ML20101M219
| ML20101M219 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/25/1992 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20101M207 | List: |
| References | |
| PROC-920625, NUDOCS 9207080111 | |
| Download: ML20101M219 (169) | |
Text
v INSERVICE TESTING PROGRAM PLAN FOR PUMPS BRAIDWOOD STATION UNITS 1 AND 3 Revision 5 l
J SECTICH 3.0 INSERVICE TESTING PRCbW PLAN FOR PUMPS BRAIDWOOD STATION UNITS 1 AND 2 r.
l f
9207080111 920625 gDR ADOCK 05000456 PDR 1 217(041092)
'ZD79G
INSERVICE TESTING PROGRAM PLAN POR PUMPS BRAIDWOOD STAT 20N UNITS 2, AND 3 Revision 5 TABLE OF CQtTENTS 3.0 Inservice Testing Program Plan for Pumps 3.1 Program Description 3.2 Program References 3.3 Pump Tables 3.4 Pump Notes Note 1 -Deleted-Note 2 Pumps Lubricated by Pumped Fluid Note 3_ Pump Idle Suction Pressure Note 4 Deleted - Not Used at Braidwood - Byron ONLY Note 5 Not Used at Braidwood - Byron ONLY Note 6 Not Used at Braidwood - Byron ONLY Note 7 Not Used at Braidwood - Byron ONLY 3.5 Pump Technical Approaches and Positions PA-01 Performance Testing of the Boric Acid ( AB) Transfer Pumps 3.6 Pump Relief Requests PR-01 Pump Vibration PR-02 Pump Bearing Temperatures PR-02a Pump Bearing Temperatures PR-03 -Deleted- Not used at Braidwood - Byren ONLY PR-04 -Deleted- Not used at Braidwood - Byron ONLY PR-05 Use of Ultrasonic Flowmeters PR-06 Diesel Oil Transfer Pump Differential Pressure PR-07 Not used at Braidwood - Byron ONLY 3.0 - Page 1 of 1 217(041092)
ZD79G/2
INSERVICE TESTING PROGRAM PLAN FOR PUMPS BRAIDWOOD-STATION UNITS 1 AND 2 Revision 5 SECTIGt 3.1 PROGRAN DESCRIPTICM l-l 217(341092)
ZD79G/3 l
INSERVECE TESTING PRGGRAM PLAN POR PUMPS BRAIDWOOD STATION UNITS 1 AND 2 Revision 5 I
PROGRAM DESC2IPT10N The Pump Inservice Testing (IST) Program Plan for Braidwood Nuclear Power Station Units 1 and 2, 1s implemented in accordance with the requirements of Subsection IWP of Section XI of the ASME Boiler and Pressure Ve sel Code, 1983 Edition, through the Summer of 1983 Addenda. j Where there requirements are determined to be impractical, specific relief is requessed. Additional pump relief requests may be necessary )
and these willibe identified during subsequent inservice tests. The l pamps subject to IST testing are those pumps which are identified in j accordance with the scope of ASME Section XI, subsection IWP-11001 l "IWP-1100 SCOPE.. . This Subsection provides the rules and requirements j for inservice testing of Class 1, 2, and 3 centrifugal and displacement i type pumps that are installed in light-water cooled nuclear power plants, that are required to bring and maintain the plant in cold shutdown i condition or mitigates the consequences of an accident, and that are provided with an emergency power source. The results of these ts.sts are to be used in assessing operational readiness of the pumps during their service life."
The only exceptions are the diesel driven auxiliary feedwater pumps (IAF01PB and 2AF01PB), which are not supplied by an emergency power source. The diesel oil transfer pumps (1/2 DOO1PA, 1/2DOO1PB, 1/2DOO1PC and 1/2DOO1PD) are classified non-ASME Class G.
Pump reference values shall be determined f rom the results of a pre-service test, which may be run during pre-operational testing, or from the results of the first inservice test run during power operation.
Reference values shall be at points of operation readily duplicated during subsequent inservice testing. Additional reference values may be necessary and these will be taken in accordance with IWP-3111 and 3112:
- 1. After a pump has been replaced,
- 2. When a reference value or set of values may have been affected by repair or routine servicing of a pump, or
- 3. If it is necessary or desirable for some other reason than 1 or 4 above.
Per NRC Generic Letter- 89-04, Attachment 1, Position 18, whenever pump data is determined to be within the Required Action Range, the pump is inoperable, and the Technical Specification LCO Action statement time starts.
In the event a pump must be declared inoperable as a result of inservice testing, limitations on plant operation will be as stated in the Technical Specifications.
Section XI of the ASME Boiler and Pressure Vessel Code shall not be construed to supersede the requirements of any Technical Specification.
3.1 - Page 1 of 1 217(041092)
ZD79G/4
- s. -
INSERVICE TESTING PROGRAM PLAN FOR PUMPS BRAIDWOOD STATTON UNITS 1 AND 2 Revision 5 SECTICM 1.2 PROGRAM REFERENCES
.e-I
+{
217(041092)
ZD79G/5
INSERVICE TESTING PRGGRAM PLAN FOR PUMPS l BRAIDWOOD STATION UNITS 1 AND 2 Revision Se PROGRAM REFERENCES .
- 1. Title 10, Code of Federal Regulations, Part 50, Domestic Licensing of Production and Utilization Facilities, particularly Section 50.55a, Codes and Standards. ,
i
- 2. ASME Boiler and Pressure Vessel CodesSection 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 1989 Addenda, Part 6, Inservice Testing of Pumps in Light Water Reactor Power Plants.
- 4. U.S. Nuclear Regulatory Commission, Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs.
- 5. Braidwood Station UFSAR, Section 3.9.6.1, Inservice Testing of Pumps.
- 6. Braidwood Station Technical Specification, 4.0.5, ASME XI Program Requirements.
- 7. Braidwood Station Technical Staff Procedure, BwVP 200-1, ISI Requirements for Pumps.
- 8. NRC Safety Evaluation Reports (SER's):
- a. SER dated October 19, 1991 for Revision 4/4A.
l l
I l
l 3.2 - Page 1 of 1 217(041092)
ZD79G/6 l
~
INSERVICE TESTING PROGRAM PI.AN FOR PUMPS.
BRAIDWOOD STATION UNITS 1 AND 2 Revision 5 l
l l
I i
i l
SECTION 3.3 PUMP TABI.ES 217(041092)
ZD79G/7
INSERV2CE TESTING PROGRAM PLAN POR PUMPS BRAIDWOOD STATION UNITS 1 AND 2 Revision 5 PUMP TABLE DESCRIPTICM The following information is included in the summary tables:
The first four columns include the unique Braidwood Station Equipment Piece N umbe r, the Pump Name, the Code Class (1, 2, 3, N for non-Code, and T for tracking purposes only), and the system P & ID for the pump listed.
Spead: Speed will be measured by a tachometer for variable speed drives.
Inlet Pressure Inlet pressure will be meestred via permanently installed gauges or other means, provided the equipment accuracy meets the requirements of IWP-4150. This is to be measured both before pump startup and during the test.
Differential Pre 1Eurg: Differential pressures will be measured using calibrated differential pressure gauges or by recordino the difference between calibrated inlet and outlet pressure gauges.
Flow Rate: Plow rates will be measured using permanent 1, installed instrumentation or other means, provided that equipment accuracy meets the requjrements of IWP-4150. Also, refer to relief request PR-05.
Vibration: Vibration measurement shall be made using portable or hand held instruments at locations marked on the pumps, relief request PR-01.
Smaring Temperature: Bearing temperature is nat measured per PR-02.
- Test Interval An inservice test shall be run on each pump nominally every 3 l months during normal plant operation, in accordance with IWP-3400, except L during periods when the pump is not required to be operable.
Lubrication Level Lubrication level will be observed through sight glasses for the pumps listed in the program, when provided.
l l Remar11: Any applicable note (s) are referenced here.
- i. .
Revision NumbeI: The currant revision of the program is listed.
InhJa_fagg: The table pages are numbered sequentially and show the total number of pages.
l l
3.3 - Page 1 of 1 217(041092)
ZD79G/6
INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3 and AUGMENTED PLHP5 - '
- BRAIbWOOD NUCLEAR POWER STATION.
UNITS 0, 1, 2 .
. Revision 5 t
} C g TEST PARAMETERS A
l LLUBRI-S SYSTEM INLET DIFF FLOW BEARING TEST CATION PUMP NUMBER P1TMP NAME S P& ID _,HPIED PREL EFI13 ATE XIDRATION TTJ'iP_ INTERVAL LEVEL REMARKS OAB03P Boric Acid T M-55 No No PA-1 PA-1 PA-1 PA-1 Quarte-ly Yes Transfer Pump 4
1AB03P Boric Acid T M-65 No do PA-1 PA-1 PA-1 PA-1 Quarterly Yes Transfer Pump
- 2AB03P Boric Acid T M-65 No No PA-1 PA-1 PA-1 PA-1 Quarterly Yes l Transfer Pump
~
1AF0lPA Auxiliary Feedwater 3 M-37 No Yes Yes Yes PR-1 Yes Quarterly -Yes l Pump-(Mator) i 1AF0lPB Auxiliary Teedwater 3 M-37 Yes Yes Yes Yes PR-1 Yes Quarterly Yes Pump (Diesel).
! 2AF01PA Auxillary Feedwater 3 M-122 No Yes Yes Yes PR-1 Yes Quarterly Yes j rump (Motor) I i 2AFOlPB Auxiliary Teedwater' 3 M-122 Yes Yes Yes Yes PR-1 Yes Quarterly Yes
, Pump (Diesel) j OCCOlP Compor3nt Cooling 3 H-66 No Yes Yes PR-5 PR-1 PR-2 Quarterly Yes Note 3 Pump a -
} ICCelPA Component Cooling' 3 M-66 No Yes Yes PR-5 PR-1 PR-2 Quarterly Yes Note 3
- Pump
[ ICC0lPB Component Cooling 3 M-66 No Yes Yes PR-5 PR-1 PR-2 Quarterly Yes Note 3 I j Pump '
[
2CC01PA Component Cooling 3 M-66 No Yes Yes PR-5 PR-1 PR-2 Quarterly Yes Note 3 Pump ,
- 17(041092) 3.3 PUMP TABLES - Page 1.of 4 ?
ZD79G/9 .
l i 3
m- ' , - , , -- -_ _ - - - - _ - - - - - _ - _ - _ _ - - - - _ _ _
INSERVICE TESTING PROGRAM PLAN
' CLASS 1, 2, 3 an* AUGMENTED PUMPS BRAICWOOD NUCLEAR POWER' STATION UNITS 0, 1, 2 i Revision 5a C
TEST PARAMETERS t.
A LUBRI-5 SYSTEM- .
INLET DIFF FLOW BEARING TEST CATION i PUMP NUMPIR PUMP NAME S P & ID SPEED ' PREL*P2ES RATE VIBRATION TEMP INTMLVAL LEVEL REMARKS 2CC0lPB Component Cooling 3 H-66 No Yes' Yes PR-5 PR-1 PC-2 Quarterly Yes. Note 3 Pump 1CSoli'A .. Containment Spray 2 M-46 No Yes Yes Yes PR-1 PR-2 Que 'erly No Note 2 Pump 1CS0lPB Containment Spray 2 M-46 No Yes Yes Yes PR-1 PR-2 Quarterly No Note 2
, Pump 2CS0lPA Containment Spray 2 M-129 No Yes Yes Yes PR-1 PR-2 No Pump Quarterly Note.2 2CSolPB Containment Spray 2 M-129 No Yes Yes Yes PR-1 PR-2 Quarterly No Note 2 Pump 1CV0lPA Centrifugal Charging 2 M-64 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump 1CV0lPB Centrifugal Charging 2 M-64 No Yes 'la s Yes PR-1 Yes Quarterly Yes Pump 2CV0lPA Centrifugal Charging 2 M-138 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump 2CV0lPB Centrifugal Charging 2 M-138 No Yes Ycs Yes PR-1 Yes Quarterly Yes Pump 1D00lPA Diesel Oil Transfer 3 M-50 No Yes PR-6 Yes PR-1 PR-2 Quarterly No Note 2 l Pump j
._1 3.3 PUMP TABLES - Page 2 of 4 4
217(041093)
ZD79G/10
TNSERVICE TESTING PROGRAM PLAN CLASS 1, 3, 3 and AUGMENTED PUMPS BRAIDWCDD NUCLEAR POWER STATION UNITS 0, 1, 2 Revision 5a C
TEST PARAMETERS L
A l LUDRI-S SYSTEM ' INLET DIFF FLOW BEARING TEST CATION PU1'P NUMBER PUMP NAME- S P& ID JPEED PRES PRES RATE VIBRATION TD4P INTERVAL LEVEL REMARES 1DOO1PB Diesel Oil Transfer M-50 No PR-6 Yes Punrp 3 Yes PR-1 PR-2 Quarterly- No Note 2 .I' 1DOOlPC Diesel Oil Transfer 3 M-50 No Yes PR-6 Yes PR-1 PR-2 Quar t. = rly No- Note 2 I Pump 1DOOlPD Diesel Oil Transfer 3 M-50 No l'e s PR-6 Yes PR-1 PR-2 Quarterly No Note 2 l Pump 2D00lPA Diesel Oil Transfer 3 M-130 No Yes PR-6 Yes PR-1 PR-2 Quarterly No Note 2 l Pump 2DOO1PB Diesel Oil Transfer 3 M-130 No Yes PR-6 Yes PR-1 PR-2 Quarterly No Note 2 l Pump
'2DOO1PC Diesel Oil Transfer 3 M-130 No Yes PR-6 Yes PR-1 PR-2 Quarterly No Note 2 I Pump 2DOO1PD Diesel Oil Transfer 3 M-130 No Yes PR-6 Yes PR-1 PR-2 Quarterly No Note 2 l Pump 1RH0lPA Residual Heat 2 M-62 No Yes Yes Yes PR-1 PR-2 Quarterly No Note 2 Removal Pump 1RH01PB Residual Heat 2 M-62 No Yes Yes Yes PR-1 PR-2 Quarterly No Note 2 Removal Pump 2RH0lPA Residual Heat 2 M-137 No Yes Yes Yes PR-1 PR-2 Quarterly No Note 2 Removal Pump 2R50lPB Residual Heat 2 M-137 No Yes Yes Yes PR-1 PR-2 Quarterly No Note 2 Removal Panp 217(041092) 3.3 PUNP TABLES - Paga 3'of 4 ZD79G/11
INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3 c.nd AUGMENTED PUMPS BRAIDWOOD NUCLEAR POWER STATION UNITS 0, 1, 2 Ravision Sa C
TEST PARAMETERS L
A LUBRI-S SYSTEM INLET DIFF FLOW BEARING TEST. CATION PUMP NUMBER PUMP NAME S P &'ID SPEED PRES PRES RATE VIBRATION TEMP INTERVAL LEVEL REMARES ISIO1PA Safety Injection 2 M-61 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump ISI0lPB Safety Injection 2 M-61 'No Yes Yes Yes PR-1 Yes Quarterly Yes Pump 2SI0lPA Safety Injection 2 M-136 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump 2SIOlPB Safety Injection 2 M-136 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump ISX0lPA Essential Service 3 M-42 No Yes Yes PR-5 PR-1 Yes Quarterly Yes Note 3 Water Pump ISXOlPB Essential Service 3 M-42 No Yes Yes PR-5 PR-1 Yes Quarterly Yes Note 3 Mater Pump 2SX01PA Essential Service 3 M-42 No Yes Yes PR-S PR-1 Yes Quarterly Yes Nots 3 3 Water Pump 2SXOlPB Essential Service 3 M-42 No Yes Yes PR-5 PR-1 Yes Quarterly Yes Note 3 Water Pump ISXO4P la AFW SX 3 M-42-3 Yes Yes Yes PR-5 PR-1 PR-2 Quarterly Yes Note 6 Booster Pump 2SX04P 2B AFW SK 3 H-136-1 Yes Yes Yes PR-5 PR-1 PR-2 Quarterly Yes Note 6 Booster Pump
[
, OWOOlFA Control Room 3 M-ll8 No Yes Yes Yes PR-1 PR -2 Quarterly Yes Note 3 Chilled Water Pump OWOOlPB Control Room 3 M-ll8 No Yes Yes Yes PR-1 PR 3 Quarterly Yes Note 3 Chilled Water Pump 217(041092)/ZD79G/12 * ~
"9'
INSERUTCE TESTING PROGRAM PLAN FOR PUMPS =
DRAIDWOOD STATICH UNITS 1 AND 3 Revision 5 l
l i
l SECTICM 3.4 ITMP NUIES 217(041092) 2D79G/13
INSERVICE TESTING PROGRAM PLAN FOR PUMPS BRAIDWOOD STATICH UNITS 1 AND 3 Fevision Sa ItKP MOTES HOTI 1 l
-Deleted-HQIL2 i The Diesel Oil Transfer (1DOO1PA-D and 2DOO1PA-D), Residual Heat Removal (1RH01PA/B and 2RH01PA/B) and Containment Spray (ICS01PA/B and 2CS01PA/B), j pumps cannot be measured for lubrication level.- These pumps are lubricated by j the fluid pumped and hence have no indication for lubrication level.
I 1
l BDTE 1 l l
The Component Cooling Water pumps (OCC01P, ICC01PA/B and 2CC01PA/B), Essential i Service Water Pumps (ISX01PA/B and 2SX01PA/B), and the Control Room Chilled Water Pumps-(0 WOO 1PA/B) are in systems which are in continuous operation. The idle inlet pressure for these pumps cannot be obtained without interrupting normal system operation and causing system transients. The idle inlet
. pressure will be recorded only if the pump to be tested is not in operation at ;
the start of the test. Proper pump operation is ausured by continuous pump !
operation as well as quarterly monitoring of the remaining ISI pump parameters.
l~
l _- FOTE 4 l
-Deleted-i- NOTE 5 I Not Used at Braidwood - Byron ONLY l
HQIE_1 The 1/2SXO4P, Essential Service Water Booster Pumps are being added in conjunction with the station " Blackout" implementation schedule. Ultrasonic L flow instrumentation is being purchased and will be installed by the end of 1992, at which time these pumps will be tested quarterly per the IST Program Plan for Pumps.
KQTI 1 Not Used at Braidwood - Byron ONLY 217(041092) 3.4 - Page 1 of 1 ZD790/14
)
-INSERVICE TESTING PROGRAM PLAN FOR PUMPS BRAIDWOOD STATION UN2TS 1 AND 3 ;
Revision 5 l
SECTION 3.5 PUMP TECENICAL APPROACHES AND POSITICBIS 217(041092)
ZD79G/15
Revision 5 IST Technical Approach and Position No. PA-01 A. COMEDatat Identificatigma ;
i
- 1. Description Performance Testing of the Boric Acid ( AB) Transfer Pumps I
- 2. Component Numbers: OAB03P, 1/2AB03P
\
.l'
- 3.
References:
(a) Engineeri,J Correspondence'(CHRON 9161733) uated January 17, 1991
- 4. Code Class: 3/T (Tracking purposes ONLY))
B. Reguiramtatt The ASME Section XI Code requires safety related pumps performing a spvelfic function in shutting down the reactor or in mitigating the consequences of an accident, and that are provided with an emergency power supply be included in the inservice-testing program (IST). However, the AB pumps do not have an
" emergency" power supply, so consequently, they ere DDL_Ltquited to be included in the program. Braidwood was licensed as a " hot shutdown" plant. This means it was only. required to be capable of hot shutdown using non-safety related systems or repair . to postulated damaged equipment, for this reason the electrical support for the emergency boration function is Safety Category II.
Also, the RNST (Refueling Water Storage Tank) is a seismic Category I structure as described in the UFSAR Table 3.2-1 and is designed to withstand design basis accidents, including tornados. The RWST is required for ECCS (Emergoney Core Cooling Systems) operation.
The AB pumps are tested per the Technical Specification requirement that requires an 18 month flow verification of 30 gpm to the ECS. Also, the AB pumps are monitored per the station's vibration monitoring program requirements.
C. Egittina:
1
~ The AB pumps f all outside the sc)pe of the ASME Section XI and the IST program.
However,.because of the operating significance of these pumps, and based on l
i correspondence and discussions with NRR-and CECO Engineering, Braidwood Station has decided to list the AB pumps in the program for tracking purposes only.
They will' be tested in a like f ashion to the ASME Section XI program. The hydrculic limits used will be similar to those specified in ASME/ ANSI OMa-1988, Part 6. Meaning that the differential pressure limits will be plus or minus-10 percent of 'ts reference value_(flow rate will be a set value). -There will be no alert lim.ts placed on differential pressure. The AB pumps will be trended
-to monitor ftr degradation or abnormal / erratic operation. Also, the vibration readi.ngs and limits will be similar to those in ASME/ ANSI OHa-1988, Part 6.
3.5 - Page 1 of 1 217(041092)
ZD79G/16
Revision 5 SECTIQlt 3.6 ETMP RELIEr REQUESTS 217(041092)
ZD79G/17
Revision $a RELIEP REQUESI._ liq. . PR-01
- 1. Ei&lLiiUliEE: 1,11 pumps in the program plan.
- 2. NUMBER OF ITEMS: 44 pumps.
-3. ASHELCODE CLASfit .&3
- 4. AS11]LCQDE. SECTION XI REOUIREMQilS In reference to Table IWP-3100-2, "A13owable Ranges of Test Ouentities",
pump vibration is to be measured in and compared to values given in mils displacement.
- 5. BASIS FOR RELIEF:
The measurement of pump vibration is required so that developing problems can be detected and repairs initiated prior to a pump becoming inoperable.
Heasurement of vibration only in displacement quantitles does not taka into account frequency which is also an important factor in determining the se9erity of the vibration.
- 6. ALTERNATE TESTING:
The ASME Code minimum standards require measurement of the vibration amplitude in mils (displacemeat). Braidwood Station proposes an alternate program of measuring vibration velocity (inches per second) which is more
-comprehensive than that required by Section XI. This technique is an industry-accepted method which 1 much more meaningful and sensitive to small changes that are indicative of developing mechanical problems. These velocity measurements detect not only high amplitude vibration, that
~
- indicate a major mechanical problem such as misalignment or unbalance, but also the aqually harmful low amplitude, high frequency vibration due to bearing wear that usually goes undetected by simple displacement measurements.
The allowable ranges of vibration and their associated action levels will be patterned af ter the requirements established in ANSI /ASME OHa-1988, Part '
- 6. These ranges will be used in whole to assess equipment operational readiness for all components.
.The acceptable perf,e A*cc range for all components will be 1 2.5 times the reference vLlue, not 'tceed .325 inches per second. The alert range, at which time the testi> o ( oquency would be doubled, will be > 2.5 to 6 times the reference value, not to exceed .70 inches per second. Any vibrating velocity greater than 6 times the reference value or greater than .70 inches per second will require corrective actions to be performed on the effected component.
Vibration measurements for all pumps will be obtained and- recorded in velocity, inches per second, and will be broadband unfiltered peak measurements. The monitored locations for vibration analysis will be marked so as to permit subsequent duplication in both location and plane.
3.6 - Page 1 of 10 217(041092)
ZD79G/18
Revision So RELIEr REOQEST NO. PR-J21 The frequency response range of the vibration transducers and their readout system shall be capable of f requency responses f rom one-third minimum pump shaft rotational speed to at least one thousand herts.
The Vertical Line Shaft Pumps in the program will have vibration measurements taken on the upper motor bearing housing in three orthogonal directions, one of which is the axial direction.
- 7. Jt)SIIIICAIlotis Heasurements of vibration in mils displacement 3re not sensitive to small changes that are Indicative of developing mechanical problems. Therefore, the proposed alternate method of measuring vibration amplitude in inches /second provides added assurance of the continued operability of the pumps. Also, there are no positive displacement pumps or centrifugal pumps which rotate at less than 600 RPM in Braidwood's IST program.
- 8. AEILI. CABLE _Ilt!I_IIPJ0D1 ,
7:.ls relief is requested once per qua: '.er during the first inspection interval.
- 9. AEEPalAL_STAILS1
- a. Relief grented per NRC Generic Letter 89-04.
- b. Added the 1/2 SXO4P Booster Pumps, Rev. Sa.
l
[
i 3.6 - Page 2 of 10 217(041092)
ED79G/19
Revision 5 FELIEf__ REQUEST NO. PR-02
- 1. EUtiP_liUtiDEE: OCC01P, ICC01PA, ICC01PD, 2CC01PA, 2CC0lPD, ICS01PA, ICS01PW 2CS01PA, 2CS01PB, IDOO1PA, IDOO1PB, 1DOO1PC, IDOOIPD, 2tW lPA, 2DOO1PB, 2DOO1PC, 2 DOO1PD, 1RH01PA, 1RH01PB, 2RH01PA, 2RH01PD, ,
OWOO1PA, OWOO1PD
- 2. NUtiBER OF ITEMS: 23 pumps
- 3. ASHILCQDE . CLASS: 2 f. 3
- 4. AStiE_CQP2. SECTI0tLKLEEOUIREliEttIS:
Per IWP-3100, Inservice Test, Procedure pump bearing temperatures are required to be measured to detect any change in the mechanical characteristics of a bearing. 1HP-3500(b) requires three successive readings taken at ten minute intervals that do not vary more than 3%.
5.~ BASIS _f.Q)LEELIEE
- a. These pump bearings cre not provided with permanent temperature detectors or thermal wells. Therefore, gathering data on bearing temperature is impractical.
- b. The only temperature measurepents possible are frnm the bearing housing. To detect high hearing temperature at the bearing housing w>uld require that the bea:Ings in question be seriously degraded,
- c. Measurement of housing temperature on these pumps does not provide positive information on bearing condition or degradation. For example, the bearings on the Diesel 011 Transf er Pumps (1DOO1PA-D and 2DOO1PA-D) are cooled by the pumped fluid. Therefore, any heat generated by degraded bearings ja carried away by the cooling fluid and would not be directly measured at the bearing housing.
- 6. ALIIFEATE TESIllLG No direct alternate test is proposed for bearing temperatures. However, measurement of hydraulle parameters and vibration readings do provide a more positive method of monitoring pump condition and bearing degradation.
- 7. JUSIIIICAIlQH By measuring pump hydraulic parameters and vibration velocity, (as described in PR-01), pump operability and the trending of mechanical degradation is assured. Also, since these parameters (i.e., hydraulle l parameters and vibration) are measured quarterly, the pump mechanical L condition will be more accurately determined than would be possible by measuring bearing temperature on a yearly basis, i 8. APPLICABLE TIME PERIOD:
I This relief is requested once per year, during the first inspection interval.
- 9. AEEROVAL STATUS:
- a. Relief granted per NRC Generic Letter 89-04.
3.6 - Page 3 of 10 217(041092)
ZD790/20
1 Rovision So RELlIf_ECOUISLNA_ rad 2 n
- 1. PMHP_HUBEIEt All Pumps lv the program plan.
- 2. NUMBER _DE_IICHS: 44 pumps l
- 3. ASME_COPI_ CLASS: 2&3
- 4. ASHI_CODL_.SECIlftLKLRNJ1RCHENTS :
Per IWP-3100, Inservice Test Procedure pump bearing temperatures are required to be measured to detect any change in the mechanical characteristics of a bearing. IWP-3500(b) requires three successive readings taken at ten minute intervals that do not vary more than 3%.
- 5. BASIS FOR RELIE[t
- a. The CC, CS, DJ, RH, SX and WO pump bearings are not provided with permanent temperature detectors or thermal wells. There(ore, gathering data on beating temperature is impractical. The only temperature measurements possible are from_the bearing housing.
Measurement of housirig temp 1.ature on these pumps does not provide positive luformation on bearing condition or degradation.
- b. Even those cases where bearing temperature monitoring equipment is available, bearing temperature measurements will not provide significant additional Information regarding bearing condition other than that already obtained by measuring vibration. Measurement of vibration provides more concise and consistent information with reapect to pump and bearing condition. The usage of vibration measurements can provide information as to a change in the balance of rotating parts, misalignment of bearings, worn bearings, changes in internal hydraulle forces and general pump Integrity prior to the condition degrading to the point where the component is jeopardized.
Bearing temperature does not always predict such problems.
- c. An increase in bearing temperature most often does not occur until the bearing has deteriorated to a point where additional pump damage may occur. Bearing temperatures are also affected by the temperature of the medium being pumped, thus the hydraulle and vibration readings are more consistent. Also, the Code specifically esempts temperature measurement for pump bearings in the main flow path (l.e., the diesel oil transfer pumps).
3.6 - Page 4 of 10 217(041092)
ZD79G/21 L
l l
Revision 5 )
RELIET REQUISI_HQ J I:023
- 6. ALIIBHATE TEST 1HG Quarterly measurement of hydraulle parameters and vibration readings provide a more positive method of monitoring pump condition and bearing degradation.
- 7. JESI1rICATION:
By measuring pump hydraulle parameters and vibration velocity, (as described in PR-01), pump operability and the trending of mechanical degradation is assured. Also, since these parameters (i.e.,
hydraulle parameters and vibration) are measured quarterly, the pump mechanical condition will be more accurately determined than would be possible by measuring bearing temperature on a yearly basis.
- 8. APf11EABLILIIME_FIRIOD:
Tnas relief is requested once per year, during the first inspection Interval.
- 9. AEflQ2ATMs This relief is a proposed change to the approved PR-02 and is NOT approved for use. Formal written approval from the NRC la required EI12I to use. Expedited review and approval is requested.
l 3.6 - Page 5 of 10 l
217(041092) l ZD79G/22 h
Revision 5 1 :
EILIIr_Rt0VISTJf 21_fR _03
-Deleted-3.6 - Page 6 of 10 217(041092)
ZD790/23
, ,v, a_:; ; _ ! . ;g ; ,t
- ,~,,
~' ; _; '
- - ~
'O INSERVICE TESTING PROGRAM PLAN FOR IVHPS ;
i BRA!! MOOD STATIC.N UNITS 1 AND 2 i
,' Revision 5 j p'
RELIIL_P100LST_ NO. PR-01 l
i i
-Deleted-i l
i..
217(041092) 3.6 - Page 7 of 10 ZD79G/24
. Rovision 5a RELLEL.EEOUISI_liQuPlc.M IP, w
- 1. IT11P_l!U11BER: OCC01P, ICC01PA, ICC01PB. 2CC01PA, 2CC01PB, ISX01PA, 1$E01PBi 2SX01PA, 2SX01PB, 1SXOU, 2SX04P l
- 1 *
- 2. Hi&lDER OF IIEtiSt 11 Pumps ,
- f. > I
- 3. ASME_CQDE_CLASSI 2 f. 3 TWJ
- 4. ASME_Lont,_5ECTION XI_REQU.1REMElilS:
01 Per IWP-4120, the full scale range of each instrument shall be three times the reference value or less.
- 5. !) Asis ron REL1Ett i
The full scale range of ultrasonic flowmeters, used to collect Section XI flow data, exceed three times the ref erence value.
- 6. ALIERHAIE_IESIlliG t Ultrasonic flowmeters, with digital readouts and totalizer f eatures will be utilized to obtain Section XI flow data.
- 7. J11SIII1CAllDtit Ultrasonic flowmeters provide an accurate means of measuring flowrote.
They utilize a digital display whose accuracy is independent of the full scale range. The ultrasonic flowmeter is well within the requirements of IWP-4110 and IWP-4120, which refer to an instrument accuracy of 1 2 % of full scale for an instrument with a range of three times the reference value or less. The following examples will illustrate this point. The component cooling pumps (OCC01P, 1/2CC01PA, and 1/2CC01PB) have a reference value of approximately 4500 gpm. Using the Code requirements, an instrument with a full scale range of 13,500 gpm (3 x 4500 gpm), the acceptable instrument accuracy is i 270 gpm (.02 s 13500 gpm). Using the ultrasonic flowmeter, with an accuracy of 1 44 of the indP r.ted reading, provider an instrument accuracy of i 180 gpm.(.04 x 4500 gpm).
Use of an ultrasonic flowmeter, with totalizer and integrator feature, instead of other instrurnents allowed by IWP-4110 and IWP-4120, will provide more precise and accurate flow measurements.
- 8. APELICABLI_lltiE_fVlOD:
This relief is requested once per quarter, during the first inspection interval.
- 9. APEROVAk.EIA2115 c a. Relief granted per NRC Generic Letter 89-04.
- b. Added the 1/2SXO4P SX Booster Pumps, Rev. Sa.
3.6 - Page 8 of 10 217(041092)
ZD79G/25 1
-__-_____-_-____________-____-_______-____-_________-__-______._______________-____a
, Revision 5 RELIIE_EEWESI_.N0dA:R1
- 1. EUMP NUMBER: 1DOO1PA, IDOO1PB, IDOO1PC, IDOO1PD, li 2DOO1PA, 2DOO1PB, 2DOO1PC, 2DOO1PD,
- 2. HUMBER OF ITEMS: 8 pumps
- 3. ASME.CODK_ CLASS: 3
- 4. ASME CODE. SECTION KI REW1REtiglilS:
Per IWP-3100, dif ferential pressure shall be measured on all pumps that are tested.
- 5. BASIS FOR'RELIIE:
These pumps are positive displacement Diesel 011 Transfer Pumps. The pump dif ferential pressure is not a f actor af fecting pump performence, but rather dependent only on the inlet pressure to the pump. As the pump discharge pressure is constant, and the inlet pressure varies with tank level, the differential pressure is not a valid operational parameter.
- 6. ALIIFEATE TESTIt[G Pump 31scharge pressure for positive displacement pumps is a valid operational parameter. This will be used to evaluate the Diesel 011 Transfer Pumps performance.
- 7. JUSIII1CATIDti
-Using pump discharge pressure in lieu of pump differential pressure will provide meaningful pump performance data for evaluation of operational readiness of the DJesel Oil Transfer Pumps.
- 8. AEELICABLE TIME PERIOD:
This_ relief is requested once per quarter during the first inspection Interval.
- 9. AEEROVAL STATUS:
- a. Re11ef granted per NRC Generic Letter 9-04 3.6 - Page 9 of 10 l' 217(041092)
ZD79G/26 I
L -, . . ~ . . - , _ . - - _.__. _ _ _ _ , _ , _ . _ . _ , _ . _ . _ . _ . . _ . . . . , _ . . ,_.
Ravision 5 REL1ILIEQUEE7JiQutR-01 Not Used at Braldwood - Byron CNLY 3.6 - Page 10 of 10 217(041092)
ZD79G/27
Ravision 5 l
l 1
SECT 10Bf 4.0 INSERVICE TESTING PROGRAM PLAN FOR VALVT.S BRAIDMOOD STATIQt UNITS 1 AND 2 217(041092)
ZD79G/28
i Revision 5 TAst.E Or CarI73rrs 4.0 Inservice Testing-Program Plan for Valves 9 .
4.1 Program Description i
4.2 -Program References
]
.4.3 Valve Tables
)
4.4. Valve Notes ,
i Note 1 Main Steam Isolation Valves Note 2 CV Emergency Boration System Flowpath Valves Note 3' Nain reedwater Isolation Valves '
Note 4. CV System Letdown and Make-up Isolation Valves Note 5 . RHR Pump Suction- Isolation Valves i Note 6 Intersystem LOCA Valves I
, Mote '7 ~ Reactor Vessel Head Vent Valves !
Note 8 CV, RHR Pump' Discharge Check Valves '
Note 9 RHR.ECCS Check Valves Note 10 Main reedwatar Wate'tv ner Prevention Valves Note;11 VQ Purga Supply and Exhcust Isolation Valves i
-Note 12 AF Suction and Steam Gent rator Check Valves i Note 13 'CV High Head Injection Isolation Valves Note 14 EVAG Valves Note 15 -Deleted- t
-Note 16 Main reedwater Regulating Valves Note 17 .Maln reedwater Regulating Bypass Valves s
'Noto'18 -Deleted- (Incorporated into. Note 21) !
Note 19 -Deleted- (Incorporated into Note 14)
Note 20. Position Indication Testing of Solenold Valves Note'21 Main.Feedwater Tempering-Flow Isolation Valves ,
Note 22 - Hydrogen Monitoring System Check Valves Note 23, Event V Check Valves Note 24 _ Pressure Relief-Check Valves t Note _25; SI Pump Suction Check Valve (1/2SI8926)
Note 26 (CV. Pump Suction Check Valve (1/2CV8546)
Note 27 RH Pump Suction Check Valves (1/2SI8958A/B)
Note 28' VCT Outlet Check Valve (1/2CV8440)
Note 29 Emergency Boration' Check Valve (1/2CV8442)
Note'30 Ar. Check Valve Leak Checks (1/2Ar014A-H)
Note 31 -' CV/SI Mini-Flow Recirculation Line Check Valve Full Flow Testing (1/2CV8480A/B.and_1/2SI8919A/B)
Note 32 CC. Pump Discharg. Check . Valves - (1/2CC9463 A, 1/2CC9463B, OCC9464)
-Note:33 Not Used at-Braidwood - Byron ONLY
- ' Note 34 SD Containment Isolation Valves (1/2SD002A-H, 1/2SD005A-D)
Note 35 . RH Containment Isolation Valves (1/2RH8705A/B)
Note 36 PZR-PORVs 1(2)RY455A/456 Test Frequency (GL 90-06) 4.0 - Page 1 of 2 217(041092)
ZD79G/29
Revision Se TABLE OF Corrt2fTS 4.5 Valve Technical Approaches and Positions VA-01 Method of Stroke Timing Valves VA-02 Method of Fall Safe Testing Valves VA-03 Hethod of Exercising Check Valves VA-04 Determining Limiting Values of Full-Stroke Times for i Power Operated Valves l
VA-05 Testing of the Boric Acid Transfer Pumps Discharge Check l Valves )
l 4.6 Valve Relief Requests VR-1 Appendix J Type C Tested Valves VR-2 Containment Spray NaOH Additive Check Valves VR-3 Safety Injection ECCS Check Valves VR-4 Containment Spray Discharge and Ring Header Check Valves VR-5 Accumulator Discharge Check Valve Testing During Refueling VR-6 SI Pump Suction Check Valve VR-7 -Deleted-VR-8 Component Cooling RC Pump Thermal Barrier Valves VR-9 RC Pump Seal Injection CV Ch ek Valves VR-10 Instrument Air Containment Isolation Valves VR-11 -Deleted-VR-12 Valves Stroking Normally in 2 Seconds or Less VR-13 Diesel Generator Starting Air Solenoid Valves VR-14 -Deleted-VR-15 Safety injection ECCS Check Valve Testing During Refueling VR-16 Containment Sump Outlet Isolation Valve Testing During Refueling VR-17 Motor Driven Aus111ary Feedwater Pump LO Cooler Solenold Valve Stroke Testing VR-18 Deleted - Rev. Sa.
VR-19 Auxiliary Feedwater Pump Suction Check Valve Closure Testing Using Acoustic Monitoring Techniques VR-20 Fixed Alert Ranges for Power Operated Valves VR-21 Not used at Braidwood Station - Byron ONLY - Deleted VR-22 Not Used at Braidwood Station - Byron ONLY - Deleted VR-23 Deleted - Rev Sa.
VR-24 PR Check Valve Back Flow (Bt) Testing During Refueling VR-25 PS Check Valve Back Flow (Bt) Testing During Refueling VR-26 RY Check Valve Back Flow (Bt) Testing During Refueling VR- 2 7 WO Check Valve Back Flow (Bt) Testing During Refueling 4.0 - Page 2 of 2 l
217(041092)
ZD79G/30
. ~
Ravision 5 SECTIOg 4.1 PROGRAM DESCRIPTICM 9
4 217(041092)
ZD79G/31
.- _- , -- - _ _ . - - . - - . . . . - - . - . ~ . - . - . - - _ . - ~ . .
l Revision 5 l PROGRAM DESCRIPTICE The Inservice Testing (IST) Program for Class 1, 2, & 3 valves meets the requirements of Subsection INV of the ASME Section XI Code, 1983 Edition, through the Summer of 1983 Addenda. Where code requirements are determined to be impractical, specific. requests for relief are written, referenced, and included with the tables.- Additional valve relief requests may bo necessary and these will be identified and submitted during-subsequent program revisions. Per NRC Generic Letter 89-04, the status of relief requests as stated in the SER is unchanged.. Any modifications to Braidwood's Station relief requests approved in the SER which are covered by one of the eleven l positions discussed in NRC Generic Letter 89-04, Attachment 1, must be performed in accordance with the guide 1(nes given in the Generic Letter.
Pre-approval is granted forLall relief-requests submitted which are consistent with the eleven positions given. New relief requests deallag with a position n91' covered by NRC Generic Letter 29-04, Attachment 1, must recelye NRC approval prior to implementation. The table lists all code Class 1, 2,-& 3 valves which have been assigned a specific code category as directed by Subsection IWV of Section XI. -The table is organised according to operating system'and.11sted'in valve number order using P&ID references to further categorize.
The valves subject to 1SI 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 laservice testing to assess operational readiness of certain Class 1, 2, and 3 valves (and.their actuating and position Indicating systems) in light-water cooled nuclear power plants, which are required to perform a specific function'in shutting.down a reactor to the cold shutdown condition.or in mitigating the consequences of an accident."
-Exceptions.to this scope are those valves which are exempt,z but added to the '
- program based on NRC mandates. .These valves are identified in the program notes and relief requests.
After installation:and prior'to service, all valves identified in this program-were tested as' required by Subsection IWVJJ100 of Section XI of the ASME Code. These tests were conducted under conditions similar to those to be
' emperienced during subsequent inservice tests. When a valve or its control system has been replaced or undergone maintenance that could af fect its performance, it will be retested; prior to its return to service, to demonstrate that all performance parameters are within acceptable limits.
4.1 - Page 1 of 2 217(041092)
ZD79G/32 3
-- 4 - . . . . - . - . . . . . _ . . . _ . . _ - , - - _ . - - . . , _ _ - . - . - . . . . . , . -
Revision 5' As-required by NRC Generic Letter 89-04, Attachment 1, Posit!.on 5, the limiting value of full-stroke time will be based on the valve reference or average stroke time of the valve when it is known to be in good condition and ,
operating properly. This limiting value is based on a reasonable deviation from this reference stroke time based on valve size, valve type, actuator type, system design, dual unit / dual train design, etc. The deviation should not be.so restrictive that it results-in a valve being declared inoperable due '
to reasonable stroke time variations. However, the deviation used to establish the limit should be such that corrective action would be taken for a >
valve that may not perform its intended function. New or additional reference values may be required its ;
i
- 1) A. valve has been replaced,
- 2) When a reference value or set of values may have been affected by repair or routine servicing of a valve, or
- 3) If-it is necessary or desirable for some reason other than 1) or-
- 2) above.
NRC Generic Letter 89-04, Attachment 1, Positions 1-3 discuss full stroke, alternatives to full stroke, and backflow testing of check valves, respectively. A valid full stroke test is one in which verification of
- maximum required accident condition-flow through the valve is obtained. The minimum acceptable . flow value for a specific valve is determined f rom ,
Technical Specifications, UTSAR,. manufacturers data, engineering calculations, [
etc. An alternative to full stroke testing includes, but is not limited to, a sample disassembly and inspection progrnm of valves g> ouped by similarity of design (manuf acturer, size, model number, materials of construction, etc. ) and '
service conditions (including valve orientation). This sample disassembly and inspection program will be performed during refueling outages. A backflow test verifies that the disc travels to the seat promptly on cessation or reversal of flow, for check valves which perform a safety function in the closed direction. For category A/C check valves'(valves that have a specified ,
leak rate limit and are self-actuated in response to a system characteristic),
the backflow test is satisfied by performing the. leak-rate test.
Per NRC Generic Letter 89-04, Attachment 1, Position 48, whenever valve data is determined to be within the' Required Action Range, the valve is inoperable, and the Technical Specification LCO Action Statement time starts. In the event _a valveLmust be declared inoperable as a result of inservice testing, limitations on plant operations will be as stated in the Technical Specifications. ,
Section XI of the ASME Boiler and Pressure Vessel Code shall not be construed to supersede the requirements of the Technical Specifications.
l 4.1 - Page 2 of 2 l
h
-217(041092)
'ZD79G/33
_ a. -_ _._ .. ~_ . . . . _ . .- _- _ _ . . . _ _ _ - , . . _ . _ . . . , . . .
R2 vision 5 i
l I
1 l
J l
SECTICM 4.2 PROGRAM REFERENCES l i
217(041092)
ZD79G/34
Revlslon 5a PROGRAM RrrERENCFS
- 1. Title 10, Code of rederal Regu4ntions, Part 50, Domestle Licensing of Production and Utillsation racilities, particularly Section 50.55a, Codes and Standards.
- 2. ASHE Boller and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1983 Edition, Summer 1983 Addenda.
- 3. ASME/ ANSI OH-1987, Operation and Halntenance of Nuclear Power Plants, including 1988 Addenda, Part 10, Incervice Testing of Valves in Light Water Reactor Power Ptsnts.
- 4. U. S. Nuclear Regulatory Commission, Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs.
- 5. Braldwood Station UTSAR, Section 3.9.6.2, Inservice Testing of Valves.
- 6. Braldwood Station Technical Specification 4.0.5, ASME XI Program Requirements.
- 7. Braldwood Station Technical btaff Procedures, BVP 200-2, 200-3, & 200-4, IST Requirements for Valves.
- 8. NRC Safety Evaluation Reports (SER's):
- a. SER dated October 15, 1991 for Rev. 4.
4.2 - Page 1 of 1 217(041092)
ZD79G/35
R; vision 5 SECTION 4.3 VALVE TABLES 1
217(041092)
ZD79G/36
Revielen 5 Tant.E DESCP.IPTIm The f ollowing information is included in the valve sunnary tables:
A- RWISICti The revision corresponde to the current revision of the program.
D. E}&E The pages are nu;abered sequentially and show the total number of tables.
C. VALVE NUHDER:
The valve number references the unique Braidwood Station equipment piece number (EPN). This specific valve number identifies the unit and system.
D. EhlD The P&lD column references the specific P&ID number which the valves are located on. The Unit 2 P&ID number is given directly underneath the Unit 1 P&ID number.
E. CLASS:
This column refers to the ASME Code Class assigned to the specific valve (1, 2, 3, N for non-Code, and T for tracking purposes only).
- r. VALVE CATESQEX:
The valve estegory identifies the valve category defined in subarticle IWV-2200 of ASME Eection XI.
G. YALYLSIZL The valve size lists the nominal pipe size of each valve in incher.
l.
t l
l 4.3 - Page 1 of 5 l
l- 217(041092) l ZD79G/37 l
l
- w. . - - - -
f R2 vision 5
, l TABLE DESCRIPTION H. EALYE_IVEE:
The vai~.e type eategorises the valve as to its valve design. The following abb:eviations will be used to identify specific valve typece ,
I Cate GA
-Vlobe GL i Dutterfly DTT i Check CK l
Safety Valve SV Relief Valve RV Power Operated Relief Valve PORV Diaphragm Seated D Plug P Angle AN
- 1. ACI2_I1EC The actuator type identifies the valve actuator. The following ebbreviations will be used to designate specific types of valve actuators:
Motor Operated H.O.
.Alr Operated .O.
Hydraulic Operated H.O.
Self Actuated S.A.
Manual M Solenoid Operated S.O.
J. t[OffiAL POSIT 10ti Normal position identifies the normal operating position of a specific valve. O for open and C for closed.
K. ETROKE DIRE 31Dti The stroke direction identifies the direction the valve actuator moves a specific valve stem to place the valve disc in a position to perform its designed safety function. O for open, and C for closed. This identifies the direction the valve stem will move when tested.
Notes Exercising of a power operated valve will involve stroking the valve to both its open and closed position. The valve will only be timed, however, in the direction designated to perform its safety function. Therefore, the program plan specifies only the direction in which valves must be stroked to be timed.
! 4.3 - Page 2 of 5 217(041092)
ZD79G/38
Revision 5 TABLE DESCRIPTION L. IIST METHRD:
The test method column identifies specific tests which will be performed on specific volves to fulfill the requirements of Subsection IWV of ASME Section XI. ThL tests and abbreviations used are as follows:
- 1. (Dt) Check Valve Back Plow Test The check valve dise will be exercised to the closed position required to fulfill its safety function by verifying that the disc travels to the seat promptly on cessation or reversal of 21ev, except for those valves that can only be back flow tested by me6ne of a seat leakage test.
- 2. (Ct) Check . Valve Puli ltrAke_ Irs _t The check valve disc will be exercised to the open position required to fulfill its safety function by verifying the maalmum required accident flow ?.hrough the valve or alternatives to full flow testing, per NRC Genoric Letter 89-04, Attachment 1, Positions 1 and 2.
- 3. If1Lf_alUAfn__Telt Valves with fall safe actuators will be tested to verify the valve operator moves the valve ster to the required fall safe position upon loss of actuating povar, in accordance with INV-3415.
This will be accomplished during ths normal stroking of the valve. Upon stroking a valee to its fall safe position, the solenoid operator is de-energized causing air to be vented whjch in turn allows t..e spring to move the valve to its fall 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. Ilt) Position IndicAtlan Check Valves which are identified to require a Position Indication Test will be inspected in accordance with IWV-3300 of ASME Section XI.
.5. ILt) Seat Leakage Test The seat leakage tests will meet the requirements of INV-3420 for Category A valves. On these valves, seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their safety function.
4.3 - page 3 of 5 217(041092)
ZD79G/39
_ , . , , , _ __ _ _ _ _ __r- _ . - - -u_---.----- - - -
Ravision 5 TABLE DESCRIPTION
- 6. 1Et) Safety Valve Setpoint Cheri Safety valve setpoints will be verified in accordance with IWV-3510 of ASME Section XI.
- 7. (St) rull Strqi d n t Valve exercising tests of Category A and B valves will be performed in accordance with IWV-3410. The test will include full stroke testing to serify operability in the direction required to fulfill the required safety function.
- 8. IXt) Partial-SitDi G M1 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. IEST MORE:
't Denotes the f requency and plant condition necessary to perf orm a given test. The following abbreviations are usedt llDInn) Operation (OP)
Tests designated "0?" will be performed once every 3 months, except in those modes in which the valve is nc- required to be operable.
Semiannual (S)
Tests with this designation will be conducted once every 6 months, except in those modes in which the valve is not required to be operable.
Co_Id Shutdown (CS1 Valves that cannot be operated during plant operation shall be f ull stroke exercised during cold shutdowns. Valve testing will commence within 48 hears after shut 6own, with completion of old shutdown valve testing not belu, a prerequisjte to plant stcrtup. Valve tests which are not completad during a cold shutdowa, shall be completed during subsequest cold shutdowns tu meet the Code Specified Testing f requency.
For planned shutdowns, where ample time is available, and testing all the valves identified for cold shutdown test frequency in the IST Program will be accomplished, exceptions to the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may be taken.
In case of frequent cold shuudowns, valve testing need not be performed more often than once during any three-month period.
Esactor Eclutlin2 M Tests with this designation will be conducted during reactor refueling outages only.
4.3 - Page 4 of 5 217(041092)
ZD7QG/40
Revision 5 TABLE DESCRIPTICM !
l H. RELIEF REQUISI:
Relief requests reference a specific request for relief from code requirements. All relief requests are included in Section 4.6.
e O. NQIES:
Notes provide a short explanation cot:erning a particular IST valve. All notes are included in Section 4.4.
P. TECP.NICAL APPROACHES E D POSITIONS:
Technical approaches and positions provide detailed discussions on a particular IST , topic. All technical approaches and positions are included in Section 4.5.,
O. REMARKS: -
Remarks reference other information u-2eful in determining valve testing requirements or, methods.
.a
$b, c '
2 4
1 l 4.3 - Page 5 of 5 l 217(041092) >-
ZD79G/41
l!- 1l ;1 S
K R
A N
E R
H .l CSA 5 5 EOV TPi 3 4
f o
S I E
T e O g N a P
S E
L T B FS A EE) T IUR LQV E EEi V RR L A
V 3
.E . .
TP E CY A. A.
AT S S E
VE . 0 0 LZM AII 2 2 VSi Y
V L
A N S N VO S A I A T T LDT L P T A C T T MNS A E R MR A A GGE 5 5 O U W D - -
R A O I 5 5 P P & 6 6 d P - -
G n R M M N aA E I 2 T . L S3C &
E U )
V . N , 3 7 2 1 5 R 7 8 2 E 0 EE 4 4 9 C ,
0 , n VB 8 8 0 2 4
I 1 o0 o i M B 8 1 V w L.
r U A A 4 /
R S D S s VN O 2 0( G9 E S I T i /
S AA I N L R N e I CB U R v 1
_ 7 7 1
2 Z D
, fll l l lf l!1! ll
INSERVICE TESTING PROGRAM P'J14 CLASS 1. 2. 3. tnd AUGMENTED VI.LtTS BRAID 6 NUCLEAR POWCR STATION UNITS 0, 1. & 2 R vision S VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH.
NUPEER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES P05. RENA7tKS (IN.) (VR) (VA) 1/2/I001A N37 3 C 6.0 CK S.A. C 0 Xt/Ct OP/CS 12 3 N122 C Bt RR VR-19 3 1/2Af0018 M ~7 3 C 6.0 CK S.A. C 0 Xt/Ct OP/CS 12 3 5122 C Bt PR VR-19 3 1/ZAf003A M-37 3 C 6.0 CK S.A. C 0 Xt/Ct OP/CS 12 3 W122 1/ZAf0038 M-37 3 C 6.0 CK S.A. C 0 Et/Ct OP/CS 12 3 W122 1/2Af006A N37 3 8 6.0 GA M.0. C 0 St OP 1 M-122 It RR 1/2Af0068 5 37 3 8 6.0 GA M.0. C 0 St OP 1 N122 It RR ,
1/2Af013A M-37 2 8 4.0 GL M.0. O C St OP 1 M 122 It RR 1/2Af0138 M-37 2 8 4.0 GL M.0. O C St OP 1 M-122 It RR 1/ZAf013C M-37 2 8 4.0 GL M.0. O C St OP 1 M-122 It GR 1/2AF0130 W37 2 8 4.0 GL M.0. O C St CP l M-122 It RR 1/2/.f 013E N37 2 8 4.0 GL M.O. O C St OP 1 M-122 It RR 1/2Af013f % 37 2 8 4.0 GL M.0. O C St op 1 M-122 It RR 1/2AF013G N37 2 8 4.0 GL M.0. O C St 07 1 M-122 It JR 1/2Af013H M-37 2 8 4.0 GL M.0. O C St OP 1 5122 It RR 1/2AF014A N37 2 C 4.0 CK A. C - 0 Ct CS 12 3 M-122 . . . C lt CS 12. _ 3 L 3 1/2Af0148 N37 2 C 4.0 CK S.A. C 0 Ct CS 12 3 5122 C Bt CS 12. 20 3 4.) VALVE TABLES - Page 2 of 43 217(041092)
ZD79G/43
- s - -
-INSERVICE TESTING PROGRAM PLAN -
7 .j'
)CLAS5: 1.-2,'3, and AUGMDtTED. VALVES BRAIDWOOD NUCLEAR POWER STATION' l UNITS 0 -1, t 2 3 Revision 5 UALVE VALVE VALVc VALVE ~ACT. NORMAL STROKE . TEST TEST RELIEF . TECH.
NUPSER PLID- CLASS CATEGORY SIZE TYPE- TYPE POSITION DIRECT.. ' METHOD MODE- REQUEST NOTES P05. RDuRKS fik.) (VR) fVA) 1/2AF014 N37 - 2. C 4.0 CK 5.A. C -0 Ct C5 12 3 N122 C Bt C5 12. 30 3 1/20F0140 N37 2- C 4.0 CK 5.A. C 0 Ct C5 12 ?
N122 C st' C1 12. 30 3 1/2AF014E N37 2 C 4.0 CK 5.A. C 0 Ct C5 12 - 3 i N122 C 8t ~C5 IL 30 3 1/2AF014F. N37 2 C 4.0 CK - 5.A. C 0 Ct C5 12 3 N122- C Bt C5' 12. 30 3 1/2AF014G N37 2 C 4.0 CK 5.A. .C 0 .Ct C5 12 - 3 ft N122 C Bt CS 12. 30 3 1/2AF014H N37 2- C- 4.0 CK- 5.A. C 0 Ct C5 12 3 NJ22 C 8t C5 12. 30 3
'1/2AF017A N37 3 8 6.0- GA n.0. 'C 0 St OP I
~ N122 .
It RR 1/ZAF0178- N37 3 8 6.0 GA M.0. C 0 St OP 1 N122 It RR 1/ZAF029A N37 3 C 6.0 CK 5.A. C 0 Ct. C5 12 3 N122
-1/2AF0298 N37 -3 C 6.0 CK 5.A. C 0 Ct C5 12 3 N122 l
1 4.3 VALVE TABLES - Page 3 of 43 l
l I
i p j 217(001092) I
[--2D79G/44 i !
. . ~. _ _ _ _ . _ . _ _ _ _ _ _ _ _ , . . __ _ ___ O
I SERVICE TESTING PROGRAM PLAN.
. CLASS 1. 2. 3.'and AUGHENTED VALVES BRAIOw000 NUCLEAR POWER STATION UNITS 0. 1. & 2 R; vision 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH.
NUPSER P&ID CLASS . CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MDOE REQUEST NOTES P05. RENARKS (IN.1 (VR) (VA)
I/2CC685 N66-1A -2 A 4.0 GA M.0. O C it CS VR-8 1 It RR M-139-1 Lt RR VR-1 1/2CC9412A M-66-2 3 8 12.0 GA M.0. C 0 St OP 1 M-139-2 It RR 1/2CC94128 PS-66-2 3 B 12.0 GA M.0. C 0 St OP 1 M-139-2 It RR 1/2CC9413A N66-1A 2 A 6.0 GA M.0. O C St CS VR-8 i N139-1 It RR Lt RR VR-1 1/2CC9414 M-66-1A 7 A 6.0 GA M.0. O C St CS VR-8 i M-139-1 It RR Lt RR VR-T 1/2CC9416 M-66-1A 2 A 6.0 GA M.0. O C St CS VR-8 1 S139 ' It RR Lt RR VR-f 1/2CC9437A M-66-1A 2 8 3.0 GL A.O. C C St/Ft OP 1.2 N139-1 It RR 1/2CC94378 M-66-1A 2 8 3.0 G1. A.O. O C St/Ft OP 1.2 N139-1 It RR 1/2CC9438 M-46-1 A 2 A 4.0 GA M.0. O C Lt RR VS-1 M-139-1 It RR
_ St CS VR-8 1 1/2CC9463A M-66-38 3 C 12.0 CK S.A. C 0 Ct/Bt CS 32 3
_ C Xt OP 3 s 1/2CC94638 M-66-38 3 C 12.0 CK S.A. C 0 Ct/Bt CS 32 3 C Xt 09 3 OCC9464 N66-33 3 C 12.0 CK S.A. C 0 Ct/Bt CS 32 3 C Xt OP 3
, 1/2CC9473A N66-38 3 8 16.0 GA M.0. C 0 St OP 1 It RR l 4.3 VALVE TABLES - Page 4 of 43 217(041092)
ZD79G/45
l S _
K -
R A
M E _
R _
H .
f _
o S 5 E 4 T 4 e O 2 2 g N a P
S E
T L FS B EE 8 8 8 A T
IU , ,
LQ ,
E EE 1 d 1 8 1 8 V RR - - - - - -
L R R R R R R A V V V V V V _
V _
3 _
TE 4 _
S0 P R R P R R R R E0 O R R O R R R R TH 0 t t t 8 B B S'0 ET H t 5
t I
/
t t
C t
/ t /
C t C t
TE L L L N
ET KC OE 0 C 0C 0 C 0 RR TI SD N
.E . . . .
TP 0 A. A.
CY A.
AT M S S S E
VE LP A K K K AY G C C C VT E 5 5 VE U 0 7 7 LZ
. AI 6 0 0
- VS
_ Y R
EO VG C C C LE 8 A A AT VA _A S C E
V L
_ A N S N VO S A I A 3 2 2 2
_ L DT L
_ PE TAT C
_ M NS A E R MR GGE 8 A 1 A 1 A 1 O U W D 3 1 1 - 1
_ R AO I - - % - 9 - %
P P & 6 6 3 6 3 6 3
_ d P 6 6 1 6 1 6 1 nR
% M- H -
_ ~G - - - -
_ N o. EA 2 M MM M I
. T .L
_ S 3C &
E ,UN 8 )
T . a 3 6 8 4
_ 2 1 5 R 7 8 1 3 2 E O EE 4 4 5 5 9 C ,O , n VB 9 9 9 9 0 6
. I 1 O 0 o LM C C C C 1 4
_ V W i AU C C C C 4 /
0 G R S D S s VN 2 2 2 Z
. E S I T i / / / / ( 9 S AAI v 1 1 1 1 7 7
_ N L R N e 1 D I C B UR 2 Z j'1'. j5 , h , 1 !
i! i ,
t
,.s., .,
, LINSFRVICE TESTING FC:0 GRAM PLAN CLASS'1, 2,.3. tnd AUGMENTED VALVES-BRAIDWOOO NUCLEAR F0WER STATION gj
. UNITS 0, 1, & 2 :
R::visicn 5 -
1-VALVE . .
VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH.
NUMBER.-l'P&ID.
, CLASS . CATEGORY SIZE .. TYPE TYPE- POSITION DIRECT. ' METHOD N00C REQUEST NOTES POS. - ROWtKS
, IINJ (VR1 fvAl
- -1/2C5001A 561-4 2 B 14.0 GA M.0. O C- St Or I i
W136-4 It' RR i 1/2C50018 M-61-4 2 B 14.0 GA M.0. .0 C St' OP 1: ;!
I S136-4 ~ It RR 1/2CS003A' 546-1A 2- C 10.0 . CK ,- S.A. C 0 Xt/Ct OP/RR VR-4 3-
- I N12%1 A j 1/2CS0038 546-1A- .2 C ,10.0 - CK- S.A. C 0 Xt/Ct :OP/RR VR-4 3'
)' N12 %1A i 1/2CS007A M-46-1C 2 A 10.0 GA M.0. C 0 Lt RR VR-1 N129-1C St '
{ OP 1
- It RR
- j. 1/2C5007B N46-1C 2 A 10.0 GA. M.O. C 0 'Lt RR VR-1
[ H-129-1C St OP 1 It RR-1/2CS008A S46-1C .2 AC 10.0 CK S.A. C 0 Ct/Bt RR VR-4 [
3 q
r4-12%1C C Lt RR . VR-1 3 1/2CS0088 S46-1C 2 AC 10.0 CK S.A. C 0 Ct/Bt RR VR-4 3 .!
- -129-1C
, C Lt RR VR-1 3 1/2C5009A t141-4 2 8 16.0- GA M.0. C 0 St OP 1
.. y N136-4 It RR 1/2C50098 561-4 2 ,B 16.0 GA M.0. C 0 St CP i 1
H-136-4 It RR ~
1/2C5011A S46-1A 2 C 6.0 CK S.A. C 0 Ct 09 3 N12%1 A 1/2CS0118 i N46-1A 2 C 6.0 CK S.A. C 0 Ct OP 3 N12%1 A
- 1/2C5019A M-46-18 2 B 3.0 GA M.O. C 0 St OP 1 N12%18 .
It RR 1/2CS019a %46-1B 2 8 3.0 GA M.0. C 0- St OP I j 5 12 % 18 It RR 1/2C5020A S46-18 2 C 3.0- CK S.A. C 0 Ct RR VR-2 3 i N12%1A 1/2C50208 N46-18 2 C 3.0 CK S.A. C 0 Ct RR VR-2 3 ,
M-129-1A 217(041092) 4.3 VALVE TABLES - Page 6 of 43 ZD79G/47 t
V m - ie -w _ _e_ _ _ __-_mc - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ _-
INSERVICE TESTING PROGRAM PLAN
' CLASS 1, 2. 3. tnd AUGHENTO VALVES BIAIDWOOD NUCLEAR POWER STATION UNITS 0, 1, & 2 Rivision 5 VALVE VALVE VALVE VALVE ACT, NORMAL fR0kE Ti_ST TEST RELIEF TECH.
NUMBER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES POS. REMARKS (IN.) (VR) (VA) 1/2CV1128 +64-4A 2 8 4.0 GA M.0. O C St CS 4, 28 1 N138-48 It RR 1/2CV112C M-64-4A 2 8 4.0 GA H.O. O C St CS 4, 28 1 M-13 A 48 It RR 1/2CV112D N64-48 2 B 8.0 GA M.0. C 0 St CS 2 1 N138-4A It RR 1/2CV112E H-64-48 2 B 8.0 GA M.0. C 0 St CS 2 1 W13b4A It RR 1/2CV8100 N64-2 2 A 2.0 GL M.0. O C St RR VR-9 N138-2 It RR 1 Lt RR VR-1 1/ZCv8104 M-64-48 2 B 3.0 GL M.0. C 0 St CS 2 I N138-4A It RR 1/2CV8105 N64-38 2 B 3.0 GA M.0. O C St CS 4 1 M-138-38 It RR 1/2CV8106 N64-3B 2 B 3.0 GA M.0. O C St CS 4 1 N13%3B It RR 1/2CV8110 M-64-3A 2 8 2.0 GL H.O. O C St OP 1 M-138-3 It RR 1/2CV8111 N64-3A 2 B 2.0 GL M.0. O C St OP i W138-JA It RR 1/2CV8112 564-2 2 A 2.0 GL M.0. O C St RR VR-9 i M-138-2 It RR Lt RR VR-1 1/2CV8113 +64-2 2 AC .75 CX S.A. C C Lt/8t RR VR-1, 9 3 M-13b2 0 Ct RR VR-9 24 3 1/2CV8114 H-64-3A 2 8 2.0 GL 5.0. O C St OP 1 Wl38- 3 It RR 20 1/2CV8116 564-3A 2 B 2.0 GL S.0. O C St OP 1 N13%3A It RR 20 4.3 VALVE TABLES - Page 7 of 43 217(041092)
ZD79G/48
-m . _.
- y.
- INSERVICE TESTING' PROGRAM PLAN ;
'~p.
CLASS')."2. 3. and' AUGMENTED VALVES)
! ?- BRAIDWOOO MUCLEAR POWER STATION -
UNITS 0.-1 &'2-
+ 'Rsvision 5- ,
I' VALVE . .. . -VALVE' . VALVE. VALVE ACT.. NORPat. STROKE. TEST TEST -RELIEF TECH.
{- NUPEER -P&ID CLASS- CATEGORY SIZE TYPE- TYPE POSITION DIRECT. METHOD- MODE- REQUEST,- MOTES P05. . RO%RKS <
, -(IN.)' fVR) fVA1 1/2CV8152 +64-5 2- A- 3.0 GL A.O. O C. St CS. 4 1 5138-5A lIt RR It CS 4 2-t Et PR- VR-1
, 1/2CV8160 N64-5 2- A. 3.0 GL A.O. O C- St. CS 4 1 N 138-5A :It RR
< 1/2CV8442 K-64-48 2 C. 2.0 CK - 5.A. .C -
0 Ct CS- 2, 29 3-t W138-4A j 1/2CV8480A N64-3A 2 C 2.0 CK S.A. .C 0- Ct OP 38 3 N138-3A C Bt OP 1 =
- 1/2CV84808 564-32 2 C 2.0 CK S.A. C 0 Ct OP 31 3-
- M 138 3A 'C Bt OP 3 1/2CV8481A M-64-3A 2 C 4.0 CK S.A. C 0 Ct/Xt RR/0P VR-15 3-
+
W138-3A C- Et RR VR-15 3-
- .l/ECV84818 M-64-3A 2 C 4.0 CK .. S.A. C 0 Ct/Xt RR/0P VR-15 3 7 M-138-3A 'C' 8t RR VR-15 3 1 1/2CV8546 M-64-48 2 C - 8.0 CK- 5.A. C 0 Ct RR VR-15 2, 26 3 W138-4A
+ 1/2CV8804A N64-48 .2 8 8.0 GA M.0. C 0 St CS 2 1
, N138-4A It SR 5
l 4.3 VALVE TABLES - Page 8 of 43 217(041092)
! ZD79G/49
INSERVICE TESTING PROGRAM FtAN '
' CLASS 1. 2. 3. tnd At,T> TENTED VALVES 8RI.IDW000 NUCLEAR POWER STATION UNITS 0. 1, & 2 R; vision 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST . TEST RELIEF TECH.
NUMBER P&ID CLASS CATEGCRY SIZE TYPE TYPE POSITION DIRECT. METHOD H0DE REQUEST NOTES POS. REHARKS ffN.1 (VR1 (val 1/2DG5182A f+-54-4 NONE B 3.0 GA - S.0. C 0 St OP VR-13 1/2DG51828 N-.152-20 NONE B 3.0 GA S.0. C 0- St OP VR-13 1/2DG5183A 554-4 NONE B 3.0 GA S.O. C 0 .. St OP VR-13 1/2DG51838 H-54-4 NONE S 3.0 GA S.O. C 0 St OP VR-13 1/2DG5184A N152-20 NONE C 3.0 CK S.A. C 0 Ct OP VR-13 3 1/20G51848 N152-20 NONE C 3.0 CK S.A. C 0 C' OP VR-13 3 1/2DG5185A 5152-20 NONE C 3.0 CK S.A. C 0 Ct OP VR-13 3 1/2DG51858 N152-20 NONE C 3.0 CK S.A. C 0 Ct OP VR-13 3 4.3 VALVE TABLES - Page 9 of 43 217(041092)
ZD79G/50
1 >
S K
R A
M E
R H .)
CSA3 3 3 1 3 3 3 3 EOV 3 TP(
4 f
o S 0 E 1 T
O e g
N a
P S
E T L FS B EE) A IUR T LQV EEf E RR V L
A V
3 TE 4 S0 P 9 P P P P P P E0 O 0 G O O O O O TN 0
T0 SH t t t t t t t t ET C B C B C B C B TE M
ET KC C OE 0 C 0 C 0 C 0 RR TI SD N
.P
.E . . .
TP CY A. A. A. A..
AT S S S S e
E VE LP K K K K AY C C C C VT E )
VE . 5 5 5 5 LZN AII 1 1 1 1 VS(
Y R
EO VG -
LE C C C C AT VA S C E
V L
A N S N V O S A I A 3 3 3 3 L DT L P E A C T T M NS A E R A B A B GG 1 OU4 D B
1 1
A 1
1 8
1 1
A 1
1 R A 0 P ' r I
& 0
- 0 3 0
- 0 -
3 0 0
3 0
- 0 3
d P 5 1 5 1 5 1 5 1 G oR - - - -
N cA MM M M M W5 N I
T .E2L S 3C&
E U T .N ,
A 8 C 0 )
2 1 5 R 3 3 3 3 2 E O EE 0 0 0 0 9 C
I 1
.O O0 o
. n VE LP 0
0 0
0 0
0 0
0 0 1 1 5 V W i AU 0 0 0 0 4 /
R S D S s VN 2, 2 2 2 0 G E S I T i / / / ( 9 S A AI v 1 1 1 1 7 7 N L R N e 1 D
I C B UR 2 Z i
' t . , lp . ! ! F > ! I. 'E I , ! j5: ', ,lE!
e e. e e S v v v v.
K i s
i s
i s
i s _
M s a
s a
s a s.
a M P P E P P R
M .)
C5A E0V 3 TP( 4 f
o 1
S 1 _
E T
O" e g
N' a P
S E
L
-T B
'fS lEl 1 1 1 1 A
- - T IUi l - -
. LQV R R R R E EE( V V. V V V RR L A
V 3 .
TE .
TO -
SH t t. t t ET L L. L L .
TE M
,. t
~
ET KC -
OE C C C C.
LO AI MT C RI C C C OS-NO P-E TP' CY M M M M AT E
VE -
VE _ 0 0 0 0 LZN AII 4 4 3 3 VS(
.Y
.S C
,E
=
,VL AN S NYO S A I .A 2 2 2 2 L DT L PE A C T T MNS A E R MR GG E -
A A 8 C 8 C OUW D 1 1 . 1 1 1 1 R A O I - - - - - -
P P .& 3 3 3 3 3 3 d P 6- 6 6 4- 6 G nR - - -
N aA I
N M MM MM T .E L 2 S 3C &
E T .N U~. 2
)
2 E : D 2 1 5 EE
.R 9 0 0_
1 1
1 1 9 0 2 C .O I 1 O 0 o
, n .
Ve L t 0
C 0 C...
0 C
0 C 1 5 V
RS DS s W i AU VN f
2 F
2 F
2 F
2 4 /
0 G E S I T i / / / / ( 9 S A AI v 1 1 1 1 7 7
- L R N e 1 D 1 CB U R 2 Z
, , i j ' ,
S K
R A
P E
R H .)
CSA 1 2 EOV TP( 3 4
f o
S 2 E 1 T
O e N g a
P S
E T L FS B EE) A IUR T LQV EE( E RR V L
A V
.E .
TP CY O.
AT A E
VE .0 LZN AII 4 VS(
Y R
V L
A N S O S MV L DT I A L
2 P E A C T T MN S A E R MR GG E 1 O U W D -
R A O I 2 P P & 5 d P -
G nR M N aA I
,EL 2 T
S 3 C &
E U T .N , 5 )
2 1 R 0 2 E D EE 1 9
C ,O , n VB 0 0 3 I 1 O 0 o LM P 1 5 V W AU F 4 /
R S DS E S I T i is VN 2
/ 0 G
D I C B U R 2 Z
INSERVICE TESTING PROGRAN PLAN CLASS 1, 2, 3, tnd AUCNENTED VALVES BRAIDWOOD NUCLEAR POWER STATION LHITS 0,1, & 2 Ravision 5 VILVE VALVE VALVE VALVE ACT. NORMAL STROKE- TEST TEST RELIEF TECH.
HUteER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. NETH00 H00E REQUEST NOTES POS. RENARXS' FIN.) (VR) (VA) 1/2fW O9A W36-1C 2 8 16.0 GA H.O. O C St/xt CS/CP , 3 I H-121-1B It RR 1/2fu0098 N36-1A 2 8 16.0 GA H.O. O C St/Xt CS/0P 3 1 M-121-10 It . RR 1/2fWOO9C 536-1D 2 8 16.0 GA H.O. O C St/Xt CS/GP 3 1 H-121-1A It RR ~
1/2FWOO90 H-36-18 2 B 16.0 GA H.O. O C St/Xt CS/0P 3 1 W121-1C It RR 1/2fu034A M-36-1C NONE B 2.0 GL A.0 0 C ft RR 21 2 W121-18 1/2fw0348 536-1A MONE B 2.0 GL A.O. O C ft RR 21 2 N121-10 1/2fWO34C M-36-ID NONE B 2.0 GL A.O. O C ft RR 21 2 H-121-1A I/2fw0340 %36-1B NONE B 2.0 GL A.O. O C ft RR 21 2 N121-1C 1/2fWO3SA N36-1C 2 B 3.0 GL A.O. O C St OP 1 P-121-18 It RR ft OP 2 1/2fWo358 N36-1 A 2 8 3.0 GL 4.0. O C St OP 1 M-121-ID It RR ft OP 2 1/2fw035C 536-ID 2 8 3.0 GL A.O. O C St OP I H-121-1A It RR ft OP 2 1/2fWO3SD 536-1B 2 B 3.0 GL A.O. O C St OP 1 W121-1C It RR ft OP 2 1/2fWO39A N36-1C 2 8 6.0 GA A.O. O C St OP 10 i H-121-18 It RR
_ ft CS 10 2 4.3 VALVE TABLES - Page 13 of 43 217(041092)
ZD79G/54
INSERVICE TESTING PROGaAH PLAN CLASS 1, 2, 3, and AUGHENTED VALVES BRAIDWC00 NUCLEAR P0WER STATION UNITS 0, 1, & 2 Revision S VALVE ACT. NORMAL STROKE TEST TEST RELIEF T EO..
VALVE VALVE VALVE TYPE POSITION DIRECT. METHOD N00E REQUEST NOTES P95. REMARKS NUteER P&ID CLASS CATEGORY SIZE TYPE (VR1 (VA1 IIN.)
A.O. St CS 10 1 1/2FWO398 536-1A 2 L 6.0 GA O C It RR H-121-1D Ft CS 10 2 St CS 10 1 1/2fw039C H-36-1D 2 8 6.0 SA A.O. O C H 521 1A It RR Ft CS 10 2 1/2fw0390 H-36-18 2 8 6.0 GA A.O. O C St CS 10 1 It RR H-121-1C Ft CS 10 2 1
1/2rWO43A H-36-IC 2 B 3.0 GL A.O. C C St OP 1 j
It RR M.-121-1B Ft OP 2 1/2FWO438 N36-1A 2 8 3.0 GL A.O. C C St OP 1 It RR M-121-10 Ft OP 2 1/2FWO43C H-36-10 2 B 3.0 GL A.O. C C St OP 1 It RR H-121-1A Ft OP 2 1/2FWO430 S36-1B 2 B 3.0 GL A.O. C C St OP 1 It RR M-121-1C Ft OP 2 A.O. Ft RR 16 2 1/2FW510 N 36-1C NONE B 16.0 AN O C 5121-1 2 1/2FW510A N 36-1C NONE B 4.0 GA A.0 C C Ft RR 17 N121-1 16 2 1/2FW520 M-36-IA NONE B 16.0 AN
- A.O. O C Ft RR
%121-1 17 2 1/2FW520A N36-1A NONE B 4.0 GA A.O. C C Ft RR .
l H-121-1 2 1/2FW530 S 36-ID NONE B 16.0 AN A.O. O C Ft RR 16 M-121-1L 4.3 VALVE TABLES - Page 14 of 43 217(041092)
ZD79G/55
7 S
K R
A N
E R
H .)
CSA 2 2 2 EOV 3 TPf 4 f
o S 5 1
E 7 6 7 T' 1 1 1 e
O g N a P
S E
T L FS B EE) A T
IUR LQv E EEf V RR L A
V 3
.E . .
TP 0 CY' O. O.
AT~ A A A E
VE . l 0 0 0 LZ AIU4 VS(
6 1
4 Y
V L
A N S E E E NV 0 S N N N A 1 A O O O L DV L N N N P E A C T T MNS A E R MR A C C G D B B O KE W 1 1 1 D I - 1 - 1 -
R P
MOP I
& 6
- 1 2 6
- 1 2 5
- 1 2
d P 3 1 3 1 3 1 G nR N aA I E2 H- % M -
NNN T ,L S 3 C &
E ,3 V C
, 5 A A )
2 1 R 0 0 A 2 E D EE 3 4 4 9 C ,O I 1 O 0 o
. n Ve L t W M 5 W 0 6 1 5 V W i AU VN f f f 2
4 /
R S DS s 2 2 E
S S I T i A AI v
/
1
/
1
/
1 0%
(
7 7 N L R N e - 1 D I C B U R 1 2 Z
l S
K R
A M
E R
H .)
CSA 1 2 1 2 3 EOV 3 TP( 4 I
f o
S 6 1
E T _ e O g N a P
I S
E T 0 t FS 0 0 0 0 1 8 EE) 1 1 1 1 1 1 A
- - , T IUR - - - -
LQV R R R R R R 1 E
EE( V V V V V V -
V RR R L V
A V
3 TE 4 SD R R R R R R R R R EO R R R R R R R R R TM
- D t TO 8 SH t t t t t t t t /
.E- . .
TP 0 A.
CY' O.
AT A A S E
VE' LP L L K AY G G C VT E 1 5 VE 0 0 7 LZN AII 3 3 0
_ VS(
Y R
EO VG C
- LE A A A
. AT VA S C E
V L
A N S N VO S A I A 2 2 2 L DT L P E A C T T M N S A E R MR 0 5 5 GGE 0 5 10 O U W D 1 1 1 1 1 R A O I - - - - - -
P P & 5 5 S 5 5 5 d P 5 5 S 5 3 5 G nR N aA I E 2 5M -
NM -
%5 T ,L S 3C &
E U )
T ,N ,
2 2 1 5 R 5 6 1 9
E D , n EE 6 6 9 0 7 C ,O VB 0 0 0 5 I 1 O0 o LM A A A 1 4 /
V W i AU VN I
2 1
2 I
2 0 G R S D S s / / ( 9 E S I T i 1/ 1 7 7 S AAI v 1 1 D NL R N e 2 Z I C B UR
-INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3, and AUG4ENTED VALVES BRAIDWOOD NUCLEAR POWER STATION UNIVS 0. 1 & 2 Revision 5 UALVE VALVE VALVE VALVE ACT. NORMAL- STROKE TEST TEST RELIEF TECH.
NUMBER P&ID CLASS CATEGORY SIZE . TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES POS. REMARKS IIH.) 'fVR) (val I/2MS001A M-35-2 2 B 30.25 GA H.O. O C St/Xt CS/09 1 1
~~
M-120-2A It RR 1/2NS001B M-35-1 2 B 32.75 GA H.O. O C St/Xt CS/0P 1 1 M-120-1 It RR 1/ZMS001C M-35-2 2 B 32.75 GA H.O. O C St/Xt CS/09 1 1 M-120-28 _
I1_. RR 1/2M5001D M-35-1 2 8 30.25 GA- H.O. O C St/Xt CS/OP 1 1 M-120-1 It RR 1/ZM5013A H-35-2 2 C 6.0 m SV S.A C 0 Rt RR M-120-2A 10.0 1/2M50138 M-35-1 2 C 6.0 x SV S.A. C 0 Rt RR M-120-1 10.0 1/2NS013C M-35-2 2 C 6.0 m SV 5.A. C 0 Rt RR M-120-28 10.0 1/ZM50130 M-35-1 2 C 6.0 x SV S.A. C 0 Rt RR M-120-1 10.0
-1/2M5014A M-35-2 2 C 6.0 x SV 5.A C 0 Rt ER H-120-2A 10.0 1/2M50148 M-35-1 2 C 6.0 m SV S.A. C 0 Rt RR M-120-1 '10.0 1/ZMS014C M-35-2 2 C 6.0 x SV S.A. C 0 Rt RR M-120-28 50.0 1/2M50140 H-35-1 2 C 6.0 m SV 5.A. C 0 Rt RR M-120-1 10.0 1/2MS015A M-35-2 2 C 6.C x SV S.A. C 0 Rt RR M-120-2A 10.0 1/2M50158 M-35-1 2 C 6.0 x SV S.A. C 0 Rt RR M-120-1 10.0 1/2M5015C M-35-2 2 C 6.0 x SV S.A. C 0 Rt RR M-120-2B 10.0 1/ZM50150 H-35-1 2 C 6.0 x SV 5.A. 0 0 Rt RR M-120-1 10.0 4.3 VALVE TABLES - Page 17 of 43 217(041092)
> ZD79G/58
INSERVICE TESTING PROGRAM PLAN CLASS 1. 2. 3. and'AUGHENTED VALVES BRAIDWOOD NUCLEAR POWER STATION :
UaITS 0. 1, & 2 Ravision Sa VALVE VALVE VALVE VALVE ACT. NORMAL STROKE- TEST TEST RELIEF TECH.
NUMBER P&ID- CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. HETH00 MODE REQUEST NOTES POS. REMARKS ffN.1 (VR1 IVA1 1/2MS016A M-35-2 2 C 6.0 m SV 3.A. O O Rt RR M-120-2A 10.0 1/2HS0168 M-34-1 2 C 6.0 x SV S.A. 0 0 Rt- RR M-120-1 -10.0 1/2M5016C M-35-2 2 C 6.0 x SV 5.A. 0 0 Rt RR H-120-2F 10.0 1/2M50160 M-35-1 2 C 6.0 x SV 5.A 0 0 Rt RR M-120-1 10.0 1/2M5017A M-35-2 2 C 6.0 x SV S.A. 0 0 Rt RR M-120-2A 10.0 1/2MS017B H-35-1 2 C 6.0 x SV S.A. 0 0 Rt RR M-120-1 10.0 1/2M5017C M-35-2 2 C 6.0 m SV 5.A. 0 0 Rt RR H-120-2B 10.0 1/2M50170 M-35-1 2 C 6.0 x SV S.A 0 0 Rt RR M-120-1 12.0 1/2M5018A M-35-2 2 B o.O x PORV H.O. C C St OP VR-12 1 M-120-2A 6.0 It RR Ft OP 2 1/2M501BB M-35-1 2 B 6.0 y PORV H.O. C C St OP VR-12 1 M-120-1 6.0 It RR Ft OP 2 1/2MS018C M-35-2 2 8 6.0 x PORV H.O. C C St OP VR-12 1 H-120-28 6.0 It RR 1/2M50180 Ft OP 2 H-35-1 2 B 6.0 x PORV H.O. C C St OP VR-12 1 M-120-1 6.0 It RR Ft OP
_ _ _ _1/2MS101A M-35-2 2 8 4.0 GL A.O. ~2 C C St OP 1 l
H-120-2A It RR i
Ft OP 2
{ 4.3 VALVE TA8tES - Page 18 of 43 217(041092)
ZD79G/59 l
l l {
S K
R A
M E
R H .
f o
S 9 E 1 T
O e g
N a
P S
E T L FS B EE A IU T LQ EE E RR V L
A V
3 TE 4 S0 P R P P R P P R P E0 O R O O R O O R O TM 0
T0 SH t t t t t t t t t ET S I F S I F S I F TE N
.E . . .
TP CY O. O. O.
AT A A A E
VE h 0 0 LZ AI 4 4 VS Y
V L
A N S N V O S A I A 2 2 2 L DT L P E A C T T MNS AE R MR B G G E 1 2 1 O U W D 1 - 2 - 1 -
R A O I - 0 - 0 - 0 F P & 5 2 5 2 5 2 j P 3 1 3 1 3 1 G nR - - - - - -
- N E A I
,EL 2 M M M H MM
- T S 3C&
E' U T .N , a B C 0 )
- 2 1 S R 1 1 1 2 E D EE 0 0 0 9 C ,O , n V) 1 1 1 0 0 I 1 O 0 o W
LM AU S
M S
M S
M 1 6 V i 4 /
RS D S s VN 2 2 2 0 G E S I T i / / / ( 9 S AA I v 1 1 1 7 7 N L R N e 1 0 I C B U R 2 2 6
_L1 ,"' J w
~
iINSERVICE TESTING PROGRAM PLAN -
' CLASS 1, 2.'3, tnd AUGMENTED VALVES:.
.BRAIDWOOO NUCLEAR-POWER STATION,
-tJNITS 0, 1,.& 2-Revision 5 ,
VALVE VALVE VALVE- VALVE ACT. . NORMAL' STROKE TEST TEST -RELIEF- : TECH.
' NUMBER P&ID.
CLASS CATEGORY: SIZE TYPE -TYPE . POSITION DIRECT. METHOD MODE -REQUEST NCTES POS. REMARKS
' TIM.) fVR1 fVA)'
1/2CG057A M-47-2 A- 3.0 - 8TF M . O .- C C' Lt RR VR N150-2 St - OP- 'Il -
- It RR'
-1/20G079 N47-2 2 .A. . 3.0 .8TF .M.U. C C- Lt' -RR VR-1 - '
N150-2 St: OP 1 t
'It 'RR 1/20G080 547-2 2 .A. 3.0- 8TF. M.O. C C Lt RR VR-1 M-150-2 St OP ~ 1 '.
It RR -t 1/20G081. 547-2 2 A' 3.0 BTF M.0. C C Lt RR VR-1 '
r W150 St . .OP 1 It RR 1/2CG082 M-47-2 2 A . 3.0 BTF- M.O. C 'C Lt RR VR-1 M-150-2 St OP 1 "_
It RR 1/20G083 M-47-2 2 A - 3.0 BTF M.0. C C Lt .RR VP-1 ,
W150-2 St OP 1- ~
It- RR ,'
1/20G084 54/-2 2 A 3.0 BTF M.0. C C Lt RR VR-1 N150-2 5t OP 1 It RR 1/20G085 N47-2 2 A 3.0 BTF M.O. C C Lt RR VR-l M-150-2 '
St OP 1 ft RR 4.3 VALVE TA8LES - Page 20 of 43 217(041092)
ZD79G/61
INSERVICE TESTING PROGR#t PLAN CLASS 1. E 3, rnd AUGHENTED VALVES BRAIDWOOO fiUCLEAR POWER STATION UNITS 0, 1, & 2 R vision 5a VALVE VALVE VALVE- VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH.
NUMBER. P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES P05. REMARKS (IN.1 (VR1 (VA1 1/2PR001A M-78-10 2 A 1.0 GL A.O. O C Lt RR VR-1 N151-1 ft OP 2 St OP 1 It RR 1/2PR0018 N78-10 2 A 1.0 GL. A.O. O C Lt . RR VR-1 N151-1 Ft OP 2 St OP 1 It RR 1/2PR002E N78-6 2 A 2.0 GL M C C Lt RR VR-1 Passive 1/2PR002F N78-6 2 A 2.0 GL M C C Lt RR VR-1 Passive 1/2PR002G N78-6 2 AC 2.0 CK S.A. C C Lt RR VR-1 Passive 1/2PR002H N78-6 2 AC 2.0 CK S.A. C C Lt RR VR-1 Passive l '.
1/2PR032 N78-10 2 AC 1.0 CK S.A C C Lt/Bt RR VR-1, 24 3 5151-1 1/2PR033A N78-6 2 A 2.0 GL M C C Lt RR VR-i Passive 1/2PR0338 N78-6 2 A 2.0 GL M C C Lt RR VR-1 Passive 1/2PR033C N78-6 2 A 2.0 GL M C C Lt RR VR-1 Passive 1/2PR0330 N78-6 2 A 2.0 GL M C RR C Lt VR-l Passive 1/2PR066 578-10 2 A 1.0 GL A.0 0 C Lt RR VR-1 N151-1 Ft OP 2 It RR St OP 1 4.3 VAtVE TABLES - Page 21 of 43 217(041092)
ZD79G/62
~ ~ --
._ y ,
^
1 INSERVICE TESTING PROGRAM PUM - ,
,' 7,7
-: CLASS 1.-2. 3.'and AUGMENTED VALVES *
' ; BRAIDWOOD NUCLEAR POWER STATION: ,
' tmITS.0.'1. & 2?
R* vision 5'
. VALVE -
VALVE- ' VALVE VALVE ACT. NORMAL- STROKE . TEST ' TEST RELIEF- TECH.
. ' NUMBER. P&ID ' . CLASS- CATEGORY SIZE- TYPE ' TYPE POSITION DIRECT. METH00 ' MODE REQUEST ' NOTES P05. REMARKS!
' ( IiL 1 fVR) fVA) 21/2PS228A Lt- RR - .VR M-48-7 ~2- -A-' 'O.50 GA" :S.O. .0 .- C - S t' - OP. VR-12 1. -
%140 t Ft - . OP. 2
_,, It RR ' 20 -
.1/2PS2288 ' tt "RR VR-1 568 2- A 0.50' GA S.O. 0- C- St. OP 'VR-12 '1 5140-6l Ft' OP' 2-
~It RR 20
- il/2PS229A .
Lt SR VR-1 M-68-7 21 'A 0.50 CA 5.0. O C. St .C VR-12. 1 5140-6 Tt OP. 2 it RR 20 1/2PS2298 .
' Lt RR. .VR-1 568-7 : .A 0.50 GA _ S.O. 0 -C St OP' 'VR-12' 1.
N140-6 Ft OP 2 It RR '20 l 1/2PS230A' Lt' 'RR VR-1 M-68-7 2 .'A 0 50' GA 'S.O. 'C' C -St OP VR-12 1 4 M-140-6 Ft OP. '2' r
- It - RR 20 l
1/2PS230B Lt RR VR-1 >
M-48-7 2: A 0.50' .GA S.0. C C St OP- VR 1 i M-140-6 ft OP 2 l It RR- 20 1/2PS231A N-68-7 .2 O.75 AC' .CK S.A. .C C Lt/Bt RR VR-1, 25 .3 M-140-6 0 ft OP 22 3 1/2PS2318- M-68-7 2- AC 0.75 CX S.A. .C C Lt/Bt RR VR-1, 25 3 W140-6' '
O Ct OP 22 3 1/2PS9354A St OP 1 M-68-1B 2 A 0.375 GL A.O. C C Lt RR' 'VR-1 N140-1 It RR Ft OP 2
, e.3 VALVE TABLES - Page 22 of 43 i f
217(041092)
- 2D796/63 1
, n + r a
3 j ,
INSERVICE'TESTitG PROGRAM PLAN :
n iCLASS 1,'2, 3. and AUGMENTED VALVES BRAIDWOOO NUCLEAR POWER STATION'
. , UNITS.O,.:l'. & 2 -y Rovi si on . $ - -
VALVE . .
VALVE - VALVE VALVE ACT. MORMAL STROKE TEST TEST : RELIEF- -l' TECH.
NUteER P&ID CLASS CATEGORY' SIZE . TYPE . TYPE POSITION- DIRECT. METHOD .' MODE' REQUEST NOTES M)S . R*_ MARKS-FIN _1 (VRl' i -(VA1 1/2PS93548 i S t .- . OP 1 .. .
N68-1B' .2 A 0.375 GL - A.O. C C- Lt'- RR '. VR-1 H-140-1 'It RR.
' FM OP 2 1/2PS9355A .' S t - OP 1 N(,8-1B 2 A- 0.375 GL"' 'A.O. C C- Lt- RR VR-1 .
N140-1 .' I t 'RR-
' Ft OP -2' ..
, i/2PS93558 St OP 1- r j 568-1B' 2 A 'O.375 'GL- A.O. C C Lt RR VR-l' t 5140-1 It RR.
Ft OP 2 :1 1/2PS9356A St OP 1 568-1A 2 A 0.375 GL A.O. C C Lt RR VR-1 W140-1 It RR
'Ft OP 2'
+
1/2PS93568 St OP 1 M-68-1A 2 A 0.375 GL A.O. C C Lt RR VR-1 5140-1 It RR
, Ft- OP 2
, 1/2PS9357A St OP 1
+
j M-68-18 2 A 0.375 GL A.O. C C Lt RR VR-1 l W140-1 It RR Ft OP 2
, 1/2PS93578 St OP 1
! -i 568-1B 2 A 0.375 GL A.O. C C -Lt 1R VR-1 !
N140-1 It RR i
- Fi CP 2 4.3 VALVE TABLES - Page 23 of 43 2DT9G/64
> 4v s
_1 INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3, and AUGMENTED VALVES .
BUIDWOOD NUCLEAR POWER STATION LCITS 0, 1, & 2 R* vision S VALVE VALVE VALVE VALVE ACT. NORNAL STROKE TEST TEST = RELIEF TECH.
NUMBER P&ID CLASS CATEGORY SI2E TYPE TYPE POSITION DIRECT. NETH00 =H00C REQUEST NOTES P05. REMARKS (IN.1 (VR) (VA)
l 1/2RC014A M-60-18 1 8 1.0 GL 5.0. C 0 St CS VR-12 7 1-N-135-1B C Ft CS 7 2 q It RR 20 1 1/2RC0148 H-60-18 1 B 1.0 GL 5.0. C 0 St CS VR-12 7 1 l M-135-1B C Ft CS 7 -2 I It RR 20 l M-60-18 B 1.0 GL 5.0. C 0 St CS VR-12 7 I l i 1/2RC014C 1 l
N135-1B C Ft CS 7 2 l It RR 20 1/2RC0140 M-60-le 1 8 1.0 GL S.0. C 0 St CS VR-12 7 1 ,
i M-135-1B C Ft CS 7 2 l lt tR 20 Y
4.3 VALVE TABLES
- age 24 of 43 217(041092)
ZD79G/65
_ . . _ _ .. 1 I
~
INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3, ced AUGMENTED VALVES:
BRAIDWOOD NUCLEAR POWER, STATION tt:ITS 0,1 & 2 Ravisien 5 VALVE VALVE VALVE VALVE ACT. N0kMAL STR0KE TEST TEST RELIEF TECH.
MheER P&ID CLASS CATEGORY S!ZE TYPE TYPE POSITION DIRECT. HETHOD N00E REQUEST NOTES P05. REMARKS ffN.) (VR) (VA1 1/2RE1003 N70-1 '2 A 3.0 "D. A.O. C C St OP' 1 S141-1 Lt RR VR-1 It RR Ft OP 2 1/2RE9157 M-70-1 2 A 1.0 D A.O. 0 C .St- OP 1 H-141-1 It RR Ft OP 2
_Lt RR VR-1 1/2RE9159A 570-1 2 A 0.75 0 .. A.O. O C St - ')P 1 H-141-1 It RR Ft OP 2 Lt RR VR-1 _
1/2RE91598 K-70-1 2 A 0.75 0 A.O. C C St OP 1
" 141-1 tt RR VR-1 It RR Ft OP 2 1/2RE9160A M-70-1 2 A 1.0 0 A.O. O C St OP 1 N141-1 It RR ,
Ft OP 2 !
Lt RR NR-1 1/2RE91608 M-70-1 .2 A 1.0 D A.O. O C St OP 1 H-141-1 It RR Ft OP 2 Lt RR VR-1 1/2RE9770 M-70-1 2 A 3.0 0 A.O. O C St OP 1 H-141-1 is RR Ft OP 2 it RR VR-1 4.3 VALVE TASLES - Page 25 of 43 217(041092)
ZD79G/66
S K
R A
M E
R H. .)
C5A 1 2 1 2 E0V TP( 3 4
f o
S 6 E 2 T
O e g
N a
P S
E T L FS B EE) 1 1 A IUR - - T LQV R R EE( V V E RR V L
A V
3 TE 4 S0 R P R P R P R P E0 R O R G R O R O T. H 0
T0 SH t t t t t t t t ET L S I F L S I F TE
.E . .
TP' O. O.
CY AT A A E
VE . 0 0 LZN AII 2 2 VS(
Y R
V L
A N S N V O S A I A 2 2 L DT -L P E A C T T M NS A E R M R G GE 8 A OUW D 4- 6-R A O I P P & 8 3 d P 4 4 G oR - -
N t A M M I
T .E2L S 3C&
E U T ,N , )
2 1 5 R 6 7 2 E D EE 2 2 9 C ,O , n V 0 0 0 7 I 1 O0 o V W i LN AU F
R f
R 1
4 /
6 R S DS s VN 2 2 0 G E S I T i / / ( 9 S AAI v 1 1 7 7 N L R N e 1 D
I C B U R 2 Z e i ,
m.,
INSERVICE TESTING PR% RAM PLAN CLASS 1. 2, 3, tnd AUGMENTED VALVES BRAIDWOOO NUCLEAR POWER STATION UNITS 0, 1, & 2 .j Revisien 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH.
NUMBER P&lD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METH00 MODE REQUEST NOTES POS. REMARKS ffN.1 (VR) (VA) 1/ZRH8701A M-62 1 A 12.0 SA M.0. C 0 St CS 5 1 H-137 It RR Lt RR 6 1/2RH87018 M-62 1 A 12.0 6A N.O. C 0 St CS 5 1 M-137 It RR Lt RR 6 1/2RH8702A M-62 1 A 12.0 GA M.0. C 0 St CS 5 1 M-137 It RR Lt RR 6 1/2RH8702B H-62 1 A 12.0 GA M.0. C 0 St CS $ 1 M-137 It RR Lt U 6 1/2RH8705A M-62 2 AC 0.75 CK S.A. C C Lt/Bt RR VR-15 6 3 M-137 0 0 Ct RR VR-15 24.35 3 l 1/2RH87058 M-62 2 AC 0.75 CK S.A C C Lt/Bt RR VR-IS 6 3 !
M-137 0 0 Ct RR VR-15 24.35 3 I 1/2RH8708A M-62 2 C 3.0 x RV S.A C 0 Rt RR M-137 4.0 1/2RH87088 M-62 2 C 3.0 x RV 5.A. C 0 Rt RR M-137 4,0 1/2RH8730A M-62 2 C 8.0 CK S.A. C 0 Ct/xt CS/0P 8 3 H-137 C Bt CS 3 1/2RH87308 M-62 2 C 8.0 CK S.A. C 0 Ct/Xt CS/0P 8 3 M-137 C Bt CS 3 4.3 VALVE TABLES - Page 27 of 43 217(041092)
ZD79G/68
- __ i
INSERVICE TESTING PROGRAM PLAN CLASS 1, 2. 3, tnd AUGNENTED VALVES BRAIDWOOD NUCLEAR POWER STATION UNITS 0, I, & 2 Rsvision 5a VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TE5T TEST RELIEF TECH.
NUMBER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. HETH00 H00E REQUEST NOTES POS. REMARKS FIN.1 iVR1 (VA) i 1/2RYD75 N2060-6 2 A .50 GL M C C Lt RR VR-1 Passive 52135-6 1/2RY455A N60-5 1 8 3.0 PORV A.O. C 0 St CS 36 1-5135-5 It RR Ft CS 2 1/2RY456 560-5 1 8 3.0 PORV A.O. C 0 St CS 36 1 W135-5 It RR Ft CS 2 1/2RY8000A H-60-5 1 8 3.0 GA M.0. O C St OP e
__ N135-5 It RR 1/2RY80008 M-60-5 1 8 3.0 GA M.0. O C St OP 1 M-135-5 It RR 1/2RY801M N60-5 1 C 6.0 SV 5.A C 0 Rt RR M-135-5 It RR 1/2R780108 N60-5 1 C 6.0 SV S.A. C 0 Rt RR M-135-5 It RR 1/2RY8010C N60-5 1 C 6.0 SV S.A. C 0 Rt RR M-135-5 It PR 1/1RY8025 M-60-6 St OP 1 N135-6 2 A 0.375 GL A.O. C C Lt RR VR-1 It RR Ft OP 2 1/2RYB026 H-60-6 2 A 0.375 GL A.O. O C Lt RR VR-1 N135-6 St OP 1 It RR Ft OP 2 1/2RY8028 M-60-6 2 A 3.0 D A.O. O C Lt RR VR-1 N135-6 St OP 1 It RR Ft OP 2 1/2RYB033 N60-6 2 A 0.75 D A.O. O C Lt RR VR-1 N135-6 St OP VR-12 1 It RR l Ft OP 2 217(041092) 4.3 VALVE TABLES - Page 28 of 43 ZD79G/69
S -
K R
A N
E R
5 H .)
CSA3 3 3 3 EOV 3 TP(
4 f
o S 9 E 2 T
O e g
N a
P
~ S E
T 6 6 L FS 2 2 B EE) A IUR , , T LQV 1 1 EE( - - E RR R R V V V L A
V 3
D TO t t SH B S ET / /
TE t t M L L ET KC OE C C RR TI SD N
.E .
TP CY A. A.
AT S S E
VE LP K K AY C C VT E ) 5 VE . 0 7 LZN AII 3 0 VS(
Y R
EO V, G C C tE A A AT VA S C E
V L
) A N S V O S M
L DT I A L
2 2 P E A C T T MNS l A E R M R GG E 6 6 OUW D 6 - 6 -
R A O I - 5 - 5 P P & 0 3 0 3 d P 6- 1 o 1 G nR - -
N aA MM N M I E2 T ,L S 3 C &
E 3 T ,C ,
6 7 )
2 1 5 R 4 4 2 E D EE 0 0 9 C ,O , n VB 8 8 0 0 I 1 O 0 o LM Y Y 1 7 V W i AU R R 4 /
R S DS s VN 2 2 0 G E S I T i S A A I v
/
1 I/ (
7 7 9
N L R N e 1 D
- I C B U R 2 Z
- , ' l l
{ -
{ -
S K
R A
M E
R H .)
CSA 1 2 1 2 EOV 3 TPf 4
f o
S 0 E 3 T
O e N g a
P S
E T L FS B EE) 1 1 A IUR - - T LQV R R EEi V V E RR V L
A V
3 TE 4 SD R P R P R P R P EO R O R O R O R O TM D
TO SH t t t t t t t t ET L 5 I F L S I F TE M
.E l.
TP O CY f.
AT ' A E
E 1 VE 5 5 LZN AII 1 1 VS(
Y R
V L' S A N N VO S A I A 2 2 L DT L P E A C T T MNS AE RMR G G E W D 2 2 OMO R
P P I
& 4 4
d P 5 5 G nR - -
N oA M M I
T .E2 S 3C &
L E
T :,NU , a )
2 1 S R 2 3 2 E O EE 3 3 9 f 1.OO0, on C V.
- M B 0 A
0 A
0 1 1 7 V W i AU VN 5
2 S
2 4 /
0 G R S D S s E S I T i / / ( 9 S AA I v 1 1 7 7 N L R N e 1 D I C B U R 2 Z
' INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3 and CJGHENTED VALVES '
BRAIDM)00 NUCLEAR POWER STATION :
UNITS 0, 1 & 2 Rzwision 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST- TEST RELIEF TECH.
NUMBER P&lD CLASS CATEGORY SIZE TYPE TYPE ' POSITION DIRECT. METHOD MODE. REQUEST- NOTES POS. RENARKS-ffN.) 'vri (VA) 1/250002A M-48-5A/B 2 A 2.0 GL A.0 0 C Lt RR 34 St OP 1 It' RR
' Ft OP 2 1/2500028 M-48-5A/B 2 A 2.0 GL A.O. O C Lt RR 34 St OP 1 It RR Ft OP 2 1/250002C M-48-5A/B 2 A 2.0 GL A.0 0 C Lt RR 34 St OP 1 It RR Ft OP 2 1/2SD002D M-48-5A/B 2 A 2.0 GL A.O. O C Lt RR 34 St OP 1 It RR Ft OP 2 1/U0002E M-48-5A/B 2 A 2.0 GL A.0 0 C Lt RR 34 St OP 1 It RR Ft OP 2 1/2SD002F M-48-SA/B 2 A 2.0 GL A.O. O C Lt RR 34 St OP 1 It RR Ft OP 2 1/2SD002G H-48-5A/B 2 A 2.0 GL A.0 0 C Lt RR 34 St OP 1 It RR Ft OP 2 1/2SD002H M-48-5A/B 2 A 2.0 GL A.O. O C Lt RR 34 St OP 1 It RR Ft OP 2 4.3 VALVE TABLES - Page 31 of 43 217(041092)
ZD79G/72
(
S K
R A
M E
R H .)
CSA 1 2 1 2 1 2 1 2 EOV 3 TP(
4 f
o S 2 E 3 T 4 4 4 4 O 3 3 3 3 e g
N a .
P _.
S E
T L FS B EE) A I
IUR LQV EE( E RR V L
A V
3 TE 4 S0 P R R P P R R P P R R P P R R P E0 O R R O O R R O O R R O O R R O TN D
TO t t t SH t t t t t t t t S
t t t t S L t
ET S L I F S L I F L I F I F TE' M ET KC E C C C C UR TI SD N
.E .
TP 0 0 0 O.
CY AT ~ A A A A E
VE LP L L L L AY G G G G VT E ) 5 5 5 5 VE . 7 7 7 7 LZN 3 3 3 3 AII VS( 0 0 0 0 Y
R EO VG LE A A A A AT VA S C E
V L
A N S N VO S A I A 2 2 2 2 L D T L P E A C T T MNS B B A E B B R H R / / / /
GG E A A A A O U W D 5 5 5 5 R A O I - - - -
P P & 8 8 8 8 d P 4 4 4 G nR 1- - - -
N aA M H M H I
T .E L 2 S 3 C &
E U C 0 )
T ,N , A 8 2 2 1 5 R 5 5 5 5 E D EE 0 0 0 0 9 C .O ,
n VB 0 0 0 D
0 0
0 3 7
I 1 O0 o L H. D 0 1 4 /
V W i AL S 5 S 5 R S D S s VN 2 2 2 2 0 E S I T i / / / / (
7 F,
S A A I v 1 1 1 1 1
D N L R N e _
2 Z I C B U R
, -INSERVICE TESTING PROGRAN PLANA
, . CLASS 1 '2.'.3. End AUGMENTED VALVES-
~BRAIDWOOD NUCLEAR POWER STATION UNITS 0. 1 & 2 Rsvisien
- VALVE .
VALVE: VALVE VALVE ACT. . NORMAL STROKE- TEST- TEST RELIEF . TECH.
. NureER P&ID CLASS- CATEGORY SIZE- - TYPE '. TYPE ' POSITION DIRECT. METH00 MODE . RECUEST- ' NOTES P05. REMARKS.
IIN.) fVR) (VA)'
-1/2518801A 561-2: 2; .8 - 4. 0 - ' GA M.0. ,C 0 St - CS -13 i WIW2 It RR 1/2518801',* 561-2 .2 8. 4.0 GA M.0. C 0 St CS 13 1 N136-2 _
It RR 1/2SI8802A PS-61-3 2 .8 4.0 GA M.0. C. O. St . CS -14 -1 M-136-3 It RR 1/25188028 .N61-3 2 .8 '4.0 taA - M.0. C 0- -St CS '14 1 WI%1 It RR 1/25188048 P+-61-1A 2 '8 8.0 GA M.0. C. O St OP 1
_ N1W1 It RR' '
- 1/2518806- 561-1A 2 0 8.0 GA M.0. 0 0 St CS 14 - 1 WIW1 It RR 1/2SI8807A 564-1A 2 8' 6.0 GA M.0. C 0 St. OP 1 N1W1 It RR 1/2SI88078 M-41-1A 2 8 6.0 .GA M.0. C 0 St OP 1 W1W1 It RR 1/ZSI8809A M-61-4 2 8 8.0 GA M.0. O C St CS 14- 1 t
M-136-4 It RR '
1/25186098 N61-4 2 8 8.0 GA - M.0. O C St CS 14. 1 N1%4 It RR 1/2 SIB 811A M-61-4 2 8 24.0 GA M.0. C 0. ~St RR VR-16 1 W136-4 Yt- RR 1/25188118 561-4 8 24.0- GA M.0. C 0 St RR VR-16 1 W136-4_ .
It RR 1/2 SIB 812A 561-4 8 12.0 GA M.0. O C St OP 1 i
W136-4 It RR
! t/2SI6o128 N61-4 2 8 12.0 GA- M.0. O C St OP 1
. .i 51 1 It RR -!
- 1/2SI8814 561-1A 2 8 1.5 GL M.0. O C St OP 1 i t
W136-1 It RR i 4.3 VALVE TABLES - Page 33 of 43 -!
217(041092)
ZD79G/74
INSERVICE TESTING PROGRAM PLAN CLASS 1. 2, 3. and AUGMENTED VALVES BRAIDWOOO NUCLEAR POWER STATION UNITS 0. 1. f. 2 R: vision S VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH.
VALVE VALVE l VALVE POSITION DIRECT. PCTH00 MODE REQUEST NOTES POS. RENARKS NUMBER P&ID CLASS CATEGORY I SIZE TYPE TYPE (IN.1 fVt1 fvA1 l
M41-2 3.0 CK S.A. C 0 Ct RR VR-IS 3 1/25I8815 1 AC C Lt/8t RR VR-15 6 3 N136-2 9 3 1/23IB818A N61-4 1 AC 6.0 CK S.A. C 0 Ct CS C Lt/St RR VR-15 6_ 23 3 N136-4 6.0 CK S.A. C 0 Ct CS 9 3 1/25188188 M41-4 1 AC o
C Lt/Bt RR VR-13 6. 23 3 N136-4 9 3 1/2SI8818C N61-4 1 AC 6.0 CK S.A. '
C 0 Ct CS C Lt/Bt RR VN15 6_ 23 3 Nf36-4 _t S.A. 0 Ct CS 9 3 1/25188180 N61-4 1 Ar. 6.0 CK C C Lt/8t RR VR-15 6. 23 3 Nf36 4 1/2 SIB 819A N61-3 1 AC 2.0 CK S.A. C C Lt/8t RR VR-15 6. 23 3 0 Ct RR VR-15 3 N136-3 1/25188198 M41-3 1 AC 2.0 CK S.A. C C Lt/8t RR VR-15 6. 23 3 0 Ct RR VR-15 3 __
5136-3
- 1/2SI8819C M-61-3 1 AC 2.0 CK S.A. C C Lt/8t RR VP-IS 6. 23 3 0 Ct RR VR-15 3 N136-3 1/25188190 M41-3 1 AC 2.0 CK S.A. C Lt/St RR VR-15 6. 23 3
,_ _ _ L 0 Ct RR VR-15 3
% 136-3 1/2SI8821A N61-3 2 8 4.0 GA M.0 0 C St CP 1 N136-3 It RR 2 8 4.0 GA M.0. G___ C St 09 1 1/25I88218 P6-61-3 It RR
14 1/2518840 M41-3 2 8 12.0 GA M.0. C 0 St CS 1 M-136-3 It CR 8.0 CX $3 i C C Lt/8t RR VR-IS 6 3 1/2SI8841A t+-41-3 1 AC 0 Ct RR VR-15 l 3 N136-3 ._
RR VR-15 6 3 1/25I88418 M-61-3 1 8.0 CK S.A. C C Lt/8t 0 Ct RR VR-15 3 M-T36-3 4.3 VALVE TABLES - Page 34 of 43 217(041092)
ZD79G/75
INSERVICE TESTING PROGRAM PLAN CLASS 1. 2. 3. and AUGMDICD VALVES BRAIDWOOO NUCLEAR POWER STATION CITS 0,1. 4. 2
{ Rsvision 5 STROKE TEST TEST RELIEF TECH.
VALVE VALVE VALVE ACT. NORMAL VALVE METMX) MODE RE0tJEST NOTES POS. REMARKS P&ID CLASS CATEGORY SIZE TYPE TYPE FOSITION DIRECT.
NUPEER (VR1 _
(VA)
(IN.)
2 A 0.75 GL A.0 C C St OP 1 1/2518371 Lt RR VR-1 S61-6 It RR
+136-6 Op 2 Ft 2 A 1.0 GL A.O. C C St OP i 1/2518880 VR-1 Lt RR N61-6 It RR W136-6 2 l Ft OP St OP 1 f 1/25I8688 2 A 0.'75 GL A.0 C C Lt RR VR-1 561-3 It RR Nf36-3 2 Ft OP 0 Ct ER VR-15 3 l 1/2 SIB 900A M 1-2 1 AC 1.5 CK S.A. C C Lt/Et RR VR-15 6 3 5136-2 Ct RR VR-15 3 561-2 AC 1.5 CK S.A. C 0 1/25189008 1 C Lt/B t RR VR-15 6 3 M-736-2 Ct RR VR-15 3 PS-61-2 AC 1.5 CK S.A. C 0 1/ZSIB900C 1 C Lt/Bt RR VR-15 6 3 N136-2 0 Ct RR VR-15 3 1/25189000 M-41-2 1 AC 1.5 CK S.A. C C Lt/Bt RR N15 6 3 Nf36-2 Ct RR VR-15 3 2.0 CK S.A. C 0 1/2SI8905A M-41-3 1 AC C Lt/B t RR VR-15 6 3 Nf36-3 Ct RR VR-15 3 2.0 CK S.A. C 0 1/25189058 H-61-3 1 AC C Lt/Bt RR VR-15 6 3
%136-3 Ct RR VR-15 3 1/ZSIB905C 561-3 i AC 2.0 CK S.A. C U C Lt/Bt RR ._VR-15 6 3 N136-3 0 Ct RR V9-15 3 1/25189050 561-3 1 AC 2.0 CK S.A. C C Lt/Bt RR VR-15 6 3 M-136-3 Ct OP 3
+41-1A 2 1.5 CK S.A. C 0 1/2SI8919A C C Bt CP 31 3 5136-1 0 0 Ct OP 3 1/25189198 561-1A 2 C 1.5 CK S.A.
C 5t OP 31 3 S136-1 a.3 VALVE TABLES - Page 35 of 43 217(041092)
ZD79G/76 m . I
INSERVICE TESTING PROGRM PLAN CLASS 1. 2. 3. and AUGPENTED VALVES BRAIDWOOO CJCLEAR POWER STATION '
UNITS 0, 1. & 2 R visi a 5 VALVE VALVF VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH.
NUMBER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. NETH00 NODE RE%TST NOTES POS. REMARKS (IM.) (VR1 (VA) 1/2518920 N61-1A 2 8 1.5 GL M.0. O C St OP 1 N136-1 It GR 1/2SI8922A N61-1A Z C 4.0 CK S.A. C 0. Ct RR VR-3 3 N136-1_,, C Bt RR W-3 3 1/2518922B N61-1A 2 C 4.0 CK S.A. C 0 Ct RR VR-3 3 N136-1 C Bt RR VR-3 3 1/2518924 N61-1A 2 B 6.0 GA M.0. O C St 09 1 Nf36-1 It RR 1/2518926 N61-1A 2 C 8.0 CK S.A. C 0 Ct/Xt RR/0P VR-6 25 3 W136-1 _ 3 1/ZSI8948A N61-5 1 AC 10.0 CK S.A. C C Lt/Bt RR VR-5 6. 23 3 Nf36-5 d Ct RR VR-5 3 1/25189488 N61-5 AC 10.0 CK S.A.
1 C C Lt/Bt RR VR-5 6. 23 3 W136-5 0 Ct RR VR-S 3 4
1/2SI894SC N61-6 1 AC 10.0 CK S.A. C C Lt/Bt RR W-5 6 3 N136-6 0 Ct RR VR-5 3 1/25I89480 N-61-6 1 AC 10.0 CK S.A. C C Lt/St RR VR-5 6 3 N136-6 0 Ct G VR-5 3 1/ZSI8949A N61-3 1 AC 6.0 CK S.A. C C Lt/Bt RR VR-15 6 3 N136-3 0 Ct RR V%15 3 1/25189498 N61-3 1 AC 6.0 CK S.A. C C Lt/Bt RR VR-15 6 3 M J6-3 0 Ct RR VR-15 3 I/ZSI8949C N61-3 1 AC 6.0 CK S.A. C C Lt/Bt RR VR-15 6 3 i
N136-3 0 Ct RR VR-15 3 1/25189490 N61-3 1 AC 6.0 CK S.A. C C Lt/St BR VR-15 ___6 3 W136-3 0 Ct RR VR-15 3 1/ZSI8956A N61-5 1 AC 10.0 CK S.A. C C Lt/Bt RR VR-5 6 3 1
N136-5 0 Ct RR VR-5 3 1/2518956B N61-5 1 Ar. 10.0 CK S.A. C C Lt/Bt RR VR-5 6 3 W136-5 O Ct RR VR-5 3 !
l 1/2 SIB 956C N61-6 1 AC 10.0 CK S.A. C C Lt/Bt RR VR-5 6 3 J N136-6 3 Ct RR VR-5 3 4.3 VALVE TABLES - Page 36 of 43 217(041092)
ZD79G/77
l l,l S e K v
? i
% s s
D P a
D f .)
f o
S 7 7 7 E 2 2 3 T
O , . e g
N 6 9 9 a P
S E
T L FS B 5 5 A EK)
IL R -
1 1
- T LQV R R R EE( V $- V V E V
FR L A
V l
3 TE 4 SD R R S 5 P R R P R EO R R C C O R R GE TM D t TO S SH / t t t t t t L t ET t CC C S L I F L TE t L
ET KC OE C 0 0 0 C C RR TI SD N
.E . . . . .
i TP A. A. A. O. A.
CY AT S S S A 5 E
VE LP K K K L x AY C C C G r_
VT E ] 5 VE .0 0 0 7 0 LZN AIT 0 2 2 0 1 VS( 1 1 1 Y
R EO VG C C LE A C C A A AT VA S C E
V L
A N S N V O S A I A 1 2 2 2 2 L DT L P E A C T T M
A O $.
R P R G G E 6 4 4 6 6 OU W D 6- - 4 - 4 - 6 - 6 6 R A O I 6 - 6 - 6 - 6 -
P P & 1 3 1 3 1 3 1 3 1 3 d P 6 1 6 1 6- 1 6 1 4- 1 G nR N aA 5WMW -
5 7 5MM MM I
T ,EL 2 S 3C &
E ,UN , 0 A 8 T a 6 8 8 4 8 )
2 1 5 R 5 5 5 6 6 2 E D EE 9 9 9 9 9 9 C ,O I 1 O0 o
. n VS LP 1 8 8 1
8 I
8 1
8 I
0 8 1 7 V W i AU 5 5 S 5 5 d /
O G R 5 DS s VN 2
- 2 2 2 E 5 I T i / / / / / ( 9 S A I v 1 1 1 1 1 7 7 N tA. R N e 1 D
I C B U R 2 Z I (l t llll! ll lf lIl{r 1 ,
s
, . INSERVICE TESTING Mt0ERAM Puel '
' Cl. ASS 1, 2.'3; and ADEMENTED VALVES
'BRAIDWOOD MUC1. EAR POWER STATION'- '
i ICITS 0, 1, & 2 !
Ravision 5. .,
i- !
j .- 'VILVE- .
VALVE VALVE VALVE ACT. NORMAL STROKE TEST FEST RELIEF NUPSER P&ID- TECH. l a
CLASS CATEGORY SIZE. TYPE TYPE POSITION DIRECT. METHOD MODE REOUEST NOTES F45.
C Bt OP 3 j 1/ZSX0028 N42-1A 3 C 36.0 CX 5.A. C -0 Ct OP 3 C Bt OP 3 5 i 1/2SX016A M-42-58 2 8- 16.0 BTF M.0. 0 0 St OP. I N126-3 It RR
, 1/ZSX0168 M-42-5A 2 8. 16.0 BTF- M.D. 0 0 St OP 1
4-126-3 It RR '
j 1/ZSX027A 542-58 2 8 - 16.0 BTF. M.0. 0 0 St OP 1 i ,
l N126-3 It RR 1/2SX0278 542-5A 2 8 16.0 BTF M.0. 0 O St "
OP 1 j N126-3 It RR
{ I/2SX101A N42-3 3 8 1.5. GL 5.0. C 0 St OP VR-17
' i W125-1
Ft OP j 1/2SX112A N42-3 3 8 , 12.0 BTF A.O. O C St OP 1 i i N126-1 It RR Ft OP 2 j 1/ZSX1128 M-42-3 3 8 12.0 BTF A.O. O [
C St OP 1 g
1
( N126-1 It RR
! i i I Ft OP 2 !
I/2SX114A M 42-3 3 8 12.0 ETF A.O. O St I- C OP I 4
i M-126-1 8 L
4 It RR i
,1 Ft OP 2
[ _,t/ZSX11m W42-3 3 8 12.0 BTF A.O.
t O C St OP 1 l a M-126-1 !
It RR !
I 1
~
Ft OP 2 4.3 VALVE TABLES - Page 38 of 43
]
t i
217(041092) *,
ZD79G/79 1
f 1
.e --+.-u ,. +g:- , ,e . . , . = .,.c >~. -, , , , . ,.c,.. -.., ., , - . . . , + , , - , - , . . ~ - . . - . . . . , -
INSERVICE TE'; TING PROGRAM PL#8 CLASS 1. 2, 3, and AUGMENTED VALVES BRAIDw000 NUCLEAR POWER STATION UNITS 0, 1, & 2-R vision 5a VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TEOt.
MJPEER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES POS. REMARKS f1N_) (YRI (VA1 1/2SX147A %42-3 3 B 16.0 BIF A.O. M/A 0 Ft OP Z M-126-1 t/2SX147B %42-3 3 8 16.0 BTF A.O. M/A 0 Ft OP 2 5126-1 1/ZSX169A %42-3 3 8 10.0 BTF A.O. C 0 St OP 1 M-126-1 It RR Ft CP 2 1/2SX1696 %42-3 3 8 10.0 BTF A.D. C 0 St OP l 5126-1 It Ea Ft CP 2 1/2SX173 %42-3 3 8 6.0 GA A.O. C 0 St CP 1 N126-1 Ft OP 2 1/2SX178 M-42-3 3 8 6.0 GA A.O. C 0 St OP 1 5126-1 Ft OP 2 1/2SX174 M-42-3 3 C 5.0 CK S.A. C 0 Ct CP 3 Will be N125-1 tested by ocd of L l
4.3 VALVE TABLES - Pa9e 39 of 43 217(041092)
ZD79G/B0
INSERVICE TESTING PROGRArt PLAN CLASS 1.- 2, 3, and AUGMENTED VALVES BRAIDWOOD NUCLEAR POWDt STATION tmITS 0.1, & 2 R2 vision 5 VALVE VALVE VA1.VE VALVE ACT. NORMAL STROKE TEST TEST RELIEF IECH.
NUMBER P&ID l CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES POS. RENARKS [
IIN.1 (VR1 (VA1 1/2VQ001A 5105-1 2 A 48.0 STF H.O. C C Lt- S 411 - 1 11 N106-1 5t CS 11 1 It RR 1/2VQ0018 N105-1 2 A 48.0 BTF H.O. C C Lt S VR-1 11
&l06-1 it CS 11 1 It RR 1/2VQ002A N105-1 2 A 48.0 BTr H.O. C C Lt S VR-1 11 5106-1 st Cs u i It RR 1/2VQOO2B 5105-1 2 A 48.0 BTF H.O. C C Lt S VR-1 11 N106-1 St CS 11 1 It RR 1/2YQ003 N105-1 2 A 8.0 Bir A.O. C C Lt OP - VR-1 11 N106-1 St OP 1 It RR 1/2VQ004A M-105-1 2 'A 8.0 BTF A.O. C C Lt OP VR-1 11 W106-1 St OP 1 It RR 1/2VQ0048 M-105-1 2 A 8.0 BTF A.O. C C Lt OP VR-1 11 N106-1 St OP 1 It RR 1/2VQ005A M-105-1 2 A 8.0 BTF A.O. C C Lt OP VR-1 11 N106-1 5t OP 1 It RR 1/2VQ0058 M-105-1 2 A 8.0 STF A.0. C C Lt OP VR-1 11 5106-1 St OP 1 It RR !
1/2vQ005C 5105-1 2 A 8.0 STF A.O. C C Lt OP VR-1 11 N106-1 St 09 1 It RR I
4.3 VALVE TA8tES - Page 40 of 43 1
217(041092) !
ZD79G/81
S e e e e _
K v w v v R i t i i A s s s s M s s s s E a a a a R P P P P t .1 OSA EOV TP( 3 4
f o
S 1 E 4 T
O e g
N a
P S
E T L FS B EE11 1 l 1 A R - -
IWV L
EE( V R R V
M V
R V
T E
RR V L
A V
3 i 4 R R R R R R R R C
D TO SH t t t t ET L L L L TE M
.E TP CY AT M M M M E
VE LP L L L L AY G G G G VT E 0 0 0 0 VE1_ 5 5 5 5 LZM .
AII VSI
-Y R
V L
A N S NV O I S A A 2 2 2 2 L DT L PE A C T T MNS AE R MR GG E 3 3 3 3 O UW D - - - -
R A O I 5 5 5 5 P P & 0 0 0 0 d P 1 1 1 G nR N aA N 1N 5 N I
T .E2 L
S 3C&
E U T . N , )
2 1 5 R 6 7 8 9 2 E D , n EE 1 1 1 1 9
C '.O VB 0 0 0 O I 1 O0 o LM Q Q 0 Q 10 82 V W i AJ v Y v Y RS DS s E S Z T i VM Z
/
2
/
2
/
2
/
4 /
0 G S AAI v 1 1 1 1 ( 9 N L R N e 7 7 I C B U R 1 D 2 2
ti I . [
5 e e _
K v v .-
P i i A s s M s s E a a R P P i .)
O5A E0V 1P! 3 4
f o
S 2 E 4 T
O e N g a
P S
T E L
FS B EE) 1 1 A
I L'R - - T LQVR R EE( V V E RR V L
A V
%IT t
RI C C OS NO P
.E .
TP CY A.
AT M 5 E
VE 1_ 0 0 LZM AIf 2 2 VSf Y
V L
A N S N VO S A I A 2 2 L DT L P E A C T V M NS A E R M R G G E A 9 A B OUW D I 1 1 1 R A 0 I - - - -
P F & 9 9 9 9 d P 4 4 4 4 G nt N a u J NMNN -
I T
S 3C&
J2 '
E U T , N , )
2 1 5 R 0 1 2
E 0 EE 19 9 9 C , 0 , n VB 1 0 3 I 1 o0 o LM M M 8 V w i AU W W 1 4 /
R SDS s VN 2 2 0 G E S I T i / / ( 9 S AAI v 1 1 7 7 N CLS RL RW e I
1 D 2 Z
INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3, and AUGMENTED VALVES BRAIDWOOD CJCLEAR POWER STATION UNITS 0, 1, & 2-R vision 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH.
NUPBER P&ID CLASS CATEGnRY SIZE- TYPE TYPE POSITION DIRECT. METH00 BODE RErlUEST NOTES P05. BEMARK5 ffM.) . (VR) (VA1 1/2w0006A St OP 1 N118-5 2 A 10.0 CA M.O. O C Lt RR VR-1 N118-7 It RR 1/2w00068 St OP I N116-5 2 A 10.0 GA M.0. O C Lt RR VR-1 N118-7 It RR 1/2w0007A M-118-5 2 AC 10.0 CK $.A. C C Lt/Bt RR VR-1, 27 3 N118-7 1/2w00078 N118-5 2 AC 10.0 CK 5.A. C C Lt/Bt UR VR-1, 27 3 N118-7 1/2 WOO 20A St OP 1 M-11E -5 2 A 10.0 GA M.0. O C Lt RR VR-1 N118-7 It RR i 1/ZWJ208 St OP 1 !
N118-5 2 A 10.0 GA M.0. O C Lt RR VR-1 i M-118-7 It RR 1/2 WOOS 6A St OP i
) j N113~5 2 A 10.0 GA M.D. O C Lt RR VR-1 i
M-118-7 It RR 1/2 WOOS 68 St OP 1 5118-5 2 A 10.0 GA M.O. O C Lt RR VR-1 N118-7 It RR 4.3 VALVE TA8"JS - Page 43 of 43 L
s 217(041092)
{ .2D79G/84
R vislos 5 i
l l
l l
SECTIGE 4.4 VALVE NUTES L 217(042292) l- ZD79G/85
Rovlslon 5 VALVE NOTES UQIC_1 Closure of the Main Steam isolation valves IMS001A-D or 2M5001 A-D during unit operation would result in reactor trip and safety injection actuation. To avoid this transient, these valves will be partially stroked every three months. Full stroke testing will be done during Modes 4, 5, or 6 as plant conditions allow, per IWV-3412.
HQIE_2 The testing of any emergency boration flowpath valves during unit operation is not practical. Stroke testing the Boric Aeld injection isolation valve 1CV8104/2CV8104 and check valve ICV 8442/2CV8442, the RH to CV pump suction isolation valve ICVB804 A/2CV8804 A, or the RWST to CV pump suction isolation valves 1CV112D,E/2CV112D,E, could result in boration of the RCS, resulting in a cooldown transient. Aligning the system in this configuration even for a short duration is, t herefore, unacceptable. These valves will be stroke tested during cold shutdown,-in accordance with IWV-3412.
HOIK_1 These valves are the Main reedwater isolation valvest irWOO9A-D/2rWOO9A-D, and cannot.be f ully stroked during operation as feedwater would be terminated causing a reactor trip. They will, however, be partially stroke tested during operation as well as full stroke tested during cold shutdown, per the requirements of IWV-3412.
HOILi Closure of these letdown and makeup valves ICV 112B,C/2CV112B,C, icv 8105/
2CV8105, ICV 8106/2CV8106, 1CV8152/2CV8152, and ICV 8160/2CV8160 during normal unit opiration would cause a loss of charging flow which would result in a reactor c)olant inventory translent, and possibly, a subsequent reactor trip.
These valves will be full stroke / fall safe exercised during cold shutdown as required by IWV-3412.
HDII_5 The IRH8701A/B, IRH8702A/B, 2RH8701A/B, and 2RH8702A/B valves are the isolat!on boundary between the Residual Heat Removal Pumps and the Reactor Coolant System. Opening one of these valves during unit operation will leave only one valve Isolating RHR from the high RCS pressure. This would place the plant-in an undesirable condition. Therefore, these valves will be full stroke tested during cold shutdown, per IWV-3522.
4.4 Page 1 of 7 217(042292) l ZD79G/86
. . . - - = - - . . .
Ravlsion 5 UDTE h The following valves have been Identitled es Intersystem LOCA valves. They form a pressure bohndary between the RCS and other essential components in order to protect these components from damage. These valves will be leak tested in accordance with the Braidwood Technical Specifl,*tions. Performance of the leak test on these valves also satisfles the back-alow test required for check valves by HRC Generic Letter 89-04.
1 Intersystem LOCA Valves _;
1RH8701A/B 1RH8702A/B 2RH8701A/B 2RH8702A/B ;
1RH8705A/B 1818815 2RU8705A/P 2518815 IS18818A-D- ISI8905A-D 2SI8818A-D 2SI8905A-D ISI8819A-D IS18948A-D 2SI8819A-D 2SIe948A-D IS18841A/B IS18949A-D 2 SIB 841A/B 2 SIB 949A-D 1SI8900A-D ISI8656A-D 2S!8900A-D 2SI8956A-D U21E-.1 The Reactor Pressure Vessel Vent Valves 1RC014 A-D and 2RC014 A-D cannot be stroked during unit operation, as they provide a pressure boundary between the Reactor Coolant system and containment atmosphere. Pallure of one of these valves in the open position would result in leaving only one valve as the high pressure boundary. These valves will be full stroke / fall safe esercised when the RCS pressure is at a minlmum during cold shutdown, per IWV-3412.
KQ1L.B The Residual Heat Memoval Pump discharge check valves IRR8730A/B and 2RH8730A/B cannot be-full stroke exercised during unit operation due to the high.RCS pressure. These check valves will Le partial stroke tested, however, on a quarterly basis and full stroke exercised during cold shutdown. This is
-in accordance with IWV-3522.
NDIEJl Due to the RCS pressure, the check valves listed below cannot be full stroke exercised during unit operation:
ISI8818A-D 2SI8818A-D RHR Cold Leg Injection 1SI8958A/B 2S!8958A/B RWST to RHR Pump Suction These valves will be full stroke exercised during cold shutdown, in accordance with IWV-3522.
4.4 Page 2 of 7 217(042292)'
ZD79G/87
m . . - . - . - - . . .~. . - - - _ - . - . = - . . - - . - . . - - . - .. - - . -.
Rovlslon S KQIE_12 The IrWO39A-D and 2rWO39A-D valves cannot be stroke tested during unit operation as closure of these valves would result in termination of the waterhapper peevention feedwater flow. This would result in undesirable i affects on the Steam Generators. These valves will be full stroke / fall safe tested.during cold shutdown, per IWV-3412. (
+
H2IC_11 The Primary _ Containment purge Supply and Exhaust Valves IVQ001A/B, IVQ002A/B, 2VQ001A/B, .and 2VOOO2A/B cannot be stroke timed during unit operation, These ,
48-luch valves are the only Isolation points between the containment atmosphere and the environment. Stroking these valves at any time other than mode 5 or-6 would be a violation of the Braldwood Technical Specifications.
These valves will be full stroke tested during cold shutdown, in accordance with IWV-3412. These. valves will be leak tested semlannually, in accordance with Braldwood Station Technical Specifications.
The Primary Containment Minl-Purge and r,xhaust Valves IVOOO4A/B, IVOOO5A/B/C, 2V0004A/B,- and 2V0005A//B/C, and the Post LOCA Purge Exhaust Valves IVQ003/
2VQOO3 will be leak tested every 3 months, in accordance with Braldwood Station Technical Specifications.
NOTE 12 The Auxillary reedwater check valves 1Ar001A/B, 1Ar003A/B, 1Ar014A-H, 1Ar029A/B, 2Ar001A/B, 2Ar003A/B, 2Ar014A-H, and 2Ar029A/B cannot be full stroke tested during unit operation, as this would Induce potentially damaging therma 1' stresses in the upper feedwater nozzle piping. The 1Ar001A/B, IAr003A/B, 2Ar001A/B, and 2Ar003A/B valves will be partially stroke tested during operation, and all valves full atroke tested during cold shutdown.
This will be performed per Tech Spec 4.7.1.2.2 and is in accordance with IWV-3522.
NOTE 13 The-High Head Injection-Isolation Valves ISIB801A/B and 2SI8801A/B cannot be stroke tested during unit operation. These valves isolate the CV system from the RCS. Opening them during- operation would enable charging flow to pans
- directly Into the RCS, bypassing the regenerative heat exchanger. The temperature difference of the-charging flow and the RCS could result in damaging thermal stresses to the cold leg nossles as well as cause a reactivity change which would,~1n turn, cause a plant transient. These valves l will be full-stroke tested during cold shutdown in accordance with IWV-3412.
l l'.
4.4 Page 3 of 7
- 217(042292)
. ZD79G/88 l
-9E..'.,-,,-r.ar,if_ . - . , , . - , - . _ _ . + ,wo.-- ,.,-..-r.m.e
Rovlslon 5 HQIE_li The safety injection system SVAG (Spurious Valve Actuation Group) valves ISI8802A/B, 1S18806, IS18809A/B, 1518813, 1S18835, 1518840, 2 SIB 802A/B, 2518806, 2SI8809A/B, 2518813, 2S18835, and 2S18840 cannot be stroke tested during unit operation. -These valvos are required by the Technical Speelfications to be de-energized in their proper positions during unit
-operation. Stroking them would be a violation of the Technical Specifications as well as defeating the de-energlzed SVAG valve principle. These valves will be stroke tested during cold shutdown when they are not required to be de-energired. This is in accordance with IWV-3412.
M071L_ lit
-DELETED-HQIE_1ft These feedwater valves are exempt from all ASME Section XI testing requirements per INV-1100 and IWV-1200. They are included in the program for operability tracking purposes only. The closure of the Main reedwater Regulating Valves irW510, IrW520, irW530, IrW540, 2rW510, 2rW520, 2rW530, and 2rW540 during unit operation would cause a loss of feedwater to the steam generators, resulting in a plant transient with a possible reactor trip as a result. These valves will be fall safe (rt) tested pursuant to the Braldwood Station Technical Specifications.
HRIL11 These feedwater valves are exempt from all ASME Section XI testing requirements per INV-1100 and IWV-1200. They are included in the program for operability tracking purposes only. The closure of the Main reedwater Regulating Bypass VL1ves IrW510A, IrW520A, IrW530A, IrW540A, 2rW510A, 2rW520A, 2rW530A, 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 (rt)-tested pursuant to the Braldwood Station Technical Specifications.
NOTE 18
-DELETED-(Incorporated into NOTE 21)
NOTE 19
-DELETED-(Incorporated into NOTE 14) 4.4 rage 4 of 7 217(042292)
'ZD79G/89
. -. - - . , - - .. - . . . - - - - . - . - = _ - - - - . . -
Revision 5 l l
KDIL. ZQ The remote position Indicator'for these valves cannot be observed directly due to the encapsulated design of the solenold valve body. During the indlcation l test, Indirect evidence of the necessary valve disk movement shall be used, in accordance wlth IWV-3412 (b). The valves affected are listed below 1CV8114 1PS230A/B 2PS228A/B ;
1CV8116 1RC014A D 2PS229A/B 1PS228A/B 2CV8114 2PS230A/B IPS229A/B 2CV8116 2RC014A-D i
HDIE_11 The Maln reedwater Tempering Flow Isolation Valves 1/2rWO34A-D are exempt from i all ASME Section 11 testing requirements per IWV-1100 and IWV-1200. They are included in the program' for operability tracking purposes only, and will be fall safe (FL) tested pursuant to the Braldwood Station Technical Speelfications.
NOTE 22 Per NEC 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.
EQ1E-.21
-1/2SI8813A-D, 1/2SI88191.-D,.and 1/2SI8948A/B are Event V check valves, which
- are defined as two check valves-In series at a low pressure /RCS Interface Lwhose failure may result'in a LOCA that bypasses containment. They.are individually leak-tested in accordance with NRC generic letter 89-04, position "
04b. -
NOTE 24 1/2CC9518 1/2CC9534, 1/2CV8113, and 1RH8705A/B are check valves designed to
. relieve pressure between twol containment isolation valves.. The full flow limiting value is sero, since- the safety function of these valves in the open direction is to relieve pressure only.
HQILZ.5 Check valve 1/2SI8926 prevents flow from the Safety Injection (SI) pump suction line to the Refueling Water Storage Tank (RWST). The SI pumps are normally lined up in the INJECTIQ4 MODE to. take suction f rom the RWST. This check valve would stop reverse flow-when the SI pumps are transferred to
' HOT / COLD LEG RECIRCULATION MODE to prevent contamination of the RWST.
1However, the 1/2518806 M.O.V. is in series with this check valve and would be closed to: prevent' reverse flow as_ directed by the emergency procedures.
~
-Therefore, no backflow-test (Bt) is required for 1/2SI8926. +
4.4 Page 5 of 7
- 217(042292)
ZD79G/90 t
sE g-c,-- --q dr , y 4.J-+,- -<--..w ,w w *- .m,-, .r --
~ - a + = = ==m"+ww=--+-e-e=-- -a- ----**---e+ - - - - - - * " - -
- - - . ... - . . . --.- _~ - - _ - . .. - - - - . . -
HOTC 2h Check valve'1/2CV8546 prevents flow from the Chemical and Volume Control (CV) pump suction line 'to the Refueling Water Storage Tank (RWST). The CV pumps are normally. lined up in the INJECfl0H MODE to take suction from the RWST. ,
This~ check valve would stop reverse flow when the CV pumps are transferred to HOT / COLD LEG INJECTION MODE to prevent contamination of the RWST. However, +
the 1/2CV112D and 1/2CV112E M.O.V. 's are in series with this check valve and .
would be closed to prevent reverse flow as directed by the emergency procedures.- Therefore, no back flow test (Bt) is required for 1/2CV8546.
KQIE_.21 Check valves 1/2S18958A/B prevent flow from the Residual Heat (RH) Ren. oval pump suction line to the Refueling Water Storage Tank (RWST). The-RH pumps are normally lined up in the INJECTICH MODE to take suction from the RWST.
.These check valves would stop reverse flow when_the RH pumps are transferred to HOT / COLD LEG RECIRCULATION MODE to prevent contamination of the RWST. .
However, the 1/2 SIB 812A/B H.O.V. 's 'are in series with these check valves and would be closed to prevent reverse flow as directed by thw emergency procedures. In addition, the RH suction valves 1/2SI8812A/B, 1/2RH8701A/B or 1/2RHB702A/B,.and'1/2S18811A/B are electrically interlocked to prevent the backflow to the RWST when the RH system is in a RECIRCULATION MODE. Thus, no back flov . testing of 1/2SI8958A/B is required.
RQIX_2.8 NRC' Generic Letter 89-04, Attachment 1, Position 3 lists-the CVCS Volume Control Tank (VCT) outlet check valve as an example of ASME Code Class check valves that perform a safety function in the closed direction that are frequently not back flow tested. At Braldwood Station, check valve 1/2CV8440 prevents flow from the Chemical and Volume Control (CV) pump suction to the VCT. The VCT is normally aligned to the CV pumps during normal plant operation. During a Safety Injection signal, the VCT is-automatically isolated by closure of the 1/2CV112B and 1/2CV112C M.O.V.'s, which are in
. series with the 1/2CV8440 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.
NOTE 29 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 emergency boratiou' valve. This valve would only be ,
opened during an emergency with the -boric acid transfer pump running. This check valve 'is unnecessary with the current system operation, and thus, no
'back flow-testing of 1/2CV8442 is' required.
l l
lL 4.4 Page 6 of 7
- . 217(042292)'
ZD790/91.
p
Revision 5 HQIC_lf Check valves 1/2AF014A-H are verified to be closed each shift by the Operating ;
Department, by verifyl> that the temperature at 1/2Ar005A-H is 1 130' r. If j the temperature is >- F at any 1/2AT005 valve, then an abnormal operating -l j
procedute la entered t .solate and cool down the affected lines. This shiftly monitoring o? 1, A r014A-H in the closed position adequately monitors '
the status of thes ss. No additional monitoring / trending by the IST Group is required.
tiQIE_ll Check valves 1/2CVP 480A/B and 1/2SI8919A/B are the Centrifugal Charging Pump and Safety Injection Pump mini-flow recirculation line valves which open to allow recirculation flow during IST Surveillances. Acceptable full-stroke will be verified whenever the recorded mini-recirculation flowrate is within the " acceptable" or " alert" ranges given in the IST Pump Surveillance.
HDIE_ll Check valves 1/2CC9463A/B and OCC9464 are the Component Cooling Water Pump discharge check valves. The full design accident flow through any one pump cannot be obtained during normal operation without causing low flow alarms in adjacent loops and possible equipment damege due to low cooling water flowrates to the Reactor Coolant Pump (RCP) seals. These valves will be full-stroke exercised during cold shutdowns when plant conditions allow all four RCP's off.
HRIE_11
- Used at Byron Station ONLY*
NOTE 3 4 Per Braldwood Technical Specifications Amendment, valves 1/2SD002A-H, 1/2SLOO5A-D have been removed from the list of valses to be tested under 10CTR50 Appendix J and will now be tested per ASME Code Section XI, IWV-3420.
HOII_15 The 1/2RH8705A/B check valves will be operability tested by verifying that there is depressurization in line 1/2RH26AA-3/4 and 1/2RH26AB-3/4 when they are opened. This is a test method which was approved by the NRC in Byron's SER dated 9/14/90.
NOTE 36 In response to GL 90-06, "PORV and Block Valve Reliability and Additional LTOP for LWRs," the 1(2)RY455A and 1(2)RY456 valves will be restricted from stroke t ting in Mode 1. Technical Specifications will provide direction for any It cher operability testing required.
(Reference NTS Item - 456-130-90-4.4-0100)
, 4.4 Page 7 of 7 I
l 217(042292)
ZD79G/92 L_
Rsvision 5 l
l l
SECTI(M 4.5 VAINE TECIMICAL AITROAC11ES AND N)SITIONS 217(042292)
ZD79G/93 L'-
Ravision 5 IST Technical Approach and Position No. V A-01 A. Comp.0.ntnLidJntifications
- 1. Descriptions Metnod of Stroke Timing Valves - Timing using control board position Indication lights (St).
- 2. Component Numbers: See IST Valve Tables.
- 3. Referencess ASME Code,Section XI, Subsection INV, paragraph IWV-3413(a).
- 4. Code Class 1, 2, and 3. i l
B. Hequirfment:
- Use of the control board open and closed lights to determine the stroke time of power-operated valves has recently become an issue for discussion in the industry. Paragraph INV-3413 of ASHE XI defines " full-stroke time" as "that time laterval f rom initiation of the actuating signal to the end I of the actuating cycle." It is common industry practice to measure stroke i 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. Positions It is recognized that the way in which the limit switch that operates the remote position Indicator lights is set may result in " closed" or "open" indication before the valve obturator has actually completed its travel.
This is not considerv3 to be a problem, as the purpose of the test is to determine if degradation of the valve operator system is occurring, which is determined by observing changes in stroke time relative to the reference stroke time. Stroke time measurements should be rounded to the nearest tenth (0.1) of a second, except that stroke times less than one half (0.5) second may be rounded-to 0.5 second, if appropriate.
-Standard rounding techniques are to be used when rounding stop watch readings during valve _ stroke time testing (e.g., 10.45 rounds to 10.5 and 10.44 rounds to 10.4). Rounding to the nearest second for stroke times of
- 10 seconds or less, or 10V of the specified limiting stroke time for stroke times longer than 10 seconds, as allowed by ASME Section XI subparagraph IWV-3413(b), will not be used.
4.5 - Page 1 of 9 217(042292)
ZD79G/94
Rovision 5 IST Technical Approach and Position No. VA-02 A. .Capnnt.nt Identificatlon:
- 1.
Description:
Hethod of Tall Sete Testing Valves.
- 2. Component Numbers: See IST Valve Tables (FL).
- 3.
References:
ASME Code,Section XI, Subsection IRV, paragraph IRV-3415.
- 4. Code Class: 1, 2, and 3.
B. Enguitsments Paragraph IWV-3415 of ASME XI states that "When practical, valves with fall-safe actuators shall be tested by observing the operation of the valves upon loss of actuator power." Most valves with fall-safe positions have actuators that use the fall-safe mechanism to stroke the valve to the fall-safe position during normal operation. For example, an air-operated valve that-falls closed may use air to open the valve against spring pressure. When the actuator is placed in the closed position, air is vented from.the diaphragm and the spring moves the obturator to the closed position.
C. Position:
In the cases where normal valve operator action moves the valve to the closed position by de-energizing the operator electrically, by venting air or both (e.g., an electric soler.old in the air system of a valve operator moves to the vent position on loss of power), no additional fall-safe testing is required. Valves with fall-safe actuators that do not operate as part of normal actuator operation must be tested by other means. This may be accomplished for motor-operated valves by opening the circuit breaker supplying operator power and observing that the valve moves to its fail-safe position. Lifting leads is not required unless it is the only method of de-energizing the actuator.
Using a valve temote position Indicator as verification of proper fall-safe operation is acceptable, provided the indicator is periodically verified to be operating properly as required by ASME Code,Section XI, Subsection-IWV, paragraph IWV-3300.
4.5 - page 2 of 9 217(042292)
ZD79G/95
. -. = - - -
I Ravlslon 5 )
IST Technical Appr:::h and Position No. VA-03 A. C9mP2 Dent Identifications
- 1.
Description:
Method of full Strohs (Ct) and Back flow (Bt) Exercising l of Check Valves. !
l
- 2. Component Numbers: See IST Valve Tests (Ct and Bt), j
- 3.
References:
(a) HRC Generic Letter 89-04, Guldance on Developing i Acceptable Inservice Testing Programs, Attachment 1, Positions 1, C, and 31 (b) ASME Code,Section XI, Subsection IWV, paragraph INV-3522; i (c) SHAD Report H-1078-91, "SI Accumulator Check Valve Acoustic Test."
- 4. -Code Class: 1, 2, and 3. '
B. Erquir.gment s Paragraph INV-3522.of Article XI states " check valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation. If only limited operation is practical, during plant operation the check valve shall be part-stroke exercised during plant operation and full-stroke exercised during cold shutdovns." For check valves with no external position indication devices, the. determination of when they are in full open position has proven difficult to determine. The verification of when a valve is the full open position affects the determination of which valves are only part-stroked and thus require additional full-stroke testing during cold shutdown or refueling.
C. Ensition:
Valid full-stroke exercising to the full-open or full-closed position may be accomplished by observing an external position indicator which is considered to be a positive means of determining obturator position.
Where external position Indicators are not provided, manual stroking of the_ valve is acceptable. Where a mechanical exerciser is used, the torque required-to move the obturator must be recorded and meet the acceptance stor.dards of subparagraph INV-3522(b). Per the requirements of HRC Generle Letter 89-04, Attachment 1, Position 1, the other acceptable
^ "
method of full-stroke exercising a check valve to the open position is to
-verify that the valve passes the maximum required accident condition flow. Any flow less than this is considered as a part-stroke exercise.
Flow through the valve must be determined by positive means such as permanent.ly -installed flow -instruments, temporary -flow instruments, or by measuring the pressure drop across the valve or other In-line component.
Measuring total flow through multiple parallel lines does not provide verification of flow through individual valves.
l 4.5 - Page 3 of 9 217(042292) l ZD79G/96
. . --. . - . = . - . -
f .
Revision 5 IST Technical Approach and Position No. VA-03 i 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 (SI) Accumulator Back-up Check Valves, 1/2 SIB 956A-D. Because of the high ;
maximum design flow rate of these valves, a maximum design accident flow !
rate test is physically impossible to perform. For these valves, an l' Engineering calculation has been performed to determine the minimum flow rate for full disc lift. An acceptable full-stroke esercise of these valves will be performed each refueling outage by measuring the pressurizer level increase over time, converting these parameters to a flow rate through the valve, and verifying this value is greater than or equal to the engineering calculated minimum flow rate for full disc lift.
Per reference e above, these valves were also verified to full-stroke open by using a " time of arrival" acoustic emission technique on the unit one valves that was performed in conjunction with the injection test described in VR-05. This method is superior to sample disassembly and inspection of one valve per outage which would require unusual system line-ups, freeze seals s radiation exposure, and possible plant transients. l 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 HRC Generic Letter 89-04, Attachment-1, Positions 1, 2, and 3 are utillzed OR specific relief requests are approved by the NRC.
Stroking a valve to the full closed position-for valves without a manual exerciser or ,nosition indicator must be verified using Indirect means.
These include, but are not limited to, (1) observing pressure indications on both sides of the valve to determine if the differential pressure expected with the valve shut is obtained, or (2) opening a drain connection on the upstream side of the valve to detect leakage rates in excess of that expected with the valve shut.
Valves that cannot be full-stroke tested or where full-stroking cannot be verified, shall be disassembled, Inspected, and manually exercised.
Valves that require disassembly for full-stroke testing during cold shutdowns or refueling still require quarterly part-stroke testing, where possible.
Testing of check valves by disassembly shall comply with the following:
- a. During valve testing by disassembly, the valve Internals shall be visually inspected for worn or corroded parts, and the valve disk shall'be manually exercised.
- b. Due to the scope of this testing, the personnel hazards involved, and system operating restrictions, va' " disassembly and inspection may be performed during reactor-refueling outages. Since this frequency differs from the Code required frequency, this deviation must be specifically noted in the IST program.
4.5 - Page 4 of 9 217(042292)
ZD790/97 L
'n . . , .
Rsvision 5 IST Technical Approach and position No. VA-03
- c. Where it is burdensome to disassemble and inspect all applicable valves each refueling outage, a sample disassembly and inspection plan
.for groups of identical valves in similar applications may be employed. The NRC Generic better 89-04 guidelines for 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 same design (manuf acturer, size, model number, and materials of construction) and have the sane sers '.ce conditions including valve orientation. Additionally, at each disassembly the licenaee must verify that the disassembled valve is capable of full-stroking and that the internals of the valve are structurally sound (no loose or corroded parts). Also, if the disassembly is to verify the full-stroke capability of the valve, the disk should be manually exercised.
A different valve of each group is required to be disassembled, inspected, and manually full-stroke exercised at each successive refueling outage, until the entire' group has been tested. If the disassembled valve l la not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in that group must also be disassembled, inspected, and manually full-stroke exercised during the same outage. Once this is completed, the sequence of disassembly must be repeated unless extension of the interval can be justified.
Extending the valve sample dibassembly and inspection interval f rom disassembly of one valve in the group every' refueling outage or expanding the group size would lucrease the time between testing of any particular valve lu the group. With four valves in a group and an 18-month reactor cycle, each valve would be disassembled and inspected every six years. If the fuel cycle is increased to 24 r:onths, each !
valve in a four-valve sample group would be disassembled and inspected only once every eight years.
l Extension of the valve disassembly / inspection interval f rom that l allowed by the Code (quarterly or cold shutdown frequency) to longer l than once every 6 years is a substantial change which may not be !
justifled 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 l should be decreased or whether more valves f rom the group should be disassembled during every refueling outage.
I Extensions of_the group size will be done on a case by case basis, i 4.5 - page 5 of 9 217(042292)
ZD790/98
, - . - . . . = - --
Ravtsion 5 IST Technical Approach and Position No. VA-04 A. CQttpanent Identificatimmt
- 1.
Description:
Determining Limiting Values of Tull-Stroke Times for Power Operated Valves.
- 2. Component Numbers: See IST Valve Tables (St).
- 3. References
- 6. ASME Code,Section XI, Subsection IWV, Sub Article IWV-3413.
- b. NRC Generic Letter 89-04, Attachment A, Position 5.
- c. ANSI /ASME OH-1987 through OMb-1989 Addenda, Par t 10, Section 4.2
- 4. Code Class 1, 2, and 3.
B. R12uiriment The .6T program originally assigned a limiting value of full-stroke time based on the most conservative value from plant Technical Speelfications (TS) or Updated final Safety Analysis Report (UTSAR). For valves not having a specified value of full-stroke, a limiting value was assigned based on manufacturers design input, engineering input, or initial. valve
_ pre-operational-testing. This methodology is contrary to NRC Generic Letter 89-04.
According to NRC Generic Letter 89-04 the limiting value of full-stroke should be based en an average reference stroke time of a valve when It is known to be operating properly. The limiting value should be a reasonable deviation from this reference stroke time based on the valve size, valve
. type, and actuator type. The deviation should not be so rertrictive that it results in a valve being declared inoperable due to reasonable stroke time variations. However, the deviation used to establish the limit should be such that corrective action would be taken for a valve that may not perform its Intended function. When the calculated limiting value for a full-stroke is greater than a TS or safety analysis limit, the TS or safety analysis limit should be used as the limiting value of full-stroke time. Based on this, a review of each valve operating history was
. performed and an average / reference value of full-stroke determined. In addition, valves were grouped together by system, train, unit, valve type, and actuator type to provide for a more thorough review in determining what would be a " reasonable" deviation from the average / reference full-stroke value.
The 1983 Edition through Summer 1983 Addenda of ASME Section XI does not provide guidance for determlaing values of full-stroke.
4.5 - Page 6 of 9
-217(042292) 2D79G/99
Rsvision 5a IST Technical Approach and Position No. VA-04 C. Positlnn The following criteria will be used as general guidance to establish REQUIRED ACTION ranges for power-operated valvest EOVs/HOVs/AOVs - Legs than or equal to 10 seggnf,g REQUIRED ACTION VALUE Greater than (2.0)(Tref)
EDVs/HOVs/AQys - Greater than 10 seconds:
REQUIRED ACTION VALUE: Greater than (1.75)(Tref) or (77,g+20 see)
MOVs - Less'than or equal to 10_itconds1 REQUIRED ACTION VALUES. Greater than (1.5)(7,,g)
HOVs - creater than 10 seconds:
REQUIRED ACTION VALUE: Greater than (1.25)(Tref) or (Tref +20 see) ,
Additional Notes
- 1. T is the reference or average stroke value in seconds of an in$fvidual'valveorvalvegroupingestablishedwhenthevalveisknown to be- operating acceptably.
- 2. Standard rounding techniques are to be used when rounding off stopwatch readings during valve stroke timing (e.g. 10.45 rounds to 10.5, and 10.44 is rounded to 10.4 seconds).' Round off all measured stroke time to the nearest tenth of a second.
- 3. When reference stroke valves or average stroke valves are affected by other parameters or conditions, then these parameters or conditions must be analysed and the above f actors 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. . Limiting, values of full stroke will be rounded to the nearest second.
- 6. REFER to relief request VR-20 for fixed ALERT Ranges.
4.5 - Page 7 of 9 217(042292)
ZD79G/100
- . . _ , . _ _.. ..,_ _ ~ _ _ _ _ . , . _ _ .._. _ _ . . . _ .
Rovlelon 5 IST Technical Approach and Position No. VA-04 Additional Notes: (continued)
- 7. Fast acting valves (valves which normally stroke in less than 2 secor.=s consistently) are included in Relief Request VR-12. These valves are HQI assigned ALERT RANGES and are HQI trended.
- 8. The above criteria is a guide and cannot cover all valves. The REQUIRE ACTION VALUES are selected based on comparison between the REFERENCE VALUE, LIMITING VALUE given in Technical Specifications /UTSAR, operating history, and calculated values using the above criteria.
- 9. Valves which serve the same function on dual trains (i.e., ICC9473A and 1CC94738) and dual units (i.e. ICC9473A and 2CC9473A) are assigned the same REQUIRED ACTICH VALUE based on human f actors considerations, unless valve or system design differences exist between the trains / units.
4.5 - Page 8 of 9 217(042292)
ZD79G/101
Rovision 5 IST Technical Approach and Position No. VA-05 A. ComponenLidentificfttlant
- 1. Description Tescing of the Boric Acid Transfer Pumps Discharge Check Valves
- 2. Component Numbers: 0AB8473, 1/2AB8487 I
- 2. References (a) Engineering Correspondence (CHRON i 161733) dated )
January 17, 1991 l
- 4. Code Class: 3/7 (Trach 8ng purposes ONLY)
B. Regulrtegnit These check valves ace tested per the Technical Specification requirement )
that requires an 18 month flow verification of 30 gpm to the RCS. Because the AB pumps were added to the program, the discharge check valves will also be added for tracking purposes only.
C. Ensitlen The boric acid transfer pumps were added to the IST program per pump technical position PA-01. Since this was done, it was decided to put the discharge check valves in the program as well for tracking purposes only, These valves are required to pass a minimum of 30 gpm in order to meet the Technical Specification requirement. The quarterly pump test will verify greater than 30 gpm, which la significantly more frequent than the current Technical Specification frequency. Back flow 1s prevented from the chemical and volume control system (CV) by. check valve 1(2)CV8442 and motor operated valve 1(2)CV8104 in the emergency boration flow path.
Also, ta s system uses only a single pump in series which precludes short circultang of flow through the parallel pump's discharge check valve, so no back flow test will be performed.
4.5 - Page 9 of 9 217(042292)
ZD79G/102
R2vicion 5 SECTICM 4.6 VALVE RELIEF REQUESTS L
- c. 217(042257-7'1790/103
R; vision 5a EELIELFIQUESl_YR:1
- 1. Valve Numbart All Type C tested primary containment isolation valves in this program are listed as Category At YALVE t VALVE I VALVE I
- 1) ICC685 41) IPR 0338 81) ISI8838 j
- 2) ICC9413A 42) IFR033C 82) 1S18964 !
- 3) ICC9414 43) IPR 033D 83) 1518968 l
- 4) ICC9416 44) IPR 066 84) IVQ001A
- 5) ICC9438 45) 1PS228A 85) 1VQ001B
- 6) 1CC9486 46) 1PS2288 86) IVQOO2A ;
- 7) ICC9518 47) 1PS229A 87) IVQ0028 j
- 8) ICC*i34 48) IPS229B 88) 1VQ003 !
- 9) 1CS007A 49) IPS230A 89) IVQOO4A i
- 10) ICS007B 50) IPS230B 90) IVQOO4B I
- 11) ICS008A 51) IPS231A 91) IVQOOSA
- 12) ICS008B 52) IPS2318 92) 1VQ005B 1
- 13) 1CV8100 53) 1PS9354A 93) IVQOO5C !
14 '. ICV 8112 54) IPS9354B 94) 1VQOl6 l
- 15) 1CV8113 55) IPS9355A 95) IVQO17
- 16) ICV 8152 56) 1PS9355B 96) IVQ018
_ l'7 ) 1CV8160 57) IPS9356A 97) IVQO19 le) 1TC009 58) IPS9356B 98) IWH190
- 19) ITC010 59) IPS9357A 99) IWM191 i 3) 1FC011 60) IPS9357B 100) IWOOO6A l .1) ITC012 61) 1RE1003 101) IWOOO6B
- 22) IIA 065 62) 1RE9157 102) IN0007A
- 23) IIA 066 63) 1RE9159A 103) IN0007B
- 24) IIA 091 64) 1RE9159B 104) IWOO20A
- 25) 10G057A 65) 1RE9160A 105) IWOO20B
- 26) 10G079 66) 1RE91608 106) 1NOO56A
- 27) 10G080 67) 1RE9170 107) IWOOS6B
- 28) 10G081 68) 1RF026
- 29) 10G082 69) 1RF027
- 30) 10G083 70) 1RYO75 g
- 31) 10G084 71) 1RY8025
- 32) 10G085 72) 1RY8026
- 33) IPR 001A 73) 1RY8028
- 34) 1PR001B 74) 1RY8033
- 35) IPR 002E 75) 1RY8046
- 36) 1PR002F 76) 1RY8047 3~' IPR 002G 77) ISA032
- 38) 1PR002H 78) 1SA033
- 39) 1PR032 79) ISI8871
- 40) 1PR033A 80) 15I8880 4.6 - Page 1 of 58 217(042292)
ZD79G/104
4 R3 vision 50-1 RELIZE_REQQEST VR .
Valve N"=hgIt-;(continued)
VALVE YALYE_t VALVE i 108). =2CC685. 1148)- 2PR033B 188) 2SI8888 l 109) -2CC9413A 149)- 2PR033C 189)- -2SI8964' .i 110) 2CC9414. 150). 2PR033D- 190)- 2S18968 l
-151) 2PR066 191)- 2VQ001A -l 411) 2CC9416.
112) 2CC9438 152) 2PS228A 192). 2VQ001B ,
. 113) 2CC9486: 153)- ,2PS228B 193) 2VQ002A l 114)L 2CC9518: 154)- 2PS229A 194) 2VQ0028-115) -2CC9534- .155) 2PS229B: 195) 2VQ002 1 116) 12CS007A'-- 156)' 2PS230A- 196) 2VQ004A 117)1 2CS007B. 157)J -2PS230B- 197) 2VQ004B .
118)~ --2CS008 A . 150 ) = 2PS231A 198) 2VQ005A 119): 2CS008B 159)y 2PS231B 199) 2VQ005B
- - 120)- 2CV8100 160)~ 2PS9354A 200)' 2VQ005C 121)- -- 2 CV 8112 161) 2PS9354B 201) 2VQ016-122) -2CV8113 162) 2PS9355A .202) 2VQO17.
123). 2CV8152 163) 2PS9355B- 203) . 2VQ018 124). 2CV8160 16 4 ) '- '2PS9356A- 204) 2VQO19 125) .2rC009f 165)- _2PS9356B 205) 2WM190 126). -2FC010- 166) '2PS9357A. 206). 2WM191 127): 2TC011. 167) 2PS9357B -207) 2 WOO 06A ,
"128)? 12TC012 -168)1 .2RE1003 208) 2WOOO6BJ 129) 2IA065; 169) 2RE9157- 209) 2WOOO7A-1130) '2IA066 ' 17 0 ) ' 2RE9159A- 210) 2WOOO7B 131)- 2IA091' 1171) '2RE9159B 211)- 2 WOO 20A
.132): 20G057A ?172) 2RE9160A 212) 2 WOO 208
-133) -20G079 173) -2RE9160B 213) 2 WOOS 6A 134) 20G080; ~174) -2RE9170 214)- 2 WOOS 6B-
- - 13 5 ) . ;20G081 ;- 17 5 ) : 2RT026 ,
13f) z20G082 176) 2RF027-137)L 20G083; 177) 2RYO75
_ 128) T20G084 178)- 2RY8025' s 13 9) L- - 20G0 8 5 -- '179) 2RYB026 140) -2PR001A- '180)- 2RY8023 141) 2PR001B 1181 ) .-- 2RY8033
.. 142)- 2PR002E 182) :RY8046 143)- I2PR002T- 183). 2RY8047 1144), 22PR002G ' 18 4 ) - 25A032- ,
-. 1145) =2PR002H- 185)- '2SA033
- 146) 2PR032 1186) .2SI8871 .
? -147) 2PR033A '187). 2SI8880
[.
L 4.6 - Page 2 of 58
- 217(042292) e ZD79G/105 L
L
R2 vision Sa' L
RELIEF REQUEST VR-1 2.- Number of Itemst 214
- 4. ASME Code.Section XI._Re2uirements:
Seat Leakage Measurement per INV-3420 and Corrective Action per INV-3427(b).
- 5. ' Basis for Relieft-Primary containment isolation valves will be seat leak tested in i accordance with 10 CFR 50, Appendix J. For these valves,Section XI testing requirements are essentially equivalent to those of Appendix J. ,
l 6' . Alternaig Testings
-Primary containment isolation valves shall be seat leak rate tested in accordance with the requirements of 10 CFR 50, Appendjx J. The results of such leak rate measurements shall be analyzed and corrected, as necessary, in accordance with the guidance set forth in ASME Code Section XI,
- Sul section INV, paragraphs IRV-3426 and INV-3427(a). The trending requirements of IWV-3427(b) will nat be utilised.
- 7. -Justification No additional information concerning valve leakage would be gained by performing separate tests to both Section XI and Appendix J. Therefore, overall plant safety is not affectwd. As specified per NRC Generic Letter 89-04, Attachment 1, position 10, the usefulness of IWV-3427(b) does not
. justify the' burden of complying with this requirement.
B. Applicable Time Period:
This. relief is requested'once per two years during the first inspection interval.
- 9. Approval Status:
- a. Relief granted per NRC Generic Letter 89-04.
- b. Deleted SD valves per Technical Specification Amendment 426.
- c. Added 1/2RYO75 due to Appendix J, Type C Testing per Rev. Sa.
4.6 - Page 3 of F8 217(042292)
ZD79G/106
Ravisico 5s RELIEF REOUEST VR-2
- 1. Valve NumbeI: ICS020A 2CS020A 1CS020B 2CS020B
- 2. Number of Ittma 4*
- 3. ASME Code CatRS2Iy C
- 4. ASME Code.Section XI ReguilcmeAta Exercise check valves to the position required to fulfill their function (Ct/Open; Bt/ Closed) quarterly, unless such operation is not practical during plant operation per INV-3521, or exercise during cold shutdown per INV-3522.
- 5. Basis for Re1111:
These check valves in the spray additive system (CS) cannot be stroked without introducing NaOH into the CS syctem, unless the piping between the NaOH storage tank and the injection isolation valves, 1/2CS021A/B, is drained into containers, which amounts to almost two 55 gallon drums of potentially (radioactive / toxic) mixed waste that requires either recyling or disposal. Then, primarily water is connected to the CS system and is used to flow test the line to ensure that the proper Technical Specification eductor flow rate can be passed, via special test connections.
The problem with disposal stems from the caustic being slightly contaminated, as well as having a high ph. Recyc11cq (pouring the contents of the drums bank into the NaOH tank) is not always a viable option either, considering the caustic has been contained in a stagnate line (up to five years) and may not meet chemistry requirements. Thus storge of hazardous mixed waste can become very costly. This is due to the non-existance of commercial disposel facilities for mixed waste, which means that any mixed waste generated would have to be stored on-site.
Also, the draining and handling of this highly caustic material poces a significant hazard to personnel, and can result in loss of eye sight and/or chemical burns, if splashed or spilled.
- 6. Alternate Testinct Group 1 Group 2 j UNIT 1 1CS020A 2CS020A 1CS020B 2CS020B The A and B train valves are of the same design (manufecturer, size, model number, and materials of construction) and have the same service conditions, including orientation. This forms an acceptable sample disassembly group per Generic Letter 89-04, Position 2c.
Each group will be disassembeld and visually inspected at the same frequency as the Technical Specification eductor flow test, conducted at least once every five years. The visual inspection of internals will precede the eductor flow test.
4.6 - Page 4 of 58
-217(042292)
ZD79G/107
Rsv1Fion SS ESLIII_ REQUEST VR-2
- 7. duttificat1DR:
If the disassembled valve is not capable of being manually full-stroked exercised or there is binding or failure of internals, the remaining valve on the af fected unit will be evaluated for further action as well.
Full flew testing of these valves cannot be accomplished without posing a serious threat to the safety of equipment and personnel. It is impractical to either full or partial stroke exercise these valves since flow through them requires draining and flushing the piping to prevent the introduction of caustic effluent into the CS system. The problem of mixed waste disposal or recycling created by system draining of approximately two 55 gallon drums is considered an undue hardship, if the Code requirements are imposed.
The alternate test f requency (same f requeny as the Technical Specification eductor flow test of at least once every five years) is justifiable in that maintenance history and provious inspections of these valves at both Byron and Braidwood stations have shown no evidence of degradation or physical impairments (i.e. corrosion, chemical buildup, wear). This is to be expected since these valves see limited operation (flow in line during eductor flow test only).
Industry erperience, as documented in NPRDS, show no history of problems with these valves. A company wide check valve evaluation addressing the "EPRI Application Guidelines for Check Valves in Nuclear Power Plants" revealed that the location, orientation and application of these valves are not conducive to the type of wear or degradation correlated with SOER 86-03 type failures.
The alternate test inethod, visual inspection of internals followed by the Technical Specification eductor flow test, at least once every five years, is sufficient to ensure operability of these valves and is consistent with Generic Letter 89-04 guidelines, The hardship involved with the hazardous mixed waste disposal and handling caustic material with regards to personnel safety does not provide a compensated increase in safety of the CS system equipment.
- 8. Applicable Time Period:
This relief is requested for the first inspection interval.
t l 9. Aggintal Status:
i
- a. Relief granted per Generic Letter 89-04, Rev. 4/4a.
- b. This relief request is being resubmitted based on further experience gained during inservice testing and inspections, Rev. 5.
l
- c. Resubmitted for mixed waste considerations, Rev. 5 Supplement.
- d. Incorporated into Rev. Sa; previously reviewed per OSR 92-017. '
4.6 - Page 5 of 58 l
217(042292)
ZD79G/108 l
R: vision 5 RELIEF REOUIST VR-3
- 1. Ealve Numbert ISI8922A/B 2 SIB 922A/D
-2. Number of Itemg 4 3.- ASME Code Category: C
- 4. ASME Code.Section XI Requirements:
Exercise for operability (Ct/Bt) of check valves every 3 months, per INV-3521.
- 5. R. asis for Relief:
These check valves cannot be full flow tested during operation as the shut-off head of the Safety Injection pumps is lower than the reactor coolant system pressure. Performance of this test with the RCS depressurized,-but intact, could lead to inadvertent over-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 Testing:
These valves will be full-stroke tested during refueling outages as a minimum, but no more frequently than once per quarter.
- 7. dustificatina:
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 ten as safely possible.
- 8. Applin kle Time Period:
This relief is requested once per quarter during the first inspection interval..
- 9. Approval Status:
- a. Relief granted per NRC Generic Letter 89-04.
f.
l 4.6 - Page 6 of 58 l
217(042292)
'ZD79G/109 l-
A R visica 53 EgLIEr REQUEST VR-4
- 1. Yalve..N umhtt s ICS003A/B 2CS003A/B 1CS008A/B 2CS008A/B
- 2. Rumber of Items 8
- 4. ASME Code,Section XI Requirements: -
-a. . ' Exercise check valves to the position required to fulfill theAr function (Open/Ct; Closed /Bt), unless such operation is not practical during plant operation, per IWV-3522.
- b. When a valve has been repaired, replaced, or has undergone maintenance that could affect its performance and prior to the time it is returned to service, it shall be tested to demonstrate that the performance parameters, which could have been af fected by tlee replacement, repair, or maintenance, are within acceptable limits, per IWV-3200.
The 1/2CS003A/B check valves are on discharge of the CS pumps and function in the open direction to allow flow from.the refueling water storage tank (RNST) to the. spray rings inside containment. They f unction in the closed direction to prevent water column separation and reverse rotation of the CS pumps. The 1/2CS008A/B check valves are the inboard containment isolation valve for the spray header piping and furetion in the open direction to allow flow. They function in the closed direction to provide
~
for containment isolation, which is a redundant function to the outboard CIV. These valves cannot be full flow tested as a matter of course during unit operation or cold shutdown as water from the CS pumps would be discharged through the CS ring headers causing undesirable effects on many critical 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 borated water from the refueling water storage tank. This would adversely affect the reactor head components (e.g. Control. Rod Drives). The filling of the cavity, via temporarily installed large bore piping, would require the removal of the reactor vessel head so as to preclude equipment damage f rom borated water. The erection of temporary piping f rom the CS line to the reactor cavity would take an estimated nine to twelve shifts, compared to one to two shifts for valve inspection. This estimate does'not take into account the time required to drain and remove the piping from containtment. Testing in this manner would also require overriding protective electrical interlocks in the pump start circuitry, full flow recirculation flow paths do not exist from the discharge of the CS pumps through these check valves to the refueling water storage tank.
The addition of such flow paths would require extensive modifications to eristing plant designs: including additional penetrations of the containment boundary, and electrical system changes to allow for pump start without' the need of jumpering out protective interlocks.
4.6 - Page 7 of 58 217(042292)
ZD79G/110
R2 vision 5a RELIEF REOUEST VR-4
- 5. Basis for Rellelt (continued) ,-
Partial stroking of the 1/2CS008A/B valves with air using existlug LLRT connections does not provide adequate flow to obthin any meaningful acoustic monitoring data, relative to valve condition or its performance parameters. This acoustic testing was attempted at Byron Station per special process procedure, SPP 91-054,
- 6. Alternate Testing Group 1 Group 2 UNIT 1 1CS003A 1CS008A 1CS0023 1CS00H__
Group 1 Group 2 UNIT 2 2CS003A 2CS008A 2CS003B 2 C S 0083_._
The A and B train valves are of the same design (manufacturer, size, model number, and materials of contruction) and have the same service conditions, including orientation, therefore they form a sample disassembly group.
One valve from each group, on a per unit basis, will be examined each refueling outage. If the disassembled valve is not capable of being manually full stroked exercised or if there is binding or failure of internals, the remaining valve on the affected unit will be inspected.
In addition to the above, the 1/2CS003A/B valves will be partial stroke tested during the' quarterly pump surveillance and af ter maintenance in order to verify that it was installed correctly. The 1/2CS008A/B are required to be leak tested before and after visual inspection per Appendix J requirements. The leakage test following reassembly of the valve into the system will serve as post-maintenance verification that the valve was installed correctly. Parital flow testing the 1/2CS00BA/B following maintenance in not practical for the same reasons given in the " Basis for Relief" section.
7.. Justification:
The 1/2CS003A, B and 1/2CS008A, B valves are removed from the system and visually examined per the strict detailed inspection requirements of the Station Check Valve Program. This inspection adequately verifies that the valves are maintained in a state of operational readiness and that their performance parameters are adequately assessed. The valves are verified to be functional by performing a thorough visual inspection of the internals and by performing a manual full-stroke exercise of each disc. Previous inspections of these particular valves at both Byron and Braidwood Stations have repeatedly shown them to be in good condition.
! 4.6 - Page 8 of 58 i 217(042292)
ZD790/111
Ravision So RELIEE_EEQUfST VR-A
- 7. 'Justifiqatigms (continued)
The wafer type design.of the valve body for these valves makes their removal a simple process, with-little chance of damage to their internals.
Also, there is no disassembly of internal parts required; all wear surfaces are accessible to visual excnination. After inspection and stroke testing, the valve is reinstalled into the line and post maintenance testing is performed. The 1/2CS008A, B valves receive a local leak rate test per the requirements of 10CFR50 Appendix J, and the 1/2C5003A, B valves are partial flow tested. These tests verify proper installation of the check valves, and the valve inspection procedure requires post-inspection visual examination of the check valve to ensure that the '
pin is oriented properly and that the flow direction is correct.
The alternate test frequency is justifiable in that maintenance history and previous inspections of these_ valves at both Byron and Braidwood stations has shown no evidence of degradation or physical impairments. In addition, industry erperience, as documented in NPRDS, show no history of problems with these valves.
A company wide check valve evaluation addressing the "EPRI Application Guldelines for Check Valves in Nuclear Power Plants" revealed that the location, orientation and application of these valves are not conducive to the type of wear or degradation correlated with SOER 86-03 type problems.
However, they still require sonee level of monitoring to detect hidden problems.
The altwrnate test method _is sufficient ta ensure operability of these valves and is consistent with Generic Letter 89-04. The hardship involved with full stroke exercising these check valves, if the Code requirements were imposed, does not provide a compensated increase in safety of these g CS system valves.
- 8. . Applicable Time Period:
This relief is requested once per quarter during the first inspection interval.
- 9. Approval Status:
- a. Relief gre.nted per NRC Generic Letter 89-04, Rev. 5.
- b. Changed to incorporate acoustic test results, Rev. Sa.
4.6 - Page 9 of 58 217(042292)
ZD79G/112
Revision 5a RELIEL_BIQUISLYA-5
- 1. Valve Numbert ISIB956A-D 2SI8956A-D SI Accumulator Check Valves 1 SIB 948A-D- 2 SIB 948A-D SI Accumulator Check Valves
- 2. tiumbitt_of Items: 16
- 3. ' ASME_ Code Category: AC
- 4. ASME Code. Sectlan XI RequiremeAtJ:
Check valves that cannot be exercised during p? ant operation shall be specifically identified by the owner and shall be full stroke (Ct/Open; Bt/ Closed) exercised during cold shutdowns per IWV-3521 and IWV-3522.
- 5. Hasis for Religf The SI accumulator check valves cannot be tested during unit operation due to the pressure differential between the accumulators (650 psig) and the reactor coolant system (2235 psig). These check valves are physically located inside containment,.inside the missile barrier, in the line between - the accumulator and the reactor coolant system (RCS) cold legs.
The radiation fleid in this area ranges from 70 to 300 (or more) mrem /hr whole body due to the reactor coolant loop isolation valves, reactor coolant pumps, and the bottom (primary side) of the steam generators all being in the near vicinity. These valves function in the open direction to permit flow of 1900-2100 ppm borated water into the RCS during a LOCA resulting in an RCS pressure below approximately 600 psig. They function in'the closed direction as pressure isolation valves and are also identified ascintersystem LOCA: valves. These valves are required by Technical Specifications to be leak tested following opening evolutions to ensure their closing, seat tightness capability.
' Exercising these valves at times other than refueling poses an undesirable situation as discussed in NRC Intromation Notice 89-67: " Loss of Residual Heat Removal. Caused by Accumulator Nitrogen Injection."
4.6 - Page 10 of 58 217(042292)
.ZD79G/113
Revision 5a RELLELREWEST VR .5
- 6. A11mInmir_Itsiing1 All four accumulator trains will be discharged into the reactor vessel during each refueling outage to perform a full stroke exercise (Ct/Bt) of these valves. An acceptable full stroke exercise of these valves will consist of mearuring either the pressurizer level increase over time or accirmulator decrease over time, converting these parameters to a flow rate through the valve, and verifying this value to be greater than or equal to the engineering calculated minimum flow rate. In addition, acoustic testing will be used to confirm the full disc lift by the time-of-arrival technigue.
The time of arrival technique utilizes two sensors, one mounted at the backstop location and the other at the seat' location. When the valve full strokes open, the disk arm impacts on the backstop (valve body) creating an acoustic event...This acoustic event pro, $ gates through the body at a specific velocity based on the material of construction. The sensor at the backstop detects the event first, with the sensor at the seat detecting the event at a later point in time. This lag or time delay between the backstop sensor and the seat sensor represents the time of arrival method and is used to demonstrate that the valve full strokes.
- 7. Jus tificallsn:
It-is impractical to full stroke these valves during cold shutdowns, planned or urplanned, due to the time and system constraints, the adverse affects on the plant and the costs involved. The reactor coolant system (RCS) must be at approximately 40 psi with all 4 reactor coolant pumps (RCPs) off and accumulator pressure at 100 psi over RCS pressure.
Installing special test equipment to record pressurizer level increase could interfere with the required Technical Specification leakage test, required prior to entering Mode 2. Also, at later points in core life, boron concentration in the RCS is relatively low compared to the 2000 ppm concentration.in the accumulators. This injection test uses an estimated 8 to:10 thousand gallons of water, which will increase the RCS boron concentration, resulting in potential delays with startup of the reactor, and creates a situation for possible nitrogen injection into the RCS.
4.6 - Page 11 of 58 217(042292)
ZD79G/114
Revision 50-RELIEF __EEQUEST VR-5
- 7. Justitication: (continued)
In addition,.to dilute the RCS boron concentration, the feed and bleed process will greatly increase the amount of high grade water rejected f rom the site and could increase the amount of radioactive ef fluents discharged to the environment. The cost of the nitrogen required to test these valves -
is at least $2500, and although not quantified, the cost of processing the reactor coolant to restore the optimun boron concentration are not inconsequential.
Additionally, all of these check valves-have been acoustically tested-during the above described injection test. Using the " time of arrival" technique, the accumulator check valves are positively verified to f ull stroke to the open position as flow developes threugh each valve. The alternate test method is superior to sample disassembly and inspection of one vcive per outage which would require unusual system line-ups, freeze seals, radiation exposure (estimated 2.0 c.an-rem), and possible plant transients.
- 8. Applicable _Ilme_EerioAt
.This relief is requested once per quarter d2 ring the first inspection interval.
- 9. Approval Status:
- a. Relief granted per NRC Generic Letter 89-04 for Rev. 4.
b.
Requesting refueling frequency for the CT exercise test; incorporated >
the necessary-information and justification, Rev. 5.
- c. Incorpora*,ed additional technical information and justification and acoustic time-of-arrival, per Rev. Sa.
4.6 - Page 12 of 58 217(042292)'
ZD79G/115
i 1
hl fs a88 -
stil 855 S v!
i's' tc o 66 " le! all 3. h 8 0g
!a:!e: ::: :: i ! ; le : _ 3 jT -
Mid~ -
V ati is:
t t
- :: a e ,g IS
,,,j(
t(
I tr r r ;
l i < .i t t G'
~-
- gt . si. 'e : I I
" f'ra
?? -sisi l e 0 8' .
h *--
6lNO ?;
- k e:; ! ! N N- : , ? w --u
..~
9 g t u a se; e:i l oo O
- i,! $ 1:1 m m m m
5 5 s a ;;
$I %-S h
ja,all o
la :
o let m :1
. . . ~ . . . . le:; gia:1 e:I Mununummuuumunumnummusuu muuua ui
, ,a.
1
? :cQ, 51155115 ji d:
i ,, m
.2 -
-u a :
4-:@gil .
irx
,m p
- tr-:Q, I;i !!, I i!!!I!!
E
_c me 1= 1=
4 a_ 1- 1-
=
(
d;:GDgl' g
- 5 101101 .
5 I y !a: la:
g nW
-J
novision 5 1
EELIEF REOUEST VPd
- 1. Yalve Number ISI8926 2SI8926
- 2. Rumber of Items: 7 2
- 3. ASME Code Categgry: C PdS;;;
- 4. ASME Code,Section XI R1pulrements:
(Ct i Exercise for operability (Ct) of check valves every 3 months, per IWV-3521.
- 5. Basis for ErlitI
'M e Full stroke exercising hf the Safety Injection pump suction check valves, ISI8926 and 2 SIB 926 canot n 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 protecting against over-pressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
- 6. Alternate Testing:
The 15I8926 and 2 SIB 9262 valves will be partial stroke tested during periodic inservice tests with the SI pumps in the recirculation mode.
Full stroke exercising for the valves will be done during refueling outages as a minimum, but no more frequently than once per quarter.
- 7. Justificatinn:
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. Applienble Time Period:
This relief is requested once per quarter during the first inspection interval.
- 9. Approval Sintus
- a. Relief granted per NRC Generic Letter 89-04.
4.6 - Page 13 of 58 217(042292)
ZD79G/116
Ravision 5 RELizr REQUrsI_yg:1
-DELETED-Deleted relief request VR-7. Incorporated valves formerly covered by VR-7 into VR-12 and VR-17.
4.6 - Page 14 of 58 217(042292) e ZD79G/117
Ravision Sa RELIEF REOUISI_YE-2
- 1. Valve Number: ICC685 2CC685 Thermal Barrier Return ICC9438 2CC9438 Thermal Barrier Return ICC9518 2CC9518 Pressure Relief Check 1CC9413A 2CC9443A Motor / Thermal Barrier Supply ICC9486 2CC9486 Motor / Thermal Barrier Supply ICC9414 2CC9414 Motor Bearing Return ICC9416 2CC9416 Motor Bearing Return ICC9534 2CC9534 Pressure Relief Check
- 2. Number of Items: 16
- 3. ASME Code Category: A, B, and C
- 4. ASME Codb_Section XI RegR11.EMAntE Exercise for operability: full stroke timing and exercising (St) of Category A & B valves; full stroke and back flow testing (Ct/Bt) of Category C valves every 3 months per IWV-3411 and INV-3421, respectively.
Per INV-3412 for power operated valves, and INV-3522 for check valves, valves _that cannot be exercised during plant operation shall be specifically identified by the owner and exercised during cold shutdowns.
- 5. RAgis for Reliefs _
All of the above listed valves function in the closed position to provide a limited leakage barrier between the containment atmosphere and the environment during accident conditions (containment isolation). The isolation valves function in the open position to allow component cooling water flow (monitored by flow sensing instruments) to the upper and lower RCP motor bearings and to the thermal barrier between the RCS ~ and the RCP mechanical seals. .ne 1/2CC9518 and 1/2CC9534 check valves function in the open direction only when both of the associated containment isolation l valves (CIVs) are closed during an accident condition 3nvolving adverse j containment conditions. _ Each valve opens in a manner that will bypass the j upstream isolation valve to relieve excess pressure. This is to orevent hydraulic-locking of the associated isolation valves in the closed positions which can be accomplished manually by using the manual vent between the two isolation valves. They are also needed for pressure integrity purposes. >
Component cooling (CC) water flow to the Reactor Coolant Pumps (RCPs) is required at all times while the pumps are in operation. The failure of one of these valves in a closed position during an exercise test would
' result in a loss of cooling flow to the RCPs and possible pump damage and/or trip, which can further lead to disruptions in RCS pressure j control. In addition, the RCPs provide the necessary driving head to the pressurizer spray valves for pressure control in the RCS while a steam bubble exists in the pressurizer during power operation and cold shutdown.
4.6 - Page 15 of 58 217(042292)
ZD79G/118
Revision Sa RELLEE_EKOUEST VR-8
^
5 .' - Ensis for Reliefs (continued)~ r
- A' reactor coolant pump- start ' involves two operations personnel in y<~
attendance to monitor and report pump shaf t rotation information to the control room.- This- involves a containment entry, inside the. inner misslie
- barrier', which-is'a high radiation area. The exposure to personnel is
. dependent: on .the number- of " bun.ps" needed -(normally 2-3 bumps at' an estimated-9-12 hours) to rid the system of-air, i
The Code requires that the 1/2CC9518, 1/2CC9534 and the 1/2CC9486 check ;j
-valves:be tested in theEclosed direction to verify their seating ;
capability. .However, these check valves can only be verified closed by i performing the Appendix J, Type C local leakage rate-test (LLRT).
Performing the LLRT requires placing the system in an inoperable status (removed from service) for an extented period of time due to the need to isolate'and drain portions of the system, and' connecting a-leak rate monitor (LRM). This will prevent starting the RCPs and could delay reactor startup. .These tests will require a minimum of three shifts each to perform.
This would cause undue hardship with no compensating increase in plant or component safety, if'the Code requirements were imposed. ,
- 6. Alternate Testing: !
-The isolation' valves will be stroked on a refueling frequency or at
. planned. cold shutdowns'when~all four RCPs are no longer required to support. plant conditions and can be removed form service'. The RCPs will not be shutdown.for the sole purpose of stoke timing the isolation valves. ;
Check valves:1/2CC9486 (total) CC supply flow to the_RCPs will be back Lflow tested (Bt) closed on the same frequency. as their. Appendix J seat
-leakage: test. . The-1/2CC9518 and:1/2CC9534 pressurr 'ck. valves'will be >
exercised ~and backlflow tested (Ct/Bt) each refue ~ 3ge in conjunction with their associated Appendix J set- .. 5ege test. .This.
- frequency is at-least once per two years, to be . performed during reactor refueling outages.
'7.> Justification:
This alternate testing will adequately maintain these portions of the CC
-system in a statet ot operational readiness, while not impacting the safety of the: plant. It also eliminates unnecessary personnel radiation
-exposure,.possible damage to the RCP seals, and minimizes tne potential RCS pressure: transient' involved with restarting RCPs at low temperatures.
Back' flow testing these check valves'en the-same schedule as-thelt-Appendix J 1eakage test will ' adequately maintain.this portion of the CC. -
system-in a state of operational rea'liness without' causing unnecessary.
personnel radiation exposure, possible damage - to the RCPs or delays in reactor startup. In addition,.the Code only requires a five year frequency for pressure relief testing.
Performance of leakage testing on a two year (refueling) frequency is
. adequate to demonstrate-structural integrity and valve seating capability per both Appendix J and ASME Section KI requirements..
4.6 - Page 16 of 58 217(042292)
ZD79G/119
-4 a. , a, ._ , . a .~
R3 vision 5a p.ELIEF REOUEST VR-B
- 7. Justifications (continued)
There_ is no reason to perform the Appendix J, Type C (Iow pressure air at approximately 45 psig) seat leakage test more often than that already require ' by 10CTR50. This low pressure air test is adequate to monitor the val => ability to seats the smallest amounts of dirt, general corrosion, and forlegn material can be detected between the seating surfaces by this test.
Performing an LLRT to prove valve closure would only draw manpower away from the task at hand, and could hamper attempts to restart the unit. An LLRT requires personnel involvement from operations (valve manipulations and out of services), radiation protection (radiation surveys and ;
monitoring), instrument maintenance (installation of test equipment), and technical staff (LLRT test equipment operation and test supervision) that -
results in increased exposure. This excess exposure conflicts with stellon ALARA goals and radiation work practices. For these reasons, performing I an LLRT to verify valve closure is considered to be impractical during cold shutdevn.
Quarterly and cold shutdown testing requires a containment entry which would conflict with station ALARA goals and and radiation practices in ,
reducing exposure, and it is not prudent from a personnel safety '
standpoint. For personnel safety considerations, two individuals must always enter containment together, whenever containment integrity is set.
The performance of this test would require a minimun of three (3) shifts with personnel working in a high radiation area. In addition, performing the LLRT test. on a more f requent basis has an adverse impact on the i required test equipment (LRMs).
The leak rate monitors (LRM).used for T*oe C LLRTs are required to be shipped off-site for calibration. Duri > J operation and cold shutdown when containment integrity is set, the LRM(s) would need to be taken inside the !
j containment. If the LRM is ' contaminated and then unable to be - -
. decontaminated, this would prevent its calibration and render it unusable. This equipment is expensive and the number of monitors available for use is limited. During refueling outages, a staging area is set up outside contairment in a low dose, non-contaminated area and hoses are run inside to the various containment isolation valves. This is possible due to the relaxed containment integrity requirements. Thesa '
precautions are taken' to prevent the LRMs from becoming contaminated.
- 8. Applicable Time Periqd This relief is requested once per quarter during the first inspection interval.
- 9. Approval Status
- a. Relief granted per NRC Generic Letter 89-04.
- b. Requesting additional relief for valves 1/2CC9518 & 1/2CC9534, Rev. 5.
- c. Added additional technical information and justification, Rev. Sa.
4.6 - page 17 of 58 c 217(042292) i l
ZD79G/120 l
R3 vision 53 '
1 RELIEF REOUEST VR-9
- 1. Valve Number ICV 8100 2CV8100 RCP Seal Water Return ICV 8112 2CV8112 RCP Seal Water Return ICV 8113 2CV8113 Pressure Relief Check
-2. Number of Items: 6
- 4. ASME Code.Section XI Requirements:
Exercise for operability: full stroke timing and exercising (St) of Category A & B valves; full stroke and back flow testing (Ct/Bt) of Category C valves every 3 months per INV-3411 and IWV-3421, respectively.
Per INV-3412 for power operated valves, and IWV-3522 for check valves, valves that cannot be exercised during plant operation shall be specifically identified by the owner and exercised during cold shutdowns.
- 5. Rnsis for Religf All of the above valves function to provide for a limited leakage barrier between the containment atmoshpere and the environment during accident conditions (containment isolation). Their open function is to allow a return path for filtered seal water flow for cooling and flushing to the RCP mechanical seals during plant operation. During startup and shutdown, the pressure in the RCS is too low to maintain the gap across the number 1 seal. Under such conditions, the number-1 seal bypass flow is established which assures - adequate cooling of the pump's lower radial bearing and limits the temperature rise of water cooling the number 1 seal. The 1/2CV8113 pressure relief check valves function in the open position only when both of the associated containment isolation valves (CIVs) are closed
- during an accident condition involving adverse containment conditions.
Each valve opens in a manner that will bypass the upstream isolation valve ,
to relieve excess pressure. This is to prevent hydraulic locking of the associated isolation valves in the closed positions which can be accomplished manually by usirg the manual vent between the two isolation valves. They are also needed for pressure integrity purposes.
These valves cannot be tested during unit or pump operation as seal water [
flow from the CV system is required continuously while the reactor coolant pumps are in operation. Loss of. flow could result in damage to the seals from overheating and contamination by foreign material. Also, 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 relief valve upstream of the isolation valves, generating significant quantities of liquid radwaste. The RCPs are also needed to provide the driving head to the pressurizer spray valves for pressure control in the RCS while a steam bubble exists in the pressurizer during power operation and cold shutdown.
(
A reactor coolant pump start involves two operations personnel in attendance to monitor and report pump shaf t rotation information to the control room. This involves a containment entry, inside the inner missile barrier, which is a high radiation area. j 4.6 - Page 18 of 58 217(042292)
-ZD79G/121
Revision 5a RELIEF REQUEST VR-9
- 5. Ensis_{nI_Relhtis (continued)
The exposure to personnel .is dependent on the number of " bumps" needed (normally 2-3 bumps estimated at an 8-12 hours) to rid the system of air.
The closure test for the 1/2CV8113 (seal return pressure relief check valves)-can only be verified by performing a local leakage rate test (LLRT). Performing this test requires placing the system in an inoperable j status, isolating the seal return line portion of piping,-and connecting >
an external pressure supply. This test will require a minimum of two shifts to perform. The opening test requires isolating both the inboard motor and manual isolation valves and running a centrif ugal charging pump on mini-flow recirculation to supply pressure for opening the valve. The j inboard manual vent is opened to verify that the check valve is capable of !
relieving pressure.- This would require a minimum of I shif t to perform.
- 6. Alternate _71 sting:
The 1/2CV8113 and 1/2CV8112 1 solation valves will be stroked on a !
refueling frequency or at planned cold shutdowns when all four RCPs are no f longer required to support plant operations and can be taken out of service. The RCPs will not be shutdown for the sole purpose of stroke timing the isolation valves. ,
The 1/2CV8113 pressure check valves will be exercised and back flow (Ct/Bt) tested each refueling outage in conjucntion with their associated Appendix J 1eakage rate test. This f requency is at least once per two years, to be performed- during each reactor refueling outage.
i
- 7. Justification:
This alternate testing will adequately maintain this portion of the CV system in a state of operational readiness, while not impacting the safety of the plant. It also eliminates unnecessary personnel radiation exposure, possible damage to the RCP seals, and minimizes the potential RCS pressure transient involved with restarting RCPs at low temperatures.
Back flow testing these check valves on the same schedule as their ,
Appendix J 1eak rate test will adequately maintain this portion of the CV l system in a state of operational readiness without causing unnecessary ,
personnel radiation exposure, delays in reactor startup or possible damage l to the RCPs. In addition, the Code only requires a five year frequency I for. pressure relief testing.
Performance of leakage testing on a two year (refueling) frequency is adequ ate to demonstrate structural integrity and valve seating capability per both Appendix J and ASME Section XI requirements. There is no reason to perform the Appendix J, Type C (low pressure air at approximately 45 psig) seat leakage test more of ten than that already required by 10CTR50.
This low pressure air test is adequate to monitor the valve's ability to i seat; the smallest amounts of dirt, general corrosion, and forlegn material can be detected between the seating surfaces by this test.
4.6 - Page 19 of 58 217(042292)
ZD79G/122
Revision Sa RELIEF REOUEST VR-9
- 7. dultifications (coctinued)
During forced outages, limited manpower and resources are available to perform the necessary prerequisites involved with an LLRT. Performing an LLRT to prove valve closure would only draw manpower away from the task at hand, and could hamper attempts to restart the unit. An LLRT requires personnel involvement from operations (valve manipulations and out of services), radiation protection (radiation surveys and monitoring),
instrument maintenance (installation of test equipment), and technical staff (LLRT test equipment operation and test supervision) that results in increased exposure. This excess exposure conflicts with station ALARA goals and practices. For these reasons, performing an LLRT to verify valve closure is considered to be inpractical during cold shutdown.
Quarterly and cold shutdown testing requires-a containment entry which would conflict with station ALARA goals and and radiation practices in reducing man-rem, and it is not prudent from a personnel >afety standpoint. For personnel safety considerations, two individuals must always enter containment together, whenever containment integrity is set.
The performance of this test would require a minimun of three (3) shifts with personnel working in a high radiation area. In addition, pe r f o rming the LLRT test on a more frequent basis has an adverse impact on the required-test equipment (LRMs).
The leak rate monitors (LRM) used for Type C LLRTs are required to be shipped off-site for calibration. During operation and cold shutdown when containment integrity is set, the LRM(s) would need to he ' San inside the containment. .If the LRM is contaminated and then usa' bis A . Je
-decontaminated, this would prevent its calibration and render it
- unus able .- This equipment is expensive and the number of monitors available for use is limited. During refueling outages,,a staging area is set up outside containment in a low dose, non-contaminated area and hoses are run inside to the various containment isolation valves. This is possible due to the relaxed containment integrity requirements. These precautions are taken to prevent the LRMs from becoming contan.inated.
- 8. - Applicable 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.
- b. Roquesting additional relief for the 1/2CV8113 check valves, Rev. 5.
- c. Added additional technical infomation and justification, Rev. Sa. l l
4.6 - Page 20 of 58 217(042292)
- ZD79G/123 l
l' I
. . - ~ . . . - . . . . . .
Rsvisica Sa
-RELIEF REOUEST VR-10
- 1. Valve Number s ' IIA 065 2IA065 Outbd Instrwnent Isolation
.11A066 2IA066 -Inbd Instrument Isolation IIA 091 21A091 Inbd Isolation Supply Check 2.. Number of Items: '6 3.. ASME Code Cateoory: A and AC
- 4. -ASUE Code,'Seglion:XI Requirementes Exercise for operability: full stroke timing and exercising (St) of Category A.& B valves; full stroke and back flow testing (Ct/B&' of Category C valves _.every'3 months per IWV-3411 and INV-3421, respectively.
Per INV-3412.for power operated valves, and IWV-3522 for check valves,
= valves that cannot be exercised daring plant operation shall be Especifica11y-identified by the owner and exercised during cold shutdowns.
'rallisafe test actuators per INV-3415.
-5. Rasis for Relief: .
The 1/21A065 and'1/2IA066 valves are air-operated containment isolation valvesEfor.the instrument air line to containment; they fail closed on
. loss,ofl air supply / power. The 1/2IA091 check valves are in the supply air l line to theJ1/2IA066 valves, which taps off the line between the two j isolation valves.1These check valves also perfc- m a containment isolation function in the closed position. l l
LStroke testing of these-valves during plant operation or cold shutdown {
would,-by design,11solate the airLoperated instruments and valves inside Lthe-containment building. The loss-of instrumect air to. containment
-creates a-very serious situation and should be avoided for testing
- purposes. ~This situation involves loss of pressure control via the !
spraysi' letdown isolation, and loss ofLcharging flow. Additionally, loss of- air would . leave the pressurizer PORVs with only their accumulators as E
-an air supply, limiting'the number of operations available.
i
- 6. -Alternate Testing:
?.These valves will be exercised during refueling outages.' The back flow (Bt) test for the 1/2IA091 check valves will be done in conjunction the Appendix-J' seat'. leakage test.
Thisitesting period will.be each refueling outage as a minimum, but no .
more frequently than'once per quarter. (
)
- 7. Justificatinn l I
The full stroke-exercising of the instrument' air containment isolation valves during unit power operations or cold shutdowns introduces the ,
possibility of causing major operating perturbations and/or personnel .
-safety concerns during the test. Additionally, should these valves fall !
to re-open during testing activities, the transient would be exacerbated. !
4.6 - Page 21 of 58 L217(042292)
ZD79G/124
R3 vision Sa j i
l l
imLIET RE W EST VR-10
- 7. Justificat3nn (continued)
The failure of these valves in the closed position, as a result of testing activities during plant operation or cold shutdown, would subsequently isolate the air operated instru3ents and valves inside the containment building thus resulting in one or more of the following scenarios:
A, Loss of Pressuriser Pressure Control The pressurizer spray valves 1/2RY455B & C and the pressurizer auxiliary spray valve 1/2CV8145 would f all closed and not be available for pressurizer pressure control.
B. Loss of Chemical Volume Control System Letdown Flow (both normal and excess) and Charging Flow The loss of instrument air would cause a disruption in the unit letdown flow paths resulting in pressurizer level increases. Such valves as the letdown orifice containment outlet header isolation valve 1/2CV8160, the letdown line isolation valves 1/2CV459 and 1/2Cv460, the letdown orifice outlet isolation valves 1/2CV8149 A, B&
C, the excess letdwon heat exchanger inlet isolation valves 1/2CV8153A
& B, and the regen heat exchanger letdown inlet isolation valves 1/2CV8389A & B would go to their f all closed positions. AdditionaAly, the ability-to normally make up reactor coolant inventory and adjust the reactor chemical shim (i.e. normal boration/dllution) would also be lost as the regenerative heat exchanger inlet isolation valves 1/2CV8324A & B would fall to their respective closed positions.
An additional detrimental effect would be the thermal cycle imposed on the reactor vessel nozzle upon restoration of system operation.
C. Loss of Component Cooling to containment Penetrations The loss of instrument air supply would cause the penetration cooling supply flow control valve 1/2CC053 to go to its fail closed position.
The loss of penetration cooling would result in elevated temperatures being imposed on the penetrations being supported by the component cooling system.
D. Loss of Personnel Breathing Air The loss of instrument air supply to the service air downstream isolation valve 1/2SA033 would cause this valve to go to its fall closed position. This loss of service air in the containment building would eliminate the normal source of supplied breathing air needed to support numerous maintenance and component inspection activities in a contaminated radiological environment.
4.6 - Page 22 of 58 217(042292)
ZD79G/125
i Rsvision Sa !
l EELitr.Ju:ouzSLYA-10 8.. Applicable Time Parlod This relief is raguested once per quarter during the first inspection interval.
9.- byproval Statu18
- a. Revised (to address NRC concerns) in Byron's response to SER 12/16/88 (Byron Station Letter 88-1321).
- b. Added check valves 1/2IA091, regarding back flow testing. Rev. 5.
- c. Added additional technical information and justification, Rev. Sa. f
- f -
4.6 - Page 23 cf 58 217(042292)
ZD'i9G/125
/
1/2 IA091 i ?
a E'
i C
E T M IA091
/
' 4 ex Vs r3 as A $ $
IA066 IA065 Inboard Cnmt Outboard Cnmt Isol Viv isol Viv
~
GENERAL DIAGRAM FOR INFORMATION ONLY
Rsvision 5 EELIEF REQUEST VR-11
-DELETED.
Deleted relief request VR-11 per EG&G Idaho (Technical Reviewers) recommendation to Byron. This was a request for extension of position indication tests from every two years to every three years.
4.6 - Page 24 of 58 217(042292)
ZD79G/127
. . __ ._ . ~ . _ _ . _ _ ._
-Revision $
A+ ,
RELIEF REOUEST VR '1. Eglve Number t -Valves that normally stroke in 2 seconds or less VALVE I VALVE I 1MS018A-D ~ 2MS018A-D IPS228A,,B' 2PS238A, B IPS229A, B- 2PS229A, B 1PS230A, B- 2PS230A, B 1RC014A-D 2RC014A-D 1RY8033- . 2RY8033
. 2. E Number of Items: 30
- 3. ASME' Code Category: A&B 4.- ASME Code,Section XI'Reouirements:
Verification, by._ trending of power _' operated valve times, that an increase-
.in stroke' time of 50% or. mots, from the previous test,-does not occur, per IWV-3417(a).
1$. .: Rggis for Re1lifa Minor _ timing inaccuracies, .with sr..all stroke. times can lead to substantial increases (percent ~ wise).._in stroke times. -For example, a valve with a
. stroke time of I second in an initial test, and 1.6 seconds in the subsequent' test, has experienced an apparent 60% increase in stroke time.
If the accuracy _requiroments of INV-3413(b)-are utilized,'it could be ,
argued that stroke times'between 1 and 2-seconds could constitute as much as a;100% increase in stroke time when,~1n fact, only a 0.2 second increase occurred. For instance, if the initial time was 1.4 seconds, (measured to the nearest second is 1.0 second) and'if the next time is then 1.6 seconds, (measured to the nearest second is 2.0 seconds) the percent increase 'is
_100%.
6.- Alternate Testing:
Fast ~ acting valves .can-be defined as those . valves that normally stroke in 2 seconds or.less. -No trending of stroke time.will be tr,;uiredi and upon exceeding _2 seconds, corrective action shall be taken immediately in accordance with IWV-3417(b).
4.6 - Page 25 of 58 217(042292)
ZD79G/128
.~ , - - , , . - . . . . - - - - . . - ,
4 2 8 aN E d .a -p , . _ _
J 5 , 0 55 f E si l$ % $3 s ,un hh hh 0 a * -+ $ d 8 8
8
- e e = w w
, El &: ~- g..
l$ $ eOKj lD DXl 11 gx 11 sp _ e j it oxi xcip Abdh$
NO VW N3d e.4 t t t t <
fd fd fii} fd
.h r .- .
5
-. r -
5.
~-
r - .NrU -
1 S S" S S" xx yx xx xj
.k. .
.f. .f. .k.
R3 vision $
EELIII_REWEST VR-12 l
- 7. JusLLikcnkkunt for short stroke times, the trending requirements are too stringent for the accuracles speelfled in the Code. The alternative specified will adegastely maintain the system in a state of operational readiness, while not imposing undue hardships or sacrificing the safety of the plant.
- 8. Applicable Time.Perigdt This relief is requested once per quarter, during the first inspection Interval. i
- 9. AppI&ol Statu.at
- a. Revised (to address NRC concerns) in Byron's response to SER 12/16/88 (Byron Station Letter 88-1321).
- b. Relief granted per NRC Generic Letter 89-04.
(
l 4.6 - Page 26 of 58 l
.217(042292)
ZD79G/129
Rovlsion 5 RELIEP EEOUIST VR-13
- 1. Valve Number 1 1DGU182A,B 2DG5182A,B 1DG5183A,B 2DG5183A,B IDG5184A,B 2DG5184A,B 1DG5185A,B 2DG5185A,B
- 2. Number of Item &t 16
- 3. ASME Code _.CAttgary: B&C
- 4. AStiE_ Code.Ses.tinn XI Regn11emantal These valves are not with!n the scope of ASME Code,Section XI, Subsection IWV tequirements. However, the requirements for stroke timing and trending of the valves associated with the Diesel Air Start System are being mandated by the NRC as an augmented testing requirement pursuant to 10CTR50.55 (a) (g).
Therefore, valves associated with the Diesel Air Start System shall be exerci,ed tu the position required to fulfill their function during plant operation per INV-3412 and' IWV-3522. Additionally, the atroke testing of power eperated valves shall be measured to the nearest second and such stroke times trended to document continued valve operational readiness per IWV-3413 (b) and IWV-3417.
- 5. Basis for Relief The monthly Diesel Generator testing program, outlined in Braidwood Station's Technical Specifications and implemented by station operating procedures, exceeds the intent of the quarterly valve testing program which would hs required by ASME Code,Section XI. Additionally, the stroke timing of solenoid operated valves associated with the Diesel Air Start System is impractical due to the f ast actuation of these valves.
1 Alternate Taiting The performance of Braidwood Station's Diesel Generator operability monthly surveillance will verify the operational readiness of the valves
~
associated with the Diesel Air _ Start System.
I 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 operated and self-actuated check valves associated with the Diesel Air Start System can be adequately demonstrated.
4.6 - Pars 27 of 58 l'
217(042292)
ZD79G/130
R3 vision 5 Rf11Er REOUIS7_.Y.R-12
.7. dustificatisms !
Proper valve operation will be demonstrated on a monthly basis by the verification of Diesel Generator air start capability. Such verification will compare the air pressures contained in the receiver t.anks both before and after the Diesel Generator start, thus verifying the operab(*. tty of the air start control valves. The proposed testing methodo1.g; at the increased frequency satisfies the intent of the Section XI reguirements without posing undue hardships or difficulties.
- 8. Applicable Time Period:
This relief is requested once per quarter during the first inspection interval.
- 9. Appinyal Stat.ust
- a. Relief granted NRC Generic Letter 89-04.
4.6 - Page 28 of 58 217(042292)-
ZD79G/131'
'M Rovision 5 EILIEr REQUEST VR-11
.i.
-DELETED-
.>e, ,
Deletedrelief!;qq'ue'stVR-14. This was a request for exemption for pocition indicatIb~g t'ests for solenoid operated valves. Alternate testing allowed by the ASME Code will be used instead.
r 4.6 - Page 29 of 58 217(042292)
.ZD79G/132-
. _ _ . _ _ _ _ _ . ~ . , _ . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ . _ _ . _ _ _ . _
R3vlelon 5e
-I AILIR_RIQUIST VR-15 1.' Yalve NumbetAl
- 1RH8705A, B 2RH8705A, D RH Suction Pressure Rellef 1CV8546 2CV8546 CV Pump Combined Suction 1CV8481A, B 2CV8481A, B CV Pump Disch 15I8815 2S18815 CV Injection Combined Har :
ISIB900A-D 2SI8900A-D CV Injection to Cold Legs
- 1S!881SA-D 2SI8818A-D RH Injection to Cold Legs ISI6581A,B 2SI8841A,B RH Injection to Hot Legs ISI8819A-D .2SI8819A-D SI Injection to Cold-Legs isI8905A-D 2S18905A-D SI Injection to Hot Legs ikie '9A/P 2SI8949A/C SI/RH Injection to Hot Legs inf34. ^ '418949B/D SI Injection to Hot Legs
- These checw vij + 4 <gte 44d.ed after the initlal SER approval.
'SEE Section y os 4 -la relief request for current status and !
approval information .
- 2. Number _of-Valvent. 56-(28 talves per unit) 4
- 3. ASMI_ Code' Category 3- ACL
- 4. ASME Code, Section_XI.Regnitamentas '
Check valves that cannot be emereised during plant operation shall be
.specifically~1dentified by the owner and the11 be exercised to the .
position (s) required'to fulfill their function (Ct/Open; Bt/ Closed) during cold shutdowns per'IWV-3522. }
5.- Rasis for Relieft l The ' closure test- for' the 1/2RH8705A/B (RHR suction line isolation valves a pressure' relief) . check valves can only be verified by performing a local i leakage rate test (LLRT). The opening test'(pressure. relief function) is performed by isolating the PH suction piping penetration, connecting a ,
primary water supply and pressure gauge, and recording the highest {' !
~!
pressure obtained prior to valve ' opening. : Performing this test requirus placing.aitrain of residual heat removal in an inoperable condition and requires that the'RCS be depressurized with no Reactor Coolant Pumps
- running. In' addition,-Technica1' Specifications specifically exempt the RHR ,
i suction isolation valves from a LLRT followlng flow through the valves.-
. l The fu11' stroke esercising of check valves not stroked quarterly is _
l required' to be performed during cold shutdowns by the . Code. However, the j stroklng of check valves 1(2)SI8815, 1(2)S18900A-D, 1(2)SI8949A-D, and l ,
1(2)SI8841A-B, associated-with Emergency Core Cooling System, during cold shutdowns w111' Induce thermal stresses on their respective reactor vessel nozzlesLas the Reactor Coolant System (maintained approximately 180'r) is injected with water from the Refueling Water Storage Tank .(maintained
'approximately 65'r.
{;
}
4.6 - Page 30 of 58
- 217(042292)
ZD79G/133
_ . .. _ __ - . . . - . . u_.._.._ .-
Revision 5a EELIEL_RIQUISLVA-15
- 5. Dasis_ tat _Et11tt s (continued)
There are further concerns regarding the RCS boron concentration and limited volume in the pressuriser to receive the volume of water needed to be injected to exercise these valves. 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 is obtainable only by full flow through the 1(2)SI8815 and 1(2)SI8900A-D (in series). 1 l
Additionally, Braidwood Station Technical Specifications require that all Safety Injection Pumps, and all but one Charging Pump, to be inoperable during Modec 4, 5 and 6, except when the reactor vessel head is removed (the reactor head in removed only during refueling). This requirement minimizes the possibility of low temperature over pressurization (LTOP) of the Reactor Coolant System. Therefore, check valves 1(2) SIB 819A-D, 1(2)S18905A-D, and 1(2) SIB 949A-D, cannot be full stroke exercised during both planned and unplanned cold shutdowns, as required by IWV-3522. ;
In addition to the stroke test exercise used to verify operational readiness of these check valves, the act of such stroking causes the necessity for the Technical Specification required leakage rate test 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 a planned outage (longer for unplanned) if these valves are exercised, this creates additional radiation exposure to workers who must connect flowmeters and differential pressure gauges directly to pipes containing radioactive fluids inside high radiation areas. '
i
- 6. Alternate __.Tetting:
The 1/2RH8705A, B check valves will be exercised (Ct) each refueling outage. This frequency is at least once per 18 months, to be performed during a reactor refueling outage.
The back flow test of these pressure isolation check valves can only be individually verified by performing 3 local leak rate test when pressure in the RCS is greater than 350 psig. Braidwood Station's Technical Specification 3/4.4.6.2 requires routine leak rate testing to be performed on the RCS pressure isolation (PIVs) check valves:
- 1. At least once per 18 months;
- 2. Prior to entering Mode 2 whenever the plant has been 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 /> or more if leakage testing has not been performed within the previous nine months;
- 3. Prior to returning the valve to service following maintenance repair, or replacement work on the valve;
- 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 operation or flow through the valve, except for the 1/2RH8701A, B and 1/2RH8702A, B.
Based on this, Braidwood will back flow (Bt) test these check valves on the same frequency.
The full stroke (Ct) exercise test of these check valves will be performed at each refueling outage.
4.6 - Page 31 of 58 217(042292)
ZD79G/134
Revision $a RELIELREQUESLYR .15 7 dultiLicat12D8 The 1/2RH8705A, B check valves function in the open direction when both of the associated containment isolation valves (CIVs) are closed during an accident condition involving adverse containment conditions. Each valve opens in a manner that will bypass the upstream isolation valve to re11 eve excess pressure, Exercising (Ct/Bt) these check valves on a refueling frequency will adequately maintain this portion of the RH system in a state of operational readiness without causing unnecessary personnel ;
radiation exposure, possible delays in startup of the reactor, and takes
- away the availablilty of the backup / redundant train of residual heat i removal, reducing plant decay heat removal capab111tles.
Otroke exercising (Ct) of check valves 1(2)SI8819A-D, 1(2)SI8949A-D and 1(2)SI8905A-D can only be safely performed in Hode 6 with the reactor ;
vessel head removed. Also, these valves cannot be full stroked without I
- exceeding Technical Specificatlon 3/4.5.3 requirements, which requires that all-safety injection pumps be demonstrated Anoperable when RCS temperature is less than 350'T. Stroke exercising check valves !
-1(2)S18819A-D, 1(2)S18905A-D and 1(2) SIB 949A-D at least once per Reactor !
Refueling mode of operation will insure compliance with Draidwood Station Technical Specifications and reduce the risk of a j low-temperature-over-pressurlsation (LTOp) event of the Reactor Coolant !
System.
It is impractical to full stroke test the 1(2)CV8481A, B, 1(2)CV8546, and 1(2)SI8815, 1(2)SI8900A-D and 1(2)SI8841A, B check valves as it will: 1)
Induce unnecessary thermal strasses to the reactor vessel nossles and i reduces the margin of safety for brittle fracture prevention, 2) Cause the necessity to perform the Technical Specification required LLRT, and 3)
Inject large quantities of 2000 ppm borated water into the RCS which has a relatively small capacity in the pressuriser to receive it. Injecting high concentrations of borated water into the RCS will significantly impact the time required to restart the reactor at times in core life (greater than 9 months per TS 3/4.4.6.2), when boron concentration is maintained at a much .
Iower value (700 ppm). To dilute the RCS boron concentration, the feed and bleed process will greatly iner, case the amount of high grade water processed and rejected f rom the site. This could increase the amount of radioactive effluents discharged to the environment.
The local leakage rate tests require personnel involvement from operations '
(valve manipulations and out-of-services), radiation protection (radiation surveys and monitoring), instrument maintenance (installation of test equipment), and technical staff (leakage collection and test supervision) that results la increased exposure. This excess exposure conflicts with station ALARA goals and and radiation work practices. The majority of these tasks are located in high radiation areas inside the containment.
i In-addition, performance of leakage testing on a 18 month (refueling) frequency is adequate to demonstrate structural integrity of valve seating capability per both Technical Specifications and ASME Section XI i
requirements; this is their safety function in the closed position.
I 4.6 - page 32 of 58 217(042292)
ZD79G/135
. - . . . . _ _ _ . . . .-. - . _ _ _ - . . _ ~ _ _ .. _ _ . _ -
Rsvision So EEk1EE REQUESI YE 15
- 8. Appl.lcable Time Perip4:
This relief is requested once per quarter during the first inspection Interval.
- 9. ApproXal Statust
- a. Revised (to address NRC concerns) in Byron's response to SER 12/16/90 (Byron Station Letter 88-1321).
- b. Relief granted per SER dated October 15, 1991 (Rev. 4/4A) fort 1/2SI8819A-D, 1/2518905A-D, and 1/2S!8949A-D at refueling outage only:
1/2CV8481A&B, 1/2CV8546, 1/28I8815, 1/2S18841A&B, and the 1/2SI8900A-D i >
at certain cold shutdowns and during refueling outages. l
- c. Added check valves 1/2RH8705A,B and 1/2S18818A-D for closure testing, and refueling frequency for exercising the 1/2R118705A, B pressure reliefs. In addition, requesting refueling frequency for the following: 1/2CV8481A&B, 1/2CV8546, 1/2SI8815, 1/2SI8841A&B, and the 1/2S18900A-D SI check valves. These changes are per Rev. 5.
- d. Added additional technical information and justification per Rev. Sa.
b
(
e l
I l 4.6 - Page 33 of 58
! 217(042292) l, ZD79G/136 l
0 99 !"
5
- r. D8 i!!! es :
'" 8 . i$
66 --
"la: ad Qi 8eg fa :fa :: : :; i i S 12 : f_1 lT hld -
} t eti ja :
If .
t 1
- :: e ,1!
. c.
r r tr t r r; b, ~ , ', qs'
! !r t a
t a
a:
- et! ., 9: * -
$N
" sis l '
{N S 0 8' 3
a:l mum-
, m -
6a: *iFCi i e
+-8N e g.-f f
.Q g ..._h
'~
19 O c u o se: e;i I,i + ni u o- o ,
O
- 5 5 5 ii f I
- 4
% o o jat a :l la : la : a:I
....... .... Ist; aia:1 a:1 mMuummuunnumutuu ununummuu umaa muumu i ,
is :
's I
Al 15k3 j
+Ht-}
w
~
I _
-g , , . =
~
- 4;-:d9gli ?"
p
'" II !!!_c- I n_ II!!!!!
- tt-:Otti c
~
% I L
- 9-:egli a agl ia gi s I la : la :
i n
. - .- . ~ , ~ . ~ .
e Kevision 5 RELIEL350UESLYR-1ft
- 1. . Yalve NumbgI3 4 ISI8811A, B 2SI8811A, B
. 2. Ibaher_9L_YALY11 4'
- 3. ASME code Cattgnry: B
-4. $EME_ Code,Section XI Requirements:
Valves that cannot be_ exercised during plant operation shall be specifically ldentified by the owner and shall be full stroke exercised during' cold shutdowns per IWV-3412.
$. Ragis for Relief The full stroke esercising of valves not stroked quarterly is required to be performed during cold shutdowns. However, the stroking of the Containment Sump Outlet Isolation valves,1/2SI8811A,B requires the
-suction of the Residual Heat Removal pumps to be drained, thus rendering one train of fthe system inoperable.
For Cold Shutdown operations with the Reactor Coolant Loops filled and one train of Residual Heat Removal declared inoperable, Braldwood 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), Brai6 wood 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.
~
-Tor 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),
Braldwood Statlon's Technical-SpecificationL3.4.1.4.2 would preclude the testing of the-Containment Sump Outlet Isolation Valves as. it mandates -
that "two residual heat : removal- (RHR) Loops'shall be operable and at least one RHR Loop shall be in operation.
- 6. AltgInnte Testing:
Braidwood Station will full stroke exercise the Containment Sump Outlet Isolation Valves,11/2SI8811A, B during refueling outages vice cold shutdown.
4.6 - Page 34 of 58 217(042292)
- 2D790/1371 0
Revision 5 EII,.1EL_ REQUEST VR-16
- 7. Justification The full stroke testing of the 1/2SI8811A, B valves; in conjunction with system draining, filling and venting of each train, accounts for an additional six days (3 days per train) of scheduling requirements and increased radiation dose to operators and radiological control personnel.
Processing of thousands of gallons of contaminated water, and subsequent required 11guld effluent discharges would also result f rom the draining, refilling and venting of the RHR system. This time duration required to perform the surveillance testing of the Containment Sump Outlet Isolation Valves during Cold Shutdown activities, could, as a result, cause a violation of the action requirements for Braldwood Station's Technical Specifications 3.4.1.4.1 and 3.4.1.4.2. The violations would occur since these action statements require (as noted in their respective foot note sections) the return of the inoperable residual heat removal loop to service within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, if such loop was removed for surveillance testing provided the other RHR Loop is operable and in operation.
In addition, NRC Generic Letter 88-17, Loss of Decay Heat Removal, highlights the consequences of a loss of RH during reduced Reactor Coolant System inventory (below three feet below the reactor vessel flange). If
- the operating RH pump is lost due to air entrainment, and the other train is inoperable for the stroke test, then the " operable" train must be vented to restore decay heat removal. Under yntit conditions, boiling in the core would occur in approximately 10 minutes, the core would be uncovered in approximately 30 minutes, and fuel damage would occur in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Given the apparent disparity between the Technical Specification time requirements for an inoperable RHR Loop return to service (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and the time required to perform surveillance stroke testing of the Containment Sump Outlet Isolation valves (3 days) during Cold Shutdown, the proposed alternate testing frequency of refueling outage periodicity will adequately maintain the system in a state of operational readiness, while not imposing undue hardships or sacrificing the safety of the plant.
- 8. Applicable Time Periodt This relief is requested once per quarter, during the first inspection interval.
- 9. v Status.:
AppIn.al
- a. Revised (to address NRC concerns) in Byron's response to SER 12/16/90.
4.6 - Page 35 of 58 217(042292)
ZD79G/138
Revision So RELIIT RE0QEST VR-17
- 1. EalYt_ilwnbara ISX101A 2SX101A
- 2. Number of Valves 2
- 3. ASMI_Cade category: B '
- 4. hSME code.Section XI Requiremggts:
- a. Full-stroke time power operated valves per IWV-3413(a) and IWV-3413(b).
- b. Fall-safe test actuators per IWV-3415. ,
- c. Take corrective action per IWV-3417(a) and IWV-3417(b).
- 5. Rania_inr_lalini The 1/2SX101A valves are the essential service water cooling outlet isolation valves for the motor driven auxiliary feedwater ( ArW) pump lube oil coolers. These solenoid valves are completely encapsulated per design (valve stem not visible) and do not have any type of limit / reed stitches for remote position indication, or that can be used to trigger a change in valve stem position. These valves are energized closed by the pump's control switch being in the OFT position. On pump start, when the control switch is taken to ON, a contact opens de-energising the valve's coll.
This causes the valve to open by both spring force against the plunger and differential pressure accross the main disk caused by the pilot disk l openings this lifts.the main disk up into the body allowing flow through the valve (refer to Figure 1 for a simplified schematic of the valve).
These valves cannot be stroke-timed using conventional Code stroke timing techniques (stopwatch - using switch to light timing) without a system modification to add position indicating switches. These valves change !
position in a matter of milliseconds (e.g. rapid acting), and because l there is no means to control the dif ferential pressure across the valve, !
establishing a repeatable stroke time test to meet the Code requirements is not prectical or possible. _Using Generic Letter 89-04, Position 6, for rapid-acting valves is not feasible either due to these valves stoking in the 70 to 250 milli-second range.
Using available acoustic technology, it is possible to monitor certain valve characteristics by analyzing the acoustical signature trace, which is based on capturing structural borne noise caused by the movement of the valve internals. The acoustical trace is obtained by mounting an accelerometer to the valse body at a pre-selected Jocation and recording the opening event. These accelerometers are very similar to those used In the loose parts monitoring system. By converting the analog signal from the accelerometers into a digital signal using an analog-to-digital card in a computer, the data can be stored in a file. The non-safety related sof tware program which is used for check valve acoustic monitoring is used for data analysis. 1 4.6 - Page 36 of 58 217(042292)
ZD79G/139
Revision Sa EELIEI 2121ES.TML-11
- 5. Bnsis for Rellsis Impacts and rubbing of internals can be viewed and evaluated using similar techniques to those developed for check valve acoustical monitoring. The full stroke time that can be obtained from the acoustic trace is often difficult to analyze for a specific value. This is due to the variations in the differential pressure across the main disk, which can cause the valve to stroke slowly, resulting in a small magnitude Impact event which cannot be distinguished f rom the flow noise. By understanding the principles of valve operation and construction, the acoustical events provide a picture, or signature of the valve, that can be used to evaluate valve performance and condition by comparison with previous traces and/or changes in the " key" events within the valve.
- 6. Alternate Tgatjng:
The 1/2SX101A valves will be verified to open during each quarterly ASME surveillance of the motor driven auxiliary feedwater pumps by observing that the temperature upstream the valve changes when the pump starts.
This is Indirect evidence of flow through the valve, and la considered to ,
be an acceptable method of verifying that the valve opens (enercises). In I addition, observing that proper ATW pump Inbe oil temperatures are able to be maintained during the test run, serves as more indirect evidence to i
substantiate the valve's opening capability. These valves are also stroke tested in the same manner during the ArW pump operability run required by Braidwood Technical Specifications, on a monthly basis.
In addition to the above, these valves will be tested using acoustic monitoring technigues prior to each refueling outage. Based on test results, additional maintenance activities may need to be initiated to invesitgate anomolles (electrical or mechanical), or to require internal inspections and/or repair, as required. The temperature indicator on the cooling water outlet also serves to help determine valve seating l condition, this will also be used in evaluating tho valve's condition.
- 7. Justification:
The temperature of the SX cooling vater exiting the lube oil cooler is i monitored, just upstream of the SX101A valve, and provides information regarding both seating and opening capabilities. Normally, the differential temperature f rom pump start (ambient air temperature in the t Aux.-building) to when the bearing lube oli temperature stabilizes j (approximately intake lake water temperature), Indicates that the valve opens. In addition, an acoustic type diagnostic test is used to monitor valve condition. The alternate testing will adequately maintain the ATW system in a state of operational readiness, while not sacrificing the safety of the plant or imposing undue hardships associated with a valve !
position Indication modification. I 4.6 - Page 37 of 58 217(042292)
ZD79G/140 l
Rovision $a EELIIf_REWISLR _11
- 8. Applisab1m_.Ilme_Firiodi This relief is requested once per quarter during the first inspection interval.
- 9. AppI.Dral_SlatRE I
- a. Relief is being resubmitted per Rev. 4/4A SER response.
- b. Changed to incorporate acoustic testing, Rev. Sa. l o
4.6 - Page 38 of 58 217(042292)
ZD79G/141 1
- - _ _ - - _ _ _ - _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _a
-Rsvision Sa.
i i
ar*1rr_araars u n-12 ;
riouns 1 j i
~
PLUNGER x \s/
SPRING
)h v V COIL CORE i !
STEM i
i MAIN DISC 7 DISC CONNECTING ,
PILOT DISC o N PIN MAIN DISK SEAL
[
/ RING I
. SUPPLY ORIFICE / ' l PILOT ORIFICE s \ OUTLET-AIAIN SEAT l- i SIMPLIFIED SCIIEMATIC OF TIIE 1/2SX101A PILOT OPERATED - ETC I: 4.6 - Page 39 of 58
'217(042292)
ZD79G/142 H
_ _ . _ . , _ . . _ ~ . _ . . , , . . _ _ _ _ _ _ . . _ , _ = - _ . _ _ , _ . , . , _ . . - . . _ . _ _ . . . , , .
Rovision So RELIEF REOUEST VR-11 Deleted per Revision Sa. Valves are passive and only require leak testing per IWV-3700.
4.6 - Page 40 of 58 217(042292)
-ZD790/143
t* Ravision 5a .
1 1
RELIIf REQEST VR-19 jar ^ _ ,.
i 4r'
- 1. . Valve Numbglst 1Ar001A' 2Ar001A
- 1Ar001B 2Ar001B
- 2. Number of Valyga 4
- 3. ASME code catrgory* C,t2'LX-J, t
- 4. ASME Code. 52etion XI Regg{tements e Exercise check valves to $hE position required to fulfill their function ,
(Bt/ Closed, Ct/Open), unless such operation is not practical during plant operation, per INV-3522.
RAll.s for Relldt
~
5.'
The 1/2Ar001A/B valves _are the suction check valves to the ATW pumps from the condensate storage tanks',' and function to prevent backflow of essential service water if'that suction source is required.
It is undesirable to'!ull stroke'open these valves quartertly due to the i transients placed on the feedwater system and the thermal stresses imposed on the steam generator (S/G)- nossles (refer to program note 12).
t
' i With respect to acoustically,' testing these valves to prove closure, versus disassembly, the operating surveillance procedure used for the auxillary feedwater (ArW). check valve ' cold shutdown full stroke test is written to test a single train of ArN=at a time. With an ArW pump running on mini-flow recirculation, flow is initiated to each S/G on a gradual basis, while. simultaneously reducing feedwater flow. As soon as the required flow
' data is obtelned, APW flow is: gradually reduced, while simultaneously
' increasing.feedwater flow, t6 minimize feedwater flow perturbations to the S/Gs. Due to this gradual change in flow, the open and close acoustical impacts cannot be observed from that of the flow noise.
However,the'acousticdatathkenduringthe18monthdualpumpinjection ,
test, has provided suf ficien3 data to determine valve disk closure (refer to SMAD Report M-6479-91, dated 10-28-91).- This test is. scheduled during the shutdown process, preceding reactor refueling, due to the large ;
. transient placed on feedwater flow and the thermal stresses imposed on the S/Gs.
The application of.RCM (Relihbility' Centered Maintenance) to the Ar system has. both concludedL and recommended' that performing acoustic monitoring on a 3 year frequency is sufficient to~ detect if the check valves fall to
.close. The failure analysis? process required that the functional failures identified be evaluated usl6g the failure modes and effects' analysis ,
(FMEA)..LThe THEA provides a" format'for identiflying the dominant' failure modes of' component failures' leading to a functional failure and the impact of each. component failure locally-at the component, on the system, and on
.the plant'.
4.6 - Page 41 of 58 217(042292)
ZD79G/144
Revision Sa EELIET REQUEST VR-19 4
- 5. DAala Icr._Relleil (continued)
Additionally, the closure capability of these valves cannot be verified adequately by performing a back pressure test due to the multiple boundary l 1 solation points. The system configuration makes it impossible to assign )
any observed leakage to any individual valve or component using standard ,
mass make-up or pressure decay techniques. ;
i
- 6. Altenutte Testing:
The 1/2Ar001A and 1/2Ar001B suction check valves will be acoustically tested for closure (Bt) on an alternating refuel frequency in conjunction
- with the ArW full flow test and coulpment response time of the ArW pumps. l The "A" train valve will be tested during one refuel outage, the "B" train valve will be tested at the next, on a bi-refueling outage frequency. The ,
open stroke (Ct) test _will be tested during cold shutdowns, or at least I once during each refueling cycle (approximately 18 months). l i
7 dnatificatigms Performing a pressure test to verify closure is impractical due to the system configuration. To perform this test it would be necessary to attach a pump or some_ other type of pressure source to a test connection and pressurize the line containing the valve. However, this line also contains many potential leakage paths (valves, pump seals, and instruments). It is not possible to assign a leakage value to any ;
specific path using available methods of seat leakage testing.
Maintenance history and previous inspections of these valves at both Byron
'and Braidwood' stations has shown no evidence of degradation or physical ,
impairments. Industry erperience, as documented in NPRDS, has shown no history of problens with these valves. A company wide check valve evaluation-addressing the "EPRI Application Guidelines for Check Valves in Nuclear Power Plants" revealed that the location, orientation and application of _these valves are not conducive to the type of wear or ,
degradation correlated with SOER 86-03 type problems.
Acoustic testing provides ample information relative to valve condition, without physically taking the valve apart for visual inspection to prove valve closure. These valves are of the same design (manuf acturer, size, model, and materials of construction) and have the same service conditions, including orientation. Upon abnormal-or questionable acoustic test results, the valve will be scheduled for disassembly and-internal-visual inspection. The results of this inspection will be used to further evaluate the standby train valve as well, for possible action. This type of alternate testing provides more than adequate assurance of both valve ,
functional and operational requirements. l The alternate test method is sufficient to ensure both functional and operational requirements are met based on RCH failur6 mode and effect analysis for these valves.
4.6 - Page $2 of 58 217(C42292)
ZD79G/145
__ ._ ___ _____ ___ _.m _ _. , - . . _ _ -
~. - . _ _
Rovlslon So BELIET. REQUEST VR-19
- 8. Applicable Time E r.ind:
This relief is requested once per quarter during the first inspection ;
. interval.
- 9. Approval Statutt
- a. Relief granted per NRC Generic L'etter 89-04, for Rev. 5.
- b. Changed to incorporate RCH recommendations using acoustic monitoring techniques, Rev Sa.
l 4.6 - Page 43 of 58 i
l '217(042292)
ZD79G/146
R3 vision Sc Epp1Er REOUEST VR-20
- 1. Valve Numbers: All Power Operated Valves, except those identified in VR-12 (rapid-acting valves)
- 2. Number of Yalvest Various
- 3. ASME Code Cate_ggry: A and B l l
- 4. ASME Code,Section XI Requiremgat Subarticle IWV-3417(a), " Corrective Action"
- 5. Basis for Relief The Code requirement for increased frequency testing is based on a comparison between the current stroke time and the previous stroke timo. l Depending on the stroke duration and the percentage increase, monthly !
testing may be required. This approach, if not checked by trending, allows l
for the threshold for more frequent testing to slowly creep up over time. j For example, an increase of 10% at each quarterly test could take place l over a period of one year without any action being required. This variable limit is also difficult to administer because the limit is not a permanent entry in the test procedure.
A more appropriate method to be used should be based on an empirically derived fixed Ihnit using valve operating history, valve condicion and comparison with other valves of similar design (valve size, valve type, and actuator type). This allows for a more thorough review in determining what the " reasonable deviation" f rom the average / reference stroke value should be for an individual or group of valves.
For those valves that are identified for stroke testing in cold shutdown or refueling only, these valves cannot be placed on sonthly testing for ,
the reasons already presented in the valve test program. The Code does nJt i provide any direction for these frequencies of test, as to if these valves i are even to be included in the context of INV-3417(u). I
- 6. Alternate Testir.g:
For all power operated valves which normally stroke in greater than two seconds, an " Alert"' range will be established based on reaching a given percent increase from the reference / average value. The maximum limiting
.value of full stroke is established per Technical Approach and Position, VA-04, ;
The reference value used to determine the alert range will be reconfirmed following maintenance activities that could affect val e stroke time, or a new limit will be established bascd on the new stroke time.
4.6 - Page 44 of 58 217(042292)-
ZD79G/147
R3 vision 50 i
Egurr REQUES*L_YJ-2D
- 6. Alternate Testing 1 (continued)
For valves that can only be stroke timed in cold shutdown or refueling, once the valve (s) enter the alert range, an evaluation will be perf ormed to determine the cause or the valve will be stroked at the next cold shutdown condition which allows it. stroking. These valves do not degrade from frequent operations compared to valves in frequent usage, therefore, stroking the valve at the next cold shutdown is sufficient to monitor for degradation.
The followiC; criteria will be used as a starting point in evaluation of -
this fixed ALERT RANGE for power operated valves:
SOVs/HOVs/AOVs - Less than or equal to J')_siqnnds l ALERT RANGE VALUES: (1.50)(Tref) I I
SOVs/HOVs/AOVs - Greater _than 10 seggads: !
ALERT RANGE VALUES: (1.25)(T,,g), or (Tref +10 see) !
HOVs - Lgsg than or equal to 10 seconds:
- ALERT RANGE VALUES: (1.25)(Tret) l i
MOVs - Grmater than 10 seconda ALERT RANGE VALUES: (1.15)(Tref), or (Tref +10 sec) liQIE REFER to TECHNICAL POSITIO1 AND APPROACH VA-04 for additional related information REGARDING LIMITING VALUES OF TULL STROKE.
4 4.6 - Page 45 of 58 217(042292)
ZD79G/148 1
I
. _ _ - _ _ _ - - _ _ _ _ _ - - _ _ _ _ - _ - _ - - - _ _ _ _ _ _ - _ _ _ - - _ - - - .-__--___-__-_a
R3 vision So ECMEE.EEWIST VR-20
- 7. lutt111 ration:
Using fixed ALERT ranges based on the reference value established when a valve is known to be operating acceptably will ensure that gradual valve performance degradation is monitored and evaluated, by placing the valve on increased testlng frequency when the stroke time exceeds a fl=ed multiple of the reference value. This method is superior to that required by the Code in that the point of reference used to evaluate the performance trend on a valve remains fixed. This alternate test method uses the same percentage increase as the Code, except that its applied to the reference value.
Performing an engineering evaluation / investigation when a cold shutdown / refueling valve enters the Alert range or requiring the valve to be tested at the next cold shutdown is adequate to monitor the valve for degradation.
- 8. Applirahls Time Period:
This relief is requested once per quarter during the first inspection interval.
- 9. Appiaral Status I
- a. This relief-request is being submitted for Initial approval per Rev. Sa, L 4.6 - Page 46 of 58 217(042292)
'ZD790/149 i'
R3 vision 5 0
EELLIr RrourST VR 21 Withdrawn from Byron's program per SER dated 09/14/90
- Not used at Braidwood - Byron CNLY*
l a
i 4.6 - Page 47 of 58 217(042292)
ZD79G/150
. - - , . . - - - . ~ . . - . .. . . . . _ - . - - . _ _ . - .
Revision 5 E D fDJIS2__YJL-22 I
- Not used at Braldwood - Byron W Lyn
}
i 217(042292)
ZD79G/151 4.6 - Pa9e 48 of 58
Re. , So l RELIEr REOUIST_YA-11 Deleted by Revision Sa. Valves are passive and only require leak testing per IWV-3700.
i 4.6 - r. 49 of 58 217(042292)
ZD79G/152
Rovision 5a EELIEF REOUESI_YR:11 l
- 1. Valve NumbeII: 1/2PR032 l
- 2. Number of Valvest 2
'4. ASME Coddertion XI Requirements Exercise check valves to the position required to fulfill their function (Dt/ Closed), unless such operation is not practical during plant operation, per IWV-3522.
1 5.. Basis for Relieft )
The 1/2PR032 check valves are located inside containment in the return line of the process radiation monitor (PRM) (1/2PR11J panel) and are normally open. The only safety function these valves provide in the closed position is containment isolation, which is a redundant function to the outboard containment isolation valve. These valves open to allow return air flow back into containment. The 1/2PR11J PRM panel also provides the continuous means to monitor containment atmosphere during plant operation and cold shutdown.
The Code requires that these check valves be tested in the closed direction to verify their seating capability on a quarterly or cold shutdown basis. However, these valves can only be verified closed by performing the Appendix J, Type C local leakage rate test (LLRT) .
Performing the LLRT requires placing the system in an Inoperable status (removed from service) for an extented period of time due to the need to l 1solate portions of the system, and connecting a leak rate monitor (LRM). '
This would make the process radiation monitor (PRM) Inoperable requiring f entry into a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Technical Specification time clock (LCO). l l
This would cause undue hardship with no compensating increase in plant or !
component safety, if the Code requirements were imposed. l
- 6. Alternate Testing: ,
These check valves will be back flow tested each refueling outage by the j performance of their Appendix J, Type C seat leakage test, j
- 7. Justifications
' Performance of leakage testing on a two year (refueling) frequency is adequate to demonstrate structural Integrity and valve seating capability j per both Appendix J and ASME Section XI requircounts. There is no reason I to perform the Appendix J, Type C (Iow pressure air at approximately 45 l pilg) seat leakage. test more of ten than that already required by 10CTR50.
l This low pressure air test is adequate to monitor 'the valve's ability to seat; the smallest amounts of dirt, general corrosion, and foreign material can be detected between the seating surf aces by this test. i 4.6 - Page 50 of 58 217(042292)-
ZD79G/153
Revision 5a RILIEF._REWIST VR-24
- 7. dustifications (continued)
When a valve falls to meet its leakage criteria and repairs are required which make the internals accessible for inspection, a detailed visual inspection is performed per station procedures. The disassembled valve disc is verified to be capable of being full stroked and is checked for binding or failure of valve internals. Trained check s.1ve inspectors are utilized for this examination and the results are reviewed and evaluated by the station's Check Valve Coordinator. This is in addition to the root cause analysis performed per station requirements. !
Quarterly and cold shutdown testing requires a containment entry whlch would conflict with station ALARA goals and and radiation woth practices J in reducing exposure, and it is not prudent from a personnel safety standpoint. For personnel safety considerations, two individuals must always enter containment together, whenever containment integrity is set.
The performance of this test would require a minimum of three (3) shifts , I with personnel working in a high radiation area. j The leak rate monitors (LRM) used for Type C LLRTs are required to be shipped off-site for calibration. During operation and cold shutdown when containment integrity is set, the LRM(s) would need to be taken inside the containment. If the LRM is contaminated and then unabled to be decontaminated, this would prevent its calibration and render it unusable. This equipment is expensive and the number of monitors available for use is limited. During refueling outages, a staging area is i set up outside containment in a low dose, non-contaminated area and hoses ,
are run inside to the various containment isolation valves. These precautions are taken to prevent the LRMs f rom becoming contaminated.
This alternate test method is sufficient to insure the safety function of these valves is maintained at an acceptable level.
- 8. Applicable Time Period:
This relief is reruested once per quarter during the first inspection interval.
- 9. Approval StatL;,
- a. Relief is requested per Rev. 5.
- b. Added additional technical information and justification, Rev. Sa.
4.6 - Page 51 of 58 217(042292)
ZD79G/154
c _y c-f.
- JA_'
1/2PR032-1-
E' o
n n iM 1PR032
&'N 1
- nn n
- D <H> <H><H> G- -
.: i i
A .
.: n iI k r---tx3- 4 Q" i iT OOO :
RADIATION MONITOR 1PR11J i
i f
GENERAL DIAGRAM FOR INFORMATION ONLY i j
i
_ . . , ~ , ,
x a
< - R3 vision'5a D e RELIEF REQUEST VR-25
,m _ . - -
n 1. -- Valve Numbers: 1/2PS231A, . 1/2PS231B Jf 2J Hunber of Valves - 4 g 3.[ hSME Code category: -ACJ
- 4. -ASME Code,'Section XI Requirements Enercise chec'k' valves to'the position' required to fulfill their function (Bt/ Closed), unless such operation is not practical during plant operatioL, per INV-3522.
- 5. Basis for Reli1{s' KThe>1/2PS231A,B ch'eck.. valves are located inside containment in the return
~lineJof the post-LOCA hydrogen monitors and are normally closed. These check valves have a-safety function in the. closed position to provide
. containment isolation, which ~is a reduadant function to the outboard t
containment isolation valves. ;They function in the-open direction to allow the l sampled containment air to be returned to containment. ; ;
ThelCoos requires thatLthese check valves be tested in the closed direction to. verify their" seating capability on a quarterly or cold J
shutdown basis.- Howeverv these valves can only be verified closed by-
~ performing the Appendix J,, Type C local leakage rate test (LLRT).
Performing tho' LLRT requires placing the system in an inoperable status (removed froml service):-for'an'extented period of time due to the need to i isolate portions of the system, and connecting a letk rate monitor (LRM). .,
This:would make the' hydrogen monitor inoperable while the system is j j
' isolated.
t
~
ThisJwould cause. undue-hardship.with no compensating. increase in plant or component (safety, lf the Code requirements were imposed.
- 6. ? Alternate Testina These' check-valves will be:back flow tested each refueling outage by the
. j performance of their' Appendix _J, Type ~C seat = leakage test.
J 17. . Justifications-
,s Performance, of;1eakage testing on a two year (refueling) frequency is adequate.to. demonstrate structural integrity and valve seating capability ,
^ '
-per both: Appendix. J and ASME Section XI requirements. There is no reason l, -
j.
- ~to perform.the Appendix J, Type C (Iow pressure air at-approximately 45
- psig)~ seat ' leakage test more .of ten than that already required by 10CFR50. >
This lowfpressure air test;is adequate to monitor the valve's ability to j 1
saet; the; smallest amounts of dirt, general corrosion, and forlegn ltaaterial'can be detected between the seating surfaces by this test.
4.6 - Page 52 of 58 217(042292)_
} .
azD79G/155.
- e -m.
Revision Sa EEL. LEE._EEGIIST VR-25
- 7. duttifications (continued)
When a valve fails to meet its leakage criteria and repairs are required which make the internals accessible for inspection, a detailed visual inspection is performed per station procedures. The disassembled valve disc is verified to be capable of being full stroked and is checked for binding or failure of valve internals. Treined check valve inspectors are utilized for this examination and the results are reviewed and evaluated by the stati;a f Check Valve Coordinator. This is in addition to the root ;
cause analysis performed per station requirements. i Quarterly and cold shutdown testing requires a containment entry and climbing in the penetation areas which would conflict with station ALARA goals and radiation work practices in reducing exposure, and it is not prudent from a personnel safety standpoint. For personnel safety considerations, two individuals must always enter containment together, whenever containment integrity is set. The performance of this test would require a minimum of three (3) shifts with personnel working in a high radiation area. Also, quarterly testing would conflict with Technical j Specification 3/4.6.3.2, which requires the hydrogen monitors to be in the fj standby mode in order to meet the requirements set forth in NUREG 0737, Item II F.1.6 in Modes 1 and 2. !
The leak rate monitors (LRM) used for Type C LLRTs are required to be shipped off-site for calibration. During operation and cold shutdown when containment integrity is set, the LRM(s) would need to be taken inside the containment. If the LRM is contaminated and then unabled to be !
decontaminated, this would prevent its calibration and render it 4 unusable. This equipment is expensive and the number of monitors available for use is limited. During refueling outages, a staging area is set up outside containment in a low dose, non-contaminated area and hoses are run inside to the various containment isolation valves. These precautions are taken to prevent the LRMs from becoming contaminated.
This alternate test method is sufficient to insure the safety function of these valves is maintained at an acceptable level.
- 8. Agglicable Time Period:
This relief is raquested once per quarter during the first inspection interval.
- 9. -joroval Statual
- a. Relief is requested per Rev. 5.
- b. Added additional technical information and justification, Rev. Sa. l M.6 - Page 53 of 58 217(042292)
ZD79G/156
1/2PS231 A, B PS228A PS229A
= _
O W O PS231A 1 O I
E i
T GENERAL DIAGRAM FOR INFORMATION ONLY
R2 vision So EELIEF _ _REOUEST _VR-26
- 1. Yalve Numbers : 1/2RY8046, 1/2RY8047
- 2. Number of Valvigt 4
- 3. AS11E_ Code Categqty: AC
- 4. ASME Code, Section_XI PequjIrmggt:
Exercise check valves to the position required to fulfill their function (Bt/ Closed), unless such operation is not practical during plant op3 ration, per INV-3522.
- 5. Engis for Reliefs
.The RY8046 check valve is located inside containment in the primary water (PW) suppy line to the Pressure Relief Tank (PRT) and Reactor Coolant Pumps (RCPs) number thret seal head tanks / standpipes. The only safety function fos this check valve is to close for containment isolation purposes; this is redundant to the outboard air operated isolation valve.
The open function is to provide makeup water to the PRT and to each of the 13 seal head tanks. The water in the PRT serves as a quench volume for steam discharged from the PORVs and/or PZR safety relief valves, it also is used to cooldown the PRT after a steam discharge. The primary water to the RCPs 53 seal is for cooling and fl,ushing.
The RY8047 check valve is also located inside contairment in the nitrogen suppy line to the PRT. The only safety function for thia check valve is to close for containment isolation purposes; this is redundant to the outboard air operated isolation valve. The open function is to provide nitrogen gas to the PRT in order to maintain an inert atmosphere to prevent O2 and H 2 gas from combining into an explosive mixture. PRT u pressure is maintained at 3 psig and is monitored by installed
' instrumentation.
The Code requires that these check valves be tested in the closed direction to verify their seating capability on a quarterly or cold shutdown basis. However, these valves can only be verified closed by performing the Appendix J, Type C local leakage rate test (LLRT).
Performing the LLRT requires placing the system in an inoperable status (removed from service) for an extented period of time due to the need to isolate portions of the system, and connecting a leak rate monitor (LRM).
This would cause undue hardship with no compensating increase in plant or component safety, if the Code requirements were imposed.
- 6. Alternate Testing:
These check valves will be back flow tested each refueling outage by the i performance of their Appendix J, Type C seat leakage test. .
t 4.6 - Page 54 of 58 ZD79G/157
Ravision Sa EELIELEEMST VR-26
- 7. Justificatinn Performance of leakage testing on a two year (refueling) frequency is adequate to demonstrate structural integrity and valve seating capability per both Appendix J and ASME Section XI requirements. There is no reason to perform the Appendix J, Type C (low pressure air at approximately 45 psig) seat leakage test more of ten than that already required by 10CFR50.
This low pressure air test is adequate to monitor the valve's ability to seats the smallest amounts of dirt, general corrosion, and forlegn material can be detected between the seating surfaces by this test.
When a valve fails to meet its leakage criteria and repairs are required which make the internals accessible for inspection, a detailed visual inspection is performed per station procedures. The disassembled valve disc is verified to be capable of being full stroked and is checked for binding _or failure of valve internals. Trained check valve inspectors are utilized for this examination and the results are reviewed and evaluated by the station's Check Valve Coordinator. This is in addition to the root cause analysis performed per station requirements.
To perform a Type C leakage test on a quarterly basis would require that both the nitrogen and PW systems be removed from service and placed in an inoperable condition, directly impacting the operability of the PRT and the RCPs. These componnets are not required to be operable during refueling, hence, allowing for the LLRT to be performed without affecting systems or components.
Quarterly and cold shutdown testing requires a containment entry which would conflict with station ALARA goals and radiation work practices in reducing exposure, and it is not prudent from a personnel safety standpoint. For personnel safety considerations, two individuals must always enter containment together, whenever containment integrity is set.
The performance of each of these tests would require a minimum of three (3) shifts with personnel working in a high radiation area. Also, it is
-not practical to remove these valves from service, during quarterly or cold shutdowns, as these systems are required to support plant conditions (RCS pressure protection and control) and safe equipment (PRT and the RCP l 83-seal) operation.
The leak rate monitors (LRM) used for Type C LLRTs are required to be shipped off-site for calibration. During operation and cold shutdown when containment integrity is set, the LRM(s) would need to be taken inside the containment. If the LRM is contaminated and then unabled to be decontaminated, this would prevent its calibration and render it unusable. This equipment is expensive and the number of monitors available for use is limited. During refueling outages, a staging area is set up outside containment in a low dose, non-contaminated-area and hoses are run inside to the various containment isolation valves. These precautions are taken to prevent the LRMs f rom becoming contaminated.
This alternate test methc4 is suf ficient to insure the safety function of these valves is maintained at an acceptable level.
4.6 - Page 55 of 58 217(042292)
ZD79G/158
Revision 5a EELlEf 11 @ EST VR-26
- 8. App.ljngble Time Perisd:
This relief is requested once per quarter during the first inspection interval.
- 9. Approval Status
- a. Relief is requested per revision 5 submittal.
- b. Added additional technical information and justification, Rev. Sa.
4.6 - Page 56 of 58 ZD79G/159
1/2RY8046,l8047 n 2s' S vi " ~
- lu#tY RY8091 RY8034 RY8047 RY8033 O ' PRIMARY WATER
'd' A
' 8 MAKEUP RY8030 RY8046 RY8028 DISCH RGE -
(m am m m )e .
i S c PRESSURIZER RELIEF TANK I "
'TO ,
REACTOR '
COOLANT PUMP <
~ STANDPIPES
< GENERAL DIAGRAM FOR INFORMATION ONLY ,
RSvision St PILIIr REOUEST VR-27
- 1. Enive Numbers: 1/2WOOO7A, 1/2WOOO7B
- 2. HMaher of Valvest. 4
- 4. ASME Code, Sggtion XI RequiramEnt: -
Exercise check valves to the position required to fulfill their function (Bt/ Closed), unless such operation is not practical during plant operation, per IWV-3522.
- 5. Basis for Relief The 1/2WOOO7A, .B check valves are located inside containment in the supply lines to the Reactor Containment ran Coolers (RCFC) chilled water coils.
These valves are normally open valves requiring a closure test quarterly or during cold shutdown per the Code. These valves are not required for safe shutdown, their only safety function is to close for containment isolation. purposes. This is also a redundant function to the outboard '
motor operated valve's containment isolation function (1/2WOOO6A/B).
The Code-requires that these check valves be tested in the closed direction to verify their seating capability. However, these valves can only be verified closed by perfonning the Appendix J, Type C local leakage rate test (LLRT). Performing the LLRT requires placing the system in an inoperable status (removed from service) for an extented period of time due to the need to isolate and drain portions of the system, and connecting a leak rate monitor (LRM).
This would'cause undue hardship with no compensating increase in plant or component safety, if the Code requirements were imposed.
- 6. Alternate Taiting:
These check valves will be back flow tested each refueling outage by the
. performance of their Appendix J, Type C seat leakage test.
- 7. Justification:
Performance of leakage testing on a two year (refueling) f requency is adequate to demonstrate structural integrity and valve seating capability per.both appendix J and ASME Section XI requirements. There is no reason to perform the Appendix J, Type C (low pressure air at approximately 45 psig) seat leakage test more of ten than that already required by 10CFR50.
This low pressure air test'is adequate to monitor the valve's ability to seat; the smallest amounts of dirt, general corrosion, and forlegn material can be detected between the seating surf aces by this test.
4.6 - Page 57 of'58 217(042292)
ZD79G/160
Revision 5a .
i l
EELIIr__FIQUESL&21 1 I
- 7. Justificatinnt (continued)
When a valve falls to meet its leakage criteria and repairs are required which make the internals accessible for inspection, a detailed visual inspection is performed per station procedures. The disassembled valve disc is verified to be capable of being full stroked and is checked for binding or failure of valve internals. Trained check valve inspectors are utilised for this examination and the results ere reviewed and evaluated by the station's Check Valve Coordinator. This is in addition to the root cause analysis performed per station requirements.
To perform an LLRT on a quarterly or cold shutdown basis would require that the containment chilled water (WO) system be removed from service and placed in an inoperable condition for an extended period of time. It is impractical to perform this test during power operation because the WO system is needed to keep containment temperatures below 120'F. This is based on the environmental qualification of components inside containment and accident analysis assumpt!ons.
Quarterly and cold shutdown testing requires a containment entry which would conflict with station ALARA goals and and radiation practices in reducing exposure, and it is not prudent from a personnel safety standpoint. For personnel safety considerations, two individuals must always enter containment together, whenever containment integrity is set.
The performance of this test would require a minimum of ten (10) shifts (six shifts to drain the piping, I shift to test, and one day to fill and vent) with personnel working in a high radiation area.
The leak rate monitors (LRM) used for Type C LLRTs are required to be shipped off-site for calibration. During operation and cold shutdown when containment integrity is set, the LRM(s) would need to be taken inside the containment. If the LRM is contaminated and then unabled to be decontaminated, this would prevent its calibration and render it {
unusable. This equipment is expensive and the number of monitors available for use is limited. During refueling. outages, a staging area is set up outside containment in a low dose, non-contaminated area and hoses are run inside to the various containment isolation valves. These precautions are taken to prevent the LRMs from becoming contaminated.
This-alternate test method is sufficient to insure the safety function of these valves is maintained at an acceptable level.
- 8. Applicable Time Period:
This relief is requested once per quarter during the first inspection interval.
- 9. Ap_ proval Status:
- a. Relief is requested per revision 5 submittal.
- b. Added additional technical information and justification, Rev. Sa.
4.6 - Page 58 of 58 217(042292)
ZD79G/161 L , __ -- __ _ -
1/2W0007A/B 1
s i
E
& D& A WOOO7A(B) WOOO6A(B) 2 RCFC CHILLED WATER COILS WOOS 6A(B) WOO 20A(B)
GENERAL DIAGRAM FOR INFORMATION ONLY
. _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ -