ML20065Q160
| ML20065Q160 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/07/1990 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20065Q155 | List: |
| References | |
| PROC-901207-01, NUDOCS 9012140244 | |
| Download: ML20065Q160 (66) | |
Text
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ENCLOSURE 4 SECTION li.0 INSERVICE TESTING PROGRAM PLAN FOR VALVES 9012140244 901207 FDR ADOCK 0500 4
Rev. 9 IADLE or CONTr.gIs 4.0 Inservice Testing Program Plan for Valves 4.1 Program Description 4.2 Program References 4.3 Program Tables - Units 1 and 2 4.4 Notes Note 1 Main Steam Isolation Valves Note 2 CV Emergency Doration System Flowpath Valves Note 3 Main Feedwater Isolation Valves Note 4 CV System Letdown and Make-up Isolation Valves Note 5 RHR Pump Suction Isolation Valves Note 6 Intersystem LOCA Valves Note 7 Reactor Vessel Head Vent Valves Note 8 CV, RNR Pump Discharge Check Valves Note 9 RHR ECCS Check Valves Note.10 Main Feedwater Waterhammer Prevention Valves Note 11 VO Purge Supply and Exhaust Isolation Valves Note 12 AP Suction and Steam Generator Check Valves Note 13 CV High Head Injection Isolation Valves Note 14 SVAG Valves Note 15 " Deleted" Note 16 Main Feedwater Regulating Valves Note 17 Main reedwater Regulating Dypass Valves Note 18 " Deleted" Note 19 " Deleted" (Incorporated into Note 14)
Note 20 Position Indication Testing of Solenoid Valves Note 21 Main Feedwater Tempering Flow Isolation Valves Note 22 Hydrogen Monitoring System Check Valves Note 23 Event V Check Valves Noto 24 Pressure Roller Check Valves Note 25 SI Pump Suction Check Valve (1/2 SI8926)
Noto-26 CV Pump Suction Check Valve (1/2 CV8546)
-Noto 27 RH Pump Suction Check Valves (1/2 SI8958A/B)
Note 28 VCT Outlet Check Valve (1/2 CV8440)
Note.29 Emerlency Boration Check Valve (1/2 CVB442)
Note 30 AF Cn, Valve Leak Checks (1/2 AF014A-H)
Note 31 CV/SI Mint-Flow Recirculation Line Check Valve Full Flaw Testing (1/2 CV8480A/B and 1/2 SI89l9A/B)
' Note 32 CC Pump Discharge Check Valves (1/2 CC9463A, 1/2 CC9463B, OCC9464)
Note 33 SX Make-Up Pump Discharge Check Valves (OSX028A/B)
Note 34 SD Contalmnent Isolation Valves (1/2 SD002A-H, 1/2 SD005A-D)
Note 35 RH Containment Isolation Valves (1/2 RH 8705A/r (0092D/0034D/062590) 4.0 - page 1 of 2
.Rev.,91
'4.5 1 Technical. Approaches and Posit'ons
~
i
~VA-01' Method 1of Stroke. Timing Valves VA-02 Method of Fall Safe Testing Valves VA-03 Method'of Exercising Check Valves VA-04 Determining Limiting Values of Full-Stroke-Times for Power-Operated Valves.
f
-4.6 Relief Requests.
4 VR-1 Appendix J-Valves VR-2
. Containment Spray NaOH Additive Check Valves VR-3
. Safety Injection ECCS ~ Check Valves VR-4 Containment Spray. Discharge and Ring Header 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 Cooling RC. Pump Thermal Barrier Valves VR-9 RC Pump Seal Injection.CV. Check Valves
.VR-10 Instrument Air Containment Isolation Valves-t VR-11'
" Deleted" (per EG & G recommendation).
VR Trending:of Fast Actuating Valves TVRi13-Diesel Generator _ Air' Start. Valves J
VR-14 -:
" Deleted" (using ASME method instand of requesting
~
exemption from position indication testing of soledold-operated valves)
VR-15 Safety Injection ECCS. Check' Valve Testing during Refueling' Outage u
JVR-16 Containment Sump Outlet Isolation Valve Testing'During Refueling..
VR-17 Motor Driven Auxiliary, Feedwaterf pump.
L.O..Coolor: Solenoid Valve = Stroke Testing
-VR-18
. Check Valve Full Stroke'(Ct) and Back FlowL(BL)
Testing:During Refueling Outages.-
n
'VR-19 Full Stroke Valve Testing "(Ct) by Sample 1 Disassembly and' Inspection per NRC Generic.
-Letter.89-04:
~,
- Draft VR-20
. Trending of Power-Operated Valve Stroke Times VR-21 Draft!" Withdrawn" per SER 9/14/90-a d
Interim? VR-22 Full-Stroke' Check Valve Testing (Ct) Methodology for
' Safety Injection Valves.
t (0092D/0034D/062509) 4.0 - page 2 of 2
SECTION L1.1 PROGRAM DESCRIPTION
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a
-PROGRAM DEECRIPTION
.n The laservice Testing (IST) Program for Class 1, 2, & 3 valves meets
'theiroquirements of Subsection INV of the ASME Section XI Code, 1983 LEdition, through the Summer of 1983 Addenda. Where code requirements-are determined to be impractical, specific requests for relief are written, referenced, and included with the tables.
Additional valve relief requests may be necessary and these will be identified and
= submitted during subsequent program revisions.
Byron Station received a Safety Evaluation Report (SER) on September 15, 1988 and is listed in Table;2-of NRC Generic Letter 89-04 as a plant with a reviewed IST 3
Program and SER issued.
Per NRC Generic Letter 89-04, the status of relief requests as stated in the SER is unchanged.
Any modifications to Byron Station relief requests approved in the-SER (VR-1 through VR-17) which are covered by one of the eleven positions discussed in NRC Ceneric Letter 89-04, Attachment 1, must be performed in accordance with the guidelines given in the Generic Letter.
Pre-approval _is cgranted for all relief requests submitted which are consistent with the eleven positions given. New relief requests dealing with a position nat covered by NRC Generic Letter 89-04, ~ Attachment 1, must receive NRC approval. prior to implementation. 'The table lists all code Class 1, 2,
& 3 valves which have been assigned a specific code category as directed.by Subsection IWV.of Section XI.
The table is' organized according to operating system and listed in valve number' order using P&ID references to further categorize.
'The valves subject to ISI testing are those valves which are identified in accordance with the scope of ASME'Section XI, Subsection INV-1100s.
"This Subsection provides the rules and requirements for inservice testing to' assess operational 1 readiness of certain Class 1, 2, and 3 valves (and their actuating and--position indicating systems) in light-water cooled nuclear >poweriplants, which are required to perform a specific function in shutting down a.reacto-to the cold-
~
shutdown condition or in mitigating the com quences 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.'
~After installation.and prior.to service, all valves identifiedLin this program were tested as-required by Subsection INV-3100 of Section XI of the ASME Cod 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 5R 1
that could affect its performance, it will be retested prior to its 7
return to service, to demonstrate that all performance parameters are'
,within acceptable limits, h
(0092/0031D/062590) 4.1 - page 1 o f 2
i Rev. 9 As required by NRC Generic better 89-04, Attachment 1, Position 5, the limiting value of full-stroke time will be based on the valve reference or average stroke time of the valve when it is known to be in good condition and operating properly. This limiting value is bssed on a reasonable deviation from tt.is 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 may not perform its intended function. New or additional reference values may be required ift
- 1) A valve has been replaced,
- 2) When a reference value or set of values may have been affected by repair or routine servicing of a valve, or 3)
If it is necessary or desirable for some reason other than 1) or 2) above.
HRC Generic Letter 89-04, Attachment 1, Positions 1-3 discuss full stroke, alternatives to full stroke, and backflow testing of check valves, respectively. A valid full stroke test is one in which verification of maximum required accident condition flow through the valvo is obtained.
The minimum acceptable flow value for a specific valve is determined from Technical Specifications, UrSAR, manufacturers data, engineering calculations, etc.
An alternative to full stroke testing includes, but *s not limited to, a samplo disassembly and inspection program of valves grouped by similarity of design (manufactutar, sise, 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 relf-actuated in response to a system characteristic), the backflow test is satisfied by porforming the leak-rate tent.
Per NRC Generic Letter 89-04, Attschment 1, Position 18, whenever valve data is determined to be witnin the Roquired Action Range, the valve is inoperable, and the Technical Specification LCO Action Statement time starts.
In the event a valve must be declared inoperable as a result of inservice testing, limitations on plant operations will be as stated in the Technical Specifications.
Section XI of the ASMr Boller and Pressure Vessel Code shall not be construed to supersede the requirements of the Technical Specifications.
(0092D/0034D/0625900 4.1 - page 2 of 2
~
l SECTION 4.2 PROGRAM REFERENCES
RQv. 9 i
j PROGRAH_REfERIINCES J
1.
Title 10, Code of Federal Regulations, Part 50, Domestic Licensing of Production and Utilisation racilities, particularly Section 50.5ba, Codes and Standards.
2.
ASME Boller and Prescure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1983 Edition, Summer 1903 Addenda.
3.
ASME/ ANSI OH-1987, Operation and Maintenance of Nuclear Powar Plants, including 1968 Addenda, Part 10, Inservice Testing of Valves Jn Light Water Ronctor Power Plante-.
4.
U. S. Nuclear Regulatory Commission, Generic Letter 09-04, Guldance on Developing Acceptable Inservice Testing Programs.
b, liyron Station UPSAR, Section 3.9.6.2, Inservice Testing of Valves.
6.
Hyron Statlon Technical Speeltication 3/4.0.5, Generic ASME Progran Requirement.
7.
Dyron Station Technical Staff Procedure, DVP 200-2, ISI Requirements for j
Valves.
B.
NRC Safety Evaluation Reports (SER't) a.
09/15/86 (Initial Program Plan Review) b.
09/14/90 (Supplemental Progrmn Plan Review) c.
09/14/90 (Relief Requests VR-21 and VR-22 Review) i
- 9. - Dyron Station IST Valve Program Plan Responses (filet 3.11.0240) n..
Dyron Letter 88-1321 (Initini Program Plan Review Response)
(0092/0034D/062590) 4.2 - page 1 of 1
SECTION 4.3 PROGRAM TABLES 4
TABLE _DESCR1EII0ti The following luformation is included in the stunmary tables:
A.
REY 1S10H The revision corresponds to the current revision of the program.
D.
PAGE The pages are numbered sequentially and show the total number of tables.
C.
YALVI_HUMBER The valve number references the unique Byron Station equipment piece number (EPN).
This specific valve number identilles the Unit and system.
D.
P41D The P&lD column references the specific P&ID number which the valves are located on.
The Unit 2 P&ID number la given directly underneath the Unit 1 P&lD number.
E.
CLASS The claas refers to the ASME cla6s assigned to the specific valve, r.
VALVI_. CATEGORY The valve category identf(les the valve category defined in subarticle IW. 2200 of ASME Section XI.
G.
VALYL SIZS The valve sise lists the nominal pipe size of each valve in inches.
_ ~,. _,_. -,. -.-. -
Hev. 9-11.
VALVE _ TYPE The_ valve type categorises the valve as to its valve design.
The following abbreviations will be used to identify specific valve types Gate GA Globe GL l
Dutterfly liTr Check CK l
Safety Valve SV Relief Valve RV power Operated Relief Valve pORV Diaphragm Seated D
Plug p
Angle AN l
1.
ACI,_ TYPE The actuator type identifies the valve actuator. The followl..g abbreviations will be used to designate speelfic types of valve actuators Motor Operated H.O.
Air Operated A.O.
Ilydraulle Operated
!!. O.
Self Actuated S.A.
l Manual M
Solenold Operated S.O.
J..
((0RMALf0S121Cti Normal position identifles the normal operating position of a speciflo valvo.
O for open and C for closed.
K.
SIR 0hE_DIRECIt 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 specifien only the direction in which valves must be stroked to be timed.
(0092D/0034D/062590) 4.3 - page 1 of 5
Rev. 9 L.
TISI_METIIRD The test method column identifles specific tests which will be performed on specific valves to fulfill the requirements of Subsection YWV of ASME Section XI.
The tests and abbreviations used are as follows:
1.
(Bt) Check Valve Back riew Test The check valve disc will be exercised to the closed position required to fulfill its safety function by verifylug that the disc travels to the seat promptly on cessation or reversal of flow.
For category A/C check valves (valves which have a specified leak rate _ limit and are self-actuated in response to a system characteristic), the back flow test is satisfied by performing the leak rate test.
2.
ICL1_Cherk_Yalyn_ Lull _SLtokc_ Test The check valve disc will be exercised to the open position required to fulfill its safety function by verifying the maximum required accidant flow through the valve or alternatives to full flow testing, per NRC Generic Letter 89-04, Attachment 1, Positions 1 and 2.
3.
IrtJ_En11_ Safe _ Test Valves with In11 safe actuators will be tested to verify the valve operator moves the valve stem to the required fail safe I
position upon loss of actuating power, in accordance with IWV-3415.
This will be accomplished during the normal stroking of the valve. Upon stroking a valve to its fail safe position, the
'l nolenoid operator is de-energised causing air to be vented which in turn allows the spring to move the valve to its fall safe
'l position. This condition simulates loss of actuating power (Electric and/or Air) and hence satisfies the fall safe test
-l requirements of IRV-3415.
4.
11Ll_EQA1110n_Indlcation_ Check li Valven which are identJfled to require a position Indication Test till be inspected in accordance with IWV-3300 of ASME Section XI.
5.
ILtl_ Scat _Lenkage_TcGt Thu seat leakage tests will meet the requirements of IWV-3420 for Category A valves.
On these valves, sent leakage is limited to a specific maximum amount in the closed position for fulfillment of their safety function.
(0092D/0034D/062590) 4.3 - page 2 of 5
Rov. 9 6.
,(RLLSaltiyJnlya_.Stip01DLChCIk Safety valve setpoints will be verlfled in accordance with IW-3510 of ASME Section XI.
7.
ISLLf_RlLSLEOkC._Itat Valve exercising tests of Category A and B valves will be perforrned in accordance with IW-3410.
The test will include ful.1 stroke testing to verify operability in the direction required to fulfill the required safety function.
8.
.(XLLE.ar.L:lttuke lent if only limited operation is practical during plant operation, the valves shall be part-stroke (Xt) exercise 6 during plant operation and full-stroke exetelsed during cold shut <10wns, in accordance with IW-3412 or IW-3 5 2 2.
Y TCilT.h0DC Denotes the frequency and plant condition necessary to perform a given test.
The following abbreviations are usedt tiormnLOpeInL1on. lop.)
Testa designated "0P" will be performed once every 3 months, except in those modes in which the valve is not required to be operable.
SeminnnunL(S).
7 eats with this designetlon will be conducted once every 6 months, except in those modes in which the valve la not required to be operable.
CultfihutdomLIIS1 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 prereguleite to pjant startup. Valve tests which l
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 l
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.
(0002D/0034D/062590) 4.3 - page 3 of 5
d Rev. 9 Itchcior._ Refueling 1RPd l
7ests with this designation will be conducted during reactor refueling l
4 outages only.
N.
ECLIE LEIOUISI Relief requests reference a speelfic request for relief f rom code J
requirements.
All relief requests are included in Section 4.0.
O.
HRIES Notes provide a short explanation concerning a particular IST valve. All notes are included in Section 4.4.
P.
TECl!N1 CAL AffROAClltSJ#u 10S1710HS Technical approachen and positions provide detailed discuosions on a particular IST topic.
All technical approaches and positions are included in Section 4.S.
O.
REMARKS Remarks reference other information useful in determining valve testing requiroments or methods.
(0092D/0034D/062590) 4.3 - page 4 of 5 9y
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SECTION 4,3 PROGRAM TABLES UNITS 1 AND 2
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INSERVICE TESTING FROGR/Ji Rev. 9 COPNONWEALTH EDISON sVRON NUCLEAR POWER STATIOM l
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l (00930/00403) 4.3 - taste 1 of 42
=
=
IM5ERVICE TESTING PROGRAM Rev. 9 COMMONWEALTH EDISON BYRON NUCLEAR POWER STATICN i
l VALVE I
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(0093D/00400) 4.3 - TABLE 7 of C2 i
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INSERVICE TESTI E FROCmAM Rev. 9 COMM0mERTii EDISON BYRON NUCLEAR POWER STATION i
i VRVE l
l l VRVE l VRVE l VRVE i ACT. l NOE % {STRCKE l TEST-l TEST I REMEF l
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(0093D/00400) 4.3 - TABLE 12 of 42 I
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INSERVICE TESTING PROGRAM Rev. 9 I
j C0998 WEALTH EDISON BYRON NUCLEAR POWER STATION i
i l
l VALVE.
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(0093D/0040D) 4.3 - TABLE 13 o' 42 i
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VALVE l
l l VALVE l valve l VALVE l ACT. I NORMAL l STROKE l TEST l TEST l RELIEF 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 METHOD l MODE.l REQUEST l
NOTES l PCs. l REMARKS l l
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(00930/00400) 4.3 - TABLE 16 of 42 1
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9 1
1 1
1 1
1 1
1 1
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INSERVICE TESTING PROGRAM Rev. 9 CDetONEALTH EDISCN 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 RELIEr l
'l-TECH.l l
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l l
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j (00930/00400) 4.3 - TABLE 21 of 42 L..
INSERVICE TESTING PROGRAM Rev. 9 CCNOWEALTH EDISCH BYRON PAJCLEAR POWER STATION l
VALVE l
l l VALVE l VALVE l VALVE l ACT. l NORMAL l STROKE l TEST l TEST l RELIEr l
l TECH.l l
l NUMBER l
P&ID' l CLASS l CATCGORY l SI2E l TYPE l TYPE l POSITION I DIRECT. l NETPOD l MODE l REOUEST l
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l l
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(00930/0040D) 4.3 - TABLE 22 of 42
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INSERVICE TESTING PROGRAM Rev.9 COMMONWEALTH EDISON BYRON PAJCLEAR POWER STATIO*4 l
VALVE l
l l-VALVE-l VALVE ] VALVE l ACT. l NORMAL l STROKE l TEST I' TEST l RELIEF j'
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{ 0093D/00400) 4.3 - TABLE 24 of 42 4
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s INSERVICE TESTING FROGRAM Rev. 9 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 l
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NOTES lPOS. lREPARKS l-l 1
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l l
It i
RR I
I I
I I
i l
1 1
I I
I I
I I
I tt i
RR I
I 6
I I
l l 1/2RH8705A l 562-l 2
l AC l 0.75 l 'CK l S.A. l C
l C
lLt/Bt l RR l VR-18 l
6 l
3.
l Passive l l
l W137 l
l I
I l
I O
l 0
I Lt l
RR I
VR-18.
I 24.35 1
3 I
' l --
l 1/2RH87058 l H-62 l
2 i
AC l 0.75 i CK lS.A. l C
l C
l Lt/Bt l RR l VR-18 l
6' l
3 l Passive [.
l I M-137 I
I I
I I
I O
I O
I Ct i
RR I
VR-18.
I 24.35 I
3 I
l l 1/2RH8708A l S62 l
2 C-l 3.0 x l RV l S.A l
C l
0 i
Rt l
RR l
l l
l l
1 l %i37 I
l l 4.0 1
I I
I I
I I
I I
I l
l 1/2RH87088 l 562 l
2 l
C l 3.0 x l RV
} S.A. l C
l 0
l Rt l
RR l
l
.l l
l l
l W137 l
I I 4.0 I
I I
I I
I I
I I
l l 1/2RH8730A l M-62 l
2 l
C l
8.0' I CK l S.A. ]
C l
0 lCt/Xt l CS/0P l 1
8 1
3 l
l.
l 1 S 137 I
I I
I I
I I
C I
Bt I
CS I
I I
3 I
l l 1/2RH8730B i M-62 l
2 l
C l
'8.0 l CK l S.A. l C
l 0
lCt/Xt l CS/0P l 8
i 3
l l
l l
I M-137 1
I I
I I
I I
C 1
Bt I
CS I
i l'
3 1
l 1
I l-1 I
I
.I I
I I
I I
I I
I i
l l
1 I
I I
I I
l-i i
I I
l I
l l
l l
l l
1 1
I I
-l i
i i
i i
1 l
1 I
I I
I I
I I
I I
I I
I I
i 1
.I l
l 1
I I
I I
I I
I I
I I
i l
1 I
I I
I i
l i
I I
l I
I I
1 I
I I
I I
I i
i i
i i
l I
i i
i t
l l
t I
l l
l I
I I
I I
I I
I l
(0093D/00400) 4.3 - TABLE 26 of 42
~
INSERVICE TESTING PROGRAM
'Rev. 9 C0rtOfWEALTH EDISON BYRON NUCLEAR F0WER 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 NUtBER l
P&ID l CLASS l CATEGORY l SIZE l TYPE l TYPE j POSITION l DIRECT. l METHOD l MODE l REQUEST l
NOTES l POS. l REMARKS l l
I i
1 1 (IN.) l I
I l
I l
1 l
I I
-l l1/2RY455A l H-60-5 l~
1 l
B l 3.0 lPORY-lA.D.l C
l 0
l St l
OP l
l l
1 l
l l
l n-i35-5 l l
l l
l l
l l
It l
RR l
l l
l l
l l
l l
I I
i 1
I I
rt i
OP I
l l
2 l
l l
l s-135-5 l l
. l 3.0 l PORY ] A.O. l C
l 0
l St l
OP l
l l
1 l
l l1/2RY456 l N60-5 l
1 l
B l
l l
l l
l It l
RR l
l l
l l
l l
1 I
I I
I I
I I
rt i
OP i
l I
z I
l l1/2RY8000AlM-60-5 l
1 l
B l 3.0 l GA lM.0.l 0
l C
l St l
OP l
l l
1
.l l
l t m135-5 I i
i I
I I
I I
It i
RR I
I I
l l 1/2RY80008 l N60-5 l
1 l
B l.3.0 l GA l M.0. l 0
l C
l St l
OP l
l l
1 l
l_
l l M-135-s I I
i i
1 1
I I
It i
RR I
I i
I" l
l 1/2RY8010A l M-60-5 l
1 l
C l
6.0 -l SV lS.A l C
l 0
l Rt l
RR l
l l
l l
l 1 N135-s 1 I
I I
I I
I i
It I
RR I
I I
I l
l 1/2RY8010B l H-60-5 l
1 l
C l 6.9 l SV lS.A.l C
l 0
l Rt l
RR l
l l
l l
l I M-13s-s i I
I I
i 1
1 I
It i
RR I
I I
I l
l 1/2RY8010C l N60-5 l
1 l
C l
6.0 l SV l S.A. l C
l 0
l Rt l
RR l
l l
l l
l I N135-s l I
I I
I I
I I
It 1
RR l
l l
I l
li/2RY8025 I s-60-6 l
l l
l l
l l
l st l
De l
l l
i l
l l
l N 135-6 l 2
l A
l D.375 l GL l A.O. l C
l C
l Lt l
RR l
VR-1 l Passive l l
l l
l l
l l
l l
l l
It l
RR l
l l
l l
l l
l 1
1 I
I I
I I
Ft I
09 I
I I
2 1
_l l1/2RY8025 l M-60-6 l
2 l
A l 0.375 l GL lA.O.l 0
l C
l Lt l
RR l
VR-1 l
l l
l l
l Ni35-6 l l
-l l
l l
l l
st i
OP l
l l
1 l
l l
l l
l l
l-l l
l l
It l
RR l
l l
l l
1 1
I I
I I
I I
I rt i
OP I
I I
2 I
l l
l M 35-6 l l
_l3.0 l
0 l A.D. l 0
l C
l Lt l
RR l
VR-1 l
l l
l i
l1/ZRY8023 l M-60-6 l
2 l
A 7
l l
l l
l l
st l
De l
l l
2 l
l l
l l
l l
l l
l l
l It l
RR l
l l
l l
l 1
1 I
i 1
1 1
I I
rt i
OP I
I I
2 I
l l 1/2RY8033 l M-60-6 l
2 l
A l 0.75 l D l A.O. l 0
l C
l Lt l
RR l
VR-1 l
l l
l l
l l M-135-6 l l
l l
l l
l st l
OP l
VR-12 l
l 1
l l
l l
l l
l l
l l
l l
It l
RR l
l l
l l
l 1
1 I
I l
i I
I I
rt I
OP l
1 l
2 I
l (0093D/0040D) 4.3 - TABLE 27 of 42
i lllll1I iI iIIlIJIIIiIIIIIi1IIlIlIi!i S
e e
X v
v R
i i
A s
s N
s s
E a
a 2
R P
P 4
9 lII lI iI iI II II II II II 1I ll ll iI i1 II II iI fo v
H.
8 e~
C S 33 33 2
R EO T P EL lIl lI 1I lI II II II II II 1I ii ii I I iI II II iI BAT S
ETO 3
N 4
llI lI lI iI II II iI II II iI i!
iI Ii iI II II iI T
8 8
F S 1
1 EE I U L Q 1
1 EE R R R
R V
V lII I1 II II II II lI II II II ii iI Il iI II II II T E S D R
R EO R
R T M IlI li iI II II II iI II II II ii II II Ii II II II D
T O t
t S H B
B ET
/
/
T E t
t M
L L'
N III II II II II II iI II II II iI II I!
iI II Il iI M
O A
I R
C R S S R R P I T I D R S D GE E N
W lI1 lI 1I II II Ii iI II lI II II Ii Il lI Ii il iI I HO T T P N
S L L O E AR T E A A I W E MT E N L R I C
C OS C O C N O I M U P
V M N R O lll lI II II II Ii II II iI II iI I1 II iI Ii iI II E CN S
O E
N R
I Y
TP A.
A.
C Y B
AT S
S llI lI lI II II lI II II iI II lI lI II II Ii iI iI EVE L P K
K A Y C
C VT lll lI l!
II II lI II II II II iI l i II I 1 Ii II lI E
5
)
V E.
0 7
L Z N A I l 3
0 VS
'f Ill II ll II II ii II II II iI iI II I1 ii Il I!
iI YR EO VG C
C L E A
A A T V AC lIl lI lI II I1 Il I1 II II l1 II l1 I1 iI 1I II II SSA 2
2 LC lll lI lI Ii Ii Ii 11 II II i1 Il l1 ll I1 1i 1I II 6
6 D
6 -
6 -
I 5
- 5 0 3 0 3 P
6 1 6 1 H H M M lll ll ll Il II II ll lI II Il Il i1 il I1 1l 1I l1
)
0 6
7 0
R 4
4 4
E E 0
0 0
V B 8
B 0
L M Y
Y
/
A U R
R D
V N 2
2 3
/
/
9 1
1 0
lllllllIiIlI illllIIilIlilIlil1llIil 0
(
L
i 1II IiII1ii1IiIIIlIiIII1iiIiII1[III1 S
_K R'
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2 R
4 9
III IiII 1iI1 Ii Ii Il I
II Ii iI Il lI Ii II Il fo v
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L 1Ii IIII liII II II Ii Ii iI Ii il Ii iI I1 II Ii BA T
. S E
TO 3
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IIi IIII liII II I1 Ii Ii l1 I1 ii I i i!
Ii Il II T
F S E E 1
1 I U L
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V R R III IiII liIl II Ii Ii Il i1 Ii ii Ii il II II II T E S D R eR O R OR O R P R P R P EO R
T M liI iiii liil II I
II Ii I1 Ii II It iI II Il Ii D
T 0 S h t t t t t t t t ET L S I r L S I r T EM N
lII lIiI lIlI II Ii II Ii li It II Ii il II Il Il M
O A
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T E T G N A K C O O T R S S O E C
C R R P IDR T I S D GE E N
W iII 1Iif 1Il II Ii II Ii iI II it II ii II II Ii I HO T T P N'
R I 0
0 L
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N RO IlI 1Iii 1!iI II lI Il II I1 II ii Il iI II II Ii E C N S
O
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T P C Y B
A T A
A llI IIii I liI II li II Il Il II ii Ii Il II Il Ii EV E L P A
A A Y G
G V T lII i1i1 iIiI I1 ii II Il i1 II ii
!i il II II 1i E
)
VE L Z 4.
5 5
A I n 1
1 V S
(
ll1 i1ii iIiI Ii ii II Ii ii II Ii ll iI II II ii YR E O V G L E A
A A T V AC lli liii lIll II l1 II
!i II II Ii Ii II II Il Ii S
SA 2'
2 LC llI 1IIi lIil II iI II II II I1 Ii Ii II II Il Ii D'
2 2
I 4
4
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5 M
M 1lI iIiI lIll II iI II I
II II Il Ii I1 II ll Ii
)
0 0
R 2
3 4
EE 3
3 0
V B 0
0 0
L M A'
A
/
A U S
S 0
V N 2
2 3
/
/
9 1
1 0
iiIiiiIiIilIIiIIIIIlIIIIiIIIlI1ilII 0
(
i,
l..
INSERVICE TESTING PROGRAM Rev. 9 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 l RELIEF l
l TECH. l l
l NUMBER l.
P&ID l CLASS l CATEGORY l SIN l TYPE-l TYPC l POSITION l DIRECT. l METHOD l MODE l REQUEST l
NOTES l POS. l REMARKS l l
I l
l'(IN.) I I
I l
l l
l I
I I
l li/2SD002A lM-48-5A/Bl 2
l-A l 2.0 l.GL 1
1 I
I I
I
, l A.0 1
0 l
C
]
Lt l
RR l
l 34 l
l l
I I
I I
St i
OP lVR-12(u-2) l l
1 l
l l
1 1
I I
I I
I I
I It i
RR l
l l
l l
l l
l 1
1 I
I l
l I
rt i
l-1 2
1 1
l i/2SD0023 l M-48-5A/Bl 2
l A
- l. 2.0 1 ~ GL l A.O.' I O
l C
l Lt l
]
l 34 l
l l
l l
1 1
I i
l l
1 i
St i
OP lvR-i2to-2) l I
i l
1 I
i l
i l
I l-i i
i It i
RR l
l l
l l
l l
1 I
I I
I I
I I
rt i
l I
2 I
l l 1/25D002C l M-48-5A/Bl 2
l A
l 2.0 l GL lp.0 l l
C l
Lt j' RR l
l 34 l
l l
l l
l l
1 l
l l
1 l
St l
OP I vR-iz tu-2) l I
i i
i I
i i
i i
l i
I I
I It i
RR l-1 I
I i
l 1
I I
1 1
I I
I I
Ft i
OP l
l l
2 I
l l T/2SD002D lH-48-5A/Bl 2
1 A
I 2.0 l GL l A.O. -l 0
l C
l Lt l
RR l
l 34 l
l-
.i l
i I
I I
I I
I I
I St l
OP IvR-12tu-2) l 1
i 1-1 I
I I
I i
i l
I I
i It i
RR 1
1 I
I i
l t
1 I
I I
I I
I I
rt i
OP l
I I
2 I
l li/250002E l M-48-5A/Bl 2
l A
l 2.0 l GL lA.0 l 0
l C
l Lt l
RR l
l 34 1
l l
l 1
I I
I I
I I
I I
St i
OP lvR-iztu-2) l I
i l
1 i
i l
I i
l I
I I
l It i
RR l
l l
l l
l l
l I
I I
I I
I I
Ft i
OP I
I l
2 I
l l i/2SD002f l M-48-5A/Bl 2
l A
l 2.0 l GL lA.O.l 0
l C
l Lt l
RR l
l 34 l
l l
1 1
I I
I I
I I
I I
St i
OP lvR-12<u-2) l I
i l
1 l
l 1
1 I
I I
I I
I It i
RR l-1 i
i i
i l
i l
i i
I I
i 1
ft l
OP l
l l
2 I
l l i/250002G l M-48-5A/Bl 2
l A
l 2.0 l GL lA.0 l 0
l C
l Lt l
RR l
l 34 l
l l
l l
l l
l l
l l
l l
St i
OP l VR-12 (u-2) l l
i l
l l
l l
l l
1 1
I I
I It l
RR l
l l
l
-l l.
I I
I I
I I
I I
I rt i
OP l
I I
2 I
l l1/250002H lM-48-5A/Bl 2
l A
l 2.0 l GL l A.O. l 0
l C
l Lt l
RR l
l 34 l
l l
1 1
1 i
l I
I i
I i
St i
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i i
i i
i i
i l
i I
I I
I It i
RR I
I I
I I
l_
l l
l l
I l
I I
Ft l
OP I
I I
2 l
l.
(OiO?D/004iD) 4.3 - TABLE 30 of 42
I 1
IllllIIlIlI lilllIIlIlI1IIIlIIIIIIIi SK RAM E
2 R
4 9
]lI llIl lIlI l1lI lIII II Ii II II II II II 1i fo v
H 1
e C S 1
2 1
2 1
2 1
2 3
R EO T P E
L lll llII l1lI lilI lIII 1I II I1 II lI II II II BA T
S ET 4
4 M
43 3
O 3
3 N
4 llI llI I lIlI lIlI lIIl II II Ii II iI II II II
~
T F S E E I U LQ 3
EE R R IIl llII lIl 1 lIll lIII II II II II II II I1 II T E S D P R R P P R R P P R R P P R R P EO O R R O OR R O O R R O OR R O T M lil liii liii liii liii II Il II II iI II II II
.D T O S H t t t t t t t t t t t t t t t t ET S L I r S t I F S L I r S t I r T EM N
lll 1IlI lIiI IIII III1 II Il II 1I iI I I II iI M
O A
I R
T E T G N A KC O O T O E C
C C
C R S S R R P I T I DR GE E S D N
W lIl lIII iIII 11II iIIl II II
!I 1I iI II II lI I H O T T P N
S L
. O L
E A R A I ENA T
MT EL R I 0
0 0
0 OS C
E N O I
t P
V N
R O IlI lIiI lIII 11II lIIl II II II iI II II 1I iI E C N S
O
.E N
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0 D.
C Y B
AT A
A A
A llI iIiI iIII l11I lIIl 1I II II II II II lI iI EV E L P L
L L
L A Y G'
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T, IlI l1i1 iIII liII lIIl 1I II II II II II lI iI E -
)
5 5
5 5
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7 7
7 L Z N. 3 3
3 3
A I I VS
(
0 0
0 0
llI llI1 IIII IIIl lIIl iI II II II I1 II II II YR EO V G L E A
A A
A AT V AC llI llII lII1 lIIl lI
- l II 1I II II il II II II SSA 2
2 2
2 LC llI IlI1
]II1 lIIl IIII II 1I II I1 il II II II B
B B
B
/
/
/
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A A
A A
D 5
5 5
5 I
8 8
8 8
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4 4
4 M
M M
M Il1 IlIl iIIl lIll lII1 II lI Il I1 iI II II II
)
D A
8 C
D 1
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5 5
5 4
EE 0
0 0
0 0
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0 0
0 0
L M D
D D
D
/
A U S
S S
S 0
V N 2
2 2
2 8
/
/
/
/
0 1
1 1
1 1
0 IllllIll1IliIill1IlIIlI1IIlIiIIIIIl
(
INSERVICE TESTING PROGRAM Rev. 9 COMMONWEALTH EDISON BYRON NUCLEAR POWER STATION l
VALVE
'l l
l VALVE 'lVALVEl VALVE lACT.l NORMAL l STROKE l TEST l TEST l RELIEF l
l IECH. l-l l-NUMBER l
P&ID l CLASS l CATEGORY l SIZE l TYPE.jTYPEl POSITION l DIRECT.lMETF00l NODE l, REQUEST l.
NOTES l POS. l REMARKS l l_
l l
I I (IN.) I I
1 1
I I
1 1
I l
l 1/2 SIB 301A l M-61-2 l
2 l
B l'4.0 l GA l M.0. l C-
' l-
.0 l
St i
.CS l
l 13 l
1 l
l l
l W136-2-l 1
l l
I i
~l l
It i
RR I
I I
I l.
l 1/25I88018 l 561-2 l
2 l
B l
4.0 -l GA lM.D.l C
l 0
l St l
CS l
l 13 l
1 l
l.
l 1 S136-2 'l i
I I
I I
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'I I
I I
j l 1/2 SIB 802A l M-61-3 l
2 l
8 l
4.0 l GA lM.0.l C
l 0
l St l
CS l
l' 14 l
1 l
l l
I *136-3 i
I 1
I I
I I
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I l
l 1/2SI8802B l M-61-3 l
2 l
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4.0 l GA l M.0. l C
l 0
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CS l
l 14 l
1 l
l l
l 1 M-136-3 I
I I
I I
i 1
1-It 1
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I I
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l 1/25I88048 l 561-1A l 2
l B
l 8.0 l GA l M.0. l C
l 0
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OP l
l l
1 l
l l
l m136-1 1 I
I I
I I
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l 1/25I8806 l N61-1A l 2
l B
l 8.0 l GA lM.0.l 0
l 0
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14 l
1 l
l l
l *136-1 l
i I
I I
I I
I it i
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I I
I l
l 1RSI3807A l %61-1A l 2
l B
l 6.0 l GA l M.0. l C
l 0
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OP l
l l
1 l
l l
l S136-1 1 I
I i
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l 1/2SI8807B l S61-1A l 2
l B
l 6.0 l GA lH.O.l C
l 0
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l l
1 l
l' l
l S136-1 I I
I I
I I
I I
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l I
I l
l 1/2SI8809A l N61-4 l
2
.l B
-l 8.0 l GA lM.0.l 0
l C
l St l
CS l
l 14 l
1 l
-l l
8 M-136-4 I
I I
I-1 I
I I
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RR I
I I
I l
l 1/25I88098 l N61-4 l
2' l
B l 8.0 l GA l M.0. l 0
l C
l St l
CS l
l 14 l
1 l
l l
1 M-136-4 I
i 1
1 I
I I
I It i
RR I
I I
l l
l 1/25I8811A l N61-4 l
2 l
B l 24.0 l GA l M.D. l C
l 0
l St l
RR l
VR-16 l
l 1
l l
l l 5136-3 I I
I I
I I
I I
It i
RR I
I I
i 1
l 1/25I88118 l M-61-4 l
2 l
8 l 24.0 l GA lM.O.I C
{
0 l
St l
RR l
VR-16 l
l 1
l l
l l S13M i I
I 1
i i
i I
It i
RR I
I I
I l
l 1/2SI8812A l M41-4 l
2 l
B l12.0 l GA lM.0.l 0
l C
l St l
OP l
l l
1
.l l
l l *136-4 I
1 i
i l
I i
i It i
RR I
l 1
I j
l 1/25I88128 l M-61-4 l
2 l
B l 12.0 l GA l M.O. ' l 0
l C
l St l
OP l
l l
7 l
l l
I M-136-4 I
I I
I I
1 i
i It i
RR l
l 1
l l1/2SI8813 l M-61-1B l
2 i
B
.l 2.0 l GL l M.0. ]
O l
C-l St l
CS l
l 14 l
1 l
l l
1 M-136-1 1
1 1
I I
I I
I It I
RR I
I I
I l
l 1/25I8814.l M-61-1A l 2
l 8
l 1.5 l GL l M.0. ]
O l
C l
St l
OP l
l l
1 l
l
[
l I m136-1 I I
I I
I I
I I
It 1
RR I
i 1
I l
(01080/00410) 4.3 - TABLE 32 of 42
INSERVICE TESTING PROGRAM Rev. 9 COMMONWCALTH 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 l
l NUMBER l
PT.ID l CLASS l CATEGORY l SIZE l TYPE l' TYPE l POSITION l DIRECT. l METHOD l MODE l REQUEST l
NOTES lP05. l REHARKS l l
1 I
I I (IN.) l I
I I
I I
I I
I
't I
l1/25I8815 l M-61-2 l
1 l
E
-l 3.0 l CK l 5.A. l C
l 0
l Ct l
CS l
VR-15 l
l 3
l l
l I M-136-2 I
I I
I I
I I
C 1 Lt/st i RR I
VR-18 I
6 1
3 I
l l 1/2SI8818A l 561-4 l
1 l
AC l
6.0 l CK l S.A. l C
l 0
l Xt/CT l CS/RR l l
9 l
3
.l l
l t m136 4 I I
I i-1 I
I C
I tt/st i RR I
VR-18 I
- 6. 23 1
3 I
l l 1/25I88188 l S61-4 l
1-l AC l 6.0 l CK l S.A. l C
l 0
.l Xt/Ctl CS/RR l l
9 l
3 8
l l
I M-136 4 I-1 I
I I
I I
C I tt/st i RR 1
VR-18 1
- 6. 23 1
3 I
l l
l I/2 SIB 818C l M-61-4 l
1 l
AC l 6.d l CK l3.A. l C
l 0
l Xt/Ctl CS/RR l l
9 l
3 l
l l
I M-136 4 I I-1 I
I I
I C
1 Lt/st i RR I
VR-18 I
- 6. 23 1
3 I
l l 1/25188180 l M-61-4
-l 1
l AC l'6.0 l CK lS.A. l C
l 0
l Xt/Bt l CS/RR l l
9 l
3 l
l' l
l M-136 4 I I
I I
I I
I C
i tt/st i RR I
VR-18 1
- 6. 23 1
3 1
l l 1/2SI8819A l %61-3 l.
1
-l AC l
2.0 l CK lS.A. l C
l C
l Lt/Bt l RR l
VR-18 l
6, 23 l
3 l
l 1 M-136-3 I
I-1 I
I I
I O
1 Ct i
RR I
vR-is I
3 I
l l 1/25I88198 l 561-3 l
1 l
AC l 2.0 l CK
-lS.A. l C
l C
l Lt/Bt l RR l
VR-18 l
6, 23 l
3 l
l l
I M-136-3 I
I I
I I
I I
o I
Ct 1
RR I
va-15 I
-1 3
I I
l 1/2 SIB 819C l M-61-3 l
1 l
AC l
2.0 l CK l S.A. l C
l C
l Lt/Bt l RR l
VR-18 l
6, 23 l
3 l
l l
l S136-3 I I
I I
I I
I O
I Ct i
RR I
VR-15 I
l 3
I l
l 1/25I88190 l 561-3 l
1 l
AC l 2.0 l CK lS.A. l C
l C
l Lt/Btl RR l
VR-18 l
6, 23 l
3 1
j l
1 5136-3 I I
I i
i i
1 0
1 Ct 1
RR I
VR-15 I
I 3
l l
l 1/2SI8821A l 561-3 l
2 l
B l
4.0 l GA l M.0. l 0
l C
l St l
OP l
l l
1 l
l l
l 5136 3 I I
I i
1 1
1 I
It i
RR 1
I I
I l
l1/25I88218jM-61-3 l
2 l
B l
4.0 l GA lM.0.l 0
l C
l St j
OP l
l l
1 l
l l
1 M-136-3 I
I I
I 1
I I
I It i
RR I
I I
I l
l 1/2SI8835 l 561-3 l
2 l
B l
4.0 l GA j M.O. l 0
l C
l St l
CS l
l 14 l
1 l
l l
l M-136-3 1 1
I I
I I
I I
It i
RR I
l 1
l l
l 1/2518840 l M-61-3 l
2 l
B l12.0 l GA l M.0. l C
l 0
l St l
CS l
l 14 l
1 l
l j
i 5136-3 I L
I I
I I
I I
It i
RR I
I I
I I
l 1/2 SIB 841A l 561-3 l
1 l
AC l 8.0 l CK lS.A. l C
l C
l Lt l
RR l
VR-18 l
6 l
3 l
'l l
l M-136-3 I
I I
I I
I 1
0 I xt/Ct I CS/R2 I VR-15 l
I 3
I l
l 1/25I88418 l M-61-3 l
1 l
AC l
8.0 l CK l S.A. l C
l C
l Lt l
RR l
VR-18 l
6 l
3 l
l l
l l 5136-3 I I
I I
I I
I o
I xt/Ct I CS/RR I VR-15 I
I 3
l l
s 4.3 - TABLE 33 of 42 (0108D/00410)
INSERVICE TESTING PROGRAM Rev. 9 COPtONEALTH 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 l RELIEF l
l TECH.l l
l NUMBER l
F&ID l CLASS l CATEGORY l SIZE l. TYPE-l TYPE l POSITION l DIRECT.l METHOD-l MODE l REQUEST l
NOTE %
l POS. l REMARKS j~
l I
l-1 I (IN.1 I I
I I
I I
I I
I I'
l l I/2SI8871 l l.2 l
A l 0.75l GL lA.0 l C
l C
l St
-l OP l
VR-12 l
l 1
.]
l-l l M-61-6 l
l l
l l
l l
l tt l
RR l
vR-1 l
l l Passive-l l
'l M-136-6 l l
l l
l l
l l
It l
RR l
l l
l l
1
'l i
I I
I I
I I
Ft-I em I
I 2
I l
l 1/2518880 l l
2 l
A l
1.0 l GL l A.O. l C
l C
l St l
l l
l' 1
l l-l l M-61-6
.l l
l l
l l
l l
tt l
RR l
vn-1 l
l l Passive l l
l M-136-6 I
.l l
l-l l
l
-l It l
RR l
l l
l
.]
l l
l 1
I l-I l
i I
rt i
OP I
I 2
I l
l1/25I8888 l l
2
.]
A l 0.75 l GL l A.0 l
C l
C l
St l
OP l
l l
1 l
l l
.lM-61-3 l
l.
l l~
l l
l l
Lt l
.RR l
VR-1 l
l l Passive j l
'lM-136-3-l l
l l
l
.I l
l It l
RR l
l l
l l
l l
1 1
1 1
I I
I I
rt I
Oo I
I I
2 l
l l 1/2SI8900A l N61-2 l.
1 l
AC l
1.5 l CK l S.A. l C
l 0
l Ct l
CS l
VR-15 l
l 3
l l
l' I m136-2 I I
I I
I I
l C
i tt/st i RR I
VR-18 I
6 1
3 I
l l 1/2518900B l S61-2 l
1 l
AC l
1.5 l CK l S.A. l C
l 0
l Ct l
CS l
VR-15 l
l 3
l l
l 1 H-136-2 I
I I
I I
I I
C 1 tt/B L I RR 1
VR-18 I
6 I
3 I
l l 1/2SI8900C l H-61 l l'
l AC l
1.5 l CK l S.A. l C
l 0
l Ct l
CS l
VR-15 l
l 3
l l-l I M-136-2 I
I i
1 1
I I
C l Lt/st i RR I
VR-18 I
6 1
3 I
l l 1/2SI89000 l M-61-2 l
1
.l AC l
1.5 l CK lS.A.l' C
[
0 l
Ct l
CS l
VR-15 l
l 3
l l
l l H-136-2 l
i 1
1 I
I I
C I tt/Bt I RR I
VR-18 I
6 1
3 l
l l 1/2SI8905A l W61-3 l
1 l
AC l
2.0 l CK l S.A. l C
l 0
l Ct l
RR l-VR-15 l
l-3 l
}
l l H-136-3 I
I I
I I
l l
c
! tt/st i RR I
VR-18 I
6 I
3 l
l.
l 1/25189058 l N61-3 l
1
'l AC l.2.0-l CK lS.A.l C
l 0
l Ct l
RR l
VR-15 l
l 3
l l.
l I H-i w 3 I I
I I
i i
I C
1 Lt/Bt l RR I
VR-18 l
6 I
3 I
l l 1/2SI8905C l M-61-3 l
1 l
AC l
2.0 l ~ CK l S.A. l C
l 0
l Ct l
CS l
VR-15 l.
l 3
l l
l l S136-3 'I I
f f
I I
I' c
I tt/st i RR l
VR-18 I
6 l'
3 I
l l 1/25189050 l M-61-3 l
1 l
AC -
l 2.0 l CK l S.A. l C
l C
l Ct l
CS l
VR-15 l
l 3
l
'l l
I M-136-3 I
I I
I I
I I
o I tt/st i RR I
VR-18 l
6 1
3 I
l l 1/2SI8919A l S 61-1A l 2
l C
l 1.5 l CK l S.A. l C
l 0
l Ct l
OP l
l l
3 l
l l
l H-136-1 1
I I
'l i
I I
I I
l I
31 1
3 I
l l 1/2SI89198 l M-61-1A l 2
l C
l 1.5 l CK l S.A. l 0
l 0
l Ct l
OP l
l l
3 l
l l
l H-136-1 _I I
i 1
I I
I I-1 I
I 31 1
3 I
l (01080/00410) 4.3 - TABLE 34 of 42
INSERVICE TESTING PROGRAM
.Rev. 9 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 l
l NOMBER l
P&ID l CLASS l CATEGORY l SIZE j. TYPE l TYPE l POSITION l DIRECT.l METHOD l MODE l REQUEST l
NOTES
-l POS. l REMARKS l l
I I
I (IN.) 1 I
I I
I I
I
-l i
I I
l1/2S18920 l M-61-1A l 2~
l B
l 1.5 l GL lM.0.l 0
l C
l St l
OP l
l l
1 l
')
l l M-136-1 I
I I
I I
I I
I It I
RR l
I I
I j.-
l 1/2SI8922A l M-61-1A ~l 2
l C
l 4.0 ' l CK l S.A. l C
l 0
l Ct l
CS l
VR-3 l
l 3
l l
l I M-136-1 1
I I
I I
I I
C I
Bt i
OP I
I I
3 I
l l1/25I89228lM-61-1A l 2
l C
l 4.0 l CK lS.A. I C
l 0
l Ct l
CS l
VR-3 l
[
3 l
l l
1 r-136-1 1
I I
I I
I I
C I
Bt I
op l
1 I
3 I
l.
l 1/25I8924 l N61-1A l 2-l B
l 6.0 l GA lM.D.l 0
l C
l St l
CP l
l l
1 l
l l
8 M-136-1 I
I I
I I
I I
I It 1
RR I
l l
1 l
l 1/25I8926 l M-61-1A l 2
l C
l 8.0 l CK l S.A. l C
l 0
l Ct/Xtl CS/0Pl VR-6 l
25 l
3 l
l l
I H-136-1 I
I
~l I
I I
I I
1 1
I I
3 I
I l 1/2SI8948A l M-61-5 l
1 l
AC l10.0 j CK lS.A. l C
l C
l Lt/Btl RR l
VR-18 l
6, 23 l
3 l
l l
1 M-136-s 1 1
1 I
I I
I o
1 xt/Ct i CS/RR I vR-s I
3 I
J.
l 1/25189488 l M-61-5 l
1 l
AC l 10.0 l CK l S.A. l C
l C
l Lt/Bt l RR l
VR-18 l
6, 23 l
3 l
}
l l M-136-s i I
I I
I I
I o
1 xt/Ct I Cs/RR I VR-s i
I 3
I l
l 1/2SI8948C l H-61-6 l
1 l
AC l10.0 l CK lS.A. l C
l C
l Lt/Btl RR l
VR-18 l
6 l
3 l
l-l l M-136-6 I
I I
I I
i 1
o I xt/Ct I CS/RR l VR-s I
I 3
I l
l 1/2SI89480 l M-61-6 l
1 l
AC j 10.0 l CK l S.A. l C
l C
l Lt/Btl RR l
VR-18 l
6 l
3 l
l l
1 N136-6 I I
I I
I I
I o
I xt/Ct I CS/RR I vn-s i
I 3
1 l 1/2SI8949A l H-61-3 l
1 l
AC l 6.0 l CK l S.A. l C
l C
l Lt/Stl RR l
VR-18 l
6 l
3 l
l l
l M-136-3 I
I I
I I
I o
I Ct i
RR I
vu-is I
3 1
l l1/2518949BlM-61-3 l
1 l
AC l 6.0 l CK lS.A. l C
l C
l Lt/Btl RR l
VR-18 l
6 l
3 l
l l
l H-136-3 I
I I
I i
1 I
o I
Ct i
RR I
VR-1s I
3 I
l l 1/2 SIB 949C l M-61-3 l
1 l
-AC l 6.0 l CK l S.A. I C
l C
l Lt/Btl RR l
VR-18 l
6 l
3 1
l l_
l H-136-3 I
I I
I I
I 0
l Ct i
RR I.
VR-1s l
3 I
l l 1/25189490 l M-61-3 l
1 l
AC l 6.0 l CK lS.A. l C
l C
l Lt/Btl RR l
VR-18 l
6 l
3' l
l l
l *136-3 I
i 1
1 I
I I
o I
Ct i
RR I
VF 15 l
I 3
I j
l 1/2SI8956A l N 61-5 l
1 l
AC l10.0 l CK l S.A.
l C
l C
l Lt/Bt l RR l
Yh18 l
6 l
3 l
l l
l S136-s -1 I
I I
I I
I O
I Ct I CSIRR I VR-s I
I 3
l l
l.1/25I89568 l H-61-5 l
1 l
AC l10.0 l CK lS.A. l C
l C
l Lt/Stl RR l
VR-18 l
6 l
3 l
l l
1 H-136-5 1
1 1
I i
1 1
0 i
Ct I CS/RR I VR-s I
I 3
l l
l 1/2SI8956C l H-61-6 l
1 l
]10.0 l ' CK l S.A. l C
l C
l Lt/Btl RR l
VR-18 l
6 l
3 l
l l
l M-136-6 1
I I
I I
I I
9 I
Ct 1 C3RR I VR-s I
3 I
l (01080/0041D) 4.3 - TABLE 35 of 42
l' jlI lli lIIlIlilIIIIIlIlIIilIIIIIIIl
.S e
e K
v v
R i
i A
s s
M s
s E
a a
2 R
P P
4 9
lII lI iI lI 1lI1 l1 II Ii iI II II II II II II l1 fo v
H 6
e C
3 3 3
3 1
2 3
3 E 'O R
T P E
L 1lI ll 11 1I llI1 Ii II Ii iI II II Il II II II iI BA T
S 7
7 E
2 2
T 3
O N
6 9
9 4
ill l1 li lI llI1 II II II ii II II II II II II II T
8 F S 8
1 EE 1 5 1
I U LQ R R R
1 EE~
V V V
R R RV Ill l1 lI I 1 llI!
lI II Ii II 1I II II Il II II II R
T E R
S 0 R /
S S
P R R p R
E 0 R S C
C OR R o R
T N C
IIi lI II l1 l lii iI II Il i i iI Il Il Il II II II D
t T O H
S H t t t
t t t t t
/
E T L C C
C S L I F t
T E L
M N
jl I 1I II 1i llI!
iI II
!i II II II Il II II II Ii M
O A
I R
T GN A ET O O T K C O E C0 0
0 C
C R S S R R P I Ti D R S 9 GE E N
W jIl ll iI lI l]II lI II i!
II II I!
II Il II II Il I HO T T P N
T
~
C
_C C
C A
T E
?
$O I
C' E
N S
C 0 C a
J I
t V
t P
F R 0 lji
]1
]!
II f lII II II ii II 1I Il II II II II I1 EC N S
O LE N
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A.
A.
A.
O. '
A.
I Y
B C Y A T S
S S
A S
L lII lI ll 1I I{iI 1I I
Ii iI 1I II Il II II II Il EV E L P K
K K
K A Y C'
C C
a C
VT lII li ll iI Ii1 I 1I II II iI lI 1I Il II 1I II Il WE
)
5 0
4 0
7 0
L ZN A I I b
2 2
0 1
V S
(
I 1
1 E
IIl
{
jI
!I iliI
] I II II II lI 1I Il II 1I II Il YR EO V G C
C L E A
C C
A A
AT V AC liI lI l1 lI jiII iI II II Ii lI lI II II iI II Il S
.SA 1
2 2
2 2
LC llI lI 11 lI 1l1I II II Ii II lI lI Il I1 II II II 6
4 4
6 6
D 6 -
4 -
4 -
6 -
6 -
l
- 6
- 6
- 6
- 6 6
i 1
31 3 1
3 1 3 1 3 P
61_ 61 6 1 6 1 6 1 5SNS Sm 5S 5S l'
lI 1l lI iI IIlI iI 1I Ii II Ii lI I l 1l II II Il
)
0 A
8 D
6 8
a 4
a 1
R 5
5 5
6 6
4 EE 9~
9 9
9 9
0 V E 8
8 8
8 a
0 L
1 I
1 I
I
/
t A U 5
S 5
5 5
0 V N 2
2 2
2 2
8
/
/
/
/
U 0
1 1
1 '
1 1
ll1iIillllIlIIIlIIIIi1IlIIlllIIIIIl 0
(
INSERVICE TESTING PROGRAM Rev. 9 COMMONWEALTH EDISON BYRON MUCLEAR POWrR 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
P&ID l CLASS l CATEGORY l SIZE l TYPE j. TYPE l POSITION l DIRECT. l METH00 l MODE l REOUEST l
NOTES lPOS. l REMARKS-l.
-l l
I 1
I (IN.) l I
I I
l I
I l
1 l
l l 1/2SX002A l N 42-1B [
3 l
C
.l-36.0 l CK lS.A.l C
l 0
l Ct l
OP l
l l
3 l
l l
l l
l l
l l
l l
C l
Bt i
OP l
I 1
3 l
l l1/2SX0028 l M-42-1A'l 3
l C
l36.0 l CK l S.A. l C
l 0
.l Ct l
OP l
l l
3 l
l l
l
'l i
I l
l'-
1 I
C l
Bt-1 OP l
I l
3 I
l l1/2SX016A l S42-5B l2 l
B l16.0 l BTF lM.O.l 0
l 0
l St l
OP l
l l
1 l Passive l l
l W126-3 I l
I I
I I
I I
It i
RR 1
I I
I l
l 1/2SX0168 l M 42-5A l 2
l 8
l16.0 l BTF lM.0.l 0
l 0
l St l
OP l
l l
1 l Passive l l
l M 126-3 I I
I l
i I
I I
It i
RR l
1 1
l l
l 1/2SX027A l M-42-58 l
2 l
8 l16.0 l BTF l H.O. l 0
l 0
l St l
OP l
l l
1 l Passive' l l
I S126-3 I I
I i
1 l
l I
It i
RR I
I I
I l
l 1/2SX027B l N42-5A l 2
l 8
l16.0 l BTF l M.O. l 0
l 0
l St l
OP l
l l
1 l Passive l l
1 M 126-3 I I
I I
I I
I I
It i
RR I
I I
I l
lOSXUzaA l H-42 6 l
3 l
C l 8.0 l CK l 5.A. l C
l 0
l Ct l
OP l
l l
3 l
l l
I I
I I
I I
I I
I I
I I
I I
l l0570288 l H-42-6 l
3 l
C l
8.0 l CK l S.A. l C
l 0
i Ct l
OP l
l l
3 l
l l
l 1
-l i
I I
I I
I I
I I
I I
l l1/2SX101A l N42-3 1
3 l
B l
1.5.l GL l5.0.l C
l 0
l St l
OP l
VR-17 l
l l
l l
I M-126-1 1
I I
I I
I I
I rt i
Op i
I 2
1 l
l 1/2SX112A l M 42-3 l
3 l
B l12.0 l BTF l A.O. l 0
l C
l St l
OP l
l l
1 l
l l
l H-126-i l
l l
l l
l l
l It l
.l l
l l
l l
1 1
I I
I I
I I
I Ft i
OP I
I I
2 I
l l1/2SX1129 l 542-3 l
3 l
B l12.0.l BTF lA.O.l 0
l C
l St l
OP l
l l
1 l
l l
l +126-i l
l l
.l l
l l
l It l
RR l
l l
l l
l l
1 I
I I
I I
I I
rt i
OP l
l 1
-2 l
l l 1/2SX11eA l N42-3
.l 3
l B
l 12.0 l BTF lA.O.l 0
l C
i St l
OP l
l l
1 l
l l
l M-126-i l
l l
l l
l l
It l
RR l
l l
l l
l l
1 I
I I
I I
I I
Ft i
OP I
I I
2 I
l l 1/2SX1148 l M-42-3 l
3 l
B l L. 0 l BTF lA.O.l 0
l C
l St l
OP l
l l
1 l
l l
l M-126-1 l
l l
1 l
l l
l It l
RR l
l l
l I
l l
l l
l I
I I
l l
rt i
OP I
I I
2 1
l i
(01080/00410) 4.3 - TABLE 37 of 42
j IlIIIlIIiIlIIlIIIIIIIIIIiiIiIIIi[II 52RA
.N' E
2 R'
4 9
lIi 1II 1II 1I 1I iI II iI II II II iI II II Il II fo v
H 8
e C S' 1
2 1
2 1 2 1 2 3
R EO T P EL lII lII iII iI iI lI II iI I1 II I i iI II II II II BAT S
ETO 3
N 4
lII lII III II i!
iI I ;
iI I1 II II lI II II 1I II T
F S E E I U L Q E E R R III lI1 II1 1l i!
iI II iI Ii II II iI II II 1I II T E S D P R P
? R P P P P P EO OR O 0R O OO OO T M II I iii 1ii iI ii iI II lI Ii I1 II iI II II iI II D
T O S H t t t t t t t t t t E T S I r S I F S F S r T EM N
IlI III II1 II iI iI II iI II I1 II II 1I II II II M
O A
I R
O O
0 R S S R R P I T I DR GE E S D N
W i1I iII iI1 iI lI lI II iI II Ii II II 1I II I!
II I HO T T P SL N
L O E
W. R A
AI T
A M T E
R I C
C C
C EN L COC OS I M J N O V M M P
R O E C N III Ii1 IIi Ii II iI II II II II II II lI II II II S
O
. E N
R O.
O.
D.
O.
I Y
T P C Y B
A T A
A A
A lII ii1 iII II II iI II II II II II Ii lI 1l Il II EV 'E r
r L P T
T A
A A Y S
B G
G V T IIi ii1 1II 1I 1I I!
II II II II II li II 11 I1 II E
)
V E.
0 0
0 0
L Z N A I I 0
0 6
V S (
1 1
6 IlI IIi lII l1 1I Ii II II II II II ii 1I il Il II Y
R EO V G B
B 8
L E B
A T V AC llI III iII i1 1I ii II II II II II II II II Il I!
S SA 3
3 3
3 LC ljI 11I
]II 11 11 II II II II II II iI
!I II Il Ii 1
1 1
1 D
3 -
3 -
3 -
3 -
I
- 6
- 6
- 6
- 6 2 2 22 2 2 2 2 P
4 1 4
1 4 1 4 1 N+
5+
SS SN III III llI lI ii Ii II II II II II II lI I1 II lI
)
0 A
B 1
R 9
9 3
8 4
E E 6
6 7
7 0
V B 1
1 i
1 0
L M X
X x
x
/
A U S
S s
S D
V N 2
2 z
2 8
/
/
/
/
0 1
1 i
1 1
IIIiIIlII!IllIiIIIIIlI!IIiIIIIiIIlI 0
(
v Rev. 9 INSERVICE TESTING PROGRAM C0tter4ALTM EDISON SYRON NUCLEAR POWER STATION l
VALVE I
j l VALVE ~ l VALVE l VALVE lACT.l NORMAL l STROKE l. TEST l.. TEST l RELIEF l
l' TECH.l
-l l
NL*BER l 'P&ID l class l CATEGORY l SIZE l TYPE l~ TYPE l P0sITION [ DIRECT. l METHOD l PODE l REQUEST l
NOTES l PCs. l REMARKS l-l 1
~I I
I (IN.i i l
I I
I I
I I
I I
l-l1/2v000ia i +105-i -1 2
l A
i48.0 i BTr lH.O.I C
1 C
l tt I
s i
vR-i I
ii I
i-
.l 1
i +ios-1 1 1
1 1
I l-1 I
st
[
Cs l
l ti l
1.Ipassive l l
l I
I I
I i
i I
i It i
RR I
I I
l l
l1/2VQ0018 l + 105-1 l 2
l
,A 1 48.0 l BTF l H.O. l C
l C
l Lt I
s l
VR-i l
it l
l l
l 1 M-105-i i
I i
l i
l i
i st 1
Cs l
l ii i
i l passive I l
l t
i I
I I
I I
I It i
RR I
I I
I l?/2VQ002A I +105-1 1
2 i
A I48.0 i BTF lH.O.l C
l C
l Lt l
s l
VR-i l
it l
l 1
l l s-10s-i i i
i i
i i
i i
st l
Cs i
1 it i
i l passin - 1 l
1 I
I I
I I
I I
I It i
RR I
I I
I l
l1/2VQ0023 l %10s-i l 2
l A
l 48.0 i BTF 1 H.O. l C
l C
l Lt l
s l
VR-i l
ii l
l l
l 1 +106-1 1
I I
i I
i I
i st i
Cs l
l 11 I
i l Passive l-l 1
1 I
I I
I I
I I
It I
en I
I I
I l
11/2VQ003 l N105-1 l 2
l A
l 8.0 l BTF l A.D. l C
l C
l Lt l
OP l
VR-i l
il I
l l
1 I n-ics-i i 1
l 1
1 I
I I
st I
Oe l
l 1
i i passive l l
1 1
I I
I I
I I
I It i
RR I
I I
I l
l 1/2V0004A I N105-1 l 2
l A
i 8.0 l Bir i A.O. l C
l C
l Lt l
OP l
VR-1 l
li l
l l
1 i N-iO6-1 i
i i
i I
l 1
i st i
Or i
I l
i I passive 1 l
1 I
I I
i i
i I
It I
RR I
I I
i l
l 1/2V00048 l NIOS-i l 2
l A
l 8.0 l BTF lA.O.l C
l C
l Lt l
00 l
VR-i l
Ti l
l l
I 1 *-106-1 1
I I
I I
I I
I se l
De I
I I
i ipassive l l
I I
I I
I I
i I
It I
RR I
I I
I I
l1/2VQ005A i 5105-1 1 2
i A
l 8.0 l BTF l A.O. l C
l C
l Lt l
OP l
VR-i l
It j
l l
l +106-1 1
I I
I I
I l
1 st 1
0e l
l l
i i passive l l
l 1
I I
I I
I I
I It 1
RR I
I I
I J
l 1/2V00058 l 5105-1 l 2
l A
l 8.0 l BTF l A.O. l C
l C
l Lt l
OP l
VR-1 l
ii l
l l
l l +106-1 I
I I
I I
i i
i st i
Op i
i i
i ipassive l-l 1
1 I
I I
I I
I I
It 1
RR I
I I
I l-1 1/2V0005C l Nios-1 1 2
l A
l 8.0 l BTF l A.O. l C
l C
l Lt l
OP l
VR-1 l
il l
l l
l 1 *-106-1 1
I I
I I
i i
i st i
Op l
1 I
i i passin l 1
I i
l l-1 I
I I
I It i
RR I
I I
I l
l 1
l
.I I
I i
l l
1 1
I i
i l
I i
i l
i i
I i
i I
I i
l I
i i
I l
l 1
1 I
i i
i I
I i
I I
I I
I 4.3 - TABLE 39 of 42 (01080/0041D) l
[
i llllI1IlI1I1IIIIIiIIIIIIIIIIlii IIiI S'
e e
e e
K v
v v
v R
i i
i i
A s
s s
s M
s s
s s
E a
a a
a 2
R P
P '
P P
4 9
llI lI ll lI lI iI II II II II II II I1 iI II II li fo v
H.
0 e
C S 4
R E O T P EL lIi lI lI lI lI II II II II
?I II II I1 iI II II
~ t BA T
S E"
TO' 3
N 4
IlI II 1I lI lI II II II II II II II Il i!
II II iI T
F S E E 1
1 1
1 I U L Q R
R R
R E E V
V V
V R R lII
]I lI lI lI I1 II I1 II iI II II Il II 1 I II iI T E S D R
R R
R E O R
R R
R T M' lll lI iI lI lI Il II I1 Ii iI II II II iI 1I II iI 0
T 0 S H t
t t
t ET L
L L
L T EN N
IlI lI lI 1I iI II II Ii Ii II II II II iI iI II II M
O A
I
.~
R T
C C
C R S S R R P I T I DR S D GE E N
W llI II II II lI II II II Ii II II Ii II iI II II II I HO T T P S L N
L O E AR AI TE A M T W E R I C
C' C
C EN L C OC O S I M U N OP V M N R O llI lI II II II II 1I II II II II Il I1 II II II II EC N S
O E'
N R
I Y
T P C Y B
AT M
N H
M.
llI lI II Ii iI II 1I Ii II lI II I( Il II II II II EVE L P L
L L
L A Y G
G G"
G V T lII lI lI lI iI II lI Ii II lI II II I1 II II II II E
)
0 0
0 0
V E.
5 5
5 5
L ZN A I I V S
(
lII II II I1 lI II lI II II II II Ii Il II II lI II Y
R E O V G L E A
A A
A A
T' V AC llI lI iI l1 iI II lI II
!I II II iI II II i1 lI II SS
.A 2
2 2
2 L
.C llI jI 1I 1l lI II 1I II II II 1I iI I1 Il l1 iI II 3'
3 3
3 D
I 5
5 5
5 0
0 0
0 P
1 1
1 1
S 5
+
+
Il1
!I I1 ll l1 II II II II II 1I Ii Il Il Il iI II
)
0 1
R 6
7 8
9 4
E E 1
1 1
1 0
V E 0
O J
3 0
L P Q
Q Q
/
/
A U V
V V
r#
0 V N 2
2 2
8
/
/
/
0 1
1 1
t 1
IllllililIlI1II1II1IIiIIiIlIlIllIII 0
(
l lliiI1i IIIIII IiIilII1IIIiiiIiIII1 I;
S o
e K
v v
R i
i A
s s
P s
s E
a' a
2 R
P P
4 9
lII 1I ii iI li II Ii Ii ii Ii Ii Ii ii Ii II Ii II fo v
H 1
e C S 3
4 y
E O' T P EL III li Ii ii lI II I i 1i ii Ii Ii Ii ii II Ii II Ii BAT S
. O 3
N 4
ilI li Ii ii Ii 1I Ii ii li Ii Ii II ii Ii II Ii Ii T
8 F S 1
E E 1
I d L Q R
1 E E V
R R RV lII Ii Ii Ii ii iI Ii Ii ii Ii Ii Ii Ii Ii Ii Ii Ii T E S D R
R EO R
R T M m
IlI iI iI Ii l
iI Ii Ii li II Ii Ii ii Ii Ii II Ii 0
t T 0 B
S H t
/
E T L
t T E L
M N
M O
III ii l!
Ii ii lI Ii Ii ii II Ii I
Ii Ii Ii Ii Ii A
I R
T G N A ET K C OO T O E C
C R S S R R P I T I DR S D G E E N
W iII li li Ii ii iI Ii Ii ii II Ii Ii li Ii Ii Ii Ii I HO T T P S L N
E A R L O A I T E A M T W E R I C
C E N L C OC OS N O I ' U t
V N
P t
R 0 E C N III Ii Ii Ii ii iI Ii Ii ii II ii
!I ii Ii Ii I
Ii S
O
. E N
R A.
T P I
Y C Y B
AT M
S IIi iI 1i II Ii II Ii Ii ii II li II ii Ii Ii Ii 1i EV E L P L
K A Y G
C V
T'
]II Ii 1
Ii Ii II Ii Ii II lI ii i1 ii II Ii Ii 1i E
. 1 V E 0
0 L Z N A I I 2
2 V S
(
III Ii 1i ii Ii iI Ii Ii Ii lI ii ii ii I!
I Ii ii YR E O V G C
L E A
A A T V AC lIi li Ii lI Ii ii Ii Ii Ii iI ii Ii ii Ii II ii II S
S A
2 2
LC III II Ii iI Ii Ii II Ii li ii li II ii Ii II lI II A B A B D
1 1
1 1
%9 I
9 9 F
4 4 4 4 MM M M III iI 1I II Ii lI II
!I ii I
II iI ii li II iI II
)
D 1
41 R
0 EE 9
9 0
V B 1
1 0
L M M
M
/
A J W
W V #
0 t
2 2
8
/
/
0 1
1 1
0 I11lIiIlI1Ii1IIIIliII1IiIiliIlIiIII
(
INSERVICE TESTING PROGRAM Rev.: 9.
COP 1PONuEALTH EDISON BYRON NUCLEAR POWER STATION l
VALVE
-l
[
l-VALVE' l VALVE l VALVE j ACT. l NORMAL I STROKE l TEST l TEST l.RELIET l
l TECH. l l
l NLh9ER l
P&ID l CLASS l CATEGORY l SIZE l TYPE ] TYPE l POSITIM l DIRECT. l METHOD l MODE l REQUEST l
NOTES l POS. l REMARKS.l l
l l
I 1 (IN.) I I
I i
l I
l l
l l
l l u2u000uA l l
l l
l l
l l
l St l
OP l
l l
T l
l l
l S 118-5 l 2
l A
l10.0 l GA lM.O.l 0
l C
l Lt l
RR.
l VR-1 l
l l.
l l
l wi18-7 I I
I I
I I
I I
It i
RR I
I i
1 l
l1/2w000sB l l
l l
l l
l l
l St
.l OP l
l l
1 l
l l
l l N118-5 l 2.
l A
l10.0 l GA l M.0. l 0
l C
l Lt l
RR l
VR-1 l
l l
l l
1 N118-7 I I
l l
l 1
I I
It i
RR l
l I
I l
l 1/2w0007A l N 118-5 l 2
l AC l10.0 l CK l S.A. l C
l C
l Lt/Btl RR l
VR-1, 18 l
l 3'
l Passive l l
l N118-7 1 1
I I
I I-I l
I I
I i
l l1/2uo007B l 5118-5 l 2
l AC l 10.0 _l CK lS.A. l C
l C
l Lt/Btl RR l
VR-1. 18 l
l 3-l Passive l l
l Niis-7 I I
I I
I I
I I
I I
I I
l-l l U:WOOZOA l l
l l
l l
l l
l St l
OP l
l l
1 l
l l
l N118-5 l 2
l A
l10.0 l GA l M.0. l 0
i C
l Lt l
RR l
VR-1 l
l l
l l
1 N178-7 I I
I I
I I
I I
It i
RR I
I I
I l
l i/2w00zc8 l l
l l
l l
l l
l St i
OP l
l l
1 l
l l
l N118-5 l 2
l A
l10.0 l GA l M.0. l 0
l C
l Lt
]
RR l
VR-1 l
l l
l' l
I S113 7 I I
I I
I I
I I
It i
RR I
I I
I I
l v2w00564 l l
l l
l l
l l
l St l
OP l
l l
1 l
l l
1 W118-5 l 2
l A
l10.0 l GA lM.0.l 0
l C
l Lt l
RR l
VR-1 l
l l
l l
1 N118 7 I I
I I
I i
1 1
It i
RR I
I t
I
_]
l v2w0056B l l
l l
l l
l l
l St l
OP l
l l
1 l
l l
l N118-5 l 2
l A
l10.0 l GA j M.0. l 0
l C
l Lt l
RR l
VR-1 l
l l
l l
l N118-7 l 1
I I
I I
I I
It l
RR I
I i
1 l
1 l
l l
l l
l l
l l
l l
l l
l l-1 I
I I
i 1
1 I
I I
I I
I i
I 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 I
I I
I I
I l
l l
l l
l l
l l
l l
l l
l l
l 1
l l
l 1
1.
I I
I I
I I
I I
I I
I l
l l
l l
l l
l l
1 l
l l
l l
l l
1 I
I i
i i
I i
I i
i i
l l
l I
l l
I l
l l
l l
1
-1 I
l l
l l
l l
l-1 I
i I
i i
I i
I i
i I
l (01080/00410) 4.3 - TABLE 42 of 42 l
v._
SECTION 4.4 NOTES
Rev. 9 IlOTE_1 Closure of the Main Steam isolation valves 1MS001 A-D or 2MS001A-D during unit operation would result in reactor trip and safety injection actuation. To avoid this transient, these valves will be partially stroked every three months.
Full stroke testing will be dono during Modes 4, 5, or 6 as plant conditions allow, per IWV-3412.
IlQIE l The testing of any emergency boration flowpath valves during unit operation is not practical.
Stroke testing the Boric Acid injection isolation valve 1CV8104/2CV8104 and check valve 1CV8442/2CV8442, the RL to CV pump suction isolation valvo 1CV8804A/2CV8804A, or the RWST to CV pump suction isolation valves 1CV112D,E/2CV112D,E, could result in boration of the RCS, resulting in a cooldown transient.
Aligning the system In this configuration even for a short duration is, therefore, unacceptable. These valves will be stroke tested during cold shutdown, in accordance with INV-3412.
IIQTE_2 These valves are the Main Feedwater isolation valves:
1FW009A-D/2FW009A-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 l
operation as well as full stroke tested du:Ing cold shutdown, per the requirements of INV-3412.
UDTEA Closure of.these letdown and makeup valves ICV 112D,C/2CV1128,C, 1CV8105/
2CV8105, ICV 8106/2CV8106, 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 j.
required by IWV-3412.-
IlRIE-S The IRH8701A/B, 1RH8702A/0, 2RH8701A/B, and 2RH8702A/B valves are the isolation boundary between the Residual Heat Removal Pwnps and the Reactor Coolant. System. Opening one of these valves during unit operation will leave only one valve isolating RHR from the high RCS pressure. This would place the plant in an undesirable condition.
Therefore, these valves will be full stroke tested during cold shutdown, per INV-3522.
(0094D/0035D/062590) 4.4 - page 1 of 8
Rev. 9 NOT W The following valves have been identified as intersystem 10CA valves.
They form a pressure boundary between the RCS and other esserLlal components in order to protect these components from damage. These valves will be leak tested in accordance with the Dyron Technical Speelfications.
Performance of the leak test on these valves also satisfles the back-flow test required for check valves by NRC Generic Letter 89-04.
Dyron Unit 1 and Unit 2 Intersystem LOCA Valves 1Ril8701A/B 1Ril8702A/B 2 RilB701 A/B 2Ril8702A/D 1Rl!8705A/B 1Ril8705A/D 2Ril8705A/B 2RH8705A/B ISI8818A-D 15I0815 2SI8818A-D 2S18815 ISI8819A-D IS18905A-D 2S18819A-D 2 SIB 905A-D 1SI8841A/D ISI6948A-D 2SI8841A/D 2 SIB 948A-D ISI8900A-D ISIB949A-D 2818900A-D 2S18949A-D IS18956A-D 2SIO956A-D MOTIL1 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.
Failure of one of these valves in the open position would result in leaving only one valve as the high pressure boundary. These valves will be full stroke / fall safe exercised when the RCS pressure is at a minimum during cold shutdown, per INV-3412.
HQT U The Residual lleat Removal Pttmp discharge check valves 1RII8730A/B and 2Ril8730A/D cannot be full stroke exercised during unit operation due to the high'RCS pressure. These check valves will be partial stroke tested, houever, on a quarterly basis and full stroke exercised during cold shutdown.
Th10 !
in accordance with INV-3522.
l HQTT _9.
Due to the.RCS pressure, the check valves listed below cannot be full stroke exercised during unit operation:
ISI8818A-D 2SI8818A-D RilR Cold Leg Injection 1SI8958A/B 2SI8950A/B RWST to RIIR Pump Suction These valves will be full stroke exercised during cold shutdown, in accordance with INV-3522.
(0094D/0035D/062590) 4.4 - page 2 of 8
Rev. 9 NOIE_19 The 1FW039A-D Lad 2FW039A-D valves cannot be stroke tested during unit operation as closure of these valves would result in termination of the waterhammer prevention feedwater flow. This would result in undesirable affects on the Steam Generators.
These valves will be full stroke / fall safe
-tested during cold shutdown, per INV-3412.
1102E.11 The Primary Containment Purge Supply and Exhaust Valves IVG001A/B, IVQ002A/B, 2VQ001A/B, and 2VQ002A/B cannot be stroke timed during unit operation.
These 48-inch valves are the only isolation points between the containment atmosphere and the environment.
Stroking these valves at any time other then mode 5 or 6 would be a violation of the Byron Technical Speelfications.
These valves will be full stroke tested during cold shutdown, in accordance with IWV-3412.
These valves will be leak tested semiannually, in accordance with Byron Station Technical Specifications.
The Primary Containment Mini-Purge and Exhaust Valves IVQOO4A/B, IVQOOSA/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 Byron Station Technical Specifications.
tIDIE_12 The Auxiliary Feedwater-check valves 1AF001A/B, 1AFC03A/B, I AF014 A-ll, 1AF029A/B, 2AF001A/B, 2AF003A/B, 2 AF014 A-il, and 2AF029A/B cannot be full stroke tested during unit oporation, as this would induce potentially damaging thermal stresses in the upper feedwater nottle piping.
The 1AF001A/D, 1Ar003A/B, 2AF001A/B, and 2AF003A/D 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.
IlRIE_ll.
The -Iligh llead Injection Isolation Valves ISIB801A/D and 2SIBB01A/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 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 l
reactivity change which would, in turn, cause a plant transient. These valves will be full stroke tested during cold shutdown in accordance with INV-3412.
(0094D/0035D/062590) 4.4 - page 3 of 8
Rev. 9 UDIL_14 The safety injection system SVA0 (Spurious Val.e Artn-Lion Group) valves ISIBB02A/D, IS18806, 18180 OA/D, 1518813, 1S18835, 1518840, 2 SIB 002A/D, 2518806, 2S18809A/D, SSICB13, 2318835, and 2S18840 cannot be st-oke tested dusing unit operation. These valves are requited by the Technical Specifications to be de-energized in their proper positions dur..
unit operation. Stroking them would be a violation of the Technical Specifications q
as veil as defeating the de-energized SVAG valve principle.
These valves will be stroke terted during cold shutdown when they are not required to be de-energized. This is in accordance with IWV-3412.
NOTE _15
" DELETE "
I HQIE_.ls These f eedwater 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 2rW540 during unit operation would cause a loss of feedwater to the steam generators, resulting in a plant transient with a possible reactor trip as a result. These valves will be fall safe (rt) tested pursuant to the Dyron Station Technical Specifications.
UUTC.L'l These feedwater valves are exempt from all ASME Section XI testing requirements per IWV-1100 and IWV-1200.
They are lacluded in the program for operability tracking purposes only. The closure of the Main reedwater Regulating Dypass Valves IrW510A, IrW520A, IrW530A, irW540A, 2rW510A, 2rW520A, 2rW530A, and 2rW540A during uni'. operation would require the Main reedwater Regulating Valves to correct for bypassed flow and could result in a plant transient with a possible reactor trip as a rest 1t.
These valves will be fall safe-(rt) tested pursuant to the Dyron Station Technical Specifications.
HQIE_.lB
" DcLETE "
HQIE_19
" DCLETE "
(Incorporated into NOTE 14)
.(0094D/0035D/062590) 4.4 - page 4 of a
Rev. 9 HOTE_20 The remote position indicator for these valves cannot be observed dliectly due to the encapsulated design of the solenoid valve body.
During the ludication test, indirect evidence of the necessary valve disk movement shall be used, in
-accordance with INV-3412 (b).
The valves affected are listed below ICV 8114 1PS230A/D 2PS22BA/B ICV 8116 1RC014A D 2PS229A/B IPS228A/D 2CV D 114 2PS230A/B IPS229A/D 2CV8116 2RC014A-u HQIE_21 T$e Main Teedwater Tempering Flow isolation valves 1/2rWO34A-D are exempt from i
all ASMC Section XI testing requirements per IWV-1100 and IWV-1200.
They are included in the program for operability tracking purposes only, and wlJ1 be fall safe (ft) tested pursuant to the Dyron Station Technical Specifications.
HQIt_22 Per NRC request, the post-accident hydrogen monitoring system check valves 1/2PS231A and 1/2PS231D will be stroke exercised open on a quatterly frequency
.to verify operability.
HQTE_13 1/2S18818A-D, 1/2518819A-9, and 1/2518948A/D are Event V check valves, which are defined as-two check valves in series at a low pressure /itCS interf ace whcae f ailure may result in a LOCA that bypasses contaltunent. They are Individually leak-tested in accordance with NRC generic letter 89-04, position 14b.
RQTE 24 1/2CC9518, 1/2CC9534, 1/2CV8113, and 1RH8705A/D are check valves designed to relieve pressure between two contair. ment isolation valves.. The full flow limiting value is zero, since the safety function of these valves in the open direction is to relieve pressure only.
Refer to Relief Request VR-18 l
MOTE. 25 Check valve 1/2S18926 prevents flow from the Safety Injection (SI) pwnp suction line to the Refueling Water Storage Tank (RWST). The SI pumps are normally lined up in the INJECTION MODE to take suction f rom the RWST. - This check valve would stop reverse flow when the SI pumps are transferred to ll0T/ COLD hEG RECL'CULATION MODE to prevent contamination of the RWST.
Ilowever, the-1/28.4006 M.O.V. Is in series with.this check valve and would be closed to prevent reverse flow as directed by the ernergency procedures.
Therefore, no backflow test (Ut) !s required for 1/2518926.
h (0094D/0035D/062590) 4.4 - page 5 of 8
i i
Rev. 9 l-1NIE_24 j
Check valve 1/2CV8546 preventa flow f rom the Chemical and Voltune Control (CV)
]
pump suction line to the Ref ueling Water Storage Tank (RWST).
The CV pumps are normally lined up in the INJECTIGi MODE to take suction from the RWST.
j This check valve would stop reverse flow when the CV pumps are transferred to j
llOT/ COLD LEG INJECT 1Q4 MODE to prevent contamination of the RWST.
- Ilowever, l
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 l
procedures. Therefore, no back flow test (DL) is required for 1/2CV8546.
1 NOTIL.21 i
Check valves 1/2518958A/D prevent. flow from the Residual llent. (Rii) Removal ptunp suction line to the Ref ueling Water Storage Tank (RWST). The Ril pumps are normally lined up in the INJECTION MODE to take suction from the RWST.
These check valves would stop reverse flow when the Ril ptunps ate transferred to IKrf/ COLD LEG RECIRCULATION MODE to prevent contamination of the RWST.
Iloweve r, the 1/2 SIB 812A/11 M.O.V.'s are in series with these check valves and j '
would be Mosed to prevent reverse flow as directed by the emergency procedures.
In addition, the Ril suction valvet4 1/2Sf0612A/D. 1/2Ril8701A/D or j
1/ 2 Ril8702 A/B, and J /2$18811A/fl are electrically ird.erlocked to prevent the backflow to the RWbT when the Ril system is in a R2 CIRCULATION MODE.
Thus, no l
back flow testing of 1/2S18958A/B le required.
1 ROIIL2fl NRC Generic Letter 89-04, Attachment 1, Position 3 lists the CVCS Volume Control Tank (VCT) outlet check valve as an example of ASME Co(e Class check valves that perform a safety f unction in the closed d'rection t hat are f requently not back flow test ed.
At Dyron Statfor., check valve 1/2CV8440
_ prevents flow f rom the Chemical and Volume Co.itt ol (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 1/2CV112D and 1/2CV112C M.O.V,'s, which are in-series with_the 1/2CV8440 check valve.
Closure of either M.O.V. will prevent reverse flow to the VCT.
Thus, no back flow t.esting of 1/2CV8440 la required.
NOTE _29.
Check valve 1/2CV8442 prevents flow from the Chemical and Volume Control (CV) ptunp_ suction headet to the boric acid transfer ptmp. This line is normally 4
- 1solated by t.he 1/2CV8104 emergency horat.lon vab e.
This valve would only be opened during an emergency with the boric acid ti e ster pump running.
This check valve is unnecessary with the current system operation, and tht.s, no back' flow testing of 1/2CV8442 is required.
P J
( 0094 D/00'15D/062 590 )
4.4 - page 6 of 8
,..~m
.m___
-___._.m____.m_._.-___...
W f
Nev. 9 i
HRIEJO 1
j Check valves 1/2Ar014A-H are verlfled to be closed each shif t, by the Operat.ing
]
Department, by ver4fying that the temperature at 1/2AF005A-H 1a i 130' F, per l
DOP 199-A40 (U-1) and DOP 199-A61 (U-2).
If the temperature is > 130' F at j
any 1/2AF005 valve, then abnormal operating procedure 1/2DOA SEC-7, " Aux 111 sty feedwater Check Valve beakage", is entered to isolate and cool down the affected lines. This shiftly monitoring of 1/2AF014A-H in the closed position I
adequately monitors the status of these valves.
No additional monitoring /
J trending by the IST Group is required.
ROICJ1 Check valves 1/2CV8400A/B and 1/2SIO919A/D are the Centrifugal Charging Pump 4
and Safet.y injection Pump mini-flow recirculation line valves which cpen to g
prevent full recirculation flow during IST Surveillances.
Since full stroke l
f or these valves will depLnd on the reference point of testing, acceptable full stroke will be verifled whenever the recorded mini-recirculation flowrote is within the " acceptable" ar " alert" ranges given In the IST Pump Susveillance.
1 MOTIL.3.2 Check valves 1/2CC'463A/B and OCC9404 are Ll'e Component Cooling Water Pump discharge check valves. The fuli denign accident flow through nny one pump cannot be obtained during normal operation without causing low flow alarms in adjacent loops and possible e<]ulpment 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.
HOII._13 The Essent ini Service Water (SX) and Make-tip Pump discharge check valves (OSX020A/B) open to permit make-up water flow from the Rock River to the SX System Basin. These check valves are downstream at, the pump ' discharge t.ap-of f to the SX Make-Up Pump Jacket Wat er Heat r,mchanger and Gear 011 Cooler.
Since this tap-off line is orificed, the flowrote through this line, and therefore the flowrote through pump discharge check valves OSX028A/D, will depend on the l
p reference point of testing.
Acceptable OSX020A/D full stroke will be verifled whenever the secorded total pump flow minus the top-off line flow is within
" Acceptable" range contained in the ASME pump surveillance.
l (0094D/0035D/062590) 4.4 - page 7 of 0 l
l i
Rev. 9 i
llRTEJ4 l
per liyron Technical Speelfications Amendment valves 1/2SD002A-ll, 1/2SD005A-D have been removed from the list of valves to be tested under 10CTR50 Appendla J and will now be tekted per ASME Code Section XI, 1WV-3420.
l l
l-NOTE _15 l
The 1/2RIIB705A/B check valves will be operability tested by verifying itat
[-
there is depressurization in lino 1/2Ril20AA-3/4 and 1/2Ril26AD-3/4 when they l
nre opened. This is a test method which was approved by the 11RC is SER j
9/14/90.
i:
L p
r l
I (0094D/0035D/062590) 4,4 - page 8 or e
.u_...;._........,_...__.-.
_ -. _. _ _ _ _.. = _ _ _ _. _ _ _. _ _ _ _, _.
l SECTION 11.5 TECilNICAL APPROACllES AND POSITIONS
m.__.
4 Rev. 9 VA-01 IST Technical Approach and Position i.
l l
A.
CoastonenL_ident1Licati.on
-1.
Description Method of Stroke Timing Valves - Timing using control board position indication lights (St).
2.
Component Numbers:
See IST Valve Tables.
3.
References AGME Code,Section XI, Subsection INV, paragraph INV-3413(a).
4.
Code Class:
1, 2, and 3.
5.
Exnmination Category (s): N/A 6.
Item Number (s): N/A U.
Regulfsment 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 INV-3413 of ASME XI defines " full-stroke time" as "that time interval from initletion of the actuating signal to the end of the actuating cycle."
It la common industry p actice to measure stroke time as the time interval between placing the operator switch on the control board in the "close" or "open" position and indication that the valve la open or closed on the control board (switch to light).
C.
Ecaltinus It is recognized that the way in which the limit switch that operates the remote position indicator lights la set may result in " closed" or "open" Indication before the valve obturator has actually completed its travel.
-This le 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 teference 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 str>ke time for
-stroke times longer than 10 seconds, as allowed by ASME Section X1 subparagraph INV-3413(b). should'not be used.
(0109D/0041D/070690).
Page 1 of 8
,_._ _ _ -_ _. -~ _ --.__. _ _ _._
kov. 9
'.' A - 0 2 IS1 Technical Approach and position A.
ComponenLidentillation:
1.
==
Description:==
Method of rail Safe Testing Valves.
2.
Component Numbers:
See IST Valve Tables (ft).
3.
Re f t,rences s ASME Code,Section XI, Subsection IWV, paragraph IWV-3415.
4.
Code Class 1,
2, and 3.
5.
Exnm1 nation Category (s): N/A 6.
Item Number (s): N/A D.
Regnitcments Paragraph IWV-341$ of ASME XI states that "When practjcal, valves with fall-safe actuators shril be tested by observing the operation of the valves upon loss of actuator power."
Most valves eith a fall-safe mechanism to stroke the valve to the fall-safe position during normal operation.
For example, an air-operated valve that falls closed may use air to open the valve against spring pressure. When the actuator is placed in the closed posillon, air la vented from the diaphragm and the j
spring moves the obturator to the closed position.
I C.
Entition:
In the cases-where normal valve operator action inoves the valve to the closed position by de-energizing the operatot electrically, by venting air or both (e.g., an electric solenold in the air system of a valve operator moves to the vent position on loss of power), no additional fall-safe testing is required. Valves with f all-safe actuators that do not operate as part ot normal actuator operation must be tested by ot.her means.
This may be accomplished for motor-operated valves by opening the circuit breaker supplying operator power and observing thet the valve moves to its fall-safe position.
Lifting leads is not required unless it is the only method of de-energizing the actuator.
Using a valve remote position Indicator as verification of proper fall-safe operation is acceptable, provided the Indicator is periodleclly verlfled to be operating properly as required by ASME Code,Section XI, Subsection IWV, paragraph IWV-3300.
(0100D/0041D/070690) page 2 of 8
Rev. 9 VA-03 IST Technical Approach and Position A.
Cpapanant Idgntiflentloat 1.
Description Method of Tull Stroke (Ct) and Back riow (BL) Erercising a>
of Check Valves.
2.
C9mponent Numbers See IST Valve Tests (Ct and Dt).
3.
Referencess (a) HRC Generic Letter 89-04, Guldance on Developing Acceptable Inservice Testing Progrmns, Attachment 1, Positions 1, 2, and 3;-(b) ASME Code,Section XI, Subsection INV, paragreph INV-3522.
4.
Code Classt 1, 2, and 3.
Examination Category (c)
N/A 6.
Item Humber(s): N/A li.
Ecquiltment t Paragraph IWV-3$22 of Article XI states " check valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation.
If only limited operation is practical, during plant operation the check valve.shall be part-stroke exercised during plant operation and full-stroke exercised during cold shutdowns." For check valves with no exttrnal posillon 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.
110Elt1Dn s 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 obturatoc nosition.
Where' external position Indicators are not provided, manual stroking of the valve le 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 HRC Generic Lett er 89-04, Attachment 1, Position 1, the other acceptable method of full-stroke exercising a check valve to the open position is to verify that the valve passes the maximum required accident condition flow.
Any flow less than this is considered as a part-stroke exercise.
Flow through the valva must be determined by positive means such as permanently installed flow instruments, temporary flow Instruments, or by measuring the pressure drop across the valve or other in-line component.
Measuring total flow through multiple parallel lines does not provide verification of flow through individual valves.
(0109D/0041D/070690)
Page 3 of B
m.
Rov. 9 C.
Position, continued 7
One except ion to the " maximum required accident flow" requirement is the methodology used to verify full-stroke exercising of the Safety Injection (SI) Accumulator Back-up Check Valves, 1/2 SIB 956A-D.
Because of the high j
maximum design flowrate of these valves, a maximum design accident flowrote test is physically impossible to perform.
For those valves, an Engineering calculation has been perfore i to determina the minimwn flowrate for full disc lift.
An accer A.e full-stroke exercise of these valves will be performed each refuell..g vatage by measuring the accumulator level decrease over time, converting these parameters to a flowrate through the valve, and verifying this value is greater than or equal to the engineering calculated minimum flowrote for full disc lif t.
This method is superior to sNeple disassembly and inspection of one valve per outage which would require unusual system line-ups, freeze seals, radiation exposure, and possible plant translents.
Other alternatives to measuring full design accident flow or disassembly i
and inspection of check valves to satisfy full stroke requirements is allowed as long as the requirernents of NRC Generle Letter 09-04, Attochment 1, Positions 1, 2, and 3 are utilized OR specific relief requests are approved by the NRC.
Stroking a valve to the full closed position for valves without a manual exercise or position indicator must be verlfled using indirect means.
These include, but are not limited to, (1) observing pressure Indications i
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 upstream side of the valve to detect leakage rates in excess of tb;t expected with the valve shut.
- Jalves that cannot be full-stroke tested or where full-stroking cannot be verifled, 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 testlng, where possible.
Testing of check valves by disassembly shall comply with the followings 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 exerclued.
b.
Due to the scope of this testing, the personnel hazards involved, and system operating restrletions, velve disassembly and inspection may be performed during reactor refueling outages.
Since this frequency differs from the Code required frequency, this deviation must be specifically noted in the IST program.
(01090/0041D/070690)
Page 4 of 8
Rev. 9 c.
Where it is burdensome to disassemble and Inspect all applicable valves each refueling outage, a sample disassembly and Inspection plan for groups of identical valves in similar applications may be employed. The NRC Gentric better 09-04 guidelines for this plaa are explained below:
The cample disassembly a*d inspection program involves grouping similar valves end testing one valve in each group during each refueling outage. The sampling technique requires that each valve in t.he group be the same design (manuf acturer, size, model number, and materials of construction) and have the same service conditiong including valve orientation.
Additionally, at each disassembly the licensee must verify that the disassembled valve is capable of full-stroking and that the internals of the valve are structurally sound (no loose or corroded parts). Also, if tua disassembly is to verify the full-stroke cepubllity of the valve, the disk should be manually exercised.
A different valve of each group la required to be disassembled, inspected, and manually full-stroke exercised at each successive refueling outage, until the entire group b1s been tested.
If the disassembled valve 1s-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 disassemoled, inspected, and manually full-stroke exercised during the anme outage. Once this is completed, the sequence of disassembly must be repeated unless extenslon of the interval can be justified.
Estending the valve anmple disassembly and inspection Interval f rom disassembly of one valve in the group every refueling outage or expanding the group size would leerease the time between testing of-any particular valve in the groto With four valves in a group and an 10-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 sanple group would be disassembled and inspected only ance every eight years.
Extension of the valve disassembly / inspection interval from that allowed by the Code (querterly or cold shutdown frequency) to longer than once every 6 years is a substantial change which may not be justified by the valve falluce rate data for all valve groupings.
When disassembly / Inspection a'ata for a valve group show a greater than 25% failure rate, the station should determine whethar the group size should be decreased or whether more valves from the group should be disassembled during every refueling outage.
Extenslor.s of the group size will be done on a case by case basis.
(0109D/0041D/070690)
Page 5 of 8
1 Rev. 9 VA-04 IST Technical Approach and Position A.
ColwonenLIdenL1ListLLion:
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 D.
Requirement:
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 (UTSAR).
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 la contrary to NRC Generic Letter 89-04.
According to NRC Generic Letter 89-04 t.he 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 stroie time based on the valve size, valve
]
type, and actuator type.
The devlotion should not bn so restrictive that It results in a valve be.Ing declared inoperable due to reasonable c'
ee 1
time variations. However, the devlation used to establish the 11G should be such that corrective action would be taken for a valve that may not perform its intended function. When the calculated limiting value for a full-stroke Is greater than a TS or safety analysis limit, the TS or safet y analysis limit should be used as the limiting value of f ull-atroke time.
Dased 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, valvo type.
and actuator type to provide for.a more therough review in determining what would be a " reasonable" deviation ftom the average / reference
' full-stroke value.
?
(0109D/0041D/070690)
Page 6 of 8 4
~o
~
me
-a-,,,n,.
,,,--,n,,
.,4,,,,,..,
.g.
,,p.4-,.m,n-w---
,,,,..m,,
-,n_--,_en.,
,,w.,_.-p,
,,wy,,-m
Rev. 9 o
i J
The 1983 Edition tbrough Summer 1983 Addenda of ASME Section XI does not provide
.ldance for determining values of full-stroke.
However, it does provide requirements for when to start monitoring a valves performance on a more frequent basis, also known as alert range testing.
If a valve strokes in 10 seconds or less, a 50% increase over the previous value requires it to be put on a monthly test fregesney, and for valves stroking in greater than 10 seconds, a 25% increase ovvr the previous value requires it to be put on a monthly test frequency. The new ANSI /ASME OM Part 10 standard does provide acceptance criterla to be used when comparing valve test results to the reference value of full-stroke. The OM Part 10 standard recognizes that operating chatacteristics of electric motor valves are more consistent than those of air-operated valves.
Ilowever, due to the requirements of UM Part 10 delineating different corrective actions to be taken when a valve exceeds its minimum stroke time than those specified in ASME Section XI, using the same criteria would not necessarily be appropriate.
Therefore, the current ASME Section XI alert value will be used as the alert range value (25% or 50%) for motor and solenold operated valves, and the current Ceco Corporate IST Group guidance (75% to 100%) will be used as the required action range limit. This criteria, in conjunction with establishing reference / average values of full-stroke, should allow for reasonable deviations in stroke time meacurements without declaring a valve Inoperable.
The corrective actions specified in IWV-3417(b) of Section XI and as described ir iST Progr am Realef Request VR-20 will be taken when a valve exceeds its limiting value of full stroke.
C.
EnnLLLons The following criteria will be used as general guidance to 6 stab 11sh ALERT and REQUIRED ACTION ranges for power-operated valves MQYis/SQYisll10Y1alAQV's Ltaa_thnitnr_tgunLtp.20 eeeo2uis:
ALERT RANGE:
(1.50) (Tret)
(2.0) (Tref)
REQUIRED ACTION VALUE:
> g2.0) (Tref)
MQYin/SQYinti!QYin_ Dreater_than30__scsonds:
ALERT RANGE:
(1.25) (Tret)
(1.75) (Tref) DI (Tref + 10 see) - (Tref 4 20 see)
REQUIRED ACTION VALUE:
> (1.75) (Tref), but 1 (Tref 4 20 sec)
AQ21s Greater _than_1R_smcsnd.s:
ALERT RANGE:
(1.50) (Tref) - (2.0) (Tref) 95 (Tref + 15 see) - (Tref + 20 see)
REQUIRED ACTION VALUE:
> (2.0) (Tref), but 1 (Treg + 20 see)
(0109D/0041D/070690)
Page 7 of B
~
~_,
Rov. 9 Notest 1.
Treg is the reference or average stroke value in seconds of an individual valve or valve grouping established when the valve is known i
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 effected by other parameters or conditions, then these parameters or conditions must be analyzed and the above far ors adjusted.
4.
If the above enlculated values exceed a Technleal Specification or FSAR value, then the TS or TSAR value must be used for the limiting value of full-stroke.
~
5.
Fast atting valves (valviin which normally stroke 1n less than-2 seconds consistently) are included in Relief Request VR-12.
These valves are HQI assigned ALERf RANGES and are NQT trended.
e 6.
The abovo criterlo 18 a gulde and cannot cover all valves.
The ALERT RANGES and REQUIRE ACTION VALUES are selected based on comparison between the RETERENCE VALUE, LIMITING VALUE given in Technical Specifications /UTSAR, operating history, and calculated values using tho abova criterla.
e 7.
Valves wh;.ch serve the same function on dua. trains (i.e., ICC9473A and ICC94?3ft) and dual units (i.e. ICC9473A and 2CC9473A) are assigned the same REQUIRED ACTION / ALERT RANGE VALUES based on human factors considerations, unless valve or syotem design differences exist between the trains / units.
D.
Refer to Rellef Request VR-20 for related information.
(0109D/0041D/070690)
Page 8 of 8 in
w
- ...A SECTION I4.6 RELIEF REQUESTS i
Rev. 9 RELIEr_FIOUISLh1 1.
Y.alyLHeters All primary containment isolation valves in this program are listed as Category As Yl&YI_t YAllE_l VALVE I 1)
ICC685 41)
IPR 033fl 81)
IS18964 2) 1CC9413A 42)
IPR 033C 82) 1818968 3)
ICC9414 43) 1PR033D 83) 1VOOO1A 4)
ICC9416 44)
IPR 066 84)
IV0001D 5)
ICC9438 45)
IPS228A 85) 1V0002A 6)
ICC9486 46) 1PS228D 86) 1V0002D 7) 1CC9528 47) 1PS229A 87) 1V0003 8)
ICC9534 48) 1PS229D 88)
IV0004A 9)
ICS007A 49)
IPS230A 89) 1V0004 tl 4
10)
ICS007B 50)
IPS230D 90) 1V0005A 11)
ICS000A 51) 1PS231A 91)
IV0005D 12) 3 CS008tl 52) 1PS23115 92) 1V000$C 13)
ICV 8100
$3)
IPS9354A 93) 1V0016 14) 1CV8112 54)'
1PS9354D 94)
IV0017 15)
ICV 8113
$5)-
IPS9355A 95) 1V0018 16)
ICV 8152 56)
IPS9355D 96) 1V0019 17)
ICVB160 57)
IPS9356A 97) 1WM190 18) 1rC000 58) 1PS9356D 98)
IWM191 19)
- 1FC010 59) 1PS9357A 99) 1WOOO6A 20)
'rC011 60)
IPS9357D 100) 1WOOO6tl 21) 1FC012 61) 1RE1003 101) 1W0007A 22) 11A065 62) 1RE9157 102)
IWOOO7B 23)
IIA 066 63)
-1RE9159A 103)
IWOO20A 24) 11A091 64) 1RE91590 104)
IWOO20D 25) 100057A 65) 1RE9160A 105)
IWOO56A 26) 10G079 66) 1RE9160D 106) 1HOOS6B
-27) 10G000 67) 1RE9170 28) 100081 68) 1Rr026 29) 100002 69) 1Rr027 30) 10G083 70) 1RYB025 31) 100084 71) 1RY8026 32) 100005 72) 1RY8028 33) 1PH001A 73) 1RY8033 34) 1PR00111 74) 1RYB046 35)
IPR 002E 75) 1RY8047 36) 1PR002r 76)
ISA032 37)
IPH002G 77)
ISA033 38)'
1PR002H 78)
IS18871 39) 1PR032 79)-
1518880 40)
IPR 033A 80) 1G18888 i
(0095D/0035D/062590) 4.6 - page 1 of 37
- ~..
Rev. 9 1.
Ynite_lhunbars (Continued)
YALYLt YALYE_t YALVE 8 107) 2CC685 147) 2PR033B 187) 2SI8964 108) 2CC9413A 148) 2PR033C 188) 2S18968 109) 2CC9414 149) 2PR033D 189) 2V0001A 110) 2CC9456 150) 2PR066 190) 2VQ001B 111) 2 Cr' 151) 2PS228A 191) 2VOOO2A 112) 2Ct - q c 152) 2PS228B 192) 2V0002B 113) 2CCVd16 153) 2PS229A 193) 2VOOO3 114) 2CC9534 154) 2PS229B 194) 2V0004A 11P,)
2CS007A 155) 2PS230A 195) 2VQ004B 116) 2CS007D 156) 2PS230B 196) 2VO005A 117) 2CS000A 157) 2PS231A 197) 2VQ005B 118) 2CS008B 158) 2PS231B 198) 2V0005C 119) 2CV8100 159) 2PS9354A 199) 2VQ016 120) 2CV8112 160) 2PS9354B 200) 2V0017 121) 2CV8113 161) 2PS9355A 201) 2V0018 122) 2CV8152 162) 2PS9355B 202) 2VQ019 123) 2CV8160 163) 2PS9356A 203) 2WM190 124) 2rC009 164) 2PS9356B 204) 2WM191 125) 2rC010 165) 2PS9357A 205) 2WOOO6A 126) 2PC011 166) 2P69357B 206) 2WOOO6B 127) 2PC012 167) 2RE1003 207) 2WOOO7A 128) 21A005 160) 2RE9157 200) 2WOOO7B 129) 21A006 169) 2RE9159A 209) 2 WOO 20A 130) 21A091 170) 2RE9159t 210) 2 WOO 20B 131) 20G057A 171) 2RE9160A 211) 2 WOOS 6A 132) 20G079 172) 2RE9160D 212) 2 WOOS 6B 133) 20G080 173) 2RE9170 134) 20G081 174) 2RP026 135) 20G082 175) 2RP027 136) 20G083 176) 2RYB025 137) 20G004 177) 2RY8026 138) 20G005 178) 2RYB028 139) 2PR001A 179) 2RY8033 140) 2PR001B 180) 2RY8046 141) 2PR002E 181) 2RY8047 142) 2PR002F 182) 2SA032 143) 2PR002G 183) 2SA031 144) 2PR002H 184) 2SI8871 145) 2PR032 185) 2818880 146) 2PR033A 186) 2S18888 l
(0095D/0035D/062590) 4.6 - page 2 of 37 I
Rev. 9 2.
HwnbeI_0LitemA s 212 3.
ASliE Inde_Categary:
A 4.
ASMG_fodt,_SectinnJLEequirmments :
Seat Leakage Measurement per IW-3420.
5.
Dasis.loL_Rellefa primary contairunent isolation valves will be seat leak tested in accordance with 10 CTR 50, Appendix J.
For these valves,Section XI testing requirements are essentially equivalent to those of Appendix J.
6.
Alternateles11ng s primery 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, es necessary, la accordance with the guldance set forth lu ASME Code Section XI, Subsection IW,. paragraphs IW-3426 and IW-3427(a).
The trending requiremento of IW-3127(b) will no.t be utilized.
7.
ilustiti. cation No edditional information concerning valve lenhage would be gained by perfvrming separate tests to both Section XI and Appendix J. Therefore, overall plant safety is not offected.
As specified per NRC Generic Letter i
89-04, Attachment 1, position 10, the usefulness of IW-3427(b) does not justify the burden of complying with this requirement.
8.
Applicablelimt_P.arindt This reller is requested once per two years during the firot inspection interval.
9.
Appro. val _ Status a.
Relief granted per SER 9/15/88 contengent upon compliance with ASME Section XI IW-34 2 6, 27.
b.
Revised to comply with ASME Section XI IW-3426, 27 in Byron SER Response 12/16/88 (Dyron Station Letter 88-1321).
c.
Relief granted per NRC Generic Letter 89-04.
d.
Deleted SD valves per Technical Specificetion Amendment $39.
'c.
Relief granted per SER 9/14/90.
(0095D/0035D/062590) 4.6 - page 3 of 37
-.. ~. -
._____-___m
._.__.___m.-_._
1 Rev. 9 I
RELIELEEm!EELYR-2
)
1.
Yalyg_llumbcIt ICS020A 2CS020A ICS020B 2CS020B 2.
H.WttbeL.nf I temn 4
3.
ASMLCode_Categ2ry C
4.
ASM LC.o d euS e c t i on_ X LI3 c qui r em e nt s :
Exercise for operability (Ct) of check valves every 3 months, per IWV-3$21.
5.
Duals.Jor_ Relief The check valves in the spray additive system cannot be stroked without j
introducing NaCH into the CS system.
I 6.
. AlteInnLe_Tustingi These valves will be dismantled becording to the sample disassembly and inspection program Identitled in Re11ef Request VR-18 during refueling
. outages, in or6er to. demonstrate operability.
In addition to this, they i
.will be full flow tested once every five years per Byron Station Technical Specificatit.as. The full flow test may be performed in lieu of dismantling these valves, if desired.
7.
Justifications This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant., by
. testing t.he valves as often as is safely possible.
l 8.
Applicahic llme_Enrindt This relief is requested once por quarter durlug the first inspection interval.
9.
' Appr.0XELStatusI a.
Rollef granted por SER 9/15/88.
t b.
Rel.lef granted per Generic Letter 89-04.
-c.
Relief granted per SER 9/14/90.
i l
1.
1 (0095D/00350/062590) 4.6 - page 4 of 37
l Rev. 9 RELIELEEQUESLYIL.1 I
l 1.
ValYC Numbert 1518922A/B 2S18922A/B 2.
Rumbet_DI_1Lems 4
3.
ASMLCodelntegory:
C l
4.
ASMLCodcuncatimt.XLReguiteme n t s.
l Exercise for operability (CL) of check valves every 3 months, per IhV-3521.
l S.
Ilanis_for_.Belici These check valves cannot be full flow tested during operation as the shut-off head of the Safety injection pumps is lower than the reactor coolant system pressure.
performance of this test with the RCS depressurized, but intact, could lead to inadvertent over-pressurization of the system. The alternate method of protecting against t
over-pressurisation by partially draining the RCS to provide a surge volume lu not considered a safe practico due to concerns of maintaining adequate water level above the reactor core.
6.
Alternative _Icatingt These valves will be f ull utroke tested during refueling outages as a minimum, but no more frequently than once per quarter.
7.
JusL111cationt i
This altornative 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.
84 Applicable.11meletloit This relief is requested once per quarter during t * (irst inspection l
Interval.
l 9.
ApproYALEtatus n.
Hellef granted per SER 9/15/88.
b.
Rollef granted per NRC Generic Letter 89-04.
l c.
Rollef granted per SER 9/14/90.
I l
(0095D/0035D/06t'590) 4.6 - page 5 of 37
Pev. 9 ELLIEf_ESWEELY1L4 1.
Valve _Humber:
ICS008A/B 2CS008A/D 1CS003A/D 2CS003A/B 2.
NumbeLcLItems 8
3.
ASME_. Code _C.ategory:
AC & C 4.
ASMC_ Code,_Se c. tion.KLRequi rement s e Exercise for operability (Ct) of check valves every 3 months, per IWV-3521 and IWV-3412.
b.
Ussis lor Bellets 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 cornponents inside containment.
Additionally, the full flow testing of these check valves during periods of cold shutdown, using the CS pumps, would fill the reactor refueling cavity with contaminated water from the refueling water storage tank.
The filling of the cavity, v!n temporarily installed large bore piping, would require the removal of the reactor vessel head so as to preclude equipment damage from borated water.
Currently, full flow recirculation flow paths do not exist from the discharge of the CS pumps through these check valves to the refueling water storage tank.
The addition of such flow paths would require extensive plant modifications to existing plant designs, including penetretion of containment integrity.
partlal stroking of the 1/2CS008A, D valves using air does not provide adequate assurance of valve operability and may be detrimental for the following reasons:
A.
There is no correlation betwoon air flow and angle of dlse movement.
U.
Venting and draining the appropriate piping quarterly may cause deposition of boric acid residue which could in turn promote binding of the check valve Interr.als.
(0005D/0035D/062590) 4.0 - page 6 of 37 l
~~,
,__- ~
-.-.-...a-..
Rev. 9 RELIEr_REQUESLY1L-it__acnt.
6.
Alternate lesiing:
'ihe 1/2CS008A, a valves will be either full flow tested or dismantled according to the sample disassembly and inspection progr am identified in Rellet Risque'et VR-18 and VR-19, to demonstrate operability each refueling outage.
The 1/2CS003A, B valves will be partial stroke tested during the quarterly pump surveillance and full flow tested or dismantled according to the samplo disassembly at d inspection program identified in Relief Request VR-18, to den:onstrato operability each refueling outage.
j
- 7..dustificat1DDI l
Tnis 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 safe 3y possible.
8,-
Applicable _Ilme. Periodi This relief'Is requested once per quarter durin1 the first inspection interval.
9.
App 10YaL.litatMA1 a.
Bellet granted per SER 9/15/88 for 1/2CS003A, B; relief denied per SER 9/15/88 for 1/2CS00BA..
b.-
Revised to address NRC concerns in Byron SER response 12/16/88 (Liyron Station Letter 88-1321).
c.
Rollef pending per SER 9/14/90. This request is being revised per SER 9/14/90 nnd will be resubmitted in March of 1991.
J l
(0095D/0035D/062590) 4.6 - page 7 of 37 l
Rev. 9 i
RELIgr REOUEST VR-S i
1.- Ynive Number:
ISI8956A-D 2 SIB 956A-D IS18948A-D 2 SIB 948A-D 2.
Number _oLitems :
16 3.
ASML_CoAn_ Category:
AC 4.
ASMLCodeuS.e ctioJ_KLRequireme nt s :
Exercise for operability (Ct) of check valves every 3 months, per INV-3521 and IWV-3412.
L.
Desla_for_ Relief The accumulator check valves cannot be tested during unit operation due to t he pressure dif ferential between the accumulators (650 psig) and the reactor coolant system (2235 psig).
Tull stroke exercising of these valves could occur only with a rapid depressurization of the reactor coolant system.
Alternate.leAting Dyron Station Technical Specifications require leak testing to be performed on these valves if the unit is in cold shutdown and if such leak rate testing has not been per(otmed within nine months.
Therefore, Byron Station will full stroke exercise (CL) these check valves on the same schedule.. This will be accomplished by providing a surge volume in the pressuriser and " burping" the accumulator discharge valves.
As a minimum, the acewnulators will be discharged into the reactor vessel during refueling outages to perform a full strok9 exercise (CL) of these valves.
Positive verification of valve operability will be by noting a change in accumulator level.
7.
daLLiLicallant Stroke exercising the check valves on the same schedule as their required Technical Specification leak rate testing will adequately maintain the system in a state of operational readiness without causing unnecessary personnel radiation exposure.
8.
App 11 cabin _Ilme_Periodt This relief is requested once per quarter during the first inspection ^
interval.
9.
Apptcycl_ Status a.
Relief granted per SER 9/15/88.
b.
Rellef granted per NRC Generic Letter 89-04.
c.
Relief granted per SER 9/14/90.
(0095D/0035D/062590) 4.6 - page 8 of 37
...a
_ _ _.. _.. _ _ _ _ _ _ _ - _ _ _ _. _ _. ~ _ _ _ _ _
Rev. 9 EELIEL.EEWEELVE 6 1.
V.nlya_Rumbe.r 1518926 2S!8926 2.
HwttheI_nL1 Lema:
2 3.
ASME Code Categ21yt C 4.
ASME_Cndo _Se.clis LXLRequit.ements Exercise for operability (Ct) of check valves every 3 months, per IWV-3521.
5.
!) Asis _.Ior_RelieI Full stroke exercising of the Safety Injection pump suction check valves, 1818926 and 2S18926 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 partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
6.
AlltInnte Teati2g8 The-1818926 and 2SI6926 valves will be partial stroke tested during periodic inservice tests wit h the SI pumps in the recirculation mode.
Tull stroke exercising for the valves will be done during refueling outages as a minimum, but no more frequently than once per quarter.
7.
Jus 1111 cation:
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.
App.11 cable _ lime _ERI.is.d1 This relief is requested once per quarter'during the first inspection Interval.
9.
AppISXal_SlatunI i
a.-
Relief granted per SER 9/15/88.
b.
Relief granted per NRC Generic Letter 89-04.
c.
Rollef granted per SER 9/14/90.
(0095D/0035D/062590) 4.6 - page 9 of 37
. - -. -.. ~
Rov. 9 RELIEr.lE21ESLY.R-1
" DELETED "
Deleted relief request VR-7. ' Incorporated valvos fortnerly covered by VR-7 into VR-12 and VR-17.
Added maximum stroke times to the valve tables for all valves in VR-12 per EG & G request.
O x2 (Od 5D/0035D/002590) 4.6 - page 10 of 37
Rev. 9 EELLELREQUEST._YR-B 1.
Yalve_Mumbert ICC685 1CC9438 2CC9414 1CC9413A 1CC9486 2CC9416 1CC9414 2CC685 2CC9438 1CC9416 2CC9413A 2CC940J 2.
l{wnbeI_of_1tems :
12 i
3.
ASMLC. ode _ Int.egoLY A
4.
ASME. Cade.,_Section_XLiteguirements:
Exercise for operability (SL) of Category A and B valves every 3 months, per IWV-3411.
5.
Dosis_I9t_RelieIt Component-cooling water flow to the reactor coolant pumps is required at j
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 t rip.
6.
Alternate _Te.s ting:
These valves will be exercised during cold shutdown, provided all-of the reactor coolant pumps are not in operation.
This testing period will be cach refaeling outage as a minimum, but no more frequently than once per quarter.
-Check valves 1/2CC9486 will be back flow tested (Bt) closed on the same frequency as the sent leakage test per INV-3420.
This frequency is at least once por two years, to be performed during reactor refueling outages.
7.- Juntification:
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.
i Stroke exercising check valves 1/2009486 on the same schedule as their leak rate testing will adequately maintain the system in a state of-
)
operational readiness without causing unnecessary personnel radiation exposure or possible damage to the Reactor Coolant pumps.
D.
Applicable _ Time _Periodt This relief is requested once per quarter during the first inspection
~ interval.
i I
9.
ApproYDLSint.us t a.
Relief granted por SER 9/15/88.
b.
Rellef granted per NRC Generic Letter 89-04.
c.
Relief granted per SER 9/14/90.
(0095D/0035D/062590) 4.6 - page 11 of 37
... ~.
.. _. - _... -..-.~
-~_ -.
Rov. 9 RELIELREQUESLYP.-9 1.
YalveJimnhet:
icv 8100 2Cv8100 ICV 8112 2CV8112 j
2.
Hwnber_oLitems :
4 i
i 3.
ASHE Code _Categcry A
4.
ASME_ Code t._S entionlLRe gn11eme nts :
Exercise for operability (SL) of Category A f. B valves every 3 months per IWV-3411.
!)enis_for._Eclief t These valves cannot be tested during unit operation as seal water flow to the reactor coolant pumps is required at all times shile t.he purnps are in operation.
Failure of one of these valves In t.he closed position during an exercise test would result in-scal water return flow being diverted to the PRT by lifting a rollet valvs upstream of the isolation valves.
6.
Alterante._.Te s ting these valves will be exercise tested during cold shutdown, providing all reactor coolant pumps are not in operation.
This testing period will be each refueling outage as-a minimum, but no more frequently than once per q ua r t.e r.
7.
dusillinatinnt 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.
5-f.pplicab.le_ Time..P.eriodit
.This relief is requested once per quarter during t.he first inspection interval.
L 9.
AppI93 AL.St.atus I a.
Rol19f granted per SER 9/15/88.
b.
Relief granted per NRC Generic Letter 89-04.
c.
Relief granted per SER 9/14/90.
- l -
l 1
(0095D/0035D/062590) 4.6 - page 12 of 37
- -. _ _. -,. - -. -. _ - - - - -. _. -. -.. -. -.. _... ~ -
Rev 9 RELIEL RWJESLYR-10 1.
Yalyr lumher:
11A006 21A066 11A065 2IA065 2.
IlumbcI of Itemal 4
3.
AStf.IoJit_CaltanLy :
A 4.
ASME_Cndea Sectinn_XLlestuluments :
Exercise for operability (St and Ft) of category A and B valves every 3 months per IWV-3411, 5.
Du1Ln fox RnLLLLs Stroke testing of these valves during plant operation or cold shutdown would, by design, isolate the air operated instruments and' valves inside the containment building.
6.
AltRLnnteltiLingi These valves will be exercised during refueling outages.
This testing period will be each refueling outage as a minimum, but no more frequently than once per quarter.
7.
Jnatification:
The full stroke exercising of the instrument air containment isolation valves during unit power operations or cold shutdowns, introduces the possibility cf causing major operating perturbations and/or personnel safaty concerns should these valves fall to re-open during testing actavities.
Thf failure of these valves in the closed posir'on, as a result of testing activities during plant operation or cold shutdown, would subsequently isolate the air operated instruments and valves inside the containment building thus resulting in one or more of the following scenarios:
A.
Loss oC Pressuriter Pressure Control The pressurizer spray valves 1/2 RY455B & C and the pressurizer auxiliary spray valve 1/2 CVB145 would fall closed and not be available for pressuriser pressure control.
(0095D/0035D/062590) 4.6 - page 13 of 37
Rev. 9 EELIEr_EEQUESIJIR 10 r
D.
Loss of Chemical Volume Control System Letdown Flow (both normal and excess) cnd Charging Flow -
\\.
J The loss of instrument air would cause a disruption.in the unit letdown flow paths resulting in pressurizer level increases.
Such valves as the.etdown ortrice containment outlet header Isolation vt41ve 1/2 CV81e % the letdown line Isolation valves 1/2 CV459 and 1/2 CV460, the lott wn netfice outlet isolation valves 1/2 CV8i49 A, D&
C, the excess letdwon heat exchanger inlet isolation valvet 32 CV8153A & B, ar.d the regen heat exchanger letdown inlet isolation valves 1/2 CV8389 A & B would go to their fall closed positiona.
Additionally, the ability to normally make up reactor coolant inventory and adjust the reactor chemien1 shim (i.e. normal borntion/ dilution) would also be lost as the regenerative heat
[-
exchanger inlet isolation valves 1/2 CV8324 A & B would fall to their resp,ctive closed positions.
C.
Loss of Component Cooling to Containment penetrations -
L The loss of instrument 71c supply would cause the penetration cooling supply flow control valve 1/2 CC053 to go to its fall closed position. The loss of penetration cooling would result in claiated temperatures being imposed on the penetrations being supported by the component cooling system.
D.
Loss of Personnel Dreathing Air -
The loss of Instrument air supply to the service air downstream Asogetion valve 1/2 SA033 would cause this valve to go to its fr.11 closed position. This loss of service air in the containment hullding weald eliminate the normal source of supplied breathing air needed to JL support numerous maintenance and component inspection activit'is in a contaminated radiologien1 environment.
8.
App 11Cnhle Time Periodt Thli relief is regrested once e quarter during the first inspection-interval.
9.
ApprQNAl_fiLatusI a.
Rollef denied por SER 9/15/88.
b.
Revised (to address NRC concerns) in Dyrea response to SER 12/16/88 (Dyron Station Letter 88-1321).
c.
Hellef granted per SER 9/14/90.
(009:0/0035D/062590) 4.0 - page 14 of 37 i
l
Rev. 9:
RELIELELGIESLY1L_11 -
" DELETED "
Deleted telle ' request VR-11 per EO & G recomtnendation. Thin.was a request for extx ;.1 -n of position indication tests f rom every two years to every three y' t-e (0095D/0035D/062590)'
4,6 - page 15 of 37
Rev. 9 RELIEL RE00ES2_VI-12 i
1.
Valye_1(Anber.:
Valves that normally stroke in 2 seconds or less YALVI_1 YAWE_1 YALYIl YALYEl 1MS018A-D 2MS018A-D IPR 066; 2PR066 1RE9157 2RE9157 1PS228A, B 2PS228A, B 1RE9159A, B 2RE9159A,B l
1PS229A, B 2PS224A, B 1RE9160A, B 2RE9160A, B IPS230A, B 2PS230A, B 1RY8033 2RYB033 1RC014A D 2PC014A-D 1S18871 2SI8871 2SD002A-H 2.
Ilumber_o LI1can:
52
-3.
ASME._Codo. Category: ' A&B 4
ASME_ Cad _e d ne. ion XI Requirements:
Veritication, by trending of power operated valve tiines, that an increase in strok. tir e of 50% or more, from the previous test, does not occur, per IWV-3417(a).
5.
Itasla_for_ Relief:
Minor timing inaccuracies, with small stroke times can lead to substantial increason (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 time.
If the accuracy requirements of IWV-3413(b) are utilised, 1, 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%.
(0095D/003SD/062590; 4.6 - page 16 of 37
Rev. 9 6.
niinInnttLIts. Ling:
Tast acting valves can be-defined as those valves that normally stroke in 2 seconds or less. No trending of stroke time will be required, and upon exceeding 2 seconds, corrective action shall be taken immediately in accordance with IWV-3417(b).
7.
JRuLiLLcnLkuns for small stroke times, the trending requ2rements are too stringent for the accuracles specifled in the Code. The alternative specified will edequately maintain the system in a stato of operational readiness, while not imposing undue hardships or sacrificing the safety of-the plans.
~
8.
App 111ablell1DA_far.10d This roller is requested once per quarter, during the first inspection interval.
9.
ApprDYDl_StatuR8 a.
. Relief denied per SER 9/15/88.
b.-
Revised' (to address N'tC concerns) in Dyron response to SER 12/16/88 (Dyron Station Letter 88-1321).
c.
Relief granted per SER 9/14/90.
5 4
(0095D/0035D/062590)=
4.6 - page 17 of 37
Rev. 9 RELlELEE01IEET_YlL-11 1.
Valve Numhttsi 1DG5182A,B 2DG5182A,B IDG5183A,B 2DG5183A,B IDG5184A,B 2DG5104A,D 1DG5185A,B 2DG5185A,B e.
Nilmhet_of Itemst 16 3.
ASME. Code _Cn11gntyl-B&C 4.
ASME._Cgdg.,Jection XI Regiti.LemenLE1 These. valves are not within the scope of ASME Code,Section XI, Subsection IRV requirements.
However, the requirements for stroke timing and trending of the valves associated with the Diesel Air Start System are being mandated by the NRC as an augmented testing requirement pursuant to 10CFR50.55 (a) (g).
Therefore, valves associated with the Diesel Air Start System shall be exorcised to the position required to fulfill their function during plant operation per INV-3412 and IWV-3522.
Additionally, the stroke testing of power operated valves shall be measured to the nearest second and such stroke times trended to document continued valve operational readiness per INV 3413 (b) and INV-3417.
5.~
IIDA12_for_KelitLL The monthly Diesel Generator testing program, outlined in Byron Station's Technien1' Specifications and implemented by station operating,.rocedures, exceeds the intent of the quarterly valve testing program which would be required by ASME Code,Section XI.
Additionally, the stroke timing of solenoid operated valves associated with the Diesel Air Start System is impractical due to the fast actuation of these valves.
j 6.
AlteInnttLI.catingi The performance of Byron Station's Diesel Generator operability monthly nurveillance will verify the operational readiness of the valves associated with the Diesel Air Start System.
I.'
This surveillance testang will require the recording of the air pressures contained in both trains A & B of the Diesel Generator Air Start Receiver Tanks both before and immediately after diesel generator start.
By the comparison of these valves between trains, the satisfactory operation of the power operated and self-actuated check valves associated with the Diesel Air Start System can be adequately demonstrated.
-(0095D/0035D/062590) 4.6 -- page 18 of 37
Rev. 9.
7.
Jun.Lif1catictat Proper valve operation will be demonstrated on a monthly basis by the verification of diesel. generator air start capability.
Such verification wlll-compare the air pressures contained in the receiver t.anks both before and_after the diesel generator start, thus verifying the-operability of' the air start control valves. The proposed testing methodology at the increased frequency satisfies the intent of the Gection XI requirements without pasing undue hardships or difficulties.
- 8.. Applicahla_Ilme Perlof1I.
b This relief is requested once per quarter d*tring the first inspection interval.
- 9.. AppInYnLStatus a.
Relief granted per SER 9/15/88.
b.
Relief grunted NRC Ceneric Letter 89-04.
c.
Rellef granted per SER 9/14/90.
(0095D/0035D/062590) 4.6 - page 19 of 37
Rev. 9 RELICE BEDURSLVR.14
" DELETED "
Deleted relief request VR-14.
This was a request for exemption for position Indienting_ tests for solenoid operated valves.
Alternate testing allowed by the ASME Code will be'uned instead.
1 h
a (0095D/0035D/062590) 4.6 - page 20 cf 37
Rev. 9
't RE!,IEC..REQUESI_YR-15 1.-
VAlVD_ Number 11 1CV8481A, B 2CV8481A, B ICV 8546 2CV8546 1818815 2SI8815 ISI8819A-D 2SI8819A-D ISIB841A,B 2SJ4841A,8 1 SIB 900A-D 2 SIB 900A-D ISI8905A-D 2SI8905A.D ISI8949A-D 2SI8949A-D 2.
Ilumber_nL1ttlics1 44 3.
ASME_ Code _ Category.t AC 4.
ASME_ Code 2Jiec11on_XL Req uiteIne ntal Check valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroko exercised during cold shutdowns per INV-3412 and IWV-3522.
5.
Dasis for.Relin[1 The full stroke exercising of check valves not stroked quarterly in required to be performed during cold shutdowns.
Iloweve r, the stroking of check valves 1(2) SIB 815, 1(2) SIB 900A-D, 1(2) SIB 949A-D, and 1(2) SIB 841A-B, associated with Emergency' Core Cooling System, during cold shutdowns will induce thermal stresses on their respective reactor vessel nozzles as the heactor Coolant System (maintained approximately 180* F) is injected with water from the Refueling Water Storage Tank (maintained approximately 65' F.
This also applies to the stroking of check valves 1(2)CV8546 and 1(2)CV8481A,B because the full stroke of these check valvos causes stroking of 1(2)SI8815 and 1(2)SI8900A-D located in the full flow path.
Additionally, Byron Station Technical Specifications require all Safety Injection Pumps and all but one Charging Pump to be inoperable during Modes 4, 5, and 6, except when the reactor vessel head is removed.
This requirement minimizes the possibility of low temperature over-pressurization of the Reactor Coolant System. Therefore, check valves 1(2) SIB 819A-D, 1(2) SIB 905A-D, and 1(2) SIB 749A-D, cannot be full streke exercised during routine Mode.5 cold shutdowns as required by IWV-3412 and IWV-T
'2.
In addition to the stroke test exercise uced to verify operational readiness of these check valves, the act of such stroking cause the necessity for Technical Specification required leak rate testing of these valves prior to unit criticality. This testing, in conjunction with the stroke exercising of these check valves, adds approximately one week to the duration of any outage and additional radiation exposure to workers who must connect flowmeters and differential pressure gauges directly to pipes containing radioactive fluids.
(0095D/0035D/062590) 4.6 - page 21 of 37
[
Rev. 9 i
Allt.f.DCLLL1 cit 1Rgl.
6.
Byron Station's Technical Specifications require routine leak rate testing to be performed on these Reactor Coolant System Boundary Isolation check valves if the unit is in Cold Shutdown for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and such leak rate testing has not been performed within the previous nine months.
Therefore, Byron Station will stroke exercise check valves 1(2) SIB 815, 1(2)SI6900A-D, and 1(2)SI8841 A,B on the same schedule. To prevent unnecessary stroking of check valves 1(2) SIBS 15 and 1(2)SI6900A-D, check valves 1(2)CV8546 and 1(2)CV8481A,0 will be stroke exercised on the same schedule as check valves 1(2)S18815, 1(2)SI8900A-D and 1(2)S18841A,B.
Additionally, stroke exercising of check valves 1(2) SIB 819A-D, 1(2)CI8949A-D, and 1(2)SI8905A-D can only be safely performed in Mode 6 with the Reactor Vessel head removed.
Full stroke exercising of these check valves will be performed at a minimum f requency of once each refueling outage.
7.
dualificationi Stroke exercising the 1(2)CV8481A, B, 1(2)CV8546, and 1(2) SIB 815, 1(2)8900A-D, and 1(2) SIB 841A, U check valves on the same schedule as their required Technical Specification fioctor Coolant System Boundary Isolation leak rat.e testing will allow the coordination of testing activities without imposing additional check valve leak rate testing-requirements.
Such activity coordination will optimize testing efforts and resources while adequately maintainins the system in a state of operational readir " '. Valves 1(2) SIB 949A-D 1(2)SI8905A-D and 1(2) SIB 829A-D ca:
Se stroked h-
.g c)1c shutdown without exceeding Technical Speciff
. limiting cor.wition for operation (LCO 2/J31,11 Since stroking these valves requires starting an SI pump.
Stroke exercising check valves 1(2)S18819A-D, 1(2)SI8905A-D and 1(2)SI8949A-D at leaut once per Reactor Refueling mode of operation, will insure compliance with Byron Station technical Specifications and minimize the possibility or low temperature over-pressurization of the reactor Coolant System.
8.
Applicabls_ lime _ferioAL This rel.af is requested once per quarter during the first inspection interval.
9.
hypIDYAl_ELnLunt I
a.
Rollef granted per SER 9/15/88 for valves 1/2SI8819A-D, 1/2SI8905A-D, and 1/2 SIB 949A-Di relief denied per SER 9/15/88 for valves 1/2S18815,
-1/2818841A-D, 1/2 SIB 900A-D.
b.
Revised (to address NRC concerns) in Byron response to SER 12/16/90
vron Station Letter 88-1321).
.lef granted per NRC Generic Letter 89-04.
c, d.
Hellef granted per SER 9/14/90.
l l
(0095D/0035D/062590) 4.6 - page 22 of 37
Rev. 9 EELLCL.EEQUEST _VR-16 1.
Yalve_Ruraltef11 ISI8811A, B 2SI8811A, B 2.
Ruroben.0 L En1_vril 4 3.-
ASME Codal ategpIy1 B 4.
ASME Code.Section XI RegniImmental Valves that cannot be exercised during plant operation shall be specifically identitled by the owner and shall be full stroke exercised during cold shutdowns per INV-3412.
5.
Dasia_for.RelinLt The full stroke exercluing of valves not stroked quarterly is required to be performed curing cold shutdowns.
However, the stroking of the Containment Snip. Outlet Isolation valves, 1/2SI8811A,D requires the suction of the 3esidual Heat Removal pumps to be drained, thus rendering one train of the ayatem inoperable.
-for Cold Shutdown operations with the Reactor Coolant Loops filled and one train of Resid'2a1 Heat Removal declared twoperable, Byron Station's Technical 5pacifications require two steam generators with a secondary side narrow range water 'e
-1 greater than 41% (Unit 1) and greater than 18%-(Unit 2).-
However, if the cold shutdown was necesaltated by a problem requiring draining of-the secondary ride of the steam Generators (1,0.
Lube leaks), Dyron Station's Technical Specification 3.4.1.4.1 would preclude the testing of the containment sump outlet isolation valves until such timo as the affected steam generators had been refilled.
For Cold Shutdown operations with the Reactor Coolant Loops not Ellied (i.e. drained down to support Reactor Vessel Incore Seal Table, Loop.Stop Valve, Ronctor 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_bo_ operable and at leest one RHR Loop shall be in operation.
6.
Alteranta_Jeating1 Dyron Station will full stroke exercise the Containment Sump Outlet
~
Iso'.ation Valves., 1/2SI8811A, B during refueling outages vice cold shutdown.
(0095D/003SD/062590) 4.6 - page 23 of 37
Rev. 9 7.-
JuSLi[1Calion!
The full stroke testing of the 1/2SI8011A, B valves; in conjunction with system draining, filling and venting or each train, accounts for an additional six days (3 days per trair
~f reheduling requirements and increased radiation doce to operatet diological control personnel.
processing of thousands of gallons ateoinated water, and subsequent required liquid effluent discharge uld also result f rom the drainite..
refilling and venting of the RHR s; This time duration required to perform the surveillance testing of ao Containment Sump Outlet Isolation Valves during Cold Shutdown activities, could, as a result, cause a violation of the action requirements for Byron Station's Technical specifications 3.4.1.4.1 and 3.4.1.4.2.
The violations would occur since these action statemeias require (as noted in thair respective foot note sections) the return of the inoperable residual heat removal loop to service within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, if such loop was removed for surveillance testing provided the other RHR Loop is operable and in operation.
In addition, NRC Generic Letter 80-17, 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 entrainment, and the other train is inoperable for the stroke test, then the " operable" train must be vented to restore decay heat removal. Under ynIAL conditiona, boiling in the core would occur in approximately 10 minutes, the core would be uncovered in approximately 30 minutes, and fuel damage would occur in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Given the apparent disparity between the Technical Specification time requirements for an inoperable RHR Loop return to service (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and the time required to perform surveillance stroke testing of the Containment Sump outlet Isolation valves (3 days) during Cold Shutdown, the proposed alternate testing frequency of refueling outage periodicity will adequately maintain the system in a state of operational readiness, while not imposing unduo hardships or sacrificing the safety of the plant.
B.
Applica!11c_Tima_Patindi This relief is requested once per quarter, during the first inspection interval.
9.
AppIDXalltatun t a.
Relief denied per SER 9/15/88.
b.
Revised (to addrens HRC concerns) in Byron response to SER 12/16/90.
c.
Relief granted per SER 9/14/90.
(0095D/0035D/062590) 4.6 - page 24 of 37
_- _. ~.
Rev. 9 EELIEr_EROUIS1.Y1L-11 1.
Y_nlyLl{umbetit ISX101A 2SX101A 2.
Hivnher_nf Valveit 2 3.
ASMLCode._ Cat.egoIy1 B 4.
ASHE_CadenS ection_X13equit ertental Stroke t1me and trend the stroke time for power operated valves per IWV-3413 and IWV-3417.
5.
Ilnsla_19.I_Re11e f i 1/2SX101A are the essential service water outlet isolation valves for the Unit 1/2 motor' driven auxiliary feedwater pump lube oil coolers.
These velves are completely encapsulated per design and do not have local or remote position Indicators which could be used to time the valve stroke.
6.
Alternate _ Ten _tingi 1/2SX101A will be verified to open during each quarterly ASME surveillance of the motor driven auxiliary feedwater pumps.
In addition, these valves are stroked monthly during auxillary feedwater pump surveillances required by Dyron Station Technical Specifications.
7 JnatificAtloni These valves will be stroke exercised to their required safety 1.,1tions each month during the-mot.or driven aux 111ary feedwater ptunp nurveillancen. This testing will adequately maintain the system in'a-state of operational readiness, while not sacrif'cing the safety of the plant.
a.
Applicabin_.Ilme_ P.ello.d.t This reller is' requested once per quarter during the first inspect.lon interval.
9.
APPI_oYDlltatus n.
Relief granted per SER 9/15/88.
b.
Relief granted per NRC Generic Letter 89-04.
c.
Rollef grunted per SER 9/14/90.
(0095D/0035D/062590) 4.6 - page 25 of 37
-~ ~
.. ~.
Rev. 9 RELIELREQUESLVE-lB 1.
YA1.ve NumbeIA:
See Table below:
2.
Rumbsr_Qi_YAlyns :
106 3.
ASME._ Code._Ca.tegor.y :
AC and C 4.
ASME_C9fle t_S e atinalL?aquir ement Exorcice for operability of check valves every three (3) months, per 1NV-3521.
5.
Ensin._191_RelinI t The valves listed in the Table below cannot be safely full-stroke exercised (Ct) open and/or back-flow tested (Dt) closed during plant operation or cold shutdowns, as required by the ASME Code. NRC Generic Letter 89-04, Attachment 1, Positions 1, 2, and 3 provide guidelines for method and frequency of testing check valves.
This request for relief in order to test these valves during refueling outages follows the guidelines set forth in NRC Generic Letter 89-04.
6.
Altariate._Inating Refer to the T951e below for a list of valves, direction, and alternate testing frequency requested:
ALTERNATE VALVES DIRECTION TESTING rREgugECL_
1/2AF001A,B Close Note 3 1/2CC9486 Close/Open Note 1/ Note 3 1/2CC9518 Close/Open Note 1/ Note 1 1/2CC9534 Close Note 1 1/2CS008A,B Close Note 3-1/ 2 CV 8113 Close/Open Note 1/ Note 1 1/2IA091 Close Note 1 1/2PR002G,H Close Note 1 1/2PR032 Close Note 1 1/2PS231A,B Close Note 1 1/2RH87tfA,B Close/Open Hote2/ Note 5 1/2RY8046 Close Note 1 1/2RY8047 Close Note 1 1/2SI8815 Close Note 2 1/2SI8818A-D Close Note 2 1/2 SIB 819A-D Close Note 2 1/2SI8841A,B Close Note 2 1/2SI8900A-D Close Note 2 1/2 SIB 905A-D Close Note 2 1/2SI8948A-D Close Note 2 1/2SI8949A-D Close Note 2 1/2SI8956A-D Close Note 2 1/2SI8968 Close Note 1 1/2WM191 Close Note 1 1L2hDQQ1L.B...
C19Be M9.te 1 (0095D/0035D/062590) 4.6 - page 26 of 37
Rev. 9 Table Notes:
.1)
Perform test during ref ueling outages in conjunction with Appendix J, Local Leak Rate Test.
See IST Program Relief Request VR-1.
- 2) Perform test during refueling outages in conjunction with Byron Station Technical Specification seat leakage testing.
See IST Program Note 6.
- 3) Perform test during refueling outages by sample disassembly and inspection in accordance with NRC Generic Letter 89-04.
See IST Program Relief Request VR-19.
- 4) See IST Program Relief Requests VR-2, VR-3, VR-4, VR-5, VR-6, VR-8, and VR-15 for additional : heck valve testing frequency extensions.
- 5) There valves are verified to oe operable by observation of depressurizatina li. the eppiscable line. This is a test method.hich was approved by the NRC in SER 9/14/90.
7.
JucLLLLcnLkons Testing these check valves on the same schedule as their required seat leakage tests will allow for coordination of testing activities without imposing additional check valve leak rate testing requirements.
Such a
tvity coordination will optimize testing efforts and resources while a&quately maintaining the system in-a state of operational readiness.
This frequency will also minimize personnel exposure to radiation by minimizing the amount of work performed inside containment during power operations. Testing of 1/2AF001A,B (close), 1/2CS008A,B (close), and 1/2RH8705A~B (open) can only be performed by disassembly and inspection due t'o system design and operating constraints.
These tests can on'y be safely performed during refueling outages when the affected syster are isolated and drained.
8.
APD11CDblR_Hri.lgriodt This relief is requested once per quarter during the first inspection interval.
9.
AppID_YAl Status a.
Relief granted per NRC Generic Letter 89-04.
(0095D/0035D/062590) 4.6 - page 27 of 37 l'
Rev. 9-RELIELBEWEST_YR-19 1.
y_alyr_llumbcIA :
1Ar001A,B 2AT001A,D ICS003A,8 2CS003A,D 1CS000A,8 2CS008A,B ICS020A,D 2CS020A,B 2.
Hwnbyr ni_Yelyts:
16 3.
ASME_C9dc_Cnic. gory :
AC and C 4.
AStiE_C.O.dn,Section XI RequiremCAtt Exercise check valves to the position required to fulfill their function (open = Ct; closed = Ut), unless such operation is not practical during plant operation, per IWV-3522.
5.
Unalador_helief:
These check valves cannot be full-stroked exorcised (CL) using NRC Generic Letter 89-04, Attachment 1, position 1, because the " maximum required accident flow" cannot be passed through the CC, CS, and Ril valves and a backflow test (BL) cannot be performed on the AT valves.
These tests cannot'be performed due to system design and operation configurations.
6.
AltcInnte Testing:
These valves will be selected for sample disassembly and inspection by choosing one valve from each of the groups listed below during each refueling outage. Normally, valves selected for disassembly will be alternated such that a different train is inspected each outage.
_ GROUP DIRECTION V ALVIS.....
1 Closed 1/2AF001A,D 2
Open 1/2CS003A,D 3
Open/ Closed 1/2CS008A,B 4_
Open 142.CSQ10A,3 Each valve will be manually stroked when disassembled, to verify the valve is capable of stroking acceptably in both directions.
Each valve will receive an internal visual inspection to insure that the valve is ntructurally sound (no loose or corroded parts).
If the disassembled valve is not capable of being manually stroked or there
'is binding or failure of valvo internals, the remaining valves in the same group on the affected ut.it will bn disonsembled and inspected during the same refuel outage, and the unaffected unit valves in the same group shall
.be disassembled and inspected at the next scheduled refueling outage.
(0095D/0035D/062590) 4.6 - page 28 of 37
Rev. 9 Extension of.the valve dlsassembly and inspection interval must meet the extension justification renuirements of NRC Generic Letter 89-04,, Position 2.
Note that relief from CS System check-vnive testing has previously been approved by Re31of Requests VR-2 and VR-4, but are included in this relief request due to the addition of sampling groups.
Also reference Section
- 4. 5, IST Technical Approach and Position VA-03, which describes Byron Station's position on check valve test.ing.
7.
Jua_tlIlcation:
This alternative testing is in compliance with specific guidance on check valve testing as required by HRC Generic Letter 89-04, Attachment 1, Positions 1, 2,
and 3.
This testing will adequately maintain the components in a state of operational readiness and, by testing the valves
'during refuel outages when '.he valves can be safely examined, will not sacrifice the smtaty of the plant.
8.
Dplicable_Il M Il04:
This relief is requested once per quarter during the first inspection interval.
9.
AppInY.Al_ItCLLus I a.
Relief granted per NRC Generic Letter 89-04.
6
(
l t
l (0095D/0035D/062590) 4.6 - page 29 of 37
e Rev. 9 1
l DRAFT
-RELIEF REQUEST VR-20
)
1.
Yalve_Mumhets:
1/2AF000A 1/2CV8116 1/2PS9357A,B 1/2518813 1/2AF006B 1/2CV8152 1/2RE1003 1/2818814 1/2AF01JA-H 1/2CV8160 1/2RE9170 1/2818821A,B 1/2AF017A,B 1/2CV8804A 1/2RF026 1/2818835 1/2CC685 1/2FP010 1/2RF027 1/2SF8840 1/2CC9412A,B 1/2FWOO9A-D 1/2RH8701A,B 1/2818880 1/2CC9413A 1/2FWO35A-D 1/2RHB702A,B 1/2818888 1/eCC9414 1/2FWO39A-D 1/2RY455A 1/2S18920 1/2CC9416 1/2FWO43A-D 1/2RY450 1/2S18924-1/2CC9437A,B 1/2IA065 1/2RYB000A,B 1/2 SIB 964-1/2CC9438 1/21A066 1/2RY8025 1/2SX016A,B 1/2CC9473A,B 1/2MS001A-D 1/2RY8026 1/2SX027A,B
.1/2CS001A,B 1/2MSt01A-D 1/2RY8020 1/2SX112A,0 1/2C6007A,B 1/200057A 1/2SA032 1/2CX114A,B 1/2CS000A,B 1/20G079 1/2SA033 1/2GX169A,B 1/2CS019A,B 1/2^G000 1SD002A-H 1/2SX173 1/2CV112D-E 11200001 1/2SD005A-D 1/2SX178 1/2CV8100 1/20G082 1/2SIBP31A,B 1/2V0001A,D 1/2/CV8104 1/20G083 1/2SI8bO2A,B 1/2V0002A,B 1/2CV8105 1/20G084 1/2818804B 1/2V0003 1/2CV8106 1/20G085 1/2SI6806 1/2V0004A,B 1/2CV8110 1/2PR001A,B 1/2SI8807A.B
'1/2VQ005A-C 1/2CV8111 1/2PS9354A,B 1/2 SIB 809A,B 1/2WOOO6A,B 1/2CV8112 1/3PS9355A,B 1/2SI8811A,B 1/2 WOO 20A,B 1/2CV8114 1/2PS9356A,8 1/2SI8812A,B 1/2 WOO 56A,B 2.
Number _pLitems:
340 3.
ASMEfcode Category:
A and B 4.
ASMLCada,_EcchionlLRnquitementa Verificatic' by trending of power-operated valve stroke t3mes, that an increase in stroke time of 25% or more from the previous test (for valves with full stroke times greater than 10 seconds), or 50% or more (for valves with full stroke times less than or eq0a1 to 10-seconds) does not occur, per IWV-3417(a).
5.
-Ensla_far-Rellefa Trending stroke times, based on the percent change from the preylqus test, an ASME Section XI requires, allows gradual degradation to occur over a long period of time without' triggering the additional trending attention l
that increased tenting frequency requires.
An improved method of component performance monitoring is proposed, which will equire 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,, Position 5.
I i
(0095D/0035D/062590) 4.6 - page 30 of 37 l
1.-
l Rev. 9
)
p.
I' DRAFT relit:F. REQUEST VR-20 L
6.
Alternate _Ienting:
L For all power-operated valves which normally stroke in greater than two seconds,.an ALERT RANGE will be established based en reaching a given porcent chango from the reference value established via NRC Generic Letter
'E 89-04.
The following table will be used as a starting point in evaluation of this fixed ALERT RANGE:
VALUE REFERENCb ALERT RANGE REQUIRED ACTION VALUE TYPE STPOKE TIME
___(ILeLL-MOV's i 10 sec.
(1.5)(Tret)-(2)(Tref)
> (2)(Tref)
SOV's HOV's
_h0V ' D_.
MOV's
> 10 sec.
(1.25)(Tref)-(1.75)(Tret)
> (1.75)(Tref),
SOV's or but 1 ('Iref + 20 sec) 110VitL IItcLtl.Q_aficl (ILcidO__.saci AOV's.
> 10 sec.
(1.5)(Tref)-(2)(T.ref)
> (2)(Trer),
or but 5. (Tref + 20 see)
.(IrrLt15 sec)-:(T.reLt10_ssa:1 Notest' A.
Fast acting vaivos (valyn which normaMy stroke in less than 2 coconds con:sittently) are included ~1n Relief Request VR-124 These valves are aqt ascigned AI.ERT RANGES and are nqt trended.
.D.
In bil cases, the REQUIRED ACTION VALUE cannot exceed i
Technical-Specification or UFSAR values, regardless of calculated values.
C.
The above Table -la a guideline and cannot cover all valves, The ALURT RANGES and REQUIRED ACTION VALUES are selected based on the comparison between the REFERENCE VALUE,.llmiting value.
9 ven in Technical SpecHi-ations/UFSAR, and calculated valueo 1
using the table abovel 1)
All values are ronaded to the nearest whvle. second.
- 2) Valves which serve the same. function on dual trains (i.e-,,
ICC9473A and 1CC94738) 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 alfferencen exist between the trains /uults.
f Refer to IST Technical Approach and Position VA-04 for related 8
information.
(00950/0035D/062590) 4.6 - puge 31 of 37
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Rev. 9 j
DRAFT RELIEF REQUEST VR-20 7.
J.uttificoLion Using fixed ALERT RANGES based on the valve REFERENCE VAhUE established when-the valve was known to be operating acceptably will onsure that gradual' valve performance degradation is monitored and evaluated, by placing the valve on increased testing frequency when the stroke time exceeds a fixed multiple of the REFERENCE VALUE. This met. hod is superior to that required by the ASME Code in that the point of reference used t.o evaluate the performance trend on a valve remains flxed.
This alternative
~
utilizes the same stroke time percentage change values as required by the ASME Code to place a valve on increased frequency testing, except. for air-operated valves, which fre.fuently exhibit fluctuating valve st.roke times.
3.
hW11 cal 21tJlmR_,l'AIlad:
This relief is request.ed once per quarter, during t.he first inspection interval.
O.
AppInyal E ntua Fince this relief _ request is a new submittal and is not specifically addressed in NRC Generic Letter 89-04, it is HQT opproved for use.
Formal written approval from the NRC.is required pIicI to implementation.
Lpeditious review and approval is requested.
d i
D
-(0095D/0035D/062590) 4.6 - page 32 of 37
~.
Rev. 9 DRAFT RELIEF REQUEST VR-21 "HITilDRAWH" This relief request was in draft form and was later-withdrawn per SER 9/14/90.
4 s
l l
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l (0095D/0035D/062590) 4.6 - page 33 of 37 i.
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Rev. 9-INTERIM RELIEF REQUEST VR-22 1.
Yalvajiumherai 1/2S!8818A 1/2SI8940A 1/2SI8841A 1/2S18818D 1/2818948B 1/2S18841D 1/2SI8818C 1/2 SIB 948C 1/2 SIB 818D 1/2 SIB 948D 2.
Ilumber_0Litems :
20 3.
ASME_ Code _ Category:
AC 4.
ASt@_Cnde. Section_KI_Requirementa Exercise check valves to the position required to fulfill their function (open = Cts closed = DL), unless such operation is not practical during plant operations, per INV-3522.
Dyron Station's testing methodology meets this regulrement.
However, NRC Generic Letter 89-04, Attachment 1, Position 1 requires that the flow through Individual valves be known, and specifically states that knowledge of total flow through multiple lines does not provide verification of flow rates through the Individual valves and is not a valid full-stroke exercise.
- 5.. Itasis..LoI_Rolief The current Dyron Station testing methodology uses available flowmeters to measure the total flow through two parallel check valves. These are given below C11ECK_yA13ES FLOW INDICATIO.N.___.
ISI8818A & ISI8818D 1FI - 618 1 SIB 810H & 1 SIB 818C 1FI
-619 ISI8841A & 1SI8941D 1FI - 618 ISIB948A & ISI8948D 1FI - 618 q
... 1SIHiBILla._1S1H18C 1El Ji19 There is currently no method available to measure the flow rates through the individual check valves. Modifications to those lines to install flow measurement devices for the individun1 valves is not warranted due to the following reasons:
A.
Flow indications exist for each pal'r of check valves.
It would be readily apparent from the flowrotes recorde. during each refuel outago if. individual check valves were not opening or weto only partially opening by comparing the flowrates recorded through each pair of check-valves.
D.
Dyron Station Technical Spec!'ications disregard the highest branch line flowrote when determining the minimum required flowrotes through these para' el injection lines. Therefore, slight differences in individur'. branch flowrates which could exist by measuring the total flowratu through two parallel injection lines was anticipated and accounted for when Byron Station's Technical SpecAfications were formulated.-
(0095D/0035D/062590) 4.6 - page 34 of 37
i Rev. 9 1
INTERIM RELIEF REQUEST VR-22 l
C.
Installation of individual injection line flow indicators would pose an increased safety hazard to operation of the plant due to installation of additional instrument lines, welds, and valves which are unisolatable from the Reactor Coolant System. This modification would increase the probability of small break LOCA's (due to pipe / weld / valve failures), forced outages (due to leaking valves / welds), and degradation of plant equipment (due to boric acid leaks).
D.
A modification to install such indications would be expensive, increase radiation dose, and possibly impact safe operation of the
-plant.
The modification would require extensive engineering and installation costs, along with replacement power ccsts, to install.
Dyron Station Technical Specifications require an ECCS full-flow balance test to b; performed as part of the modification test.
This test would extend outage durations and require a complete core offload to perform.
Several man-rem would be expended on each unit to install this modification. This modification would have to be installed during an outage by use of individual injection line freeze seals and/or complete core offload.
Both of these activities pose an increased safety hazard to plant personnel and equipment, by requiring unusual system alignments for extended parlods of time during a refuel outage when other activities-insido containment are at their hi host l
level.
The alternative to individual check valve flowrate measurement required by HRC Generic Letter 89-04 is disassembly and inspection.
Disassembly and inspection is r.ot a-vlable option for the EC"S Injection line check valves due to the following concernus A.
Radiation Doses' The radiation dose increase to disassemble, inspect, and reassemble those check valves each refuel outage would be several man-rem.
D.
Safe Operationt A total core offload and Reactor Coolant' System drain down or individual injection line freeze seals would be-required each outage in order to perform these inspections.
These actions place the plant in unusual operating line-ups for extended periods of time and decrease the availability of shutdown cooling options. These actions increase the probability of loss of residual heat removal capabilities by depending on freeze seals to isolate RCS branch connections during refueling outages.
i (G095D/0035D/062590) 4.6 - page 35 of 37 p
Rev, 9 INTERIM RELIET REQUEST VR-22 C.
Check Valve Operat3ng 1'd,.y A search of maintenance c Itory (TJM) on these valves for both Dyron and Dra14 wood Nuclear Power Stations revealed the following past maintt o activities on these check valves:
"SI8818A None
~B018D None du 818C None 1/2SI8818D None 1/2SI8841A Hone 1/2 SIB 841D None 1/2SI6948A None ISIB94BD Replaced disc arm assembly and gasket, retorqued
(
flange bolts 10/20/84 (Dyron) 2GIB94HB None 1SI894BC Inspected internals, no parts repaired or replaced, retorqued flange bolts 9/10/04 (Dyron) 2SI8948C None 1/2SI8948D None This history does not indicate any adverse operating history for these valves; therefore,-disassembly and inspection of-these valves is not warranted based on previous maintenance history.
6.
Alternallye Testing:
In lieu of disassembly, Dyron Station proposes the following tests (which are already being performed):
A.
A full stroke test of each check valvo is verified at least once per 18 months during refuel outages by verifying the total flow through each set of two parallel check valves utilizing existing permanently l'
innta]Ied flow indicators.
D.
A seat leakage test of each check valve is performed as required by Dyton Station's Technical Specification on RCS leakage. These leak tests are performed i
- 1) At least once/18 months, 2'
Prior to 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 /> and if leaktge testing has not been performed in the previous nine (9) months, 3)
Prior to returning the-valve to service following maintenance, repair, or replacemant work on the valve, and
- 4) 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 automatic or manual action or flow through the valve.
j.'
C.
An ECCS full flow balance test is performed following the completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics as required by Dyron Station Technical Specifications.
l (0095D/0035D/062590) 4.6 - page 36 of 37 l
Rev. 9 l
INTERIM RELIEF REQUEST V3-22 7.
JRatificatinn Dyron Statlon's Technical Specifications require these check valves to be full stroke tested and seat leakage tested at a minimum f requency of once per 18-months. These tests satisfy all of the ASME check valve exercise requirements (open and close) and all of the NRC G'-
'1 Letter 89-04 full-stroke and backflow testing requirements, except._at flow is measured through pairs of injection line check valves instead of Individual injection line check valves.
The burden imposed by either disassemb'ly and inspection or modification of these check valves to comply with the NRC Generic Letter 89-04 Individual flow measurement requirement is costly in terms of-capital expense, radiation dose, and possibly safe operation of the plant during refueling operations. This burden is unjustified, based on the f act that Byron Station has previously received a favorable Safety Evaluation Report (SER) on its Inservice Testing Program af ter years of in-depth review by the NRC.
Also,.it la readily apparent that Byron Station was not originally designed to allow for-either individual injection line flow measurement or for disassembly and inspection of the injection line check valves on a regular basis without extreme hardship on plant operations and maintenance during critical refueling outage periods.
The current testlug requirements of Byron Station Technical Specifications for these check valves will adequately monitor their performance and any future degradation, and maintain safe operation of the plant.
8.
Appilcabledime_hr.lods This relief is requested once per quarter during the first inspection interval.
l 9.
hEDIMYal_1thtun t a.-
Interim relief granted-for six (6) month period per SER 9/14/90.
l l-l.
('0095D/003 5D/062590 )
4.6 - page 37 of 37 Y
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