactor Coolant Loopn filled and one train of Residual lleet Removal declared Inoperable, Dyron Stallon's Technical Specifications require two steam generators rith 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), Dyron Station's Technical Specification 3.4.1.4.1 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 Tes11ng.t Byron Station will full stroke exercise the Containment Sump Outlet Isolation Valves, 1/2SI8811A, B during refueling outages vice cold shutdown.
(0095D/0035D/022192) 4.6 - page 35 of 49 1
e Rev. 11 7.
Justillcatign1-The full stroke testing of the 1/2 SIB 811A, B valves; in conjunction with system dralning, 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 contaminated 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 activlties, 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, HRC 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. Undui ym st nond111Rnn, bolling in the core would occur in approximately 10 minutes, the core would be i
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 eefuellog outage periodicity wil? adequately maintain the system in a state of operationel readiness, while not imposing undue hardships or sacrificing the safety of the plant.
8.
Applicable Time Perlodi i g the first inspection This relief is requested _once per quarter, dui n
interval.
9.
Applayal Statust a.
Relief denied per SER 9/15/88.
b.
Revised (to address NRC concerns) in Dyron response to SER 12/16/90.
l c.
Relief granted per SER 9/14/90.
l (0095D/0035D/022192) 4.6 - page 36 of 49 L
N --
b
m
_ _. _ _ _ ~ ~ _ _ -..._ _ _
Rev. 11 BELiff_1EQtlIST VR-17
}
1.
Ealve Numberst 1SX101A 2SX101A 2.
thunktI_of Valygal 2 3.
ASME Code Categoryl B Sgr,11pn XI R gu1Lement11 4.
ASME Code, A
Stroke time and trend the stroke time for power operated valves per IW-3413 and IW-3417.
5.
Basis for Relimil 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.
A11ta nte TestiFg1 A
1/2SX101A wil'. be verifled to open during each quarterly ASME surveillance of the motor 6tiven auxiliary feedwater pumps.
In addition, these valves are stroked monthly during aux 111ary feedwater pump surveillances 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.
B.
ApplisAhlR_11me ftLindi This relief is requested once per quarter during the first inspection interval.
9.
Approxal_.Sintus:
a.
Relief granted pt SER 9/15/88.
b.
Relief granted per NRC Generic Letter 89-04.
c.
Relief granted per SER 9/14/90.
h (0095D/0035D/022192) 4.6 - page 37 of 49 I
a
m
._.._ _ _. _ _ _ _ _ _ _..... _ = _. _ _ _ _ _ _ _ _... _ _. _.. _ _..
b I
Nev. 11 RELIEF'lI7dIST_VPd a
" DELETED "
i Deleted relief request VR-1B and re-organized into several new and exisiting relief requests per llRC suggestion VR-5, VR-8, VR-9, VI:-10, VR-2 3, VR-2 4.
k I ~
i (0095D/0035D/022192) 4.6 - page 38 of 49
~..~._,_
Hev. Il RELIIE_REQUISLYR 12 1,
y31re_liWnbgf.s :
1AF001A 2AF001A 1AF001B 2AF001B 2.
RW3}te r of Valve.g 4
3.
ASMC_.C2de_.CAlegply :
AC and C 4.
ASME Code.Section XI Requirement, f:xercise check valves to the position required to f ulfill their f unction i
(open = Ct1 closed = Bt), unless such operation is not practical during plant operation, per INV-3522.
5.
Resisdor_itelief :
Adequate closure capabilities of these valvos can not be verified by performing a back pressure test due to the multiple boundary isolation points.. This configuration makes it impossible to assign any observed leakage to any individual-component.
6.
Alternaie_Jgslingi The A train and B train valves are of the same design (manufacturer, size, model number, and materials construction) and have the same service condi t. ions, including orientation, therefore they form a sample disassembly group Groun1 G Enup. 2 1AF001A 2AF001A 1AF001B 2AF001B One valve from each group, on a per unit buels, will be tested each refueling outage.
If the disassembled vaMve 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.
7.
Justification Performing a pressure test to verify closure is Impractical due to the system configuration. To perform this test At would be necescary to attach a pump to a test connection and pressurite the line containing the valve.
However, this line also contains many potential leakage paths (valves, pump seal, and instrument lines).
It is impocalble to assign a l'
leakage value to any specific path.
I
(
f l*
j (0095D/0035D/022192) 4.6 - page 39 of 49 1
1.
..m.
~.. _ _..., -..,,... _ _ ~.. -..
nev. 11 R111ELINESLVE119 Cont.
7.
Justifications (cont)
The alternate test frequency is justifiable in that removal of these valves requires that the system be taken out of service for an extended period of time.
Due to Safety System Performance, Probabilistic Hisk Assessment (PRA), and availability concerns involving the Auxiliary Feedwater system these valves cannot be removed on a quarterly frequency without impacting plant safety. Maintenance history and previous inspections of these valves at Dyron and Braidwood stationo 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 "CPRI Applications Guide 11nen for Check Valves in Nuclear Power Plantst 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.
- However, l
they still required some level of monitoring to detect hidden problems.
The alternate test method is sufficient to insure operability of these valves and is consistent with Generic Letter 89-04.
Although these valves will be stroke tested per the ACMC Section XI code requirements for cold shutdown valves, they also have an addit' al Technical Specification requirement.
Per note 12 these valves ate full stroke tested during cold shutdown in accordance with Technical Specification 4.7.1.2.2 which insures the operability of the Auxiliary reedwater flow path to each steam generator by verifying flow to each 7
stemn generator following each cold shutdown of 30 days prior to entering Mode 2.
Testing at this frequency is sufficient to insure operability of this system and forms the basis of this Technical Specification.
8.
Applicable Time Period:
This relief is requested once per quarter during the first inspection interval.
9.
App _r.qycl_.Statng :
a.
Relief granted per NRC Generic Letter 89-04.
b.
Revised to include more detail on only Ar valves in reponse to 5/7/91 NRC teleconference; relief granted per Generic Letter 09-04.
s h,
(0095D/0035D/022192) 4.6 - page 40 of 49 1
~..
Rev. 11 i
DRATT RELIEF REQUEST VR-20 1.
L'Alve. Humhe13 1/2Ar006A 1/2CV8116 1/2PS9357A,B 1/2S18813 1/2AF006B 1/2CV8152 1/2RE1003 1/2510814 1/2Ar013A-H 1/2CV8160 1/2RE9170 1/2518821A,B 1/2AF017A,B 1/ 2 CV8804 A 1/2RF026 1/2S18835 1/2CC685 1/2FP010 1/2RF027 1/2Sr8840 1/2CC9412A,B 1/2FWOO9A-D 1/2RH8701A,B 1/2S18880 1/2CC9413A 1/2rWO35A-D 1/2RH8702A,B 1/25I8888 1/2CC9414 1/2TWO39A-D 1/2RY455A 1/2518920 1/2CC9416 1/2TWO43A-D 1/2RY4b6 1/2S18924 1/2CC9437A,B 1/2IA065 1/2RYB000A,B 1/2S18964 1/2CC9438 1/2IA066 1/2RY8025 1/2SX016A,B 1/2CC9473A,B 1/2M5001A-D 1/2RYB026 1/2SX027A,B 1/2CS001A,B 1/2MS101A-D 1/2RY8028 1/2SX112A,B 1/2C5007A,B 1/20G057A 1/25A032 1/2SX114A,B 1/2CS009A,B 1/200079 1/25A033 1/2SX169A,B 1/2CS019A,B 1/20G000 ISD002A-Il 1/2SX173 1/ 2 CV1128-E 1120G081 1/2SD005A-D 1/2SX178 1/2CV8100 1/20G082 1/2518801A.B 1/2V0001A,B 1/2/CV8104 1/20G083 1/2 SIB 802A,B 1/2VQ002A,B 1/2CV8105 1/200084 1/2S?8804B 1/2V0003 1/2CV8106 1/2OG005 1/2S18806 1/2V0004A,B 1/2CV8110 1/2PR001A,B 1/2S18807A,D 1/2VOOO5A-C 1/2CV8111 1/2PS9354A,B 1/2S18809A,B 1/2WOOO6A,B 1/2CV8112 1/2PS9355A,B 1/2S18811A,B 1/2 WOO 20A,B 1/2CV8114 1/2PS9356A,B 1/2518812A,D 1/2 WOOS 6A,B 2.
NMLhgr of Items:
340 3.
ASME Code _ fat _S.9.DIyi A and B 4.
ASME Codc2_Sec.tlan_KLRequirements Verification, by trending of power-operated valve stroke times, that an increase in stroke time of 25% or more from the previous test 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 Technien1 Approach and Position VA-04),
5.
Dnis f or Rel.i.gi t Trending stroke times, based on the percent change from the pn ylens test, as ASME Section XI requires, allows gradun1 degradotion
'n occur over a long period of time without triggerjng the additional tremling attention that increased testing frequency requires.
An improved method of component perf ormance monitoring is proposed, which will require a valve to be placed on increased test frequency based on the per cent change f r om tre fixed reference value established via NRC Generic Letter 89-04,,
Position 5.
(0095D/0035D/022192) 4.6 - page 41 of 49 i
. _ _ ~
a Rev. 11 DRAl'T RELIEF REQUEST VR-20 6.
Ali.cr.nate l stings for all power-operated valves which normally stroke in greater than two seconds, an ALERT RANGE will be established based on reaching e given percent change from the reference value established via URC Generic Letter 89-04.
The following table will be used as a Etatling_ppint in evaluation of this fixed ALERT RANGE:
4 VALUE RETERENCE ALERT RANGE REQUIRED ACTION VA1.UE TYPE STROKE TIME (TLcf }-
50V's
> 10 sec.
(1.25)(Tret)-(1.75)(Tief)
> (1.75)(Tref) or HOV's or
>(Tref 4 20 sec)
ADV's (Tref +10 sec)-(Tref +20 sec)
MOV's
> 10 sec.
(1.15)(Tref)-(1.25)(Tref)
> (1.25)(Tref) or 20 sec) or
>(Trof 4 (Tref 410 sec)-(Tref +20 see)
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 nat assigned ALERT RANGES and are DQL trended.
B.
In all cases, the REQUIRED ACTION VALUE cannot exceed Technical Speelfication or UFSAR values, regardless of calculated values.
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 /UTSAR, and calculated values using the table above
- 1) All values are rounded to the nearest whole second.
- 2) Valves which serve the same f unction on dual trains (i.e.,
ICC9473A and ICC9473B) and dual units (i.e.,
ICC9473A and 2CC9473A) are assigned the same REQUIRED ACTION / ALERT RANGE VALUES based on human f actorr considerations, unless valve or system design differences exist between the trains / units.
Refer to IST Technical Approach and Position VA-04 for related information.
(0095D/0035D/022192) 4.0 - page 42 of 49 1
Nov. 11 DRATT RELIEF REffdEST VR-20 1.
JusL1LicALen s ticing fixed ALERT RA11GES based on the valve REFERE13Cr. vat.lfr. established when the valve was known to be operating acceptably will ensure that gradual valve performance degradation is monitoted and evaluated, by placing the valve on increased testing Irequency when the stroke time exceeds a fixed multiple of the REFERE!1CE VALUE.
This method lo 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 utiliz.rs the same stroke time percentage change values an required by the ASME Code to place a valve on increased frequency testing.
B.
Apr1iCAhle_TlFILECLlod !
This relief is requested once per quarter, during the iltnt inspection iuterval.
9.
App 12V_eLEtB1VS Since this tellef request is a new submittal and is not F/eCif1Cally addressed in 11RC Generic Letter 89-04, it is HDI approvod for use.
Formal written approval from the 11RC is required pripI to implementation.
Expeditious review and approval are requested.
h (0095D/0035D/022192) 4.6 - page 43 of 49 L
Rev. 11 1
6 DRATT RELIET REQUEST VR,
"WITIIDRAWN"
- ~
t This relief request was in d5 aft form and was later withdrawn per SCR 9/14/90.
L l
l-I*
)
l (0095D/0035D/022192) 4.6 - page 44 of 49
[
lr
.y~.4m..
Rev. 11 l
INTERIM RELIEF REQUEST VR-22
" WITHDRAWN" The relief request was in interim form and was later withdrawn.
l (0095D/003SD/022192) 4.6 - page 45 of 49
'l
_. ~. _ _
Rev. 11=
RELlEF REQUEST VA-U 1.
Yalve Number (ASME Cqde Classit IRYB046 (2) 2RY8046 (2) (Primary Water supply to PRT) 1RY8047 (2) 2RY8047 (2) (Nitrogen supply to PRT) 2.
Rumber of Valves 1 4 3.
ASME Code. See,ilon XI BSERilemtRE1 Relief requested from the 3 month test frequency for the backflow (BT) test as stated in ASME Section AI INV-3521: " Check Valves shall be exercised at least once very 3 months, except as provided by IWV-3522".
IWV-3522 states that valves that cannot be exercised during plant operation shall be specifically e3entified by the owner and shall be full stroke-exercised during cold shutdowns.
5.
DJ:Ld s for Relieff A.
1/2RY8046 TheseLvalves are located on the Primary Water (PW) supply line to the Pressurizer Relief Tank (PRT) and to the Reactor Coole c 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.
1/2;Y8047 These valves are' located on the nitrogen supply line to the Pressurizer Relief Tank (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.
b (0095D/0035D/022192) 4.6 - page 46 of 49 I
Rev. 11 EIL1EE_.EEQUES'.YE-21 cnm i
6.
Alterna.te_leatingi A.
1/2RYB046 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.
1/2RYB047 These valves will be backflow tested (BT) each refueling outage. The backflow test will be performed in conjunction with their leakage test.
7.
Jas111Lcation:
A.
1/2RY8046 This alternate frequency will adequately maintain the syrtem 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 radia.lon exposure (approximately 20 mrem).
B.
1/2RYB047 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.esult in the creation of an explosive mixture of Hydrogen and Oxygen.
B.
Applicable Status:
This relief is requested once per quarter during the first inspection interval.
9.
Approval Statusi Rellef Pending h
(0095D/0035D/022192) 4.6 - page 47 of 49 L
t 1/2RY8046, 8047 e
O Q
p;
$k El NITROGEN
'b SUPPLY RY8091 RY8034 RY8047 F!
RY8033 u8 O
hh PRIMARY E$
WATER.
If Q- -
-M MAKEUP RY8030
)
RY8046 O
RY8028 PUMP
$fi DISCHARGE i
+
i
- n j
$3 I
i D
a M
N u
i N
e
' i
$ [d 0 O
O O
O O
O
- j y e in s oq !
E fj D t: E PRESSURIZER RELIEF TANK 0
c j
M 4 N T
M
+
r TO REACTOR COOLANT
{
- ~
PUMP STANDPIPES l
+;
GENERAL DIAGRAM FOR INFORMATION ONLY-M60-6
Rev. 11 EELIET REQUEST VR-2A 1.
y_gl.ye N umbe r ( ASME Code Clasfdl IWOOO7A, B (2)
- 2WOOO7A, B (2) 2.
RumhgL of Unives t 4
3.
ASME Code.Section XI RequirementEl Relief requested from the 3 month test frequency for the backflow (PT) test as stated in ASME Section XI IWV-3521: " Check Valves shall be extreised at least once very 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.-
Hails for Relieft 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 barier between the containment atmosphere and the enviornment 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 in plant safety.
6.
_ Alternate Testing:
These valves will be backflow tested (BT) each refueling outage. The backflow test 'will be performed in conjunction with their leakage test.
)1 (0095D/0035D/022192) 4.6 - page 48 of 49
Rev. 11 EELIELPIQUESLYfc2Lcanti
=
7.
duELiLLcgtti. cat 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 refuellag frequency.
8.
hnplicable Statugi This relief is requested once per quarter during the first inspection interval.
9.
AppInval Status 1 Felief Pending j
T (0095D/0035D/022192) 4.6 - page 49 of 49 1
1/2WOOO7A/B 1 V; O N
f' U s
I \\, S D
~a i
E i: D y E CNbC M F, N
1 bM TT ie[
/
f
>G 4
~:
WOOO 7 A(B) b WOOO6A(B) p 1::.
4 i..
r_
r.
II p;
RCFC pr CHILLED WATER d
COILS p
h:
D:fi
,uM M
tg
- 2 4.
. _._p 4.__f.._..p4_
WOOS 6A(B)
WOO 20A(B)
$u Ve GENERAL DIAGRAM FOR INFORMATION ONLY M118-5