ML20024H404
| ML20024H404 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/23/1991 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20024H399 | List: |
| References | |
| PROC-910523-01, NUDOCS 9106030268 | |
| Download: ML20024H404 (163) | |
Text
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ENCLOSURE 3 b
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SECTION II.0 INSERVICE TESTING f
PROGRAM Pl_AN FOR VALVES O
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T Revision 10 O-IAllLE_.CLSWIEllIS s 0 Inservice Testing Program Pinn for Valvan 4.1 Program Description 4.2 Progr am Peterences 4.3 program Tables - Units 1 and 2 4.4 flotes Note 1 Main Steam Isolation Valvec Note 2 CV Emergency Doration System riowpath Vs1vas Note 3 Main reedwater Isolation Valves llote 4 CV System Letdown and Make-up Isolation Valves flote 5 RHR Pump Sortion isolation Valves Note 6 Intersystem LOCA Valves tiote 7 Reactor Vessel llend Vent Valves Note i CV, EllR rump Discharge Check Valves Note 9 RHR ECCS Check Valves Note 10 Main reedwatst Waterhammer Prevention Valves Note 11 VQ Purge Supply and Exhaust Isolation Valvom O-flote 12
?.T Suction and Stemn Generator Chec!. Yalven Note 13 CV High Head Injection Isolation Valves tiote 14 SVAU Valves Note 15 " Deleted" flote 16 Main reedwater Regulating Valves tiote 17 Hain reedwater Regulating Bypass Valves flo te 18 " Deleted" tiote 19 " Deleted" (Incorporated into Note 14)
Note 20 Position Indication Testing of Solenoid Valves flote 21 Main reedwater Tempering riow Isolation Valves Note 22 Hydrogen Monitoring System Check Valves Note 23 Event V Check Valves Note 24 Pressure Relief Check Valves Note 25 SI Pump Suction Check Valve (1/2 SIB 926)
Note 26 CV Pump Suction Check Valve ( 1/ 2 CV B 54 6 )
L Note 27 RH Pump suction Check Valves (1/2 SIB 95BA/B)
Note 28 VCT Outlet Check Valve (1/2.CV8440)
Note 29 Emergency Doration Check Valve (1/2 CVB442)
Note 30 AT Check Valve Leak Checks (1/2 Ar014A-H)
Note 31 CV/SI Mini-Flow Recirculation Line Check Valve full riow Testino (1/2 CV8480A/B and l
1/2 SIB 919A/D)
!! W 32 CC Pump Discharge Check Velves t1/2 CC9463A, 1/2 CC9463B, OCro46 4)
Note 33 SX Hake-Up Pump Dascharae Check Valves (OSX028A/B) tiote 34 SD Containment Isolation Valves (1/2 SD002A-H, O
1/2 SD005A-D)
Note 35 RH Containment Isolation Valves (1/2 RH B705A/B)
-(0092D/0034D/030491) 4.0 - page 1 of 2 I
l Hevision 10 4.5 Technical Approaches and Ponielons vu 01 Met ht.,t M M.oke Ti ning Valves VA-02 Method of rail Safe Testing Valves VA-03 Method of Exetcising Check Valves VA-04 Determining Limiting Values of full-St roke Times f or Power-Operated Valves.
(reference stroke time 110 seconds)
)
4.6 Relief Requests VR-1 Appendix J Valves VR-2 Containment Spray llaOH Additive Check Valves VR-1 Safety injection ECCS Check Valves VR-4 Containment Spray Discharge and Ring liender Check Valven VR-5 Accumulator Dischasue Check Valves Testing frequency VR-6 SI Pump Fuction Check Valve VR-7
" Deleted" (Incorporated into VR-12 and VR-17)
VR-B Component Couling RC Pump The mal Dartler Valves Ve-9 0" t' ump Seal In)*ction CV Check Valves
'!R-10 h.rtrument Air Contairrent Isolation Valves VR-11
" Deleted" (per EG r. O recommendation)
VR-12 Trendina 01 rast Actuating Valves VR-13 Diesel Generator Air Start Valves VR-14
" Deleted" (uning ASME method instead of requenting esemption from position indication testing of soledoid operated valves)
VR-15 Safety Injection ECCS Check Valve Testing during Refueling Outage VR-10 Containment Sump outlet Isolation Valve Testing During Refueling.
VR-17 Motor Driven Auxiliary feedwater Pump L.O. Cooler Solenold Valve Stroke Testing VR-18 Check Valve full Stroke (Ct) and Dack flow (Dt)
Testing During Refueling Outages.
VR-19 rull Stroke Valve Testing (Ct)- by Smple Disassembly and Inspection per NRC Generic Letter 89-04 Draft VR-20 Trending of Power-Operated Valve Stroke Times (reference stroke times >10 seconds)
VR-21
-Draft " Withdrawn" par SER 9/14/00
{-
Interim VR-22 Full-Stroke Check Wlve Testima (Ct/ Methodology for i
Safety Inia"tinn "alves.
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(0092D/0034D/030491) 4.0 - page 2 of 2 l
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SECTION 4.1 PROGRAM DESCRIPTION b
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T Pevision 10 ElG EAti E S2irllCil The Inservice Testing (IST) Pr og r am for Class 1, 2, 6 3 valvs meets the requirements of Subsection IWV of the ASME Section XI Code, 1983 Edition, through the Summer of 1983 Addenda. Where code requirements are determined to be impractical, specific tequests 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 progrmt revisions.
Byron Station received a Safety Evaluation Report (SER) on September 15, 1988 and is listed in Table 2 of NRC Generic Letter 09-04 as a plant with a reviewed IST Program and SER lesued.
Per URC Generic Letter 89-04, the status of relief requests as stated in the SER is unchanged.
Any modifications to Byron C ation relief requests approved in the SER (VR-1 through VR-17) which are covered by one of the eleven positions discussed in NRC Generic Letter 89-04, Attachment 1, must be performed in accordance with the guidelines given in the Generic Letter.
Pre-approval is granted for all relief requests submitted which ar e consistent with the eleven positions given.
New relief requests deallnq with a position n21 covered by HRC 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 tabl-is cruar,1.o1 according to operating system and listed in "elve number e-Ja* raing P&!D references to further categorize.
The valves subject to ISI testing are those valves which are identified in accordance with the scope of ASME Section XI, Subsection IWV-1100:
"This Subsection provides the rules and requirements for inservice testing to assess operational readiness of certain Class 1, 2, and-3 valves (and their actuating and, 91 tion indicating systems) in light-water cooled nuclea. power plants, which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of of an accident."
Enceptions to this scope are those val res which are exempt, but added to the program based on NRC mandates.
These valves are identitled in the program notes and relief requests.
After installation and prior to servlae, all valves identified in this program were tested as required by Subsection INV-3100 of Section XI of the ASME Code.
These tests were conducted under conditions similar to those to be experienced during subsequent inservice tests.
When a valve or its control system has been replaced or undervone maintenance l
that coul1 affect its performance, it will be retested prior to ita reture to service, to demonstrate the-all perf ormance par amete rs t.r e within acceptable limits, s
i 1
(0092D/0034D/030491) 4.1 - page 1 of 2
1 Revision 10 As required by NRC Generic Letter 89-04, Attachment 1,
Position 5, the I bn a t t a a value of tuja sei b.
+ 6a will be based on tha ja, reference on aver aw st rvke L laue of the valve when it is known to be in good condition and operating pinperly.
This limiting value is based ora a reasonable deviation from this reference stroke time based nn valve size, valve type, actuator type, system design, dual unit /duni train design, etc.
The deviation should not be so restrictive that it results in a valve being declared inoperable due to t easonable..' * :k time variations.
However, the deviation used to establish the l ii l t
(, A should be such that corrective action would be taken for a valve a.
may not perform its intended function.
New or additional referte.
V,3 4
values may be required ift ty) 1)
A valve has been rapinced,
- 2) When a reference value or set of values may have been f '.'.%
(k b affected by repair or routine servicing of a valve, or 3)
If it is necessary or desirable for some teason other
(;"
than 1) or 2) above.
' 's NRC Generic Letter 89-04, A t t a c tune n t 1, Positions 1-3 discuss full stroke, alternatives to full stroke, and backflow testing of check valves, tespectively.
A valid full stroke test is one in which verification of maximum required accident condition flow through the val /a 1. ebt=ined.
The minimum acceptable flow value for a sjecific valva detar*ined from Technical Specifications, UFSAP, m a'sul ac t e 'rs
(
data, engineering calculations, etc.
An alternative to fu'.1 stroke testing includes, but is not limited to, a snmple disnmuembly and inspection program of valves grouped by similarity of design (manufacturer, size, model numbe r, materials of construction, etc.) and service conditions (including valve orientation).
This sample disassembly and inspection program will be performed during refualing outages.
A backflow test verifles that the disc trsvels to the seat promptly on cessation or reversal of flow, for check valves which perform a safety function in the closed direction.
For category A/C check valves (valves that have a specified leak rate limit and are self-actuated in response to a system characteristic), the backt;ow test is satisfied by performing the lenk-rate test.
Per NRC Generic Letter 89-04, Attachment 1.
Position 98, whenever valve data is cetermined to be within the Requirad Action Range, the valve is inoperable, and the Technical Specification LCO Action Statement time ntarts.
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 ASMC Boiler and riennure Vossel Code c. h a l l not be construed to supersede the raquiremants n! tha Technical Specifications.
O (0092D/0034D/030491) 4.1 - page 2 of 2
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O SECTION II.2 PROGRAM REFERENCES O
O
Revision 10 f.BZIEAli_EITIBIUCIS 4.
Titao 10, Code of Faderal Regulations, Part 50, Domestic L. mensing of Production and Utilization racilities. particularly Section 50.,55a, Codes and Standards.
2.
ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1983 Edition, Summer 1983 Addenda.
3.
ASME/ ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants.
Including 1988 Addenda, Part 10, inservice Testing of Valves in Light Water Reactor Power Plants.
4.
U.
S. Nuclear Regulatory Commission. Generic Letter 89-04, Guidance on Devel ping Acceptable Inservice Testing Programs.
5.
Byron Station UFSAR, Section 3.9.6.2.
Inservice Testing of Valves.
6.
Byron Station Technical Specification 3/4.0.5, Generic ASME Program Requirement.
7.
Byron Station Technical Staff Procedure, BVP 200-2. ISI Requirements for Valves.
8.
NRC Safety Evaluation Reports (SER's):
a.
09/15/88 (Initial Program Plan Review) b.
09/14/90 (Supplemental Program Plan Review) c.
09/14/90 (Relief Requests VR-21 and VR-22 Review) 9.
Byron Station IST Valve Program Plan Responses (file 3.11.0240) a.
Byron Letter 88-1321 (Initial Program Plan Review Response)
- 10. Minutus of the Public Meetino on Generic Letter ng.n4. dated October 25, 19RQ, Question 40 O
(0092D/0034D/030491) 4.2 - page 1 of 1
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O SECTION 4.3 PROGRAM TABLES I
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Pevision 10 TAJLLD4kCKArl10fl The following information is included in the num ory tables:
A.
Efil$1211 The revision corresponds to the current revision of the program.
H.
EAGE The pages are numbered requentially and show the total number of tables.
'LbkV.LlMMDEE The valve number references the unique Dyson Station equipment piece number (EPN).
This specifit valve number identifies the unit and system.
D.
EklD The P&ID column ref erences the speci fic P&ID number which the valves are located on.
The Unit 2 P&ID number is given directly underneath the Unit 1 PhlD number.
E.
CLtd5 The class refers to the ASME class assigned to the specific valve.
P.
VlLVE CATECCEI The valve category identifies the valve category defined in subarticle IWV-2200 of ASME Section XI.
G.
VlLVE SIZE The valve size lists tha nominal t'i ra nita af aech
-alfa in inchas.
(0092D/0034D/030491) 4.3 - page 1 of S
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Revision 10 k
H.
VALVE TYPE The valve type catego. m-the valve as r )
l'-
ss)ve demign.
The following abbreviations will be used to identify rpectric vaava types Gate GA Globe GL Butterfly BTF Check CK Safety Valve SV Relief Valve RV Power Operated Relief Valve PORV Diaphragm Seated D
Plug P
Angle AN 1,
ACT. TYPE The actuator-type 1_dentifies the valve actuator.
The following abbrevictions will be used to designate specific types of valve actuatorst Motor Operated M.C.
Air Operated A. O Hydraulic Operated 11. 0.
e belf Actuated S.A.
Manual M
Solenoid Operated S.O.
J.
tlRRMAL POSITION Normal position identifies the normal operating position of a specific valve. Q for open and C for closed.
K.
STROKE DIRECT.
-The stroke direction identifies the direction the valve actuator moves a specific valve stem to place the valve disc in a position to perform its designed safety function.
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 oper. and closed position.
The valve will only be timed, however, in the direction designated pe t ic.o. '. i r, ta safety function.
'st e r e f o r e. the program pir.n scecifles only the direction in which "alves must be stroked to be timed.
O (0092D/0034D/030491) 4.3 - page 2 of 5
v Revision 10 Q
L.
IEST MEIll2D The *est metnM -coloar. Identifies spacific
- .17t-which will be re.!ormed on specific valves to fulfill the requirements of Subsection IWV of ASME Section XI.
The tests and abbreviations used are as follows:
1.
(Dt) Check Valve Back Flow Test The check valve disc will be exercised to the closed position required to fulfill its safety function by verifying that the diec 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 tert is satisfied by performing the leak rate test.
2.
ICt) Check Valve Full _ Stroke Test The check valve disc will be exercised to the open position required to fulfill its saf ety f unction by verif ying the maximum required accident flow through the valve or alternatives to full flow testing, per NRC Generic Letter 89-04, Attachment 1, Positions 1 and 2.
3.
JFt) Fall Safe Tgst Valves with f all safe actuators will be tested to verify the valve operator moves the valve stem to the required fail safe position upon loss of actuating power. In accordance with INV-3415.
This will be accomplished during the normal stroking of the valve.
Upon sttoking a valve to.its fall safe position, the solenoid operator is de-energized causing air to be vented which in turn allows the spring to move the valve to its fail safe position.
This condition simulates loss of actuating power (Electric and/or Air) and hence satisfies the fall safe test requirements of INV-3415.
4.
(It) Position Indication Cheri Valves which are identified to require a Position Indication Test will be inspected in accorf.ance with INV-3300 of ASME Section XI.
5.-
11t).Siat lea]utgt.lgit The sent itakage tests will maar i,he requirements of INV-3420 for Category A valves. On these "mivas, seat leakaae is limited to a specific maximum amount in the closed position f or f ulfillment of their safety function.
l 1
l (0092D/0034D/030491) 4.3 - page 3 of 5
m Revision 10
)
5.
iRt) Safety Valve Setp2 bit CltesA Sa f e t; val n n e t po i n '.J will be c! fice in accordane.e with INV-3510 of ASME dettion 41.
7 (St) Full _Sitske Test Valve exercising tests of Category A and B valves will be performed in accordance with INV-3410.
The test will include full stroke testing to verify operability in the direction required to fulfill the required safety function.
8.
(Kt) Part-Stroke Test If only limited operation is practical during plant operation, the valves shall be part-stroke (Xt) exercised during plant operation and full-stroke exercised during cold shutdowns, in accordance with IWV-3412 or IWV-3522.
M.
TEST MODE Denotes the frequency and plant condition necessary to perform a given test.
The fol'wwsng d.b eviations are usedt t{2, mal Operation (OP) s Tests designated "OP" will be performed once every 3 months, except in those modes in which the valve is not required to be operable.
Semiannual (S)
Tests with this designation will be conducted once every 6 months, except in those modes ir which the valve is not. required to be operable.
C22d Shutdown (CS)
Valves that cannot be operated during plant operation shall be full stroke exercised during cold shutdowns.
Valve testing will commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown, with completion of cold shutdown valve testing not being a prerequisite to plant startup.
Valve tests which are not completed during a cold shutdown, shall be completed during subsequent cold shutdowns to meet the Code Specified Testing frequency.
For planned shutdowns, where ample time is available, and testing all the valves identified for cold shutdown test frequency in the IST Program will be eccomplishad y r a n e ' :m s 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 tLutuowns.
a A /e testino need no* he performed more often than once unilag any thraa-mnnth period.
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l (0092D/0034D/030491) 4.3 - page 4 of 5
_-_______.___.__..__.___.___..-.m__
Fevision 10
- RCActSL_ERMLtllD2_LER1 Tests with this J;c'gnatien will Le % cted dur.ng tectivi # e f t.c a ing
. outages only.
t H.
EELLEE REQUESI Relief requests reference a specific request for relief from code requirements.
All relief requestc are included in Section 4.6.
L 0.
(LQTES tiotes provide a short explanation conrTrning a particular IST valve.
All notes are included in Section 4.4.
P.
TECig[1C,\\L APPROACHES AllD POS1ILQ115 Technical approaches and positions provide detailed discussions on a particular IST topic.
All technical approaches and positions are included in Section 4.5.
I 1
~0 REMARKS Remarks reference other information useful in determining valve testing requirements or methods.
r (0092D/0034D/030491) 4.3 - page 5 of 5
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SECTION 4.3 PROGRAM TABLES UNITS 1 AND 2 lO i
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INSERVICE TESTING PROGRAM g,,,
g'g COMMONWEALTH EDISON BYRON NUCLEAR POWER STATION l
VALVE l
l l VALVE l VALVE l VALVE l ACT. l NORMAL l STROKE l IEST l TEST l RELIEF l
l IECH. l l
l NUMBER l
P&lD l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION l DIRECT. l NETH00 l MODE l REQUEST l
NOTES i P05.
lRENARKS l l
1 1
I IJiu_1 1
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_1_xJL 1 3 l ___ l (00930/00400/030491) 4.1 - TAsd 1 & 42
O O
O INSERVICE TESTING PROGRAM Rev. 10 COMMONWEALTH EDISON SYRON 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
P510 l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION l DIRECT. IMETH00l N00E l REQUEST l
NOTES lP05. IREMARKS l I
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4.3 - TABLE 2 of 42
O O
O INSFRVICE TEST.% PROGRAN Rev. 10 COPNONWEALTH EDISCN BYRON NUCLEAR P0wER STATION l
VALVE l
i l VALVE l VALVE.l valve l ACT. l NORMAL l STROKE l IEST l IEST l RELIEF l
l iECH. l l
l NureER l
P&!G l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION lUIRECT. l METHOD l MODE l REQUEST l
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l REMARKS l l
l
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INSERVICE TESTING PROGRAM Rev. 10 C0rm0NWEALT1 EDISON BYRCN NUCLEAR P0wER STATION l
VALVE l
l l VALVE I VALVE l VALVE l ACT. l NORMAL l 5 ROKE i TEST l TEST l RELIEF l
l
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l l
l NUteER I
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_ _ _1 _ ___ l __ __ 1 _ _ __1 _ _.._ 1 (00930/00400/030491) 4.1 - I Aid. 4 of 44
O O
O INSERVICE TESTING PROGRAM Rev. 10 COMMONWEALTH EDISON BYRON NUCLEAR POWER STATI0rt l
VALVE l
l l VALVE l VALVE l VAlvt l ACT. l NORMAL l STRomE l TE57 l TEST l RELIEF l
l IECH. l l
l NUMBER l
P&ID l CLASS i CATEGORY l SIZE l TYPE l TYPE l POSITION l DIRECT. l Pf~rt00 l MODE l REQUEST l
NOTES l"O5.
l REMARK 5 l l
l 1
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1 (00930/00400/030491) 4 g-t a.tii t 5 or 12 a
O O
O INSERVICE TESTING PROGRAM Rev. 10 COMMONWEALTH EDISON BYRON NUCLEAR POWER STAi!ON l
VALVE l
l l VALVE l VALVE l vat.VE l ACT. j NORMAL j STROPE l TEST l IEST l RELIEF l
l IECH. l l
l NUPeER l
P1!D l CLASS l CATEGORY l SIZE l TYPE l TYPE l POSITION j DIRECT. l NETH00 l N00E l REQUEST l
NOTES l POS.
[ RENARAS l l
1 1
1
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1 i
i 1
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l l inCviize I s-64-4A l
2 l
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(00930/00400/030491)
- 4. 3 - I Ast : t2 of 42 J
O O
O INSERVICE TESTING PkOGRAM Rev. 10' COMMONWEAlili CSISON BYRON NUCLEAR P%G STATION l
VALVE I
l l VALVE l VAtt/E l VALVE l ACT. l NORnAL 5 'R OP.E l TEST l TEST. l RELIEF l
- ECH-l
.l l
NUPeER l
f@
l CLASS l. CATEGORY l SIZE jTYPE I TYPE I POSITION, PIRECT. I METHOD l MODE l REQUEST l
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SECTION 4.4 NOTES e
O O
Rev. 10 i
U2TE 1 l
Closure of the Main Steam isolation valves 1HS001A-D or 2MS001A-D during unit operatio...<u ld result in reactor tiip tiid nt ety 1"i-etie. e. t u a t i o n. To avoid this transient, these salves wil' bs pattially stroked every thre*
inonths.
Full stroke testing will be done during Modes 4, 5,
or 6 as plant conditions allow, per INV-3412, NOTE 2 The testing of any emergency boration flowpath valves during unit operation is not practical.
Stroke testing the Boric Acid injection isolation valve 1CV8104/2CV8104 and check valve ICV 8442/2CV84*2, the RH to CV pump suction isolation valve 1CV8804A/2CV8804A, or the FWST to CV pump suction isolation velves ICV 112D.E/2CV112D,E, could result in boration of the RCS, resulting in a cooldown transient.
Alloning the systera in this configuration even for a short duration is, therefore, unacceptable.
These valves will be stroke tested during cold shutdown. In accordance with IWV-3412.
MTE 1 These valves are the Hain Feedwater isolation valves:
1TWOO9A-D/2TWOO9A D.
and cannot be fully stroked dati..L te?rstion as feedwater would be terminated causing a reactor trip.
Thav wil' hn wa me r, be partially *troke tested during operation as well as full stroke tested during cold shutdown, per the requirements of IWV-3412.
NOTE 4 Closure of these letdown end makeup valves ICV 1128,C/2CV1128.C, ICV 8105/
2CV8105, 1CV8 A06/ 2CV8106, ICV 8152/2CV8152, and ICV 8160/2CV8160 during normal unit operation would cause a loss of charging flow which would result in a reactor coolant inventory transient, and possibly, a subsequent reactor trip.
These valves will be full stroke / fall safe exercised during cold shutdown as required by IWV-3412.
NOTE 5 The IRH8701A/B, 1RH8702A/B, 2RH8701A/B, and 2RH8702A/B valves are the isolation boundary between the Residual Heat Removal Pumps and the Reactor Coola.st 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 ir an undesirable condition.
Therefore. these valvas will be full stroke tested during cold shutdown, per IWV-3472.
I i
O i
l (0094D/0035D/030491) 4.4 - page-1 of.8
. - -,. ~ _ _. _ _. _ _ - _ - -. _ _. - -.... _ _ _... - _. - _. _.. _ _,. _.-. _. _, - _. -,.. -. _. -,. _,
Rev. 10 I
ti2IE t The following valven have tipen idont i f ied an int et system ICCA,' a l v e s.
They r - - re n orar9ure boundary betwee-4.*
R ' T, and other ast.* v i.1 mm p :. r e n' t ir nadar to protect these compontnts from damaue.
These valvee sila be leak toeted in accordance with t.he Pyron Technical Specifications.
Patt tmance of the leak 'est on these v '.es air.o natisfies the back-flow test tes'ared for check valves by flRC Genet ic Let ter 49-04.
Dyron Unit 1.snd tin i t 2 Intersystem LOCA Valves 1 R}{ 8 7 01 A / B IPil8 7 0 2 A / D 2 R}{8701 A/ B 2PflB702A B 1RH8705A/B IPH8705A/D 2 Ril B 7 0 ', A / B 2 PilR 7 05 A / B IS18818A-D 1518815 2 SIB 81RA-D 2518815 IS18H19A-D IS!890$A-D 2510R19A-D 2S18uosA-D ISIBR41A/D IS1894RA-D 2518841A/B 2 SIR 94RA-D ISIR400A-D IS!B940A.D
? SIR 900A-D 2 SIB 940A D ISIB9%A-D 2SIO956A-D llOTL2 The Reactor Pressure Vassel Vent "nives IPC014A-D and 2RC014A-D cannot be stroked during unit operation, as they provide a pressure boundary between the Reactor Coolant system and contairvnent a t.mo = phe r e.
Fr.ilu.e ;f one of these valves in the open position would result in le av li rt on:V e na- ".. ve as the high p r e r. n u r e Soundary.
These valves will be f u '.1 stroke / fall safe exercised when the RCS pressure is at a minimum during cold shutdown, per IW-3 412.
LiCIE 3 The Residual lie st Hemoval l' ump discharoe check valves IRilB730A/D and 2Ril8730A/B cannot be fv11 stroke exettised during unit operation due to the hiuh PCS pressure.
These check valves will be partial stroke tested, however, on a <1uarterly basis and full stroke exercised during cold shutdown.
This is in accordance with IWV-3522.
!!QIL.2 Due to the RCS pressure, the check /alves listed below cannot be full stroke exercised during unit operation:
1518818A-D 2S18818A D RilR Cold Leg Injection ISIB958A/B 2 SIR 958A/B RWST to RHR Pump Suction These valves will be full stroka e x e r c i s e.1 durina <old shut &wn, in accordance with IWV 1522.
(0094D/0035D/030491) t 4.4 - page 2 of 8
v l
Pev. 10
!!2If_12 The IrwolgA.D and 20WD39A-D /alves cannot be stroke tested during unit natc*ien as clonore et 'hese ives would result in <
m' nation of the uterheter t. d s v 4. G o n f t tedwat e r flow.
This would tasult in undesirable affects on the Steam Generators.
These valves will be full stroke / fall safe t asted dus inu cold *:hutdown, per iWV-3412.
H21L__ll The Ptimary Containment Purge Supply and Exhaust Valves IVQ001A/B, 170002A/B, 2VQ001A/B, and 2VQ002A/D cannot be stroke timed during unit operation. These 49-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 5 would be a violation of the Byron Technical Specifications.
These valves will be full stroke tested during cold shutdown, in accordance with IWV 1412.
These valves will be leek tested semiannually, in accordance with Byron Station Technical Specifications.
The Orimary Containment Mini-Purae and Exhaust Valves IVQOO4A/B, IVOOOSA/D/C, 2VQOO4A/B, and 2VOOO5A//B/C, and the Post LOCA Purge Exhaust Valves IVOOO3/
2VQOO3 will be leak tested every i months, in accordance with Dyron Station Technical Specifications.
MIL 12 The Auxiliary feedwater check valves 1Ar001A/D, lAr003A/B, lAr014A-H, IAr029A/P, 2Ar001A/B, 2Ar003A/B, 2Ar014A-H. and 2Ar029A/D cannot be full stroke tested during unit operation, as this would induce potentially damaging thermal stresses in the upper feedwater nortle piping.
The 1Ar001A/B, 1Ar003A/B, 2Ar001A/B, and 2Ar003A/B valves will be partially stroke tested during operation. and all valves full stroke tested during cold shutdown.
This will be performed per Tech Spec 4.7.1.2.2 and is in accordance with IWV-3522.
U2II_12 The liigh Head Injection Isolation Valves ISI8801A/B and 2 SIB 801A/D 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 regenetative heat exchanger.
The temperature difference of the charcing flow and the RCS could result in damaging thermal stresses to the cold leo nozzles as well as cause a teactivity chance which would. in turn. cause a plant transient These salves will be full stroke tested durino ;old shutdown in accordance with IWV-3412.
(0094D/0035D/030491) 4.4 - page 3 of 8
l l
j Pev. 10 i
VQIE_11 The safety injection system SVAG (Spurious 781ve Act uat ion Group)
.alves 151. ' < 3 / B, IS!8805, 191t' 8 0 0' / '4, 131 0 11 Illkd -
1 r ! '1 10, 2319802A/D.
2S18806, 2516809A,B, 2S48813,
.2'O s a:, ano 2S18840 cannot be stroke tested during unit operation.
These valves are required by the Technical Specifications to be de-energized in their proper positions during unit operation.
Stroking them would be a violation of the Technical Upecifications as well as defeating the de-enetuised SVAG /alve principle.
These valves will be stroke t asted during cold shutdown when t hey are not required to be de-energized.
This is in accordance with IWV-3412.
l!QIE_lk
' -DELETE."
RQIC_li These feedwater valves are exempt from all AGME 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 ITW510, IrW520, ITW530, 1FW540, 2rW510, 20W520, 2rW530, and 2rW540 during unit opee ;t; m m.1*
- ause a loss of feedwater to the steam generators, resulting
+n adiam insient with a postible teactor trip as a
- result, These valves will be fail safe (rt) tested pursuant to the Byron Station Technical Specifications.
l!QIE 17 These feedwater valves are exempt from cli 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 Bypass Valves 1FW510A, IrW520A, IEW530A, IrW540A, 2rW510A, 20W520A, 2FW530A, and 2rW540A during unit 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 result.
These valves will be fail safe (Et) tested pursuant to the Byron Station Technical Specifications.
ROIE 12
- DELETE "
UOTE.1'
- E t'T E -
(Incorporated into !;OTE 11)
(0094D/0035D/030491) 4.4 - page 4 of 8
Rev. 10 UOTE 2n The remote position indicator for these valves cannot ba observed directly due
'n M., encapsulated design et 'he solenoid vt.te' ! =. J y.
Nrjug %r i..J 4 m iv.
i test, indirect evidence of the necessary valva dis k mo /r.nent shall be used, in accordance with INV-3412 (b).
The valves affected are listed below:
ICVA114 IPS230A/B 2PS228A/B ICV 8116 1RC014A-D 2PS229A/B 1PS228A'S 2CV8114 2PS230A/B 1PS229A/B 2CV8116 2RC014A-D UOIE 21 The Main feedwater Temperino flow Isolation Valves 1/20WO34A-D are exempt from all ASME Section XI testing requirements pr- < 4V-1100 and IVN-1200.
They are included in the procram for operability traening purposes only, and will be fall safe (Ft) tested pursuant to the Eyron Station Technical Specifications.
NOTE 12 ier NRC request, the post-accident hydrogen monitoring system check valves 1/2PS231A and 1/2PS231B will be stroke exercised open on a quarterly frequency to verify operability.
O UOTE 23 1/2SI8818A-D, 1/2SIBR19A-D, and 1/2SI8948A/D are Event V check vs1ves, which are defined as two check valves in series at ; low presrure/RCS interface whosa fallute may result in a LOCA that sy,nasses contninment.
They are individually leak-tested in accordance with NRC genetic letter b9-04, position 14b.
s UOTE 24 1/2CC9513, 1/2CC9534, 1/2CV8113, and 1RH8705A/B are check valves designed to re11 eve pressure betwean two contair.n..nt isolation valves.
The full flow limiting value is zero, since the safety function of these valves in the open dirtuti)n is to relieve pressure only.
Refer to Relief Request VR-1P.
UOTE 25 Cbsck valve 1/25I8925 prevente flow from the S a f e t'.
Iniaction (SI) pump s[
^
j' normally lined up in the I:MEC? ION MODE to take s uc t ie r. ( t 2n the RWST.
'.his suction line to the Defuelina Water Storace Tank (RWST).
Tha "I p c.p u e
(*
[
check valve would stop reverse flow when the SI pumpu are transfarred to HOT / COLD LEG RECIRCULATION MODE to prevent contamina* ion o f the RWST.
6 However, the e/2SI8806 M.O.V. is in series with this check valve and would be closed to prevent reverse flow as directed by the emergency procedures.
Therefore, no backfice test (Bt) is required for 1/2 SIB 926.
(0094D/0035D/030491) 4.4 - page 5 of 8
Rev. 10 U21E 25 Check valve 1/2CV8546 prevents flow ftem the Chemical and Volume Control (CV) pump suct %n A r ne y - the Nfuelino Water Storage M (PWST).
The :" y y are nu.aolir lined up an the INJECTION MODE to take suction from the RWST.
This check. valve would stop reverse flow when the CV pumps are transferred to HOT / COLD LEC INJECTION MODE to prevent contamination of the RWST.
- However, the 1/2CV112D cnd 1/~CV112E M.O.V.'s are in series with this check valve and would be closed to -
ent reverse flow as directed by the emergency procedures.
Therefore, au back flow :est (Bt) is required for 1/2CV8546.
UOTE 27 Check valves 1,2S1895BA/B prevent flow from the Residual Heat (RH) Removal pump suction line to the Refueling Water Storage Tank (RWST).
The RH pumps are normally lined up in the IHJECTION MODE to take suction from the RWST.
These check valves would stop reverse flow when the RH pumps are transferred to HOT / COLD LEG RECIRCULATICU HODE to prevent contamination ot the RWST.
However..the 1/2SI8812A/B M.O.V 's are in series with these check valves and would be closed to prevent reverse flow as directed by the emergency procedures.
In addition, the RH suction valves 1./2 SIB 812A/B, 1/2RH8701A/B or 1/2RH8702A/B, and 1/2SI8811A/" ate electrically interlocked to prevent the backflow to the RWST whe.. the RH system is in a RECIRCULATION MODE.
Thus, no back flow testing of 1/2SI8958A/D is required.
NOTE 28 NRC Gener, Letter 89-04. Attachment 1. Position 3 lists the CVCS Volume Control Tsak (VCT) outlet check valve as an example of ASME Code Class check valves that perform a safety function in the closed direction that are frequently not back flow tested.
At Byron Station, check valve 1/2CV8440 prevents flow f rom the Chemical and Volume Control (CV) pump suction to - the V CT..
The VCT is normally aligned to the CV pumps during normal plant operatior..
During a Safety Injection signal, the VCT is automatically isolated by closure of the 1/2CV1128 and 1/2CV112C M.O.V.'s, which are in serats with the 1/2CV8440 check valve.
Closure of either M.O.V. will prevent reverse flow to the VCT.
Thus, no back flow testing of 1/2CV8440 is required.
UOTE.22 Check valve 1/2CV8442 prevents flow f rom the Chemical and Volume Control (CV) pump suction header to the boric acid transfer pump.
This line is normally isolated by the 1/2CV8104 emeroency boration valve.
This valva would only be opened dur.ing an emergency with the boric 3cid transf er pump r u n n i t.o. This check valve is unne<'essary with the curtant system operation, and thus, no bact O ow te; ting af i/2CV8442 is required.
(0094D/0035D/030491) 4.4 - page 6 of 8
. - -.. ~ -.-.
-.. ~.-
. - -.. -.~ _. - -..- _ =
Rev.
'O tlOTE 30 Check valves 1/ 2 Ar014 A'-il ar e ve t i f ied to be closed each shift by the Operating 0*partment, by Wri1y v,,
that i hr + ampere. m et./2Ar00$A-H is i 130'.'
- er j
BOP 199-A40 (U-If and Dui ' %-no t tv-2).
It the temperatura is > 130' F at any 1/2AF005. valve,. then abnorrnal operating procedure 1/200A SEC-7,," Auxiliary feedwater Check Valve Leakage", is entered to isolate and cool down the affected lines.
This shiftly monitoring of 1/ 2 Af 014 A-Il in the closed position adequately inonitors the status of these valves.
fio additional monitoring /
trending by the IST Group in re<1ui t ed.
[191U1 Check vaives 1/2CV8480A/D and 1/2 SIB 919A/D are the Centrifugal Charging Pump and Safety Injection Pump mini-flow recirculetion line valves which open to prevent full recirculation flow durino IST Surveillances.
Since full stroke for these valves will depend on the reference point of testing, acceptable full stroke will be verifind whenever the t ecore.'.*d mi ni-t eci r culation flowrate is within the " acceptable" or "nlert" anges given in the ICT Ptimp Susvei11ance, t!OTE 32 Check. valves _1/2cr9462 Vb nw OCC9464 are the Component Cooling Water Pump discharge check valves.
The. full design accident flow through any one pump l
cannot be obtained during normal operation without causing low flow alarms in adjacent loops and possible equipment damage due to low cooling water fic> rates to the Reactor Coolant Pump (RCP) seals. These valves will be full-stroke exercised during ccid shutdowns when plart conditions allow all four RCP's off.
t@~lUl The Essential Service Water (SX) and Make-Up Pump discharge check valves (OSX028A, ti) open to permit make-up water flow from the Rock River to the SX System Dasin. These check valves are downstream at the pump discharge tap-ofI to the SX Make-Up Pump Jacket Water llent Exchanger and Gear Oil Cooler.
Since this tap-off-line is orificed, the flowrate through this line, and t.'iere f ore the flowrate through pump discharoe check valves OSX028A/D, will depend on the reference point of testing.
Acceptable.0SX020A/D full stroke will be verified whenever the recorded total pump flow minus the tap-off line flow is within
" Acceptable" range contained in the. ASME pump surveillance.
l l
i
(^
i (0094D/0035D/030491) 4.4 - page 7 of 8 I
l Rev. 10
!!RII-.13 Per Dyron Technical ;nc!!ications Amen tmen' nives ! '.30002.5 i!.
'?%5
- ,A-D i
have been removed from the list of valves to be t a *, t e u unoer 10CFR$0 Appendix and will now be tested per ASME Code Section XI. IWV-3420.
Ll?TE 35 The I?2RHB705A/D check valves will be operability tested by verifying that there is depressurization in line 1/2RH26AT-3/4 and 1/ 2P1120 AB-3 /4 when they are opened.
This is a test method which was approved by the flRC is SER 0/14/90.
l 1
(0094D/0035D/030491) 4.4 - page 8 of 8
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SECTION 4.5 TECHNICAL APPROACHES AND POSITIONS O
J O
m.
Rev. 10 VA-01 IST Technical Approach and Position A.
C2mEQazut..! A ntiLignGu 1.
Description Method of Scroke Timing Valves - Timing using control board position indication lights (St).
2.
Component Numbers:
See IST Valve Tables.
3.
References ASME Code,Section XI, Subsection INV, paragraph IWV-3413(a).
4.
Code Class:
1, 2,
and 3.
5.
Examination Category (s): !!/ A 6.
I tem tiun.be r ( s ) :
II/ A n.
RequiLement:
tise 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 indastty.
1iragraph IWV-3413 of ASME XI defines " full-stroke time" es "th:t time i " * : r '. a 1 from initiatloa of the actuating signal to the er.J j
of the actuating cycle."
It is common industry practice to measure stroke time as the time interval between placing the operator switch on the control board in the "close" or "open" position and indication that the valve is open or closed on the control board (switch to light).
C.
Positio_D It is recognised that the way in which the limit switch that operates the remote position indicator lights is net may result in " closed" or "open" indication before the valve obturator has actually completed its travel.
This is not considered to be a problem, as.the purpose of the test is to determine II degradation of tne valve operator system is occurring, which is_ determined by observing changes in stroke time _ relative to the reference stroke time.
Stroke time measurements should be rounded to the nearest tenth (0.1) of a second, except.that stroke times less than one.
half (0.5) second may be rounded to 0.5 second, if appropriate.
Standard rounding techniques are to be_used when rounding stop watch readings during valve sttake time testing (a.o.,
10.45 rounds to 10.5 and 10.44 rounds to 10.4).
Foundinu to the nearest second for stroka times of it seconds or less, or t a"
' the atpacified ?imitino stroke time for stroke times longet than 10 s e co r.d a, as ellowad by AGME baction Ki subparagraph IW -341Jtr>), 9hould not ha used.
U (0109D/0041D/030491) 4.5 - page 1 of 8
Rev. 10 VA-02 IST Technical Approach and Position A.
C22Prnant_d. W l11 Cati 2D:
1.
Descriptiont Method of Fall Safe Testing Valves.
2.
Component N umbe r s :
See IST valve Tables (rt).
3.
Peferences:
ASME Code.Section XI, Subsection IWV, paragraph IWV-3415.
4.
Code class:
1, 2, and 3.
5.
Examination Category (s):
N/A 6.
I tem Numbe r ( s ) :
N/A D.
R_gquirratat t paragraph INV-3415 of ASME XI states that "When practical, valves with fail-safe actuators shall be tested by observing the operation of the valves upon loss of actuator power."
Most valves with a fall-safe mechanism to stroke the valve to the fail-safe position during normal operation.
For ewample, an nia-r s ac2.'
calve that falls closed may use e
air to open the valve agains' 'orirq p enrare. When the ac*.uator is
_O placed in the closed position, air !s vented from the diaphragm and the spring moves the obturator to the closed position.
C.
D21Lttgns In the cases where normal valve operator action moves the valve to the closed position by de-energizing the operator electrically, by venting air or both (e.g., an electric solenoid in the air system of a valve operator moves to the vent position on loss of power), no additional fail-safe testing is required. Valves with fall-safe actuators that de not operate as part of normal actuator operation must be tested by other ueans.
This may be accomplished for motor-operated valves by opening the circuit breaker supplying operator power and observing that the valve moves to its fall-safe position.
Lifting leads is not required unless it is the only method of de-energizing the actuator.
Using a valve remote position indicator as verification of proper fail-safe operation is acceptable, provided the indicator is periodically verified to be operating properly as required by ASME Code,Section XI, Subsection INV, paragraph INV 1300.
I l
l (0109D/0041D/030491) 4.5 - page 2 of 8
Rev. 10 VA-03 r-IST Technical Approach and Position o-wrrPa.nL DDnLiL12At12D:
1.
==
Description:==
Method of Full Stroke (Ct) and Back flow (Bt), Exercising of Check Valves.
2.
Component Number s:
See IST Valve Tests (Ct and Bt).
3.
References:
(a) NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs, Attachment 1, Positions 1, 2,
and 3: (b) ASME Code.Section XI, Subsection IWV. paragraph INV-3522.
4.
Code Class:
1, 2,
and 3.
5.
Examination Category ( s ):
N/A 6.
Item Number (s):
N/A D.
Et2MILISinL:
Paragraph INV-3522 of Article XI states " check valves shall be exercised to the position required to fulfill their function ve.les, such c eratiop r
is not practical during plant operation.
If only limited
'p* rat.on is
(\\
practical, during plant operation the check valve shall be part-stroke exercised during plant operation and full-stroke exercised during cold shutdowns." For check valves with no external position indication devices, the determination of when they are in full open position has proven difficult to 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 durino cold shutdowns or refuelings.
C.
Position:
Valid full-stroke exercising to the full-open or full-closed position may-be accomplished by. observing an external position indicator which is considered to be a positive means of determining obturator position.
Where external position indicators ar e not prcvided, manual stroking of the valve is acceptable.
Where a mechanical exerciser is used, the torque required to move the obturator must be recorded and meet the acceptance standards of subparagraph IWV-3522(b).
Per the requirements of NRC Generic Letter 89-04, httachment 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 tnis is cocsidered as a part-stroke e.ercise, flow-through the valve must be determined by positive means suu. :s 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 linen does not provide verification of flow through individual valves.
(0109D/0041D/030491) 4.5 - page 3 of 8
Rev. 10 C.
Position, continued One exception to the " maximum required accident flow" requirement is the methodology used to verify full-stroke exercising of the Safety injection (31; t utmulator back-up i Wie
"*I"es, 1/2SI8956A-D.
Dwee of the high maximum desi gn f1swrate of these_ valves, a esximum design accident flowrote test is physically impossible to perform, for those valves, an Engineering calculation has been pertormed to determine the minimum flowrate for full disc lift.
An acceptable f ull-s tro'-= exercise o f these valves will te performed each ref*;: ling outage by measuring the accumulator. level decrease ovet time, converting these parameters to a flowrate through the valve. and verifying this value is greater than or equal to the engineering calculated minimum flowrate for full disc lif t.
This method is superior to sample disassembly and inspection of one valve per outage which would require unusual system line-ups, freeze seals, radiation exposure, and possible plant transients.
Other alternatives to measuring full design accident flow or disassembly and inspection of check valves to satisfy full stroke requirements is allowed as long as the requirements of IIRC Generic Letter 89-04, Attac hme nt 1, Positions 1,
2, and 3 are utilized QE specific relief requests are-approved by the flRC.
Stroking a valve to the-full closed position for valves without a manual exerciser or position indicator must be verified using indirect means.
Thece in:19de, but are not limited to, (1) observing pressure indicatipns on both alfles af the valve to determine if the differential pressura expected with the valve shut is obtained, or (2) opening a drain connection on the upstream side of the valve to detect leake7e rates in excess of that expected with th<, valve shut.
Valves that cannot be full-stroke tested or where f ull-stroking cannot be verified, shall be disassembled, inspected, and manually exercised.
Valves that-require disassembly for full-stroke testing during cold shutdowns or refueling still require quarterly part-stroke testing, where possible.
Testing of check valves by disassembly shall comply with the followings During valve. testing by disassembly, the valve internals shall be a.
visually inspected for worn _or corroded parts, and the valve disk shall be manually exercised.
b.
Due to the scope of this testing, the persennel hazards involved, and system operating restrictions, valve disassembly and inspection may be performed during reactor refueling outages.
Since this frequency-differs from the Code required frequency, this deviation must be i
sy e.ffcally noted in the IST procram.
- z l
(0109D/0041D/030491).
4.5 - page 4 of B
Pev. 10
("'
c.
Where it is burdensome to disassemble and inspect all epplicable valves each refueling outage, a sample disassembly and in6pection plan for groups of identical valves in similar applications may be
.q uyed.
The HRC sanat h 'ettet 19 04 q u i d: l l r.m.
Mr this plan are explained below:
The sample disassembly and inspection program involves grouping similar valves and testing one valve in each group during each refueling outage.
The sampling technique _ requires that each' valve in the group be the name design (manuf acturer, size, model number, and materials of construction) and have the s ame service conditions including valve orientation.
Additionally, at each disassembly t he licensee must-verify that the disassembled valve is capable of full-stroking and that tre internals of the valve are structurally sound (no loose or corroded parts).
Also, if the disassembly is to verify the full-stroke capability of the valve, the disk should be manually exercised.
A different valve of each occup is required to be disassembled, inspected, and manually full-stroke exercised at each successive refueling outage, until the entire group has been tested.
If the disassembled valve is not capable af bain9 full. stroke exercised or there is binding or failure o L~ "94"a internals, the remaining valves in that group most also be disassembled, inspected, and manually f ull-stroke exercised during the same outage.
Once this is completed, the sequence of disassembly must be repcated unless extension of the interval can be justified.
Extending the valve sample disassembly and inspection interval from disassembly of one valve in_the group every refueling outage or l
expanding the group size would increase the time betweenftesting of any particular_ valve in the group.
With four valves in a group and an 18-month reactor cycle, each valve would be disassembled and inspected t'
every six years.
If the fuel cycle is increased to_24 months, each valve in a four-valve sample group would be disassembled and inspected only once every eight years.
Extension of the valve disassembly / inspection interval from that allowed by the Code (quarterly or cold shutdown frequency) to longer than once every 6 years is a substantial change which may not be justified.by the valve failure rate data for all valve groupings.
When_ disassembly / inspection data for a valve group show a greater than
-25%_ failure rate, the station should determine whether the group size should be decreased or whather mora
- 1"*-
frem the group should be disas;embled during overy retaeling outage.
l Extensions of the croup size will be done on a case by case basis.
l' j
(0109D/0041D/030491) 4.5 - page 5 of 8
T Rev. 10 VA-04 IST Technical Approach and Positi6n A.
- <.cy sent Ident111 cation
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, Sect?.cn XI. Subsectica INV. Sub Article IWV-3413.
b.
NRC Generic Letter 89-04. Attachment A, Position 5, c.
ANSI /ASME OM-1967 threuch OMb-19R9 Addenda, Part 10, Section 4.2 4.
Code Class:
1, 2,
and 3.
5.
Item Number ( s):
N/A f-D.
Req.uirement:
t The IST program originally assigned a limiting value of full-stroke time based on the most conservative value from plant Technical Specifications (TS) or Updated Final Safety Analysis Report (UFSAR).
For valves not having a specified value of full-stroke. a limiting value was assigned based on manufacturers design input, engineering input, or initial valve preoperational testing.
This methodology is contrary to NRC Generic Letter 89-04.
According to NRC Generic Letter Bo-04 the limiting value of full-stroke should be based on ar. average reference stroke time of a valve when it is known to be operati y properly. _The limiting value should be a reasonable deviation from this reference stroke time based on the valve size, valve type, and actuator type.
The deviation should not be so restrictive that it results in a valve being declared inoperable due to reasonable stroke time variations.
However, the deviation used to establish the limit l
should be such that corrective action would be taken for a valve that may not perform its intended function. When the calculated limiting value for a full-stroke is greater than a TS or safety analysis limit, the TS or safety analysis limit should be ased as the limitino value of full-stroke time.
Based on this, a review of each 'ralve operatino history was performed and an average / reference value of full-stroke dataemi.ns9 in addition, valves were grouped t99 ether by system. train, a ru t, valve type, and actuator type to provide for e more thorouch review in aetermining what would be a " reasonable" deviation from the average / reference
(
full-stroke value.
l (0109D/0041D/030491) 4.5 - page 6 of 8
- ~
Rev. 10
)
The 1993 Edition through Summer 1983 Addenda of ASME Section XI does not orovide cuidancu for determining values of full-stroke.
However, it doe =
irevide r a gta i r eroe n t; fe? %: to start rnor.itoring a s1ves performas.te on a more trequent basis, also known am eiert range testing.
!f a valve strokes in 10 seconds or less, a 50% increase over the previous value requires it to be put on a monthly test frequency, and for valves stroking in greater than 10 seconds, a 25% increase over the previous value requires it to be put on a monthly test frequency (see VR-20).
Trending 9troke times, based on the percent change from the previaus test, as ASME Section XI requires, allows oradual degradation to occur over a long period of time without triggering the additional trending attention that increased testing frequency requires.
Therefore, an improved method of component performance monitoring is employed which requires a valve to be placed on increased test frequency based on the percent change from the fixed reference value established via NRC Generic Letter 89-04, Attachment 1.
Position 5.
l 1
l This criteria, in conjunction with establishing reference / average values l~
of full-stroke, should allow for reasonable deviations in stroke time measurements without declaring a valve inoperable.
The corrective actions specified in INV-3417(b) of Section XI and as described in IST Program Relief Request VR-20 will be taken when a valve exceeds its limiting value of full stroke.
C.
Position:
The following criteria will be used as general guidance to establish ALERT and REQUIRED ACTION ranges for power-operated valves:
HQV's/SOV's/HOV's/A3V's - Less than or equal to 10 seconds:
ALERT RANGE:
( ~1. 5 0 ) (Tref) - (2.0) (Tref)
REQUIRED ACTION VALUE:
(2.0) (Tref)
)
MOV's/SOV's/HOV's/AOV's - Greater than 10 seconds:
See VR-20 l
l
[
tN.
(01090/0041D/030491) 4.5 - page 7 of 8
Rev. 10 Notest ref is.the reference or averace stroke val ~ue in seconds of an 1.
T individual valve
@> e 'st^Pn na as' A'i@ a' hen the valve is k nc ;..
o to be operating accepttb's.
2.
Standard rounding techniques are to be used when rounding oIf stopwatch readings during valve stroke timing (e.g. 10.45 rounds to 10.5, and 10.44 is rounded to 10.4 seconds).
Round off all measured stroke time to the nearest tenth of a second.
3.
When reference stroke valves or average stroke valves are affected by other parameters or conditions, then these parameters or conditions must be analyzed and the above factors adjusted.
4.
If the above calculated values exceed a Technical Specification or FSAR value,-then the TS or FSAR value must be used for the limiting value of full-stroke.
5.
Fast actino valves (valves which normally stroke in less than 2 seconds consistently) are included in Relief Request VR-12.
These valves are t12I assigned ALERT RANGES-and are RQI trended.
6.
The above criteria is a guide and cannot cover all valves.
The ALERT R ANGES and RED'JIPPO
,'.C in" VALUES are selected based on comparison.
between the REFERENCE D.T,Ur, LIMITING VALUE given in Technical
..O Specifications /UTSAR, operating history, and calculated values using the above-criteria.
7.
Valves which serve the same function on dual trains (i.e.,
ICC9473A and ICC94738) and dual units (i.e. 1CC9473A and 2CC9473A) are assigned the same REQUIRED ACTION / ALERT RANGE VALUES based on human f actors considerations, unless valve-or system design differences exist between the trains / units.
8.
Refer to Relief Request VR-20 for related information.
l f
(0109D/0041D/030491) 4.5 - page 8 of 8
t 0
4 SECTION 4.6 REllEF RE0 VESTS i
f t
i i
l
= - - -
~
i l
i Pev. 10~
I i
MLIEF REOUEST VF-1 O1 1.
YAly1_llWDhi. !
All 7rmarp o c a i n~e r. - isolation valves in ' !- j + program are 1: S t ~t as CaLegosy na VEEj VALVEJ VALVE i 1)
ICC685 41)
IPR 033D 81) 1S18964 2) 1CC9413A 42) 1PR033C 82) 1518968 3)
ICC9414 43)
IPR 033D 83) 1VQ001A 4)
ICC9416 44)
IPR 066 84)
IVQ001B 5) 1CC9438 45) 1PS228A B5)
Iv0002A 6)
ICC9486 46)
IPS228D 86) 1VQOO2D 7)
ICC9518 47) 1PS229A 87)-
IVQ003 8)
ICC9534 48)
IPS2298 88) 1VQ004A 9) 1CS007A 49)
IFS 230A 89) 1VQ0048 10)
ICS007B 50) 1PS230B 90) 1VQ005A 11)
ICS008A 51)
IPS231A 91)
IVQOOSB 12)
ICS008D 52)
IPS231D 92)
IVQ005C 13)
ICV 8100 53)
IPS9354A 93) 1VQOl6 14)-
ICV 8112 54) 1PS9354B 94)
IVQO17 15)
ICV 8113 55)
IPS9355A 95) 1VQ018 16) 1CV8152 56)
IPS935SB 96) 1VQ019 1')
1CV8160 57) 1PS93toA 97)
IWM190 1H, IFC009 58)
IPS93568 98) 1HH 91
.O 19) 1FC010 59)
IPS9357A 99) 1WOOO6A 20)
IFC011 60)
IPS9357B 100) 1WOOO60 21)
-1FC012 1) 1RE1003 101)
IWOOO7A 22)
IIA 065 62) 1RE9157 102)
IWOOO78 23)
IIA 066 63) 1RE9159A 103) 1HOO20A 24)
IIA 091 64) 1R691590-104)
IWOO208 25) 10G057A 65) 1RE9160A 105) 1HOOS6A 26) 10G079 66) 1RE91600 106)
IWOOS6B 27) 10G080 67) 1RE9170 28)
.10G081 68) 1RF026 29) 10G082 69) 1RF027 30) 10G083 70).
1RY8025 31) 10G084 71) 1RYB026 32) 10G085 72) 1RY8028
-13)
IPR 001A-73) 1RY8033 34)
IPR 0018 74) 1RY8046 35)'
1PR002E 75) 1RYB047 36) 1PR002F 76)
ISA032 37)
IPR 002G 77)
ISA033 38)
IPR 002H 78) 1SI8871 39)
IPR 032 741 ISI8800 40) 1PR033A 80)
ISI88RA (0095D/0035D/030491) 4.6 - page 1 of 37
. ~... - - _
Fev. 10 1.
Valve tiumbert (Continued)
VALVE t VALVE i VALVE i 107) 2CC6dS
'. e 7, -
en03Jd 187) 7578964 108) 2CC9413A 148) 2PR033C 188) 2518968 109) 2CC9414 149) 2PR033D 189) 2VQ001A 110) 2CC9416 150) 2PR006 190) 2VQ001B 111) 2CC9438 151) 2PS228A 191) 2VQ002A 112) 2CC9486 152) 2PS2288 192) 2VQ0028 113) 2CC9518 153) 2PS229A 193) 2VQ003 114) 2CC9534 154) 2PS2298 194) 2VQOO4A 115) 2CS007A 155) 2PS230A 195) 2VQOO4B 116) 2CS007B 156) 2PS230B 196) 2v0005A 117) 2CS008A 157) 2PS231A 197) 2VQ005B 118) 2CS008B 158) 2PS2318 198) 2VQ005C 119) 2CV8100 159) 2PS9354A 199) 2VQOl6 120) 2CV8112 160) 2PS9354B-200) 2VQO17 121) 2CV8113 161) 2PS9355A 201) 2VQ018 122) 2CV8152 162) 2PS9355B 202) 2VQ019 123) 2CV8160 163) 2PS9356A 203) 2WM190 124) 2FC009 164) 2PS9356B 204)
IWM191 125) 2FC010 165) 2PS9357A 205) 2WOOO6A 126) 2FC011 166) 2PS9357B 206) 2WOOO6B 127) 2FC012 l',7 )
2RE1003 207) 2WOOO7A
-O 128)
ZIA06%
'. 6 9 )
2RE9157 208) 2WOOO7B 129) 21A066 169) 2RE9159A 209) 2 WOO 20A 130) 2IA991 170) 2RE9159B 210) 2 WOO 20B 131) 20G057A 171) 2RE9160A
.211) 2 WOOS 6A 132) 20G079 172) 2RE9160B 212) 2 WOOS 6B 133) 70G080 173) 2RE9170
.134) 20G081 174) 2RF020 135).
200082 175) 2Rr027 136) 20G083 176) 2RY8025
-137) 20G084 177) 2RY8026 138)
ZOG085 178)
-2RY8028 139) 2PR001A 179) 2RYB033 140)=
2PR001B 180) 2RY8046 141) 2PR002E 181) 2RY8047 142) 2PR002F 182) 2SA032 143) 2PR002G 183) 2SA033 144) 2PR002H 184) 2SI8871 145) 2PR032 185) 2SI8880 146) 2PR033A 186) 2 SIB 88J I
(0095D/0035D/030491) 4.6 - page 2 of 37
- - _. ~
Rev. 10
~
2.
Number of Items:
212 3.
ASME.2 ode Category:
A 4.
ASME Code, Secticn XI Recuirements:
Seat Leakage Measurement per INV-3420.
5.
Egais for Relief:
Primary containment 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.
Alternate Testing:
Primary containment isolation valves shall be seat leak rate tested in accordance with the requirements of 10 CFR 50, Appendix J.
The results of such leak rate measurements shal] he analyzed and corrected, as necessary, in accordance with the guidance set forth in ASMC Code Section XI, Sut meetion INV, paragraphs INV-3426 and INV-3427(a).
The trending requirements of IWV-3427(b) will R21 be utilized.
7.
Justification:
No additional information concerniv7 velva' 3c=.keye would be gained by performing separate tests to both Section XI and Appendix J. Therefore, overall plant shfety is not affected.
As specified per NRC Generic Letter 89-04, Attachment 1. position 10, the usefulness of INV-3427(b) does not justify the burden of complying with this requirement.
8.
Applicable Time Period:
This relief is requested once per two years during the first inspection interval.
9.
Approval Status Relief granted per SER 9/15/88 contengent upon compliance with ASME a.
Section XI INV-3426, 27.
b.
Revised to comply with ASME Section XI INV-3426, 27 in Byron SER Response 12/16/88 (Byron Station Letter 88-1321).
c.
Relief granted per NRC Generic Letter 89-04.
d.
Deleted SD valves _per Technical Specification Amendmant #39.
e.
Reliet granted par SER'9/14/90.
(0095D/0035D/030491) 4.6 - page 3 of 37
-. -. ~ _. _. _..
. _ ~
. - -. _ -.. ~
Rev. 10 FILIILE0VIET '/P-2
-0 1.
'La_1ye fiumber t ICS020A.
2CS020A 1cS0200 2rsv:'+
2.
thu@e r o f Ittma 4
3.
ASliLC2de Catt22Iy C
4.
ASME Code,Section XI Recuirements:-
Exercise for operability fCt) of check valves every 3 months, per IWV '521, 5.
aasis_for Relief:
The check. valves in the spray additive system cannot be stroked without introducing flaOH into the CS system.
6.
Alternate Testin2:
These valves will be dismantled according to the sample disassembly and inspection program identified in Relief Request VR-18 during refueling nutages, in order to demonstrate operability.
In addition to this, they will be full flow tested once every five years per Byron Station Technical Specifications.
The full flow test may be performed in );eu et
+
dismantling thase valves, if desired.
-\\
7.
Justification:
This alternative will adequately maintain the system in a state of-operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as is safely possible.
A.
Applicable Time Period:
This relief-is requested once per quarter during the first inspection interval.
9.
Approval Status:
a.
Relief granted per SER 9/15/88.
b.
Relief granted per Generic Letter 89-04
.c.
Relief granted per SER 9/14/90.
(0095D/0035D/030491) 4.6 - page 4 of 37
Rev. 10 RELIEF REOUEST VR-3
- V 1,
Valve Numisr t 1S18922A/B 2SI8922A/B
~2.
Number of I t e.is ;
4 3.
ASME Code Cateoorv C
4.
&SME Code,Section XI Recuirementst
~ Exercise for operability (Ct) of check valves every 3 months, per INV-3521.
5.
Rasis for Relief:
These check valves cannot be full flow tested during operation as the shut-off head of the Saf ety Injection pumps is lower than the reactor coolant system pressure.
Ferformance of this tert with the RCS depressurized, but intact, could lead to inadvertent over-pressurisation-of the system.
The alternate method of protecting against over-pressurization by partially draining the RCS to provide a surge volume-is.not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
6.
Alternative TeEtia21 These v e t va s "l i.1 b; full stroke. test d during refueling outages as a minimum, but no more. frequently than once per quarter.
7.
Justification This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible.
8.
Applicsble Time Period L
This relief is requested once per quarter during the-first inspection interval.
9.
Aporeval-Status:
a.
Relief granted per SER 9/15/88.
b.
Relief granted per NRC Generic Letter 89-04, c.
-Relief granted per SER 9/14/90.
l (0095D/0035D/030491) 4.0 - page 5 of 37
~
~
Rev. 10 RELIEE REOUEST VR-4 1.
1' 31ve Number :
ICS008A/B 2CS008A/B ICS003A/D E<W*0 4.
(1 umber of Iteng:
8 3.
6SME Code Catecorvt AC & C 4.
ASME. Code,Section XI Reouirements:
Exercise for operability (Ct) of check valves every 3 months. per INV-3521 and IWV-3412.
5.
D.gs i s for Religi 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 causina undesirable effects on system components inside containment.
' Additionally, the full flow testing of these check valves during periods of cold shutdown, using the CS pumps. would fill the reactor refueling cavity with cantaminated water f rom the refueling water storage tank.
The filling of the cavity, via tempcrw 11y i" talled large bore piping, would require the removal of the react;
- asel 'ead so as to preclude equipmert
(
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 teak.
The addition of such flow paths would require extensive plant modifications to existing plant designs, including penetration of containment integrity.
Partial stroking of the 1/2CS008A, B valvec using air does not provide adequare assurance of valve operability and may be detrimental for the following reasons:
A.
There is no correlation between air flow and angle of dis; movement.
D.
Venting and draining the appropriate piping quarterly may cause deporition of boric acid residue which could in turn promote binding of the check valve internaln.
s (0095D/0035D/030491) 4.6 - page 6 of 37
Rev. 10 EELIEf_EEQUEST VR-4, cent.
D
%s 6.
Alternate Testing:
Tue 1/2CS008A. B valves wil.', be either full flow tested or din.au62eo according to the sample' disassembly and inspection program identified in Relief Request VR-18 and VR-19. to demonstrate operability each refueling outnge.
The 1/2CS003A, B valves will be partial stroke tested during the quarterly pump surveillance and full flow tested or dismantled according to the sample disassembly and inspection program identified in ?elief Request VR-18, to demonstrate. operability each refueling outa(i.
7 Jg5Liticaricyt 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 possiule.
8.
Aop11 cable Time Periodi This relief is requested once per quarter during the first inspection interval.
9.
AgorovnL S!alLtus s
a.
Relief granted per SER 9/15/88 for 1/2CS003A, B; relief denied per SER 9/15/88 for 1/2CS008A.
b.
Revised to_ address t3RC concerns in Byron SER' - ponse 12/16/88 (Byron Station Letter 88-1321),
c, Relief pendino per SER 9/14/90.
This request is being revised per SER 9/14/90 and vill be resubmitted in March of 1991.
1
(
l (0095D/0035D/030491) 4.6 - page 7 of 37
l, Rev. 10 gs EELIEF PEOUEET VP-S bus) l.
v lve Numbri:
ISIB956A-D 2SI8956A-D a
Id t B w* T ' m
~118948A-D 2.
Humber of Ittms:
16 3.
h$dE Code Cattoory:
AC 4.
ASME Code,Section XI Pecuirements:
Exercise for operability (Ct) of check valves every 3 months, per INV-3521 l
and IWV-3 412.
S.
Dasis for Relief The accumulator check valves cannot lie tested during unit operation due to the pressure differential between the accumulators (650 psig) and the reactor coolant system (2235 psig).
Full stroke exercising of these valves could occur only with a rapid depressuritation of the reactor coolant system.
6.
Alternate Testing
)
B'/cor. Utstiar. Technical Specifications require leak testing to be performed on these valves if th-unit is in cold shutdown and if re-h l e s.:
rate testing has not been performed within nine months.
Therefore, Byron Station will full stroke exercise (Ct) these check valves on the same l-schedule.
This will be accomplished by providing a surge volume in the pressurizer and " burping" the accumulator discharge valves.
As a minimum, the accumulators will be discharged into the reactor vessel during refuel!ng outages to perform a full stroke exercise (Ct) of these valses.
Positive verification of valve operability will be by noting a change in accumulator level.
7.
Instifisation:
Stroke exercising the check valves on the same schedule as their required f
Technical Specification leak rate testing will adequately maintain the system in a state of operational readiness without causing unnecessary personnel radiation exposure.
8.
.Apolicable Time Period:
This relief is requested once per quarter during the first inspection interval.
9.
Acorotal Status:
a.
Relief grauled per SER 9/15/88.
g
)
/
b.
Relief granted per NRC Generic Letter 89-04.
y c.
Relief granted per SER 9/14/90.
(0095D/0035D/030491) 4.6 - page 8 of 37 i'
~_
Rev. 10 FIMII_PieUEST vn ~ 6 5
1.
Valve flumber t 15I8926 2518926 2.
Ligmber of Itemst 2
3.
ASMf_ Code Cattsg_ty:
C 1.
A$14E Code.Section XI Peguirements:
Exercise for operability (Ct) of check valves every 3 months, pe r IWV -3 5 21.
5.
Ensis for Reliefs full stroke exercising of the Safety Injection pump suction check valves.
15I8926 and 2518926 cannot be demonstrated during unit operation as the reactor coolant system pressure prevents the pumps from reaching full flow injection conditions.
Ferformance of this test with the reactor coolant system intact could lead to an inadvertent over-pressurization of the system. The alternate method of protectina 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 malt sining adequate water level above the reactor core.
1 6.
Alternate Testing:
The ISI8926 and 2SI8926 valves will be partial stroke tested during periodic inservice tests with the SI pumps in the recirculation mode.
Full stroke exercising for the valves -ill be done during refueling outages as a minimum, but no more [requently than once per quarter.
7.
Justification:
This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by l
testing the valves as often as safely possible.
8.
Applicable Time Periodi This relief is requested once per quarter during the first inspection i
t interval.
9.
Approval Status i
a.
Pelief granted per SER 9/15/88.
b; Pelief granted per t!RC Ganeric Letter a'
04 l
c.
Fellef granted per SER 9.19,ye 5
i (0095D/0035D/030491) 4.6 - page 9 of 37
r i
Rev. 10 RELIEF PEOf!EST VP.1
" -DELETED "
Deleted relief request VR-7 Incorporated valves formerly covered by VR-7 into VF-12 and VR-17.
Added maximum stroke times to the valve tables f or all valves in VR-12 per EG & G request.
l l @
i l
1 j
l l
(0095D/0035D/030491) 4.6 - page 10 of 37 l
- -. ~.. --- -,
, -. ~.. -. _ _ - - -. -.-.
Rev. 10 REL_LEf_f1R!)f ST V P - 8 1.
Valve 14umkri:
ICC685 1CC9438 2CC9414 1CC9413A ICC9486 2CC9416 2CC04 M 200685 rC'438 1CC9416
?cC0413A 2CC9486 2.
((wnbgr of Items:
12 3.
ASME Code CatJigj2II:
A 4.
ASME Code, Se cthl_Egoui r emerits :
Exercise for operability (St) of Category A and B valves every 3 months, per IWV-3411.
5.
Hasis for Jallgi Component cooling water flow to the reactor coolant pumps is required at all times while the pumps are in operation and for an extended period of time while in cold shutdown.
Failure of one of these valves in a closed position during an exercise test would result in a loss of cooling flow to the pumps and eventual pump damage and/or trip.
6.
. Alternate Testin23
'nese valves will be exarcised during cold shutdown, provide all of tbc d
reactor coolant pumps are not in operation.
This testing period will be each ref ueling 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 seat-leakage test per IWV-3420.
This frequency is at least once per two years. to be performed during reactor refueling-outages.
7.
Justification:
This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant,-by testing the valves as often as safely possible.
Stroke exercising check valves 1/2CC9486 on the same schedule as their leak rate testing will adequately maintaln the system in a state of' operational readiness without causing unnecessary personnel radiation exposure or possible eage to the Reactor Coolant Pumps.
6.
Applicable Time Periodt This relief le rac" W ed once per q' tat ter +t r ina the first inspection interv3?.
9.
-Approval Stgigs:
\\
a.
Relief granted per SER 9/15/88.
b.
Relief granted per tiRC Generic Letter 89-04.
c.
Relief granted per SER 9/14/90.
( 0095I'/ 003 5D/0304 91) 4.6 - page 11 of 37
O 9
\\
IMAGE EVALUATION 4
\\g g
TEST TARGET (MT-3) h/
N'
)7,,/
- ky f
~
l.0 l
'22 d,2 0 l,l Nhu Ell I.25 1.4 l l l.6 imme 4
150mm 6"
/'+A
[% %y$,,,
+
////h m,.
~
O g
4
~~
f I
4
=
/j//
-, et ~
IMAGE EVALUATION w
g
\\)j//
'g' TEST TARGET (MT-3)
NN/
'w
\\\\\\\\\\/
pp
([
Y
'v%
e, l.0 m
lL44 l.2 5 il I.4 h==
11 1.6 nes 4
150mm 4-6" l
I'h
.g$r l'A5 jh c
p
,y,y sp e
+
op Q3 p
F R
e 3>
IMAGE EVALUATION
/'
e, TEST TARGET (MT-3)
- (/
a s~$&
/[fQ YlQ.l*
%/
?9 tQ 4
s@'
4 l.O x
22 02q l,l L:srca Ell
-I.25 HI.4 Y i.6 hs= h!.=
--- 15 0 m m 4
6"
/s
%g, of* 4%
////p 9
, $ pjjj,,,
yy
,y 1
p.
Rev,'10
-PILIEr REOUEST VR-9 l- 'qs l '. Valve Number :
ICV B100 2CV8100 1CVR112 2CVp11<
2.
flumber of Items:
4 3.
ASME Code-Cateoory:
A 4.
ASME Code,Section XI Recuirements:
. Exercise for-operability (St) of Category A & B valves every 3 months per IWV-3411.
5.
Basis'for Relief:
These' valves cannot be tested durin? unit operation as seal water flow to the' reactor coolant puanps is raquired et all times while the pumps are in operation.
Failure of one of these valves in the closed position during an exercise test would result in seal water return flow being diverted to the PRT by lifting a relles valve upstream of the isolation valves.
6.
Alternate Testinot-These. valves will be exettiuo tested during cold shutdown, providing arl
.[.'}
reactor coolant punos a*e wat in operation.
This testing period will be Am,/
each refueling outage as a minimum, but no more frequently than once per quarter.
7
-Justifications i
This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the-safety of the plant, by testing the. valves as often as safely possible.
D 8.
Applicable Time Period:
This reliet is requested once per quarter during the first inspection interval.
9.
Approval Status
(
- a... Relief. granted per SER 9/15/88.
b.
Relief. granted per NRC Generic Letter 89-04.
l-c.
Relief granted per SER 9/14/90.
f%
(_
h
_(0095D/0035D/030491) 4.6 - page 12.of 37
T 9
Rev. 10 EILIET PE0VIST "R-10 1.
Valve NumbgIt 11A066 21A065 1
- c tX ZIA06i 2.
!JumbgI of Itenst 4
l 1
3.
ASME Code Cateooryt A
4.
ASME Code. Section_XI Recuirementq:
Exercise for operability (St and Ft) of category A and D valves every 3 months per IWV-3411.
5.
!L:uils f o r Relie f :
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.
Alternate Testino:
These valves will be exercised during refueling outages.
This testing period will be each refueli.ig sutage
.; a minimum, but no '
/
more frequently than once per querter.
%d 7.
Justificatient The f"il stroke exercising of the instrument air containment isolation volves during unit power operations or cold shutdowns, introduces the possibility of causing major operating perturbations and/or personnel safety concerns should these valves fail to re-open during testing activities.
The failure of these valves in the closed position, as a result of tes'.ing 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 of Pressurizer Pressure Control The pressurizer spray valves 1/2 RY455B & C and the pressurizer auxiliary spray valve 1/2 CV8145 would fail closed and not be available for pressurizer pressure control.
,c~g (0095D/0035D/000491) 4.6 - page 13 of 37
u Pev. 10 EELIEE_f.Er."JIIL"E-12 B.
Loss of Chem; cal Volume Control System Letdown flow (both normal and Ibar9 i*7 Flew -
cycass2 e The loss of instrument air would cause a disruption in the Snit letdown flow paths resulting in pressurl:er level increases.
Such valves as the letdown etifice containment outlet header isolation valve 1/2 CVB160, the letdown line isolation valves 1/2 CV459 and 1, 2 CV460, the letdown orifice outlet isolation valves 1/2 CVB149 A, BL C, the excess letdwon heat exchancer inlet isolation valves 1/2 Cv8153A & B, and the regen heat exchanger letdown inlet isolation valves 1/2 CV8389 A & B would oc to their fail closed positions.
Additionally, the ability to normally make up reactor coolant inventory and adjust the teactos chemical shim (i.e.
normal boration/ dilution) would also be lost as the regenerative heat exchanger inlet isolation ealvas l'2 CVB324 A& D would fall to their respective closed positions.
2 Loss of Cemponent Coolino to containment Fenetrations -
The loss of instrument air supply would cause the penetration cooling supply flow control valve 1/2 CC053 to go to its fail closed position.
The loss of penetration cooling would result in elevated temperatures being imposed on the pene t r ations being suppo. tet'. Py ene component coolleg system.
D.
Loss of Personnel Breathing Air -
The loss of instrument air supply to the service air downstream isolation valve 1/2 SA033 would cause this valve to go to 5ts fall closed position.
This loss of service air in the co ntainme nt building would eliminate the normal source of supplied breathing air needed to support nume rous maintenance and component inspection activities in a contaminated radiological environment.
8.
Applicarle Time Pulpfdl This relief is requested once per quarter during the first inspection interval.
9.
Approval Status:
Pelief denied per SER 9/15/88.
a.
b.
Fevised (to address tiPC concerns) in Byron rasponse to SER 12/16/88 (Byron Station Letter AA-1321!.
c.
P911ei urantrd per SEP 9/l4<90.
i (0095D/0035D/030491) 4.6 - page 14 of 37
~.-- - -.- - -.
Pev. 10 r
I.
EfLlLL_EEOLTEST VR-11 a
" DELETED "
4 1.
Deleted relief request VR-Il per EG & G recommendation.
This was a f
request for extension of position it,dication tests from every two years to every three years.
i i
1 i
i r
3
.i t
t e_
!~_
i e
l l
1^
t e
i i
l l
l l
l'~
i l
i r
I i-i l
l l
-(0095D/003SD/030491) 4.6 - page 15 of 37
....~... ~.- _ - - _.. -. _ _ - -.. - ~ -..
. - -.. ~ _.. -
Rev. 10 EELIET EEQUEST VR-12 1.
Valse Numbert Valves that normallv stroke in 2 saconds or less:
VALYJL_t
- fALVE 1 LLYD VAL'LE1 1hS018A-D 2MS018A-D 1PR066 2PR066 1RE9157 2PE9157 1PS228A, B 2PS228A. B 1RE9159A, B 2RE9159A,B 1PS229A, B 2PS229A, B 1RE9160A, B 2RE9160A, B 1PS230A. B 2PS230A, B 1RYB033 2RY8033 1RC014A-D 2RC014A-D 1SI8871 2318871 2SD002A-H 2.
IhnhtL_2L I12EA :
52 3.
hSME Code Catecory!
A&B 1.
A311E _ Cede, Se.q11cn XI_ltauntacIlis:
Verification, by trending of power operated valve times, that an increase in stroke time of 50% or more, from the previous test, does not occur, per IWV-3417(a).
5.
Datic for Reli11:
J Minor-timing inaccuracies, with small stroke times can lead to substantial leereases (percent wise) in stroke times.
Por example, a valve with a stroke time of 1 second in an initial test, and 1.6 seconds in the subsequent test, has experienced an apparent 60% increase in stroke time.
If the accuracy requirements of IWV-3413(b) are utilized, it could be argued that stroke times between 1 and 2 seconds could constitute as much as a 100% increase in stroke. time when, in fact, only a 0.2 second inesease 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/0035D/030491) 4,6 - page 16 of 37
g
~Rev. 10 6.
Ahnant. Te s t i ng :
Fast acting valves can be defined as those valves that no rm a 1 1 " *tenka in 2 seconde cr.l'.ws, No trendina of r t. -. c time will be t?q' tit.)
and upan exceeding e seconds, corrective action shall be taken immediately in accordance with INV-3417(b).
7 Justifications for small stroke times, the trendino requirements are too stringent for the accuracles specified in the Code.
The alternative specified will adequatelyinaintain the system in a state of operational readiness, while not imposing undue hardships or sacrificing the safety of the plant.
8.
Applicable Time Period:
This relief is requested once per quarter, during the first inspection interval.
9.
Appro"al_ Status:
Relief denied per SER 9/15/88.
a.
b.
Revised (to address NRC concerns) in Byron response to SER 12/16/88 (Byron Station Letter 89-1321).
c.
Relief granted per SER 9/14/90.
a
- (0095D/0035D/030491) 4.6 - page 17 of 37
v
-1 Rev. '
RELIEF PEOUEST VR-13 1.
Yalve Numbetsi 1DG5182A.D 2DG5182A.B IDC5193A.B
'DG5183A B
- IGS184A,b 2DG5184A,B 1DG5185A.B 2DG5185A.B 2.
Rumber of Items:
16 i
3.
ASME Code Catecory:
B&C i
4.
ASME Code Section XI Recuir?ments:
These valves are not within the scope of ASME Code,Section XI. Subsection IWV requirements.- However, the requirements for stroke timing and trending vf the valves' associated with the Diesel Air Statt System are being mandated by the NRC as an augmented testing requirement pursuant to 10CTR50.55 (a) (g).
Therefore, valves associated with the Diese! Air Start System shall be exercised to the position required to fulfill their function during plant operation per IWV-3412 and INV-3522.
Additionally, the stroke testing of power operated valves shall be memsured to the nearest second end such-stroke times trended to document continued valve operational readiness per IWV 3413 f b ! Lad I'4V-3417.
5.
Basis for Relief:
The monthly Diesel Generator testing program, outlined in Byron Station's Technical Specifications and implemented by statirn operating procedures, exceeds the intent of the quarterly valve testing program which would be required by ASME Code,Section XI.
Additionally; the stroke timing of solenoid operated valves associated with the D'.essl Sir Start System is
=-
impractical due to the fast actuation of these valves 6.
Alternate Testino:
The performance of Byron Station's Diesel Generator ope ability monthly surveillance will verify the operational readiness of the valves associated with the_ Diesel Air Start System.
This' surveillance testing will require the recording of the air pressures contained in both-trains A & B of the Diesel Generator Air.. Start Receiver
~
Tanks both before and immediately after diesel generator start.
By the comparison of these valves between trains, the satisfactory operation of the power opareted and self actueted chack mlvas associated with the Diesel Air Star
- Svntem can be adequately demonstrated, (0095D/0035D/030491) 4.6 - page 18 of 37
.. -. -. -.. =
. ~. -. - - -...... -.
Rev. 10 7
Jng11ficatieltL Proper valve operation will be demonstrated on a monthly basis by the verificat?.
,f diesel genervet *i t statt espebtlity t
ech ?tification will compare the air pressures contaiaed 1;. the seceivet tanks both before and after the diesel generator statt, thus vet if ying the opera' llity of a
the air start control valves.
The preposed testing methodology at the j
increased frequency satisfies the intent of the Section XI requirements l
without poming undue hardships or difficulties.
8 Applicable Tire Pariedi This relief is requested once per quarter during the first inspection interval.
9.
Approval S tatJAg t a.
Relief granted per SER 4/15/88.
b.
Pelief granted !TPC Generic Letter 89-04.
i c.
Feliet granted per SER 9/14/90.
L h
4 5
i l
(0095D/003SD/030491) 4.6 - page 19 of 37
- - - ~-- -- - --
~ ~ - '
~~ -~~ ~~'~~~~ '~ ~
W Rev. 10 e.
i j
RELIEr PE2' JEST "P.14 3
..., p tp."
i Deleted relief request VR-14.
This was a request for exemption for position indicating tests for solenoid operated valves, Alternate i
testing allowed by the ASME Code will be used instead.
i l
I i
e l
l l
l I
i O
t 9
(0095D/0035D/030491) 4.6 - page 20 of 37 i
....-. -. - -. -. - -- - --._.... -,-.- -..--.-- _. -. ~ -,. :
~.
_. - ~ _. -
Rev. 10 PELIEF PEOtfEST VF-15 l
1.
Valve Number s t ICVB4RIA, B 2CV8481A. D tcV6%43 2CV8546 1516815 2518815 ISI8819A-D 2 SIB 819A-D ISIB841A,8 2 SIS 841A,B 1518900A-D 2S18900A-D ISI890$A-D 2 SIB 905A-D ISI8949A-D 2SI8949A-D 2.
Rumber of Valvest 44 3 -.
ASMt.. Code Cattacryt AC 4.
ASME Code,Section XI Pe2uirementgi Check valves that cannot be exercised durino plant operation shall be specifically identified by *he owner and shall be full stroke exercised during cold shutdowns per INV-3412 and INV-3522.
5.
B. asis for Reli1L1 The full stroke exercising of check valves not stroked quarterly is teq.ia:a to be performed during cold shutdowns.
However, the stroking Of check /alves 1(2) SIB 815, 1(2)S'89G0A-D, 1(2) SIB 949A-D, and 1(2)SIRP41A-B, associated with Emergency Core Cooling System, during cold shutdowns will induce thermal stresses on their respective reactor vessel nozzles as the Reactor Coolant _ System (maintained approximately 180' F) is injected with' water from the Refueling Water Storage Tank (maintained approximately 65' r.
This also applies to the stroking of check valves 1(2)CV8546 and 1(2)CV8481A,B because the full stroke of these check valves causes stroking of 1(2)SI8815 and 1(2) SIB 900A-D located in the full flow path.
Additionally, Byron Station Technical Specifications require all Safety Injection Pumps and all but one Chargirag 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)SI6819A-D, 1(2)SI8905A-D, and 1(2)SI8949A-D, cannot.be full stroke exercised during routine Mode-5 cold shutdowns as required by IWV-3412 and IWV-3522.
In addition to the stroke test exercise used to verify operational readiness of these check volves, the act of such stroking cause the necessity for Technical Specification required leak rate' testing of these valves prior to unit criticality This testina, in conytnction with the stroke exercising of the=a check valves, adds approximately one week to the duratiert of aat omttgr-end additional radiati.;n exposure to workers who must
.cnn.-- flowmeters and diftetential pressure anuoes directly to pipes-containing radioactive fluids.
(0095D/0035D/030491) 4,6 - page 21 of.37-
~
Pev. 10 Alternate Testinal 6.
Byron Station's Technical Specifications require routine leak rate testina to be performed on these Reactor Coolant System Boundary Isolation check
.als.-
if the unit is in Coll Shutdowr tot cr eat -r + h5 T '2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and such leak rate testing has not been pa t t ei.neu w i thin the previous nine months.
Therefore, Byron Station will stroke exercise check valves 1(2)SIBB15, 1(2) SIS 900A-D. and 1(2) SIB 841A.B on the smne schedule.
To prevent unnecessary stroking of check valves 1(2) SIB 815 and 1(2) SIB 900A-D, check valves 1(2)CVB546 and 1(2)CV8481A,B will be stroke exercised on the same schedule as check valves 1(2) SIB 815, 1(2) SIB 900A-D and 1(2)SIBA41A,B.
Additionally, stroke exercisino of check valves 1(2)SI8819A-D, 1(2) SIB 949A-D, and 1(2) SIB 905A-D can only be safely performed in Mode d with the Peactor Vessel head removed.
Full stroke exercising of these check valves will be perfori,ed at a minimum f requency of once each refueling outage.
7 dagtificati;ni Stroke exercisino the 1(2)CVn481A, B.
It2)CVAS46, and 1(21S18815, 1(2)8900A-D. and 1(2) SIB 84JA, U check calves on the s ame schedule as their tequired Technical Specification Reactor Coolant System Boundary Isolation leak rate testing will allow the coordination of testing activities without imposing additional check valve leak rate testing requirements.
Such activity coordination will optimize testing efforts and resources while adaquctely noi.aining the system in a state of operational readiness.
jap.us L 21eIS949A-D, 1(2) SIB 005A-D and 1(2)SIBB19A-D can not be stroked during cold shutdown without exceeding Technical Specification limiting condition for operation (LCO 3/4.5.3)
Since stroking these valves requires starting an SI pump.
Stroke exercising check valves 1(2)SI8819A-D. 1(2) SIB 905A-D and 1(2) SIB 949A-D at least once per Reactor Refueling mode of operation, will insure compliance with Dyron Station technical Specifications and minimize the possibility of low temperature over-pressurization of the reactor Coolant System.
3.
bSplicable Time Perio<11 This relief is requested once per quarter during the first inspection interval.
9.
h1TIoval Status:
a.
Relief granted per GER 9/15/0B for valves 1/2SIBB19A-D, 1/2 SIB 905A-D, and 1/2 SIB 949A-D: relief denied per SEP 9/15/88 for valves 1/2 SIB 815, 1/2 SIB 841A-B, 1/2 SIB 900A-D.
b.
Pevised (to address tiPC concerns) in Byron response *o SEP 12/16/90 (Byron Station Letter nn_t3:13.
c.
Felief granted per tiPC Genet ic tat 'e:
a-?;
d.
Felief granted per SEE o'14/00 (0095D/0035D/030491) 4.6 - page 22 of 37
.Pev. 10 I
EELIEF REOUEST VR-16 '
1.
Vsive N umhe r s :
ISIB811A. B RSIB811A, B 2,
d_ umber of Vejy*_g.1 4
3.
ASME Code Cateoory:
B 4.
ASME Code,Section XI Recuirements:
1 Valves that cannot be exercised during plant operation shall be 4
specifically identified by the owner and shall be full stroke exercised during cold shutdowns per IWV-3412.
5.
pasis for Relieft The full stroke exercisino of valves not stroked quarterly is required to be performed during cold shutdowns.
However, the stroking of-the Containment Sump Outlet Isolation Valves. 1/2 SIB 811A,D requires the suction of the Residual Heat Removal Pumps to be drained, thus rendering one train of the system inoperable.
For Cold Shutdown operations with the Reactor Coolant Loops filled and one train of Residual Heat Pemoval declared inoperable, Byron Station's Technical Specifications require two s team gener a tern wits. a secondary' side narrow range water level greater *han 41% f t'ni c
- 1.. m.J greater than 18% (Unit 2).
However, if the cold shutdewn was necessitated by a problem requiring draining of the secondary side of the Steam Generators (i.e.
tube leaks), Byron Station's Technical Specification 3.4.1.4.1 would preclude the testing of the containment sump outlet isolation valves until such time as the affected steam generators had been refilled.
For Cold Shutdown operations with the Reactor Coolant Loops not filled (i.e. drained down to support Reactor _ Vessel Incore Seal Table, Loop Stop Valve, Reactor Coolant Pump and Seal Maintenance or primary leakage),
Byron' Station's Technical Specification 3.4.1.4.2 would preclude the testing of the Containment Sump Outlet Isolation Values as it mandates -
that "two residual heat removal (RHR) Loops shall be operable and at least one RHR Loop shall be in operation.
6.
Alternate Testinct Byron Station will full stroke exercise the-Containment Sump Outlet Isolation Valves, 1/2SIBBilA. B during refueling outages vice cold shutdown.
(0095D/0035D/030491) 4.6 - page 23 of 37 l
- ~ ~ ~ - ~ - ' -
~
'~ '
v Rev.;10 7.
IgtLif ic ation s -
The full stroke testing of the 1/2 SIB 811A, D valvest in conjunction with system draining, tillfre 'nd venting of each trela ccounts for ar.
additionel six days'(3 days per train) of scheduling requirements and increased radiation dose to operators and radiological control aersonnel.
Processing of thousands of gallons of cont aminated water, and subsequent required liquid effluent discharges would also result from the draining, refilling and venting of the RHR system.
This time duration required to perform the surveillance testing of the Containment Sump Outlet Isolativn valves during Cold Shutdown ectivities, could, as a result, cause a violation of the action requirements for Byron Station's Technical specifications 3.4.1.4.1 and 3.4.1.4.2.
The violations would occur since these action statements require (as noted in their respective foot note sections) the return of th* 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 vich loop was removed for surveillance testing provided the other RHR Loop.is operable and in operation.
14 addition, NRC Generic-tetter 88-17. Loss of Decay Heat Removal, high1.ights 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 warit conditions, boiling in che enre would occur in approximately 10 minutes, the core would * -
i tacovared in approximately 30 minutes. and fuel damage would oce. in approximately I hour.
Given the apparent disparity between the Technical Specification time requirements fer 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 ce perform surveillance stroke testing of the Contalmnent Sump Outlet Isolation valves (3 days) during Cold Shutdown, the proposed alternate testing frequency of refueling outage-periodicity will adequately maintain the system in a state of operational readiness, while not imposing undue hardships or sacrificing the safety of the plant.
8.
Applicable Time Period:
This relief is requested once per quarter, during the first inspection Interval.
1 9.
Aeproval Statust-l l
a.
Relief denied per SER 9/15/08 b.
Revised (to address NPC concerns) in Byron response to SER 12/16/90.
c.
Pelief arantad par SER o' 14 / GO.
l (0095D/003SD/030491).
4.6 - page-24 of 37
~
Rev. 10 EELiff_ f.I'Mff T '? P - 1 '
1.
'Lelve Numbern 1SX101A
- SX101A 2.
!!w t er Of Valven 2
3.
ASliE Code OLiggory:
0 4.
ASME C0db. Se c t ion KL_Eg quznentn Stroke time and trend the stroke time for power operated enives per IWV-3413 and IWV-3417, 5.
Pasis f o r R eligli 1/2SX101A are the essential service water outlet isolation valves for the Unit 1/2 motor driven auxiliary feedwater pump lube oil coolers.
These
/alves are completely ancapsulated per dasign and do not have local at temote position indicators which could ba used to time the alve stroke.
6.
Alternate Testino:
1/2SX101A will be verified te epen during each quarterly ASME surveillance of the motor driven auxiliary feedwater pumps.
In addition, these valves are stroked monthly Jutiac Pux111ary feedwater pump surveillances required by Byron Station Techaic31 9p*3cifications.
7.
Lustificatioju These /alves will be stroke axercisad to their required safety positions each month dur ing the motor driven auniliary f eedwater pump surveillances.
This testing will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant.
8.
r'GV l i c ialtlinE. Pe r i 0di This r* lief is requested once per quarter during the first inspection interval.
9.
Approval Stmigi:
a.
Pelief granted per SER 9,15/88.
b.
Pelief granted per NRC Ger. etic Letter 69-04, c.
Pelief granted par SEP 14
'M.
( 009 5D/ 003 5D/03 04 91 )
4.6 - page 25 of 37
1 Rev. 10 RELIEF PEOUEST JJ-13 1,
Eglve Number s t See Table below:
2 N unbe r o f V alves :
106 3.
ASME Code Catecory:
AC and C 4.
bj$liCde,Section XI Pecuirement Exercise for operability of check valves every three (3) months, per IWV-3521.
5.
Basis for Relief:
The valves listed in the Taole below cannot be safely full-stroke exercised (Ct) open and/or back-flow tested (8t) closed during plant operation or cold shutdowns, as required by the ASME Code.
MRC Generic Letter 89-04, Attachment t,
Positions 1, 2,
and 3 provide guidelines for method and frequency of testino 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.
Alternate Testing:
Refer to 'the Table below for a list of valves. d;raction, and alternat testing frequency requested:
ALTERNATE VALVES DIRECTION TESTING FREOUENCY 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/Open-Note 1/ Note 1 1/2CS008A,B Close Note 3 1/2CV8113 Close/Open Note 1/ Note 1 1/2IA091 Close Note 1 1/2PR002G,H Close Note 1 1/2PR032 Close Note 1 1/2PS231A,8 Close Note 1 1/2RH8705A.B Close/Open Note 2/ Note 5 1/2RYB046 Close Note 1 1/2RY8047 Close Note 1 1/2SI8815 Close Note 2 1/2 SIB 818A-D Close Unte 2 1/2 SIB 819A-D Close Mete 2 1
1/2 SIS 641A,B Close flo t a ?
t/=. SIB 900A-h Close Note 2 1/2SI8905A-D Close Nota 2 1/2 SIB 946A-D Close Note 2 1/2SI8949A-D Close Note 2 1/2SI8956A-D Close Note 2 1/2 SIB 968 Close Note 1 1/2WM191 Close Note 1 1/2WOOO7A B Close Note 1 (0095D/0035D/030491) 4.6 - page 26 of 37
=
Rev. 10 Table Notes:
1)
Perform test during refuelino outages in conjunction with Appendix J, Local Leak Pate Test.
See IST Program Raller Peg *t e s t VR-1.
2)
Perform test during refuelino outages in conjunction with Byron Station Technical Specification seat leakage testing.
See IST Program Note 6.
3)
Perf orm test during ref ueling 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, V R-6, VR-8, and VR-15 for additional check valve testing frequency extensions.
- 5) These valves are verified to be operable by observation of.
depressurization in the applicable line.
This is a test method which was approved by the NRC in SER 9/14/90.
7 Justificati2n!
7esting these check valves on the same schedule as their require v
. t.
!sakage tests will allow for coordinati'n of testing 2"*.lvitic; *;<.uant imposing additional check valve leak rcce testing. requirements.
Such activity coordination will optimize testing efforts and resources while adequately 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 1/2AP001A,B (close), 1/2CS008A,8 (close), and 1/2RHC70$A,B (open).can only be performed by disassembly and inspection due to system design and nperating constraints. These tests can only be safely performed during refueling outages when the affected systems are isolated and drained.
~
8.
Ago11 cable Time Period:
This relief is requested once per quarter during the first inspection interval.
-9.
Aporoval Status:
a.
Relief granted per NRC Generic Letter 89-04.
~
1 i-(0095D/0035D/030491) 4.6 - page 27 of 37
r 1'
~ "
Rev. 10 BELIEF PERUEST VP-19 1.
valve Numbein:
1AF001A,B 2AF001A,8 1C50038,0 F20?]A.D 1CE006A,b 2CS00BA.D 1CS020A,B 2CS020A,B 2.
Number of Valves:
16 3.
-4.
ASME Code. Section KI Recuirementt Exercise check valves to the position required to fulfill their function (open = Ct; closed = Bt), unless such operation is not practical during plant operation, per INV-3522.
5.
Basis for Felief:
These check valves cannot be full-stroked exercised (Ct) using NRC Generic Letter 89-04, A t t ac.Nne nt 1,
Position 1, because the " maximum required accident flow" cannot be passed through the CC, CS, and RH valves and a backflow test (Dt) cannot be performed on the AF valves.
These tests j
cannot be performed due to system design and operation configurations, 6.
Alte rnate 'raitim-
.These valves will be selected f or sample disassembly and inspection by t
choosing one valve from each of the groups listed below during each l
refueling outage.
Normally, valves selected for disassembly will be alternated such that a different train is inspected each outage.
R QUP-DIPECH ON VALVES 1
Closed 1/2AT001A.D 2
Open 1/2CS003A,B 3
Open/ Closed 1/2CS008A,8 4
Onen 1/2CS020A B 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 structurally sound (no loose or corroded parts).
If the disassembled valve is not capable of beino manually stroked or there L
is binding or failure of valve internels.'the remainina valves in the'same j.
group on the affected uns* will be d! assembled and inspected during the l --
same refuel outage, -sad tha unat te ;te,4 nuit >alves in tha smne group ohall l
be. disassembled and in=pseted at the next scheduled refuelino outage.
L (0095D/0035D/030491) 4.6 - page-28 of 37
o r.
i Rev. 10 Extension;of the valve disassembly and inspection interval must meet the extension justification tequigements of NRC Generic Letter 89-04,.-Position 2.
Note that relief from CS System check valv: testing has previously been
-approved by Relief 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 testing.
7 Iggtification:
{
This alternative testing is in compliance with specific guidance on check j
valve testing as required by !!RC Generic Letter 89-04, Attachment 1,.
Positions 1, 2,
and 3.
This testing will adequately maintain the-4 components in n state of operational readiness and, by testing the volves during refuel outages when the valves can be safely examined, will not sacrifice the safety of the plant.
8.
lgplicable Time Pet W This relief is requested once per quarter during the first inspection I.
interval.
i 9.
Approval Status Relief granted per NRC Ceneric Letter 89-04.
a.
(0095D/0035D/030491) 4.6 - page 29-of 37
_ _ _ _ _ _ _ _ _~_ _ _ _ _ _,. _... -. _ _ _ _. _ _
~
l l
Rev. 10 l
i i
i DRAFT RELIEF PEQUEST VR-20 1.
L'alve Nu eben:
1/2Ar006A 1/2CVR116 1/2PS9357A.B 1/2S18813 1/1Ar0068 1/2CV8152 1/2RE1003 1/2S18814 1/2AF013A-H 1/2CV8160 1/2RE9170 1/2SI8821A,8 1/2Ar017A,B 1/2CV8804A 1/2RF026 1/2S!8835 1/2CC685 1/2rF010 1/2Rr027 1/2Sr$840 1/2CC9412A,D 1/2FWOO9A-D 1/2RH8701A,B 1/2 SIB 880 1/2CC9413A 1/2rWO35A-D 1/2RH8702A,B 1/2518888 1/2CC9414 1/2rWO39A-D 1/2RY455A 1/2S18920 1/2CC9416 1/2FWO43A-D 1/7RY456 1/2518924 1/2CC9437A,B 1/2IA065 1/2RYB000A,B 1/2S18964 1/2CC9438 1/2IA066 1/2RYB025 1/2SX016A,B 1/2CC9473A,B 1/2MS001A-D 1/2RY8026 1/2SX027A,B 1/2CS001A,B 1/2M5101A-D 1/2RYB028 1/2SX112A.B 1/2CS007A,B 1/20G057A 1/2SA032 1/2SX114A.B 1/2CS009A.B 1/2OG079 1/2SA033 1/2SX169A,B 1/2CS019A.B 1/20G080 1SD002A-H 1/2SX173 1/2CV1128-E 1120G081 1/2SD005A-D 1/2SX17R 1/2CV8100 1/20G082 1/2SI8801A B 1/2VQ001A,B 1/2/CV8104 1/20G083 1/2 SIB 802A,B 1/2VQOO2A.B 1/2CV8105 1/20G084 1/2S18804B l ' 2 vWO S 1/2CV8106 1/20G085 1/2818806 1'? W.'01A,B 4
1/2CV8110 1/2PR001A.B 1/2 SIB 807A,B 1/2VQ005A-C 1/2CVB111 1/2PS9354A,B 1/2SI8809A,B 1/2WOOO6A,B 1/2CV8112 1/2PS9355A,B 1/2SI8bilA B 1/2 WOO 20A.B 1/2CV8114 1/2PS9356A,B 1/2 SIB 812A,B 1/2 WOOS 6A,8 2.
Number of Items:
340 3.
ASME Cedel atecorvt A and B 4.
ASME Code.Section XI Recuirements:
Verification, by trending of power-operated valve stroke times, that an increase in stroke time of 25% or more from the previous test (for valves with full stroke times greater than 10 seconds), or 50% or more (for valves with full stroke times less than or equal to 10 seconds) does not occur, per IWV-3417(a) (see Technical Approach and Position VA-04),
l S.
Basis fer Felief:
Trending stroke times. based on the percent chance from the prevleus test, as ASME Section XI requires, allows '2reduel decredstion to occur over a lona cerind of time without triggerina the edditional trending atteneina t '! b t. incre!.ied testing frequency iequires An improved teethod of component performance monitoring is proposed. which will require a volve 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.
l l
(0095D/0035D/030491) 4.6 - page 30 of 37
Rev. 10 O
DRATT RELIEr FEOUEST VR-20 6.
Alternate Testin28 ror all power-operated valves which normally stroke in greater than two seconds, an ALERT RANGE will be established based on reaching a given percent change from the reference value established via NRC Ceneric Letter 89-04.
The following table will be used as a star.tip eeint in evaluation of this fixed ALERT RANGE:
VALUE REFERENCE ALERT RANGE REQUIRED ACTION VALUE TYPE STROKE TIME (Tref)
MOV's
> 10 sec.
(1.25)(Tref)-(1.75)(Tref)
> (1.75)(Tref),
SOV's or but 1 (Tref + 20 rec)
HOV's (Tret+10 sec)-(Tref +20 see)
AOV's tio te s :
A.
Fast acting valves (valves which normally stroke in less than 2 seconds consistently) are included in Relief Request VR-12.
These valves are n2t assigned ALERT RANGES and are n21 trended.
B.
In all cases, the REQUIRED ACTION VALUE cannot exceed Technical Specification or UTSAR values, regardless of calculated values.
C.
The above Table is a guideline and cannot cover all valves.
The ALERT RANGEC and REQUIRED ACTION VALUES are selected based on the comparison between the REFERENCE VALUE, limiting value given in Technical Specifications /UTSAR, and calculated values using the table above:
- 1) All values are rounded to the nearest whole second.
- 2) Valves which serve the same function on dual trains (i.e..
ICC9473A and ICC94738) and dual units (i.e.,
ICC9473A and 2CC9473A) are assigned the same REQUIRED ACTION / ALERT RANGE VALUES based on human factors considerations, unless valve or system design differences exist between the trains / units.
Refer to IST Technical Approach and Position VA-04 for related information.
O 1
(0095D/0035D/030491) 4.6 - page 31 of 37
Rev. 10 DRAFT PELIEF RE7 JEST VR-20
?
h1LLilrJLLL2D s Using fixed ALERT RANGES based on the valve REFERENCE "ALUE established when the valve was known to be operating acceptably will ensure that gradual valve performance degradation is monitored and evaluated, by placing the valve on increased testing frequency when the stroke time exceeds a fixed multiple et the PEFERENCE VALUE.
This method is superior to that required by the ASME Code in that the point of refetence used to evaluate the performance trend on a valve remains fixed.
This alternative utilizes the same stroke time percentaae change values as raquired by the ASME Code to place a valvo on increased frequency testing.
8.
APrlhlLl1EL1L.fJLLi241 This relief is requested once par quarter. during the first inspection interval.
9.
Appigral Status:
Since this relief request is a new submittal and is not specifically addressed in NRC Generic Lette.' 6v-04, it-is t{QI approved for use.
Formal written approval from the t; P
in -aquireL pil2I to implemet.tation.
Expedit*ous review and approval is requested.
(0095D/0035D/030491) 4.6 - page 32 of 37
1 J
Rev. 10-j-
DRATT RELIEF PEQUEST VR-21 il if 1
i-
"WITHDRAWH" t
l l
This relief request was in draft form and was later withdrawn per SER 9/14/90.
l l
i l
I l
J i
i
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r (0095D/0035D/030491) 4.6 - page-33 of 37
F Rev. 10 IllTERIM RELIET REQUEST VR -:
1.
Valve Numbezu:
t/2 SIB 618A 1/2 SIR 94RA 1/2SI8841A 1/2SI8818B 1/2S18948B 1/25I88418 1/2 SIB 818C 1/2 SIB 948C 1/2 SIB 818D 1/2 SIB 948D 2.
tiumber of Items:
20 3.
ASME Code Cateoorv:
AC 4.
ASME Code,Section XI Recuirements:
Exercise check valves to the position required to fulfill their function (open = Ct; closed = Bt), unless such operation is not practical during; plant operations, per IWV-3522.
E-n Station's testing methodology meets this requi rement.
However. 11RC Ge te Letter 89-04, Attachment 1, Position 1 requires that the flow t t. augh individual valves be known, and specifica?.ly states that knowledge of total flow through inultiple lines does not provide verification of flow rates through the individual valves snd is not a valid full-stroke exercise.
5.
h.cfd
- Cu r fdlie f :
The current Dyron Station testing methodology uses available flowmeters to measure the total flow through two parallel check valves.
These are given I
below CHECK VALVES FLOW If1DICATIOtt ISIB818A & ISIB818D ITI - 618
-1 SIB 818B & 1 SIB 818C ITI - 619 ISIB841A & 15I8841B IFI - 618
_1SI8948A & ISIB948D ITI - 618 ISIB94BB & 1 SIB 948C 1rI - 619 There is currently no method available to measure the flow rates through the individual-check valves.
Hodifications to these lines to install flow measurement devices for the individual valves is not warranted due to the following reasons:
A.
Flow indications exist for each pair of check valves.
It would be readily apparent from the flowrates recorded during each refuel outage if individual check valves were not opening or were only partially opening by comparing the flowrotes recorded through each pair of check valves.
D.
Byroa Station letanicat Specifications disregard the highest branch line fleNt ute when determining the minimum required flowrates through these parallel injection lines.
Therefore. slight differences in individual branch flowrates which could exist by measuring the total flowrate through two parallel injection lines was anticipated and accounted for when Byron' Station's Technical Specifications were formulated.
(0095D/0035D/030491) 4.6 - page 34 of 37 m...
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v Rev. 10 l
INTERIM FELIEF REQUEST VR-22 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 expensi"e.
increase radiation dose, and possibly impact safe operation of the plant.
The modification would require extensive engineering and installation costs, alono with replacement power costs, to install.
Byron Station Technical Specifications require an ECCS full-flow balance test to be 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 ccre ;ffload.
Both of these activities pose an increased <$fety h=: ara +o pla..t personnel and equipment, by requiring unusual system alignme nt s for extended periods of time during a refuel outage when other activities inside containment are at their highest level.
The alternative to individual check valve flowrate measurement required by NRC Generic Letter 89-04 is disassembly and inspection.
Disassembly and inspection is not a viable option for the ECCS injection line check valves due to the following concerns:
A.
Radiation Dose-The radi
.._n se increase to disassemble, inspect, and reassemble these check valves each refuel outage would be several man-rem.
D.
Safe Operation:
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 isolata PCS branch connactions during refueling outages.
1 1
(0095D/0035D/030491) 4.6 - page 35 of 37
~
Rev. 10
-1 INTERIM RELIET REQUEST VR-22 C.
Check Valve Operating History:
A search of maintenance history (TJM) on these valves for both Byron and Braidwood Nuclear Power Stations revealed the following past maintenance activities on these check valves:
1/2S18818A None 1/2SI8818B None 1/2SI8818C None 1/2SI8818D None 1/2SI8841A None 1/2SI88418 None 1/2SI8948A Mone 1518948B Replaced disc arm acsembly and gasket, retorqued flange bolts 10/20/84 (Byron) 2S18948B None 1SI8948C Inspected internals, no parts repaired or replaced, tetorqued flange bolts 9/10/04 (Byron) 2 SIB 948C Hone 1/2SI8948D None This history does not indicate any adverse operating history for these valves; therefore, disassembly and inspectiun of th6se valves is nqt warranted based on previous maintenance history.
6.
Alternative Testing:
In lieu of disassembly, Dyron Station proposes the following tests (which are already being performed):
A.
A full stroke test of each check valve is verified at least once per 18 ennths during refuel outages by verifying the total flow through each set _of two parallel check valves utilizing-existing permanently installed flow indicators.
B.
A seat leakage test of each check valve is performed as required by Byror Station's Technical Specification on RCS leakage.
These leak test 9 are performed:
- 1) At least once/18 months, 2 )-
Prior to Mode 2, whenever the plant has been in COLD SifUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and if leakage testing has not been performed in the previous nine (9) months, 3)
Prior to returning the valve to service f ollowing maintenance, repeir, or replacement work on the "alve, 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 automa*ic c
manual actica or flew through the valve.
C.
Ar. ECCS f ull flow balance test is performed following the completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics as required by Byron Station Technical Specifications.
(0095D/0035D/030491) 4.6 - page 36 of 37
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- ~. - ~. _. - - - - ~..
Rev. 10 i
INTERIM 1
RELIET REQUEST VR-22 7
Justificatient Byron Station *s Technical Specifications require these check valves to be full stroke tested and seat leakage tested at a minimum frequency of.once per 18 months.
These tet.ts satisfy all of the ASME check valve exercise requirements (open and close) and all of the NRC Generic Letter 89-04 full-stroke and backflow testing requirements, except that flow is measured through pairs of injection 11ae check valves instead of individual-injection line check valves.
The burden imposed by either disassembly 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 fact that Dyron Station has previcusly received a favorable Safety Evaluation Report (SER) on its Inservice Testing Program af ter years of in-depth review by the:
NRC.
Also, it is readily apparent that Byron Station was not originally designed to allow for either individual injection line flow measurement or for fisassembly and inspection of the injection line check va.1ves un w
teqular basis without extreme hardship on plant operations ond main'.ee*?..*
{
during critical refueling outage periods.
The current testing 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.
Aeolicable Time Periodt This relief is requested once per quarter during the first' inspection interval.
9.
Aceroval Statunt a.
Interim relief. granted for six (6) month period or next refueling outage (whichever is longer) per SER 9/14/90.
O (0095D/0035D/030491) 4.6 - page 37 of 37
1 ENCLOSURE 4 i
l I
5 PLB/scl:lD867:18
Chances comprisina IST Program fgr-Valves Bevision 10a
.Section i.d-Table 91 Contents a
1.
Changed VR-19 description to " Auxiliary Feedwater Check Valves" to reflect changes to VR-19 listed below section iol Procram Description No changes to this section Section 4.2 Procram References No changes to this section Section 4.3 Program Tables
- 1. Removed reference to use of leak rate test to satisfy backflow test requirements in item 1 of the " TEST METHOD" of the " TABLE DESCRIPTION" section. This information is provided in VR-18.
2.
Removed "VR-18" references from table listing for 1/2AF001A,B valves to reflect changes to VR-18 listed below
- 3. Removed "VR-18" and "VR-19" references from table listing for 1/2CS008A,B valves to reflect changes to VR-18 and VR-19 listed below I
4.
Removed "VR-19" reference from table listing for 1/2CS003A,B and 1/2CS020A, B valves to reflect changes to VR-19 listed below Section 4.4 Notes No changes to this section Section 4.5 Technical Approaches and Positions _
- l. Modified VA-04 to show a-fixed alert range of 1.25 to 1.50 times the reference stroke time value for MOV's with reference stroke time values of 10 seconds or less. This change was made to reflect NRC concerns on more conservative alert ranges for MOV's section 4.6 Relief Reauests page 1 of 3
l
- 1. Revised VR-2 in recponse to NRC comments concerning the number of different systems referenced on Reliet Pee est VR-19. This involved transferring information frem
- (- 19 to VR-2. This information consisted of details on the impracticality of p9rforming visual inspections on the 1/2CS020A,B valves during refueling outages using a sample disassembly plan 2.
Revised VP-4 in response to URC comments concerning the level of detail contained in VR-4; the number of different systems referenced in VR-18 and VR-19; and proceduralized verification of preper valve installation:
- Provided detailed information on the detrimental effects of attempting to full flow test these valves (1/2CS003c, B and 1/2CS008 A, B)
- Provided detailed information on the ease and safety with which these valves can be removed for visual inspection Transferred information previously contained in
~ VR-18 pertaining to the back flow testing of these valves
- Transferred information previously contained in VR-19 on the practicality of performing this inspection during refueling outages using a sample disassembly plan
- Added a detailed description of the procedure used to verify proper post-inspection re-installation of these valves
- 3. Revised VR-18 in response to NRC comments concerning the number of different systems referenced in VR-18 and the level of detail provided on testing frequency discussed in note 2:
- removed 1/2CC9486 "Open" test direction information from table to correct a typing oversight
- removed informaticn on backflow testing of the 1/2CS003A,B valves (this data is now contained in relief requests VR-4)
- removed the information on backflow testing of the 1/2CS008A,B valves (this data is now contained in relief requests VR-4)
- removed the information on backflow testing of the 1/2AF001A,8 valves (this data is now page 2 of 3
)
contained in rollef request VR-19) removed reference to 1/2RH8705A,B v11ve:1 fr,
juntification section to correct a :ypias o;cor revised table note 2 to provide more detail.on the testing frequency for valves covered by this noto i
4 ~. Revised VR-19 in response to NRC comments concerning the number of different systems referenced in this relief request and the feasibility of performing a backflow test on the 1/2AFOCIA,B valves:
Removed the 1/2CS003A,Bt 1/2CS008A,B.
1/2C3020A,B sample disassembly plan inrormation (this data is now contained in relief requests VR-2 and VR-4)
Added detailed information on the infeasibility of backflow testing the 1/2AF001A,E valves; the-ease with which these valve can be removed, inspected and re-installed; and the practical 1ty of performing this inspection during refueling outages using a sample disassembly plan
- 5. Modified VR-20 to show a fixed alert range of 1.15 to 1.25 times the reference stroke time values for MOV'.s with reference stroke time values greater than 10 seconds i
to reflect NRC concerns on tighter alert ranges for MOV's; and changed less than or equal to symbol to a greater than symbol to correct a typing error
- 6. Various other cosmetic changes with no technical impact were made to improve the general appearance of the Program documentation.
page 3 of 3 v
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l ENCLOSURE 5 f
d i
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i PLB/scl:lD867:19
Rev. 10a l
l-4.5 Technical-Approaches and Positions VA-01 Method of Stroke Timing Valves VA-02 Method of rail Safe Testing Valves VA-03 Method of Exercising Check Valves VA-04 Deterinining Limiting Values of Tull-St toke Times for Power-Operated Valves.
(reference stioke time (10 seconda) 4.6 Relief Requests 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 Hender Check Valves VR-5 Accumulator Discharge Check Velves Testing Frequency VR-6
$1 Pump Suction Check Valve VR-7
" Deleted" (Incorporated into VR-12 ami VR-17).
VR-8 Component Cooling RC Pump Thermal Battler Valves VR-9 RC Pump Seal Injection CV Check Valver VR-10 In.etrument Air Contalsment Isolation Valves VR-11
" Deleted" (per EG & G recommendation)
VR-11 Trending of Fast Actuating Valves VR-13 Diebel Generator Air Start Valves VR-14
" Deleted" (using ASME method instead of requesting exemption from position Indication testing of soledold operated valves)
VR-15 Safety Injection ECCS Check Valve Test ing during Refueling Outage VR-16 Containment Sump Outlet Isolation Va]ve Testing During Refueling.
VR-17 Motor Driven Auxillary Teedwater Pump h.O. Cooler Solenoid Valve-Stroke Testing VR-18 Check Valve full Stroke (Ct) and Dack riow (BL)
Testing During Refueling Outages, i
VR-19 Auxillary.Teodwater Check Valves l
Draft VR-20 Trending of Power-Operated valve Stroke Times (reference stroke times >10 seconds)
VR-21 Draft " Withdrawn" per SER 9/14/90 Interim VR-22 Full-Stroke Check Valve Testing (Ct) Hethodology for Safety Injection Valves, (0092D/0034D/051791) 4.0 - page 2 of 2 i
r I
l< c v. 10a 1
L.
ILST Ml:T!!OD The test method column identifies speelfic tests which will be performed on specific valves to fulfi1J the s eguirements of Subsection IWV of ASME Section XI.
The tests and abbseviations used age as follows:
1.
(lit) Check Valve 11ack Flow Test i
The check valve disc will be exe cised to the closed position required to fulfill its safety function by veritying thht the disc tr avels to the sent ptomptly on cessation or revessal of fluw.
2.
ICtLChecLValvelu1LStr oke _Tes t The check valvo disc will be exe cised to the open pos!Llon required to fulfill its saf ety f unction by vtu i f ying t he maximum I
required accident flow through the valve or alt ernatives to f ull-flow testing, per NHC Generic Letter 89-04, At t achment 1, Positions 1 and 2.
3.
If tLIall Sale legit.
Valves with fall safe actuators will he teated to verify the valve operator moves the valve stem to the required fail safe a
position upon loss of actuating power, in accor dance wit h IWV-3415.
This will be accomplished during the normal sitoking of the valve. tIpon st king a valve to its fall safe position, the solenold operntor is de-enetgized causing air to be vented which a
in turn allows the spring to move the valve to its fall safe position. This condition simulates loss of act unting powet' (Electric and/or Alt) nr.d hence satisfies the fall safe test requirements of IWV-3415.
4 4.
IILLPosillonJndication_ Check Valves which are Identitled to seguire o Posit ion Indiention Test will be inspected in accordance with IWV-3300 of ASHf;Section XI.
5.
ILtLSeatlenkage.les t he sent leakage tests will meet the requirement u of IWV-3420 for Category A valves.
On theon valves, seat lenkeye is limit.ed to a speelfic maximum amount in the closed position for fulfillment of their safety function.
+
(0092D/0034D/051791) 4.3 - page 3 of 5
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t 4 1 6 1 6 1 4
1 NN Nw SN5m A 57 AN NN NN 5N %w 5N NP NP NN NN
-F 1
5 I
l1 l1 li l 1 l1 lli 1li I1 l1 l1 i 1 f
i l1 lI
!I l1 iI 0
/
0 A
8 A
8 A
B A
s A
s a
9 A
s A
s 0
R 1
1 3
3 7
7 S
s 9
0 1
9
?
0 0
4 E E 0
0 0
0 0
0 0
0 0
0 e
1 1
i 2
2 0
N V B 0
0 0
0 0
c 0
0 0
0 c
0 0
o 0
c s
s s
5 5
s 5
5 s
s s
s s
s 5
s L M; C
t C
C t
C C
C t
C C
C C
C C
C D
A A
2 2
3 n
2 2
2 2
2 n
n 2
C n
n n
V f 2
/
/
/
/
/
/
/
/
9
/
1 i
1 1
1 1
1 I
I 1
I i
i' 1
1 00 1llll1j llil )ll l ll l ll i1 ll lt jll 1 ]1 l ll!l
(
l 1
l l(fl i
lll jllfllll l!
1l
-.m..
Rev. 10a i
i The 1983 Edition through Summer 198) Addenda of ASME Section XI does not provide guidance for determining values of full stroke.
Ilowever, it does ptovide requirements for when to start, monitoring a valves perf orinance on a more frequent basis, also known as alert range testing.
If a valve strokes it 10 seconds or less, a 50% inesease over the previous value i
teqiltes it to be put on a monthly test f requency, and for valves st roking in greater than 10 seconds, a 25% increase over the previous value requires it to be put on a monthly test frequency (see VR-20).
Trending stroke times, based on the percent change from the prevlous test, as ASME Section XI requises, allows gradual degradation to occur over a long period of time without triggering the additional trending attentlon that increased testing frequency requires. Therefoto, an improved method of component performance monitoring is employed which requires a valve to be placed on increased test faequency based on the percent change faom the fixed reference value established via NRC Generic Letter 89-04, Attachment 1, Position 5.
This criteria, in conjunction with establishing reference / average values of full-stroke, should allow for reasonable deviations in stroke tline measurements without declaring a valve.uc.erable.
The cortective actions specified in IWV-3417(b) of Section XI and as described in IST Program Rollef Request VR-20 will be taken when a valve exceeds its limiting valuJ of full stroke.
C.
Poaltion:
The following criteria will be used as general guidance to establish ALERT and REQtlIRED ACTION Anges for power-operated valves:
SQYin/J10Vis1AQV h_ Leas _ than_otequeLto_10_sc. condo ALERT RA11GE:
(1.50) (T,,g)
(2.0) (Tref)
REQUIRED ACTIott VALuct
> (2.0) (Trer)
MOVit._Le s slba: Lor m.r Lto_10_ seconds:
ALERT RANGE:
(1.25) (Tref) - (1.50) (Trcf I j
REQUIRED ACT10tl VALUE:
> (1.50) (Treg)
MOV'm/.SOVis/J10VisLAQYis_ _Gtentetlha:L1!Lseconds :
See VR-20; this technical approach and position will not be put into L
application-until-relief request VR-20-la approved.
'h (0109D/0041D/051791) 4.5 - page 7 of B
i 1
SECTION 4.6 RELIEF REQUESTS t
4 l.
l r
4
_. - ~., -. _. _ _ - _,, _,
_.m Rev. 10m c
a 11ELitLREQUESLVIE1 i
1.
ValVeJhnber l
A1,1 prlinary contaiteent isolation valves in this psogram are listed as j
Category As VALVE _t VMNEI YALVE.1 l
1) 1CC685 41)
IPR 033B 81) 1518964 I
2) 1CC9413A 42) 1PR033C 82) 1518968 i
3) 1CC9414 43)
IPR 0 3 3t>
83) 1VQ001A 4)
ICC9410 44) 100066 84)
IVQ00111 5)
ICC9438 45)
IPS220A B5)
IVQOO2A 6) 1CC9480 46) 1P5228B 86)
IVQ002 ft l
7) 1CC9518 47)
IPS229A B7)
IVQOO3 l
8)
.1CC9534 4n)
IPS2290 88) 1VQ004A 9)
ICS007A 49)
IPS230A 89)
IVQ004D l
10)
IC5007B
.50) 1PS23011 90) 1VQ005A i
11)
ICS008A 51)
IPS231A 91) 1VQ005!1 12)
ICS008B 52) 1PS231D 92)-
IVQ005C f
13)
ICV 8100 53) 1PS9354A 93)
IVQOl6 l
14)
ICV 8112 54) 1PS9354B 94) 1VQ017 15)
ICV 8113 55)
IPS9355A 95)
IVQOla 16)
ICV 818> 2 56) 1PS9355B 96)
IVQO19 17)
ICV 8160 57)
IPS9350A 97)
IWH190 18) 1PC009 50)
IP!;93 56tt 98) 1WH191 19)
IPC010 59)
IPS9357A 99)
IWOOO6A 20)
IPC011 60)
IP39357D 100)
IWOOO6B-21)
IPC012 61) 1RE1003 101)
IWOOO7A 22) 11A065 62) 1RE9157 102)
IWOOO70 23) 11A006 63) 1RE9159A 103)
IWOO20A l
24) 11A091 64) 1RE915916 104)
IWOO20!i 25) 100057A fi5 )
1RE9160A 105) 1W0056A 7
26) 10G079 66) 1RE9160D 106)
IWOOb68 27) 10G080 67) 1RE9170 28) 10G081 68) 1RP026 29) 10G082 69) 1RP027 30) 10G083 70) 1RY8025 31) 10G004 71) 1RYB026 32) 100085 72) 1RYP028 33)
IPR 001A 73) 1RY8033 34)
IPR 001B 74) 1RYB046 35)
IPR 002E 75) 1RY8047 I
36)
IPR 002P 76)
ISA032 I
-37)
IPR 002G 77)
ISA033 I
38)
IPR 002H 7R) 181RR71 39)
IPR 032.
79)_
1518nn0 40)
IPR 033A HO)
IS1AHCH i
(0095D/0035D/051791) 4. t. - page 1 of 39
Rev. 10a l
1.
Valve _Bambers (Continued) i VALVE _t V ALY L.. l VALVI_t 107) 200685 147) 2PR033D 187) 2518964 108) 2CC9413A 148) 2PR033C 188) 2518968 109) 2CC9414 149) 2PR033D 189) 2VQ001A f
110) 2CC9416 150) 2PR066 190) 2VQ001B i
111) 2CC9438 151) 20S228A 191) 2VQ002A 112) 2CC9486 152) 2PS2288 192) 2VQ002H 113) 2CC9518 153) 2PS229A 193) 2VQ003 114) 2CC9b34 154) 2PS229D-194) 2VQOO4A 115) 2CS007A 155) 2PS230A 195) 2VQOO4B t
116) 2CS007B 156) 2PS230e 196) 2VQ005A 117) 2CS008A i
')
2PS231A 197) 2V0005B 118) 2C5008B 158) 2PS231n 198) 2VQ005C 119) 2CV8100 159) 2PS0354A 199) 2VQOl6 120) 2CVB112 160) 2PS9354H 200) 2VQO17 121) 2CV8113 161) 2Pb935F'i 201) 2VQOla i
122) 2CV8152 162) 2PS9355B 202) 2VQ019 123) 2CV8160 163) 2PS9356A 203) 2WM190-124) 2rC009 164) 2PS9356B 204)-
2RH191 2rC010 165) 2PS9357A 205) 2WOOO6A j
2FC011 166) 20So357H 206) 2WOOO6D 2FC012 167) 2RE1003 207) 2WOOO7A 21A065 168) 2EE9157 208) 2WOOO7D 21A066 109) 2RE9159A 209) 2 WOO 20A 130) 21A091 170) 2Rr0159h 210) 2 WOO 20D 131) 2DG057A 171) 2RT.9160A 211) 2 WOO 56A 132) 200079 172) 2RE9160H 212) 2 WOO 5bD 1
133) 20G000 173) 2RE9170 134) 20G001 174) 2RF026 135) 2DG082 175) 2Rr027 136) 20G083 170) 2RYB02$
137) 200084 177) 2RYB026 138) 200085-178) 2RYB028 139) 2PR001A 179) 2RYB033 140) 2PR0010 100) 2RY8046 141) 2PR002E 181) 2RYB047 142) 2PR002r 182) 2SA032 143) 2PR002G 183) 25A033 i
144) 2PR002H 184) 2818871 145) 2PR032 185) 2S18000 146) 2PR033A 186) 2S18888 7
i l
c i
(0095D/0035D/051791)'
4.6 - page 2 of 39
~.-. _ - - -.
V i<ev. 10a I
a 2.
RumbetoLiterns :
212 I
3.
AStiLCode_Categos y A
i 4.
ASHLCo d cud er tio nl Litequir eme nt s :
j Seat Leakage Measurement per IW-3420.
5.
!!asift_intRelle t t i
Primary containment isolatlon valves will be seat leak test.ed in accordance with 10 CPR 50, Appendix J.
For these valves, Section X1 testlng regulrements are essentially equivalent to those of Appendix J.
6.
AltrInale_ Jesting:
Primary containment luolation valven shall be seat leak rate tested in accordance with the requirements of 10 CI'R 50, Appendix J.
The results of such leak rete measurernents shall be analyzed and corrected, as necessary, in accordance with the guidance set forth in ASME Code Section XI, Subsection IW,- paragr aphs IW-3426 and IW-3427(a). The tiending requirementa of IW-3427(b) will not be utillred.
I 7.
Ast1[it it,lon g No additional Infortnation concerning valve leakage would be gained by performlng separate tests to both Secticn XI and Appendla J. Therefore, overall plant safety is not affected, As specified per NRC Generic Letter 89-04, Attachment 1, position 10, the usef ulness of IW-3427(b) does net justify the burden of complying with this requirement.
8.
Arp.11cahle. lime _Enriodt This relief is requested once per two years during t.he first inspection interval.
l 9.
ApproyaLSLALus t a.
Relief granted por SER 9/15/88 contingent upon compliance with ASME Section XI IW-3 4 2 6, 27.
l-I b.
Revised to comply with ASME Section XI IW-3 4 2 6, 27 in Dyron SER Response 12/16/88 (Dyron Station Letter 88 1321).
I c.
Relief granted per NitC Generic Letter 89-04.
d.-
Deleted SD valves per Technical Specification Amendment #39, e.
Relief granted per SER 9/14/90.
l l
(0095D/0035D/051791) 4.6 - page 3 of 39
= _ _ _ _ _ _ _ _ _. _. _ _. _... _ _ _ _ _.. _ _. ~. _., - -, _., _ _ _ _ _. _ _.. _ _, _, _ _ _
1 Rev. 10a i
ECLILLECCUCSLVit-2 1.
V al_ye_1tu @ ert ICS020A 2C8020A 1C50208 2C5020H a
l 2.
NumbetoLitema t 4
)
3.
ARIC_ Code _ Category C
4.
A DiC_Co d e2._ S ettinnlLRegui r en e nLs :
Exercise check valves to the position required to fulfill their ' unction (open= Cts closed =UL,) unless such operation la not practical during plant operation, per IVW-3522.
)
5.
Dasis int.1eM ets The check valves In the spray additive system cannot be stroked without introducing NaOH into the CS systee.
6.
Alternatedenting
- The A train and D train valves are of the same design (manufacturer, size, model number, and materials conntruction) and have the same service conditions, including orlentation, therefore they form a nample disassembly group, i
_ _G ts up_1._._ _G t 9 up_L __
ICS020A 2CS020A ICS020!!
2CS020D One valve from each group on a per unit besis, will
>e tested each refueling outage.
If the disassembled valve is not capable of being i
full-stroke exercised or if there.ls binding or failure of valve Internals, the-remaining valvo on the affected unit will be inspected.
7.
duE11LicAL10DI rull flow testing of these valves can not be accomplished without posing a serious threat to the safety of equipment and personnel.
It is impractical to either full or part n"roke exercise these valves since flow through these valves would result in the introduction of HaOH into the CS system.
Full-flow testing would require a special test hook-up and necessitate fluching the system.
The alternate test frequency in justifiable in that maintenance history and previous inspections of these, 0.1 " a n at _ityron and Dr aidwood stations
(
has shown no evidence of degradntion or physical impairment (this in to be expected since the valves see very limited <>per ation),
industsy experience, as documented in NPRI)S. showed no history of problems with these valves.
A company wide check valvo evaluation addressing the "EPRI (0095D/0035D/051741) 4.6 - page 4 of 39
I Rev. 10n i
RELIEE EEQUEST_VHr2 cont Applications guidellnes for Check Valves in Nuclear Powsr Plants revealed that the location, orientation and application of these valves are not conducive to the type of wear or degiadation correlated with SOER 80-03 type problems, but these valves still require nome level of monitoring to detect hidden problems.
The wafer type design of the valve body for t.hese valvoo make theit removal a simple process, with little chance of damage eo their internals.
Alro, there la no disassembly of internal parts required; all wear surfaces are accessible by vlsual examination.
After inspection and stroke testing, the valve is reinstalled into the line end post maintenance testing is performed. The valve inspection procedure requires post-inspection visual examination of the check valve to insure that the pin is oriented properly and that the flow direction is correct.
The alternate tect method is sufficient. to insute operability of these valves and.As consistent with Generic Letter 89-04.
B.
Applicable _IltneJeriodi This relief is requested once per quarter during the flist inspection interval.
I 9.
ApprovaLEtat.us.1.
a.
.Rellef to disassemble in place of full flow testing granted per SER 9/15/88.
b.
Relief to disassemble in place of full flow tentlug granted per Generic Letter 89-04.
c.
Relief to disassemble in place of full flow testing granted per SER 9/14/90.
1 I
d.-
Revised to include both full flow (Ct) test and back flow (Bt) testl relief granted per Generic letter 89-04.
l 1
l l
l l
(0095D/0035D/051791) 4.6 - page 5 of 39
.w,n
..+.ww-em
.-eEm-. -s..-.
g y-w y -, e w=--ww
-r+-----mw,
-s v-e.rm-.----.w,y..e-v.y
,..~,--w,~.-m-
,,e.,~w..-v~n.m.t.-w-.
llev. 10a BELIEEJEWEST_VIh3 1.
YAlvtNumber IS18922A 2S18922A 15189228 251892211 24 RumberaLItems t 4
3.
ASME. Code _ Category: C 4.
ASME Codeu Section 1.Llequitementn:
Exercise check valves to the position required to fulfill their function (open-Ctl closednBt) unless such operation is not practical during plant operation, per INV-3522.
5.
DosisJor_Rellets These check valves cannot be full flow tested during operation as_the shut-of f head of the Safety injection pumps -is lower than the reactor coolant system pressure.
Performance of this test wit h the RCS depressurized, but intact, could lead to inadvertent ovet-pressurization of the system..The alternate method of protecting against over-pressurization by partially draining the RCS to p ovide a surge volume ls not considered a safe practice due to concerno of maint aining adequate water level above the reactor core.
6.
A1ternativ.e_Testingt These valves will be full stroke tented during refuellny outages an a minimum, but no more frequently than once per quarter.
7.
JustificRLlont 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.
B.
Applicable _TimC_Periodi This relief is requested once per quarter during the fitti inspection interval.
9 Appt9ynLStatual a.
Relief granted per SER 9/15/88.
b.
Rollef 9tanted por NRC Generic Letter 89-04.
c.
Relief granted per SER 9/14/90.
(0095D/0035D/051791) 4.6 - page 6 of 39
1(e v. len-itELIEL REWEST-..V R14 1.
Valve lhmber:
IC3003A 2C8003A 1CS003 tl 2C8003U ICS00 fl A 2C800HA 1C500811 2CS008h r
2.
tiumbe to Litems:
8 3.
ASMC Code.felegory AC f C 4.
ASHt_ Cove,..Section_XI.Pequilements:
Exos cise check valves to t he positlon required to fulfill theit function (open=Ct; clored=Ht), unlens such operation in not practical during plant i
operation, per IWV-3$22.
6.
Dalilli. loLRelic[I These valves cannot be full flow tested as a matter of course duilng unit operation os cold shutdown as wates i n om the Cfi pwnpa would be dischanged thtough the CS ring headets causing undeslanble effects on system components inside contaltunent.
Additionally, the full flow testing of these check valves during periods i
of cold shutdown, using the C!i pwnpp, would i111 the scactos sciuellny cavity with contaminated wates inom the refueling wates slotage tank. The filling of the cavity, via temporarily installed large bore piping, would require the removal of the t eactor vessel head so as t o preclude equipment.
damage from bosated wates.
The erection of temporary piping from the CS
.11ne to-the reactor cavity would take an estimated nine to twelve shifts, or longer compar ed t.o one t o t wo shif t s for valve inspection.
This estimate does not take into account the time required to drain and remove the piping f rom contaisunent.
Currently, full flow recirculation flow paths do not exis;t from the discharge of the CS pumpn through ther.e check valves to thn refueling water storage tank.
The addition of such flow paths would require extensive plant modifications to existing plant designs, including penetration of containment integalty.
Part ial st.rokir.g of the 1/ 2C8008 A, H valves using air does not p Wide adequat e assurance of valve oper abilit y and may be det e lment.a1 for tha following reasons:
- A.
There in ao correlat ion het ween air flow and angle of disc movement.
H.
Vent.ing and draining the eppt ops iat e piping quar t er ly may cause deposition of botic acid residue which could in t ut n pr omote bindlug of t.h e check valve int ei nals.
(0095D/0035D/051791) 4. f; - page 7 of 39 l
~
.,m.,-
. -...,., _ - - _, -,. ~ - -, - _,. - ~...- - - - -
- _.., =
Rev. 10n BELIEF' BEWEST.Nih 4... cont.
y 6.
AlteInntcJ esti.ngt The A and B train velves ate of the saine design (rnanuf acturer, sire, model number, and snaterials constt uction) and have the same service conditions, including orientation, ther ef ore they form a surnple disnusembly gr oup.
_ Group _1, _ Group l _
1C5003A 2C5003A l
1C5003B 2CS00311
_fI Q upl.
_GIouP L_.
ICS00BA 2CS008A 1C500011 2CS000D l
One valve from each group, on a per unit basis, will be tested each refueling outage.
If tne disassembled valve is not capable of being l
full-stroke exercised or if there is binding or failure of valve
'aternals, the remaining valve on the affected unit will be inspected.
7.
ha tiLications The 1/2CS008A,B and 1/2CS003t.," valves are removed inom the system and visually esamined por the strict detailed inspection reyulternents of the Station Check Valve Program. This inspection adequately verlfles that the valves are maintained in a state of operational readineno.
The valves ate
?
veriflod to be functional by performing a thorough vicuni Inspection of i
the valve Internals and by perf orming a full stroke t est exercise of each disc. -Previous inspections of these particular valves nt both Byron and Draldwood have repeatedly shown them to be in good condition.
l The wafer type design of the valve body for t.hese valven make their removal a simple proceas, with little chance of damage to their Internals.
Also, there is no disassembly of_ internal parts requireds all wear surfaces are accessible by visual examination. Af t er inspection and stroke testing, the valve is reinstalled into the line und post maintenance testing la performed. The 1/2CS008A, a valves receive a contaltunent leakage test, and the 1/2CS003A, 11 valves aio partial flow tested. These testa verify proper Installation of the check valves, and the valve inspection procedure requires post-Inspection visual examination of the check valve to insure that the pan is oilented pt operly and t hat the flow direction is correct.
The alternate test f requency Is justifiable in that. maintenance history and previous inspections of these valves at Byron and Draldwood stations has shown no evidence of degradation or impairment.
In<1ustry experience, as documented in NPRDS, showed no history of problems with these valves.
A company wide check v61ve evaluation addressing the "El'RI Applications Guidelines for Check Valves in Nuclear Power plants" r evealed that, the Iocation, orientation and application of these valves _ ate not conducive to the type of. wear or degradation correlated with FnER 86 03 type problems.
However, they require some level of monitoring t elect hidden problems.
(0095D/0035D/051791) 4.6 - page 8 of 39
~ _ _. _ -, _ _ _ _.. _.. _ _.. _ _ _.-._.. _ - - _ _ _ _ _. _ _ _
i j
Rev. 10a a-RELIEL ELOVESLYlhi, __ cont.
1
[
1 i
!~
l B.
Applicab2e__Ilme letiedi
= This s ellef is r equest.ed once per quar t et duting the first inspection j
interval.
9.
ApprovnLStatus s I
a.
Relief to disassembin in place of full flow testing granted per i
SER 9/15/08 for 1/2C5003A, Bi relief denied per SER 9/15/88 for 1/2C8008A.
b.
Revised to add:ess 11RC conceins in flyton SEft response 12/16/88 ( fly s on
~
5tation Lettet 80-1321).
l c.
l<elief to disassemble in place of full flown testing granted per Generic Letter 89-04.
d.
Revised to addrean llRC concerna in liyt on SElt 9/14/90 and to include bcth full flow (Ct) and backflow (lit ) tests relief granted per Generic Letter 89-04.
t I
b 5
t l
t f.
(0095D/0035D/051791) 4.6 - page-9 of 39 L
Hev. 10n FEL10!Ll!0WESTJIEb i
1.
Y a1Yttl3Wnbett 1518956A-D 2818056A-D IS10 94 B A-It 2S10948A-D i
2.
If webet sLitems:
16 3.
AStiLCode _Cate991y t AC 4.
ASMLCode u5c c119n.7.Lhqui t ert e nt s :
Usercise for operability (Ct) of check valves ever y 3 inont hs, p*: 1W-3521 and IW 3412.
5.
I!csis_isr. lelleI n The accumulator check valver, cannot be tested during unit operation due to ll.e psessure dif f er ential between the aceumulators (0$0 psig) and the reector coolant system (2235 psig).
l'ull stroke exe cising of these valves could occur only with a rapid depressurizatlou of the reactor coolant system, 6.
AlteInute_.Tes. ting t Byron Station Technical Specifications require leak testing to be performed on these valves if the unit is in cold shut down and if such leak rate testing has not been per f otsted within nine months. Therefore, Dyron Station will full stroke exercise (CL) these check valven on tha name-ochedule. This will be accomplished by providing a surge volume in the pressurizer and " burping" t he accumulat or discharge valves.
As a minlinum.
the acetunulators will be dischanged into the reactor vessel during ref ueling outages to perf onin a f ull st roke esen cise (Ct) of t.hese valves.
Positive verification of valve operability will be by noting a change in
.acewnulator level.
7.
Justification:
Stroke exercising the check valves on *.he same schedule as their tequired Technical Specification leak rate testing will adequately analntain the system in a state of opetationni tendines.s without cauning unnecessary personnel radiation exposuse.
8.
Applienble. Time.leriodi
)
This rellef is request ed once per qualter during the f1ist 3nspection interval.
9.
AppI9Yal.Jtatus a.
Felief granted pes SEP 9/1'3/80.
b.
Relief granted per IIRC Gener ic Let t er 89-04, c.
Rellet granted per 30R 9/14/90.
( 0095D/003 SD/0517 91) 4.0 - page 10 of 39
a 14 e v. 10n r
s
'1 l.
Velve.Ntebeni 1818920 2S18926 i
2.
Hwn. bel oLitems 2
i i
3.
ASME_ Code.Categotyt C
i a
i 4.
ASME_Codeo SeC(19n 1 Ll?equirementc 1
i Exercise f or oper e.bilit y (Ct) of check valves every 3 months, per JWV-3$21.
b.
11 asis _ f otitellei I"u l l st.roke exercising of the f;af ety inject lon pump nuet ion check valves, 1818926 and 2518926 cannot be don'onst rat ed dus ing unit. opet at ion an t he teactor coolant system pressuie prevent.s the pumus tiom seaching full flow
[
lujection condit.lons.
Per f oninance of t hlu t est. with thu s cactos coolant.
syst em int act could lead to an inadvertent oven-ptensustratlon of the 8ystem. The alt er nat e enethod or prot ect.ing against over-pressurization by l
partial draining of the scactor coolant system to piovide a surge volume i
is not considered a safe practice due to conceinn of maintaining adequate water level above the eactos cone.
6.
Alternate Testingt j
j The 151892fs and 2818920 valves will be pa: Lini stioke t ested during periodic inservice tests wit.h t he Si pumpa in t.he recliculat.lon mode.
j rull stroke exercising for the valves will be done during refueling outages as a minimum, but no more tioquently than once per quartet.
'/.
Justif1 Cations This alternative will adequat ely maint ain the system in a state of operational readiness, while not. sect lilcing the saf ety of the plant, by
-testing the valves as often as safely posulble, O.
Aprilcable_TimttfeIl041 This_ relief is requested once per quatter during the flist i n t.pe c t i on Interval.
9.
hyptpVALEtatuu t a.
Rollef gitanted per SER 9/15/08.
b.
Hellef granted per flEC Geneste lettet f* 0 4.
I l
e.
Relief granted per S01: 9/14/90, i
i i
I
_ Ofi95D/0035D/001791) 4.6 - page-11 of 39
(
l
Rev.-10a
+
ltELIELitEQUESLYK:1 I
" DELETED "
P 4
Deleted relief request VR 't.
Incorporated valves fortner ly covet ed by VR-7 i
into VR-12 and VR.17.
Added maximtun stroke times to the valve tableo for all valves in VR-12 per EO & G tequest.
i T
P l
i L
4 k
4 l
1 i
s t
a 4
F h
r (0095D/003bD/051791) 4.6 - Prge 12 of 39.
Rev. 10a FELICEFEWEST Vibu 1.
V olyq_Hwnbe r ICC68b 1CC9438 2CC4414 1CC9413A 1CC9486 2CC9416 1CC9414 2CC68b 2CC9438 1CC9416 2CC9413A 2CC9486 2.
HwnbetrLitetes:
12 3.
ASME_ Code _ Category:
A 4.
ASME_CpAe, Secticu ll lequiIement6i Exercise for operability (St) of Cat egory A and b valves every 3 rnonths.
per IWV-3411.
S.
Daul: Liar _RelleIs Comporwnt cooling water flow to the reactor coolant pur ;c s i s r e qu'. t ed n t all times while the pwnps are la operatlun and for an extended period of time while in cold shutdown.
railure of one of these valves in a closed position during an excicise tent would result in a losu of cooling flow to the pumps and eventual pump damnge and/or ttlp.
6.
Alternate _ Testing:
These valves will be exercised during cold shutdown, provided all of the reactor coolant pumps are not in operat lon.
This tent inq period will he each refueling outage as a minimum, but no more frequently than once per quarter.
Cherk valves 1/2CC9486 will be back flow tested ( ht. ) closed on the same frequency as the seat leakage test per IWV.3420.
This frequency is at leart once per two years, to be pe formed'turing reactor refueling outages.
7.
JMELM.iCollCD 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 of t en as safely ponsible.
Stroke exercisirg check valves 1/2CC9486 on the same schedule as their leak rate testing will adequatoly maintain t he system in a state of operational readiness without cousing unnecessary personnel radiation exposure or possible damage to the Reactor Coolant Piunp s.
B.
App 3icable_ Time _PeLiodt This tellet is t oquent ed oneo per quoiter during the f1:st inspectlon interval.
9.
Appr avaLS tatBS :
a.
Relief granted per SER 9/15/88.
b.
Relief granted per NRC Generic Letter 89-04, c.
Relief granted per SER 9/14/90.
(0095D/0035D/051791) 4.6 - page 13 of 39
key. 10n P001011 PCUUEST.VF-9 ICV 8100 2CVH100 1.
Valve liwtbcr t 2 rV it t l 2 1CVB112 2.
thebe t V Litem68 4
A 3.
ASM LCode_ Category 1 4.
ASME Code, Section 1.1 Peyultementsi of Categoty A 1. Il valven evet y 3 niont hs per Exercise f or opei nbilit y (St )
IWV-3411.
6 Besittivt Relief i flow to These valves cannot be t est ed dur ing unit opet at ion as seal water the reactos coolant pumps is sequised at oli t irnes while the pumps are in operation.
Failure of one of these valven in the clot.ed position duilng flow helny divetted to tent would s esult. In r,en1 wat er toturn an exeteise the isolation valven, the pKT by lif ting a r elief valve upnt t erun of Alte Inate_.Te s_t ing :
b.
t ent ed dur ing cold uhut down, ptoviding all Thene valves will be exet eir.c tenctor coolant pwtp s nie not in oper at ion.
This testing period will be each refueling outage as a minimum, but no more f r equently 'than once per quatte.
7.
Justificatlent system in a state of This alternative will adequately maintain the while n o t. saciificing the safety of the plant, by cperational readiness, unfely potsnible.
testing the valveu or. often at.
Applicable _ Time Jctiod 8.
This relief is requested once por quart er dur ing the f i r ti t.
int.pection interval.
9.
AppI ov e l. S t.atu s i Pelief granted per SER 9/15/88.
n.
89-04.
I Felief granted per 11RC '?r m ic Lette b.
Pollef gt nnt ed pet O f~I: W 14 / 9 n._
c.
4.6 pa<je 14 of 39 (0095D/0035D/051791)
key. 10a til111:l' l'EUUEST _Vil-10 1.
Volve.!hnber 11A066 21A066 11A005 21A065 2.
N umbt; t v ( _ I tety s t 4
3.
ASMC _C e de..C a t eg ol y :
A 4.
ASMIL Cvde,Section XI Pequis events:
Exercise f or opet abilit y (St and I't) of category A and it valven every 3 months pet IWV-3411.
5.
!$ asis IRL Rellelt Stroke testing of these valves du t i nr1 plhnt opetation or cold shutdown would, by design, Isolate the als operated insttuments and valven inside the contalianent, building.
6.
AltcInnte_Ienting:
These valves will be exetcised during tefueling outages.
This testing as a min imtun, but no moie frequently pet led will be each r ef ueling out age than once per quarter.
7.
Justification:
The full stroke exercicing of the i n s t r iune n t air containment isolation valves during unit power oper at ions et cold shut downs, int r oduces t.he possibility of causing major oper ating pet turbat ions and/or personnel safety concerns should these valves fall to te-open during ter. ting activltlen.
The failure of these valves in the closed position, as a result of testing activities during plant operation or cold shutdown, would subsequently isolate the alt operated l au t t ume nt.s and valves inside the containment building thus resulting in one or more of the following scenarios A.
Loss of Pressuriter l'ressute Control The pressusleer spray valven 1/2RY45511 L C and the piessurizet auxillary spr ay valven 1/2CVH145 would f nil closed and not be available for pressurizer p essute contt01.
(0095D/0035D/051701) 4.6 - page 15 of 30
Rev. 10a l<ELIEF ltEWESLVib10 B.
boss of Chemical Volume Control System Letdown riow (both normal and excess) and Charging riow -
The loss of instrument air would cause a disruption in the unit letdown flow paths tewulting in pressurizer level increases.
Such valves as the letdown orlflee cont.alnment outlet header Isolation valves 1/2CV8160, the letdown line isolation valves 1/2CV459 and 1/2CV460, the letdown orlflee outlet isolation valves 1/2CV8149 A, 11 &
C, the excess letdron heat exchancer inlet isolation valves 1/2CV8153A
& 11, and the regenetative heat exchange letdown inlet isolation valves 1/2CV8309 A & 0 would go to thelt fall closed positions.
Addit!.onally, the ability t o normally make up reactor coolant inventory and adjust the reactor chemical shim (i.e. normal bosation dilution) would also be lost as the regenerative heat exchanger inlet isolation valves 1/2CVB324 A 6 U would fall to theit respective closed positions.
C.
hose of Component Cooling to Containment Penetrations -
The loss of instrument alt supply would cause the penetration cooling supply flow control valves 1/2CC053 to go to their fall closed positions.
The loss of penetration cooling would result in elevated temperatures being imposed on the penetrations being supported by the component cooling system.
D.
hoss of Personnel Dreathing Air The loss of lustrument air supply to the service air downstream isolation valves 1/2SA033 would cause these valves to go to their fall closed positions. This loss of service alt in the contalinent bu'1 ding would eliminate the normal souren of supplied breathing air needed to support numerous maintenance and component inspection activities in a contaminated radiological environment.
8.
APPlltablH_IlmR_PRIlDdi This relief is requested once per guarter during the first inspection interval.
9.
Appto.YAL_Statun t a.
Relief denied per SER 9/15/88.
b.
Revised (to address NPC concerns) in Dyron response to SER 12/10/88 (Byron Station Letter- '88-1321).
c.
Relief granted per SER 9/14/90.
-(0095D/0035D/051791) 4.6 - page 16=of 39
~,--_-.---..-,,~,----n-n.,,---
It e v. 10n liELIELitEWES'LVR-11
" DELETED "
t Deleted tellel request Vit-11 per EG & G recommendation.
This was a toquest foi extension of position indication tests from overy two years to every thtoo years, i
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(0095D/0035D/051791) 4,6 - page 17 of 39 l-
O i
Rev. 10a RELIEL.EERVESLYR 12 a
1.
Valyg_Nuptbe t Valves that normally stroke in 2 seconds on less:
l VALYlLi YALVE_i YALVII VALVE.1 i
1MS018A-D 2MS010A-D 1PR060 2PR006 1HE9157 2EE9157 I
1PS228A, D 2PS228A, H 1RE9159A, B 2RE9159A,0 IPS229A, D 2PS229A, D 1RE9160A, D 2RE9160A, D 1PS230A, D 2PS230A, D 1RYB033 2RYD033 i
1RC014A-D 2RC014A-D 1518871 2518871 2SD002A-H 2.
NumbeLo Litems:
52 3.
ASMElodtLCategory:
A&D i
r 4.
ASM E _ Code uS e c t i o rLX 1. Req u i r emen t s Verification, by trending of power operated valve times, that an increase in stroke time of 50% or more, from the pievious test, does not occur, per IWV-3417(a).
5.
Dosin_.fo t Relleis-Minor timing inaccurocles, with small stroke times can lead t o substantial increases (percent wise) An stroke times, for example, a valve with a stroke time of I second in an Inlllal test, and 1.0 seconds in the subsequent test, has experlenced an appaient 60% increase in stroke time.
If the accuracy requirements of 1HV-3413(b) are utilised, it could be argued that stroke times between 1 and 2 seconds could constitute as much as a 100% increase in stroke time when, in fact, only n 0.2 second increase occurred.
i'or instance, if the initial tiene was 1.4 seconds, (measured to L
the nearest second is 3.0 second) and if the next time la then 1.6 seconds, (measured to the nearest second is 2.0 seconds) the percent increase is
'100%.
t
)
I i
i (0095D/003SD/051791) 4.6 - page la of 39
.....a,
-.. -..- an.~.
.-...-.~.-.--.
u.- -----
Rev. 10a 6
Alternate TCElingt rast acting valves can be defined as t hose valves that normally st take in 2 seconds or less. No trending of stroke time will be required, and upon exceeding 2 seconds, cortective action shall be taken immediately in accordance with IWV-3417(b).
7.
JustliiCallpDI for small stroke times, the tr ending regula ctnents are too stringent f or the accurmeles specif.ied in the Code.
The alternative speelfled will adequately rnaintain the system in a state of operational readiness, while not Arnposing undue hardships or sacrit icing the saf ety of the plant.
8.
Applicabitlime.feriod:
This relief in requested once per quart.et, during the first inspection interval.
9.
Apptaval_ Status a.
Relief denied per SER 9/15/UD.
b.
Revised (to addtess NRC concerns) in flyt on response to SER 12/1(>/88 (Dyron Station Let.ter 88-1321).
c.
Relief granted per SER 9/14/90.
(0095D/0035D/051791) 4.6 - page 19 of 39
Rev. 10a RELIEEEOUCELYR-ll 1.
Yelve_NumbetEl.
1DC5182A,B 2DG5182A,B IDG;lC3A,D 2DG5183A,B 1DG5134A,0 2DG5184A,B 1DG5185A,B 2DG5185A,B 2.
tittmber_9 Litemtt 16 3.
ASME_ Code _ Category 1 B&C 4.
ASMLCe de_S_tclionlI_Re qu li etnent E i These valves are not within the scope of ASME Code, Section X1, Subr.ection IW requirements.
However, she requirements for stroke timing and trending of the valves associated with the Diesel Air Start System are being mandated by the NRC as an augment ed testing requirement pursuant to 10CFR50.55 (a) (g).
Therefore, valves associated with the Diesel Air Start System shall be exercised to the position required to fulfill their function during plant operation per IW - 3 412 and IW-352 2.
Additionally, the stroke testing of power operated valves shall be measured to tho nearest second and such stroke times trended to document continued valve operational readiness per IW-3413 (b) and IW-3417.
5.
Ilnsis_loI_Rell.eLi The monthly Diesel Generator testing program, outlined in Byton Station's Technical Specifications and implemented by station operating procedures, exceeds the intent of the quarterly valve testing program which would be required bf ASME Code,Section XI.
Additionally, the stroke timing of soleno.a operated valves associated with the Diesel Air Start System is 8
impractical due to the fast actuation of these valves.
6.
A1.ter.nate_Iestingi The performance of Byron Station's Diesel Generator operability monthly surveillance will verify the operational readiner. of the valves associated with the Diesel Air Start System.
This surveillance testing will require the recording of the air pressures contained in both trains A & B of the Diesel Generator Air Start Receiver Tanks both before and immediately after diesel generator start.
By the comparison of these valves between traine, the satisfactory operation of the power operated and self-actuated check valven associat ed with the Diesel Alt Start System can be adequately demonstrated.
I i
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(0095D/0035D/051791) 4.0 - page 20 of 39
._..._m.
_..m
~.... _,....., _. _ _.. _, _. _ _ _ _ _
-- _,~._.-
--~.._..m Rev. 10a 1.
JugLLliggLignt.
Proper valve' operation will be demonstrated _on a mor.thly basis by the verification of diesel generator air stat t capability.
Such verificati.on will compare the air pressures contained in the receiver tanks both betore and after the diesel generator start, thus verifying the operability of the air start control valves.
The proposed testing mtthodology at the increased frequency satisfies the intent of the Section XI requ3tements without posing undue hardships or difficulties.
8, Applirahle_Tlme Perindt This relief is requested once per quarter-during the first inspection interval.
9.
AppraynLEtatus a.
Relief granted per SER 9/15/80.
j i
b.
Relief granted NRC Generic t.etter 89-04.
c.
Relief granted per SER 9/14/90.
I I'
l l.
1 (0095D/0035D/051791) 4.0 - page 21 of 39-
_. _.. _ -.. _.. _. -. ~. _... _ _... _. _ _...,.. _...
.-.____m.__m.______.._
Rev. 10a EEklEE_RERVEST_YR.L4
" DELETED "
Deleted relief request VR-14.
This was a request for exemption for position indicating tests for solenoid operated valves.
Alternate testing allowed by the ASME Code will be used instead.
(:
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J d
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(0095D/0035D/051791) 4.6 - page 22 of 39
~ - -.
Rev. 10m RELIEF 3EQUELLYR-15 1.
YalYe_Humhetsi ICV 8481A, B 2CV8481A, B ICV 8546 2CV8546 1818815 2818815 ISIB019A-D 2 SIB 019A-D ISI8841A,B 2SI8841A,0 ISI8900A-D 2SI8900A-D ISIB905A-D 2S!8905A-D IS18949A-D 2SI8949A-D
-- 2. Rumber_D.LVAlyssi 44
-3.
ASt1E,_Co.de_CateggIy1 AC 4..
ASME_Csde cSerilo2LK LRequirementsi Check valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised during cold shutdowns per IWV-3412 aad IWV-3522.
5.
Balls _IcI_RelinLI The full stroke exercising of rheck valves not stroked quarterly is l
required to be performed during cold shutdowns.
However, the stroking of l
check valves 1/2SI8815, 1/2 fib 900A-D, 1/2SI8949A-D, and 1/2SI8841A,D, associated with Emergency '; ore Cooling System, during cold shutdowns will induce-thermal stresses en their respective reactor vessel nozzles.as the Reactor Coolant System, maintained approximately 180* F) is injected with water from the Refueling Water Storage Tank (maintained approximately 65' F.- This also applies to the stroking of check valves 1/2CV8546 anil_
1/2CV8481A,B because the full stroke of these check valves causes stroking
)
of 1/2SI8815 and 1/2SI8900A-D located in the full flow path.
l Additionally, Byron Station Technical Specifications require _all Safety Injection Pumps and all but one Charging Pump to be inoperable during Modes 4, 5, and 6, except when the reactor vessel head is removed. This requirement' minimizes the possibility of low temperature.
over-pressurization of the Reactor Coolant System.
Therefore, check valves 1/2SI8819A-D, 1/2SI8905A-D, and 1/2 SIB 949A-D,'cannot be full' stroke exercised during routine Mode 5 cold shutdowns as required by IWV-3412 and IWV-3522.
In-addition to the stroke test exercise used to verify._ operational readiness of these check valves,-the act of-such stroking cause the necessity for Technica1' Specification required leak rate tenting 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 worhers who must connect flowmoters and differential pressure gauges directly to pipes containing radioactive fluids.
10095D/0035D/051791) 4.6 - page 23 of 39 L.-
~
[
-~l Rev. 10a Altetuntc_les11agt 6.
Dyron Station's Technical Specifications-require routine leak rate testing to be performed un 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, Dyron Station will stroke exercise check valves 1/2818815, 1/2 SIB 900A-D, and 1/2 SIB 841A,B on the same schedule.
To prevent unnecessary stroking of check valves 1/2 SIB 815 and 1/2518900A-D, check valves 1/2CVB546 and 1/2CV8481A,B will be stroke exercised on the same schedule as check valves 1/2S18815, 1/2 SIB 900A-D and 1/2SI8841A,B.
Additionally, stroke exercising of check valves 1/2 SIB 819A-D, 1/2 SIB 949A-D, and 1/2SI8905A-D can only be safely performed in Mode 6 with the Reactor Vessel head removed.
Full stroke exercising of these check
-valves will be performed at a minimwn f requency of once each refucling
- outage, 7.
JustificatLDn1 Stroke exercising the 1/2CV8481A, D,
1/2CV8546, and 1/2 SIB 815, 1/28900A-D, and 1/2SI8841A, B check valves on the same schedule as their luired Technical Specification Reactor Coolant System Doundary Isolat e leak rate testing will allow the coordination of testing activities without imposing additional check valve leak rate testing requirements.
Such activity coordination will optimize testing efforts and resources while adequately maintaining the system in a state of operational readiness.
Valves 1/2 SIB 949A-D, 1/2 SIB 905A-D and 1/2 SIB 819A-D can not be-stroked during cold shutdown without exceeding Technical Specification limiting condition for operation (LCO 14311221 Since stroking these valves requires starting an SI pump.
Stroke exercising check valves 1/2SI8819A-D, 1/2 SIB 905A-D and 1/2SI8949A-D at least once per Reactor Refueling mode of operation, will insure compliance with Byron Station technical Specifications and minimize the possibility of low temperature-over-pressurization of the reactor Coolant System.
8.
Appligahle_ Time Perigill I-This relief is requested once per quarter during the first inspection interval.
9.
APPLQYal_StatM i a.
Relief granted per SER 9/15/88 for valves 1/2 SIB 819A-D, 1/2 SIB 905A-D, and 1/2SI8949A-D; relief denied per SER 9/15/88 for valves 1/2 SIB 815, 1/2 SIB 841A,B, 1/2SI8900A-D.
b.
Revised (to address NRC concerns) in Byron response to SER 12/16/90 (Byron Station Letter 88-1321),
c.
Relief-granted per URC Generic tetter 89-04.
d.
Relief granted per SER 9/14/90.
l (0095D/0035D/051791) 4.6 - page 24 of 39 l
---. ~.... _. -. -
Rev. 10a RELIELREQUESLYlblQ 1
YAlve Numbergi ISI8811A, D 2 SIBS 11A, D 2.
Nwnhenollalyen 4
3.
ASME_CQde_Ca.tesqI71 B 4.
ASME. Sad.e uS erlin nlLResuirem e nt u Valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised during cold shutdowns per IWV-3412, 5.
DatidoLEellett The full stroke exercising of valves not stroked quarterly is required to be performed during cold shutdowns. Ilowever, the stroking of the Containment Sump Outlet Isolation Valves, 1/2318811A,D requires the suction of the Residual Heat. Removal Pumps to be drained, thus rendering one train of the system inoperable.
For Cold Shutdown operations with the Reactor Coolant Loops filled and one train of Residual Heat Removal declared inoperable. Byron Station's Technical Specifications require two steam generators with a secondary side narrow range water level greater than 41% (Unit 1) and greater than 18% (Unit 2).
However, if the cold shutdown was necessitated by a problem requiring draining of the secondary side of the Steam Generators (i.e.
tube leaks), Byron Station's Technical Specification 3.4.1.4.1:would i
(
preclude the testing of the containment sump outlet isolation valves until
(
such time as the affected steam generators had been refilled.
For Cold Shutdown operations with the Reactor Coolant Loops not Illled (i.e. drained _down to support Reactor Vessel Incore Seal Table, Loop Stop Valve, Reactor-Coolant Pump and Seal Maintenance or primary leakage),
-Byron Station's Technical Specification 3.4,1.4,2 would preclude the l
testing of the Containment Sump Outlet Isolation Valves - as it mandates that "two residual heat removal (RHR) Loops shall be operable and at least one RHR Loop shall be in operation".
i-6.
A1 ternate _le1 Ling 1 Byron Station.will full stroke exercise the Containment Sump Outlet Isolation Valves, 1/2SI8811A, B dur_ing refueling outages vice cold shutdown.
l (0095D/0035D/051791) 4,6 - page 25 of 39
_....., ~,
Rev, 10a 7.
Justificaligni The full stroke testing of the 1/2SISB11A, B valves > in conjunction with system draining, filling and vently of each train, accounts for an additional six days (3 days per train) of scheduling requirements and increased radiation dose to operat ors and radiological control personne).
processing of thousands of gallons of contaminated water, and subsequent required liquid effluent discharges would also result from the draining, tefilling and venting of the RHR system.
This time dut ation required to perform the surveillance testing of the Containment Sump outlet Isolation Valves during Cold Shutdown activities, could, as a result, cause a violation of the action requiremants for Hyron Station's Technical specifications 3,4,1,4.1 and 3.4.1.4.2.
The violations would occur since these action statements require (as noted in their respective foot note sections) the return of the inoperable residual heat temoval 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 temoved for surveillance testing provided the other RHR Loop is operable and J' operation.
In addition, NRC Generic Letter 88-17, Loso of Decay Heat Removal, highlights the consequences of a loss of RH duting reduced Reactor Coolant System inventory (below three feet below the reactor vessel flange).
If the operating RH pump is lost due to air entertainment, and the other train is inoperable for the stroke test, then the " operable" train must be vented to restore decay heat temoval.
Under wQLst CRnditions, boiling in the core would occur in approximately 10 minutes, the cote 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 1 solation valves (3 days) duting Cold Shutdown, the proposed alternate testing frequency of refueling outage periodicity will adequately maintain the system in a state of operational readiness, while not imposing undue hardships or sacrificing the safety of the plant.
B, Applir.able_ Time _1eriodi This relief is requested once per quarter, during the first inspection interval.
9.
Apyngyal_ Status I a.
Relief denied per SEE 9/15/88.
b.
Revised (to addrens NRC concerna) in Byron response to SER 12/16/90.
c.
Relief granted per S T;E 9/14/90.
(0095D/0035D/051791) 4.6 - pnge 26 of 39
Rev. 10a-RELI ELREQUEST_YR-11 1.
YnLve_Hwu.Ji t ISX101A 2SX101A 2.
limnber_oLYalven 2
3.
A$ lie _C.cde_ Cat 2901y1 D 4.
ASMILCedea_ Section XLRequirementiil Stroke time and trend the sttoke time for power operated valves per IWV-3413 and IWV-3417, 5.
Iln a i t.& c.Fa lle lt 1/2SX101A are the essential service water outlet' isolation valves for the Unit 1/2 motor driven auxiliary feedwater pump lube oil coolers.
These valves are complet.ely encapsulated per design and do not. have local or remote position indicators which could be used to time the valve stroke.
6.
Alternate _ ItatiJigt 1/2SX101A will be verified to open during each quarterly ASME surveillance of the motor driven auxiliary feedwater pumps.
In addition, these valves are stroked monthly during auxiliary feedwater pump surveillances required by Byron Station Technical Specifications.
7 Justidcationi-
'These valves will be stroke exercised to their required safety positions each month during the motor driven auxiliary feedwater pump surveillances. This testing will' adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant.
8.
Applitahle_Timele11odt This relief is requested once per quarter during the first inspection interval.
9.
ApprO_ val _ Stat _ua i a.
Relief granted per SER,<15/88.
b.
Relief granted per NRC Generic L.etter 89-04, c.
Relief granted per SER 9/14/90 (0095D/0035D/051791) 4.6 - page 27 of 39
Rev. 10a RELIEF REQUEST _VR:10 1.
Volve Nttsbers:
See Table below 2.
Ntunbe r _0 LV alve S t 98 3.
ASME. Code Ca.t.egory:
AC and C 4.
ASME_ Code,_Sc Clie nl L Fequ i teme nt !
Exercise for operability of check valves every three (3) months, par IWV-3521.
5.
D osin _Io r__Relie f The valves listed in the Table below cannot be safely full-stroke exercised (Ct) open and/or back-flow tested (Ut) closed during plant operation or cold chutdowns, ac s eguired by t he ASME Code.
IIRC Generic Letter 89-04, Attachment 1,
lositions 1,
2, and 3 provide guidelines for method and fIequency of testing check valves.
6.
Alle;nate_TesLing*
Refer to the Table below for a list of valves, direction, and alternate testing frequency requested:
ALTERilATE VALVES DIRECTION TESTI!1G
_ -. f REUV CHCY...
1/2CC9486 Close tiote 1 1/2CC9518 Close/Open Note 1/ Note 1 1/2CC9534 Close/Open Hote 1/ Note 1 1/2CV8113 Close/Open flote 1/tio t o 1 1/21A091 Close flote 1 1/2PR002G,H Close Note 1 1/2pR032 Close Note 1 1/2PS231A,B C' lose tiote 1 1/ 2 RllB 7 0 5 A, D Close/Open No t e 2 / tio te 3 1/2RY8046 Close Note 1 1/2RYB047 Close flot e 1 1/2518815 Cloce Note 2 1/2S18018A-D Close Not e 2 1/2S18819A-D Close Note Z 1/2SI8841A,D Close flot e 2 1/2 SIB 900A-D Close tiot e 2 1/2 SIB 905A-D Closo flot e 2 1/2518948A-D Close t.c t e 2 1/2518949A-D Close flo t e 2 1/2 SIB 956A-D Cloue flot e 2 1/2 SIR 06H close tin t o 1 1/2WM101 Clone NPe 1 1/2WQQ07A,D-Close
_ - la t t 1 - _ _ _.
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(0095D/0035D/051791) 4.6 - page 2B of 39
. _. _ _ - ~ - - _ _ - _ - _ _ _ _ _ _ _ - _ _. _ _ - _ - _ - _.. _ _ _ _ _ _ - _ _._.
Rev. 10a Table Notes:
1)
Perform test. during refueling outages in conjunction with Appendix J.
Local Leak Rate Test.
See IST Ptogram Rollef Request VR-1.
2)
Perform test during in conjunction with Dyron Station Technical Specification 4.4.6.2.2 seat. leakage testing.
As follows:
a.
At least once per 18 months, b.
Ptfor to enteting MODE 2 whenever the plant has been in COLD SHUTDOWN (t+ 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and 11 leakage testing has not been pe, ormed in the previous 9 months, c.
Prior to returning the valve to service following maintenance, sepair or replacement work on t he valve, and d.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual action or flow through the valvo.
- 3) These valves are verified to be operable by observation of depressurization in the applicable line.
This is a test method which was approved by the NRC in SER 9/14/90.
7.
his111h atinD:
Testing these check valves on the same schedule as their required seat leakage tests will allow for coordination of testing act.ivities without imposing additional check valvo leak rate testing requirements.
Such activity coordination will optimize testing efforts and resources while adequately maintaining the system in a state of operational readiness.
This frequency will also minimize personnel exposure to rodlation by minimizing the amount of work performed inside containment during power l-operations.
l 8.
APPllrable_ Time _Etr.iQd 2 This relief is requested once per quarter during the first inspection interval.
i 9.
App 12yal_SinLust a.
Awaiting NRC approval.
(0095D/0035D/051791) 4.6 - page 29 of 39
Rev. 10a RELIELREWCSL&l9 1.
Malre_Humkers:
1AF001A 2AF001A IAr001D 2AT001D 1
2.
Numbet_ct Valves:
4 I
3.
ASME_Cnde_Categary:
AC and C 4.
ASME_Co.de,__S ett io n_KLRe q uiremen t. :
Exercise check valves to the position required to fulfill their function (open = Ct; closed = Bt), unless such operation is not practical during J
plant operation, per INV-3522.
5.
Basis _inr ReligIt Per note 12 these valves are full stroke tested during cold shutdown in accordance with Technical Specificat
- on 4.7.1.2.2 which insur es the operability of the Auxiliary feedwater flow path to each steam generator by verifying flow to each steam generator following each cold shutdown of 30 days prior to entering mode 2.
Testing at this frequency is sufficient to insure proper operability of this system and forms the basis of this Technical Specification.
However, the adequate closure capabilities of these valves can not be verified by performing a back pressure test due to the multiple boundary isolation points. This configuration makes it-impossible to assign any observed leakage to any individual component.
6.
Alternate _Igiting1 The A train and B train valves are of the same design (manuf acturer, size, model number, and materials construction) and have the same service conditions, including orientation, therefore they form a sample disassembly group GInsp 1 Group _1 1AF001A 2AT001A 1AF001B 2AF001B One valve from each group, on a per unit basis, will be tested each refueling outage.
If the disassembled valve is not_ capable.of being full-stroke exercised or if there is binding or failure of valve internals, the remaining valve on the affected unit will be inspected.
(0095D/0035D/051791) 4.6 - page 30 of 39
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Rev.-10a l
EELIEf_.EEQUESLYR 19 Cont.
7.
halltisatiom:
Performing a pressure test to verify closure is impractical due to the system configuration.
To perform this test it would be necessary to attach-a pump to a test connection and pressurize the lino containing the valve.
However, this line also contains many potential leakage paths (valves, pump seal, and instrument lines).- It is impossible to assign a leakage value to any specific path.
The alternate test frequency is justifiable in that removal of these valves requires that the system be taken out.of service for an extended period of time.- Due to Safety System Performance, Probabilistic Risk Assessment _(PRA), and availability concerns involving the Auxiliary Feedwater system these valves cannot be removed on a quarterly frequency without impacting plant safety. Maintenance history and previous inspections of these valves at Dyron-and Braidwood stations has shown no evidence of degradation or impairment.
Industry experience, as documented in NPRDS, showed 4.o history of problems with these valves.
A company wide check valve evaluation addressing the "EPRI Applications Guidelines for Check Valves in Nuclear Power Plants: revealed that the location, orientation and application of these valves are not conducive to the type of wear or degradation cort; Acted with SOER 86-03 type problems.
- However, they still required some level of monitoring to detect hidden problems.
The alternate test method is sufficient to insure operability of these valves and is consistent with Generic Letter 89-04, 8.-
Applicahlg Time Perio.de This-relief is requested once per quar ter during the first inspection interval.
9.
Appicyal Status:
a.
Relief granted per NRC Generic Letter 89-04.
- b. Revised to include more detail on only AF valves in reponse to 5/7/91 NRC teleconference; relief granted per Generic Letter 89-04.
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(0095D/0035D/051791) 4.6 - page 31 of 39
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Rev. 10a DRAFT RELIEF REQUEST VR-20 1.
Valve _thebe r s :
1/2AF006A 1/2CV8116 1/2PS9357A,D 1/2S18813 1/2AF0000 1/2CV8152 1/2RE1003 1/2S1'3814 1/2AF013A-Il 1/2CV8160 1/2EE9170 1/2 SIB 821A,D 1/2AF017A,B 1/2CV8804A 1/2RF026 1/2516835 1/2CC685 1/2FP010 1/2RF027 1/2SFB840 1/2CC9412A,D 1/2FWOO9A-D 1/ 2 Ril87 01 A, D 1/2S18880 1/2CC9413A 1/2FWO35A-D 1/2Ril8702A,D 1/2S18888 1/2CC9414 1/2FWO34A-D 1/2RY455A 1/2S18920 1/2CC9416 1/2FWO43A-D 1/2RY456 1/2818924 1/2CC9437A,B 1/21A065 1/2RY8000A,D 1/2S18964 1/2CC9438 1/2IA06b 1/2RYB025 1/2SX016A D 1/2CC9473A,D 1/2MS001A-D 1/2RYB026 1/2SX027A,11 1/2CS001A,B 1/2MS101A-D 1/2RY8028 1/2SX112A,B 1/2CS007A,D 1/20G057A 1/25A032 1/ 2 SX114 A,11 1/2CS009A,lt 1/20G079 1/2SA033 1/ 2 SX 16 9 A,11 1/2CS019A,D 1/20G080 ISD002A-il 1/2SX173 1/2CV112D-E 1120G081 1/2SD005A-D 1/2SX178 1/2CV8100 1/20G082 1/2S18801A,B 1/2VQ001A,Il 1/2/CV8104 1/20G083 1/2 SIB 802A,B 1/2VQ002A,B 1/2CV8105 1/20G004 1/2S18804D 1/2VQ003 1/2CV8106 1/20G085 1/2S18806 1/2VQ004A,D 1/2CV8110 1/2PR001A,B 1/ 2 S 18 807 A,11 1/2VQ005A-C 1/2CV8111 1/2PS9354A,B 1/2 SIR 809A,B 1/2WOOO6A,lt 1/2CV8112 1/2PS9355A.It 1/2S18811A,D 1/2 WOO 20A,D 1/2CV8114 1/2PS9356A,B 1/2SIU812A,B 1/2 WOO 5bA,B 2.
MmbcL..QLLtems :
340 3.
ASMLCode_Catego ry :
A and D 4.
ASMLCodeuSection XI. Requirements:
Verification, by trending of power-operated valve stroke times, that an i:1c r E BS O in stroke time of 2 5"*
o r mo r e from the previous test (for valves with full stroke times greater than 10 seconds), or 50% or more (for valves with full stroke times lenn than or equal to 10 seconds) does not occur, per IWV-3417(a) (see Technical Approach and Position VA-04).
5.
11asirt_Iodelie t:
Trending stroke times, based on t) e percent change from the prev ous tert, 8
as ASME Section X1 requires, allows g r achta l degrada* inn to occir over a long period of time without triqqering the additional trending at tent ion that increased testing frequency requires An imp. mu method of component performance monitoring is proposed, which will requite a valve to be placed on incteased test frequency based on the per cent change from the fixed reference value established via tar Generic Letter 89-04, Attachment 1,
Position 5.
(0095D/00350/051791) 4.6 - page 32 of 39
Rev. 10a DRAFT RELIEF REQUEST VR-20 s
6.
Alternale_Tetting For all power-operated valves which normally stroke in ureater than_two seconds, an ALERT RANGE will be established based on reaching a given-percent change from the_ reference value established via NRC Generic Letter 89-04.
The following table will be used as a statting_pulnt in evaluation of this fixed ALERT RANCE:
VALUE.
REFERENCE ALERT RANGE REQUIRED ACTION VALUE TYPE STROKE TIME (TteL)
SOV's
> 10 sec.
(1.25)(Tref)-(1.75)(Tref)
> (1.75)(Tref) or HOV's or
>(Tref + 20 see)
AOV's (Tref +10 sec)-(Tref +20 sec)
MOV's
> 10 sec.
(1.15)(Tref)-(1.25)(Tref)
> (1.25)(Tref) or or
>(Tref + 20 sec)
(Tref +10 sec)-(Tref +20 sec) 1 Notes:
A.
Fast acting valves (valves which normally st roke in less than 2 seconds consistently) are included in Relief Request VR-12.
These valves are not assigned ALERT RANGES nnd are not trended.
B.
In all cases, the REQUIRED ACTION VALUE cannot exceed Technica1'Specificatlon or UFSAR values, regardless of calculated values.
C.
The above Table is a guideline and cannot cover _all valves.
The ALERT RANGES and REQUIRED ACTION VALUES are selected based on the comparison between the REFERENCE VALUE, limiting value given in Technical Specifications /UFSAR, anel calculated values using the table above:
- 1) All values are rounded to the nearest whole second.
- 2) Valves which serve the same function on dual trains (1.e.,
ICC9473A and ICC94738) and dual units (i.e.,
ICC9473A and 2CC9473A) are assigned the same REQUIRED ACTION / ALERT RANGE VALUES based on human factors considerations, unless valve or system design differences exist between the trains / units.
Refer to IST Technical Approach and Position VA-04 for related i
information.
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(0095D/0035D/051791) 4.6 - page 33 of 39 I
Rev. 10a DRAFT RELIEF REQUEST VR-20 7.
Justi[ication:
Using fixed ALERT RANGES based on the valve REFERENCE VALUE established when the valve was known to be opet aling acceptably will ensure that gradual valve performance degradation is monitored and evaluated, by placing the valve on increased testing frequency when the stroke time exceeds a fixed multiple of the REFERENCE V ALUE.
This method is superior to that required by the ASME Code in that the point of reference used to evaluate the performance trend on a valve remains Ilxed.
This alternative utilizes the same stroke time percentage change values as required by the increased frequency testing.
ASME Code to place a valve on 8.
Appli.CahltL_Ilmt_PirlRd t This relief is requested once per quarter, during the first inspection interval.
9.
AppIrXal._SLatusi Since this relief request is a new submittal and is not specifically addressed in URC Generic Letter 89-04, it is NOT approved for use.
Formal written approval from the NRC is required prier to implementation.
Expeditious review and approval are requested, i
( 0095D / 003 5D/ 0517 91) 4. fi - page 34 of 39
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Rev. 10a-DRAFT RELIEF REQUEST VR-21 "WITilDRAWN" This relief request was in draft form and was later withdrawn per SCR 9/14/90.
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i (0095D/0035D/051791) 4.6 - page 35 of 39 l
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Rev. 10a INTERIM RELIEF REQUEST VR-22 1.
EDire_2nu11ner.s i 1/2S188184 1/2 Sis 94BA 1/2 SIB 841A 1/2S18818D 1/2 SIB 948B 1/2SIBB41B 1/2518810C 1/2 SIB 948C 1/2 SIB 810D 1/2 SIB 948D 2.
thunber of ItemE:
20 3.
ASMfuCode_Categon AC 4.
AS}iLCnde. Section__ xLRequinmens Exercise check valves to the position required to fulfill their function (open = Ct;-closed = Bt), unless such operation ls not practical during plant. operations, per IWV-3522.
Byron Station's testing methodology maets this requirement.
However, NRC Generic hetter 89-04, At tachn.ent 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-strcte exercise, 5.
Ensla_. int Relief:
The current Byron Station testing methodology uses available flowmeters to measure the total flow through two parallel check valves. These are given below:
CliECILVALYES FLQH_,1HDICAT19ti_-
ISI8818A & ISI8818D IFI - 618-ISI8818B & 1818818C IFI - 619 ISI8841A & 1SI8841B IFI 618 ISIB940A & ISI8948D 1FI - 618 IS_IE1 Hp_6_1HIB14RC 1fI
- 415L There_is currently no method available to measure the flow rates through s
the individual check valves.- Modifications to these lines to install flow measurement devices for the individual valves is not warranted due-to the following reasons:
A.
Flow indications exist for each pair of check valves.
It would be
(
readily apparent from the flowrates recorded during each refuel outage if individual _ check valves were not opening or were only partially i-opening by comparing the tiewrates recordad through each pair of check valves.
B.
Byron Station Technical Speeli3 cations disregard the highest branch line flowrate when determining tha minimum required flowrates through these parallel injection linea.
Therefore, slight differences in individual branch flowrhtes which could exist by measuring the total-flowrate through two parallel injection lines was anticipated and accounted for when Byron Station's Technical Specliications were formulated.
l (0095D/0035D/051791) 4.6 - page 36 of 39 1
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~.- -
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Rev. 10e INTERIM RELIEF REQUEST VR-22 c
C.
Installation of individual injection line flow indicators would pose I
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 egiipment (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 p3 ant.
The modification would require extensive engineering and installation costs, along with replacement power costs, to install.
Byron Station Technical Specifications require an ECCS full-flow balance test to be 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 nn increased safety hazard to plant personnel and equipment, by requiring unusual system alignments f or extended periods of time durino a ref uel outage when other activities inside containment are at their highest level.
The alternative to individual check valve _flowrate measurement required by HRC Generic Letter 89-04 is disassembly and inspection.
Disassembly and inspection is: not a viable option for the ECCS injection line check valves due to the following concernst A.
Radiation Doset The radiation dose increase to disassemble,-inspect, and reassemble these check valves each refuel outege would be several man-rem.
B.
Safe operation:
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.
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l (0095D/0035D/051791) 4.6 - page 37.of 39 i
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Rev. 10a INTERIM RELIEF REQUEST VR-22 C.
Check Valve operating NJstory:
A search of maintenance history (TJM) on these valves for both Byron and Braidwood Nuclear power Stations revealed the following past maintenance activities on these check valves:
1/2SI8818A Hone 1/2SI8818B None 1/2 SIB 818C None 1/2 SIB 818D None 1/2S18841A Hone 1/2SI8841D None 1/2SI8940A None ISI89488 Replaced disc arm assembly and gasket, retorqued flange bolts 10/20/84 (Dyron) 2 SIB 948D None ISI8948C Inspected internals, no parts repaired or replaced, retorqued flange bolts 9/10/84 (Byron) 2 SIB 948C None 1/2 SIB 948D None This history does not indicate any adverse operating history for these l
valves; therefore, disassembly and inspection of these valves is not warranted based on previous maintenance history.
6.
Alternatire._Ie. sting In lieu of disassembly, Byron Stellon proposes the following tests (which are already being performed):
A.
A full stroke test of.each check valve 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
installed flow indicators.
l L
B.
A seat leakage test of each check valve is performed as required by Byron Station's Technical Specification on RCS leakage. These leak tests are performed:
1). At least once/18 months,
- 2) prior to Mode 2, whenever the plant has been in COLD SIIUTDOWN for l
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and if leakage testing has not been performed in the L
previous nine (9) mo n ths,
[
- 3) prior to returning the valve to service following maintenance, repair, or replacement 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.
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 Byron Station Technical Specifications.
(0095D/0035D/051791) 4.6 - page 38 of 39
. -.a
__._.__.__.__m..
Rev. 10a INTERIM RELIEF REQUEST VR-22 7.
J.natification:
Dyron Station's Technical Specifications require these check valves to be-full stroke-tested-and sent leakage tested at a minimum frequency of once
-per 18 months. These tests satisfy _all of the ASME check valve exercise requirements (open and close) and all of the NRC Generic Letter 89-04 full-stroke and backflow testing requirements, except that flow is meesured through pairs of injection line check valves instead of individual injection line check valves.
The burden imposed by either disassembly and inspection or modification of these check valves to comply with the NRC Generic Letter 89-04 Individual-I 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 t.he fact that Byron Station has previously received a (ovorable Safety Evaluation Report (SER) on its~ Inservice Testing Program after years of in-depth review by the NRC.
Also, it is readily apparent that Dyron Station was not originally designed to allow for either individual injection line flow measurement or for diaassembly 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.
l-The current testing requirements of Dyron Station Technical Specifications for those check valves will adequately monitor their performance and any j
future degradation, and maintain safe operation of the plant.
8 h221LChh193kmtLERf LD.Q t This relief is requested once per quarter during the-first inspection interval.
9.
A2proyaLatatust o
a.
' Interim relief granted for six (6) month period-or next refueling-l-
outage (whichever is longer) per SER 9/14/90.
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l (0095D/0035D/051791) 4.6 - page 39 of 39
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