ML20138K264
| ML20138K264 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/31/1997 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20138K159 | List:
|
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 IT-535, NUDOCS 9702180087 | |
| Download: ML20138K264 (29) | |
Text
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 ;
- LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 l fg MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 Date RECORD -
DSS PaoCEcuRE vERrrrEDCuRazur n:D CHECKED FOR EMPORARY CHANGE 5 TF FIELD COPIES REQUIRED. USE PBF.0026:IAW NP 12 4 AND DO E COh0'LETE TICS BLOCK t BY: DATE: ,
1.0 PURPOSE l.1 To detect and quantify leakage from the components comprising the RHR system in accordance with the requirements of NUREG-0578 and Technical Specification Table 15.4.1-2(22). !
(
l.2 To hydrostatically test, inspect and measure leakage from components of the RHR system !
including intersystem leakage as required by Technical Specification 15.4.4.IV.A. I.(a) and 15.4.4.IV. A.2. )
l.3 Refueling frequency, quantified seat leakage testing ofvalves 2SI-854A&B, 2RH-706A&B, and 2SC-959 as required by ASME Boiler and Pressure Vessel Code, p Section XI, " Rules for Inspection of Nuclear Power Plant Components."
O 1.4 Section 7.0 of this procedure may be used with Attachment D to fulfill the 40-month functional pressure test of Class 2 RHR system piping in accordance with ASME !
Section XI and the PBNP Pressure Test Program. l
2.0 REFERENCES
2.1 Technical Soecifications:
2.1.1 Table 15.4.1-2, Item 22 2.1.2 15.4.4.IV.A.1.(a) 2.1.3 15.4.4.IV. A.2 2.2 01-65, " Post-Maintenance Pressure Testing" 2.3 P&ID 110E029, Sheet 1, Aux Coolant System 2.4 NUREG-0578, Item 2.1.6.a,' " Leakage Reduction and Preventive Maintenance Program" 2.5 EDS Nuclear report, " Leakage Reduction and Preventive Maintenance Program at Point Beach Nuclear Plant," dated 7-24 80.
9702180087 970210 Page.1 of29 ' CONTINUOUS USE PDR ADOCK 05000301
- p PDR ,
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 2.6 IR 96-006, NRC Inspection Report; NRC Commitment for Operations procedures
' PMT/QC reviews.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 RHR system fluid is radioactive. Appropriate health physics practices should be observed.
3.2 Components required for redundant decay heat removal shall be in accordance with Technical Specification 15.3.1.A.3.
3.3 When a hydro pump is connected to a radioactive liquid system, maintain the test point valve shut until hydro pump pressure is established and shut the test point valve before securing the hydro pump on depressurizing to prevent contamination of the hydro hose (s) i and pump. 1 INITIALS 4.0 SEAT LEAKAGE TEST OF 2P-10A SUCTION VALVES 4.1 Lnitial Conditions 4.1.1 The RHR system is aligned per CL-7A or 7B.
4.1.2 The RCS is:
- a. In the process of cooldown per OP-3C with decay heat removal via the RC loops and steam generators and RCS temperature is between 500 F and 350*F, or
- b. In a refueling shutdown condition with the refueling cavity flooded and upper internals removed, or '
- c. In the process ofheatup per OP-1 A with decay heat removal via the RC loops and steam generators and RCS temperature is between 350"F and 500'F. -
4.1.3 A pressure test gauge for 350 psig is available.
4.1.4 A Haskal hydro pump is available on the El. 8' of the PAB with hydro hose to connect to 2RH-VI,2P-10A suction gauge isolation, and a rule to measure reservoir water level.
Page 2 of 29 CONTINUOUS USE 9
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 x MAINTENANCE PROGRAM TEST OF THE
- ) RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS d
d 4.1.5 A graduated cylinder in cc~or ml for leak rate measurement is 4
available.
4.1.6 An RWP is available.
4.1.7 The "A" train of RHR/Lo-head SI may be taken out of service.
4.1.8 Permission to Perform Test The conditions required by this test are consistent with required plant conditions including equipment operability. Permission is
, granted to perform this test.
DSS Time Date NOTE: Prior to takingpung out ofservice, ensure 2P-1M has runfor i
~5 min. toflush test volume isolation valves.
O 4.2 Enter LCO for 2P-10A, as required.
4.3 Place the 2P-10A RHR pump control switch in " Pull-out."
I i 4.4 Isolate the test volume by shutting the following valves:
2SI-851 A 2P-10A sump "B" suction MOV i
2SI-856A 2P-10A RWST suction MOV 2RH-704A 2P-10A loop suction manual isolation 2RH-733A 2P-10A mini-recarcisolation ,'
2RH-823A 2P-10A suction drain 2RH-709A 2P-10A discharge manualisolation 4.5 Shut 2RH-VI, then disconnect the suction gauge tubing at 2RH-VI and - -~
connect the hydro hose to the welded reducer at 2RH-V1.
4.6 With 2RH-VI shut, operate the hydro pump per 01-65, Part 3 to raise discharge pressure to 100 psig. !
4.7 Open 2RH-V1 and raise test volume pressure per 01-65 to 350 j
(+25, -0) psig as indicated by 2PI-628. .
1 l
Page 3 of 29 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 I LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 l
MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS 4.8 Maintain a stable test pressure for 10 minutes, then quantify the following:
NOTE: To save time, thefollowing leakage measurements should be determined concurrently.
4.8.1 Total input pumping rate in secm by accurately measuring the pump reservoir draw down over a suitable period of time.
Minimum run time for measurement is 15 minutes unless a high '
pumping rate (>l"/ minute)is experienced. Measure the change in inches (AH) in reservoir level over a corresponding time interval (AT)in minutes and record.
AH =
inches AT =
minutes 2PI-628 =
psig 4.8.2 Quantify the leak rate at the seal of 2P-10A and record.
2P-10A seal leak rate = seem 4.8.3 Calculate the leak rate attributable to 2SI-856A and 2RH-823A using the data of Steps 4.8.1 and 4.8.2.
AH 946 cc-x = 946 x = total sccm m AT total seem - 2P-10A seal = valveleakage
= seem
- Page 4 of 29
. CONTINUOUS USE S g
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 g MAINTENANCE PROGRAM TEST OF THE
' RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS NOTE: Although the target test pressure is 350psigfor seat leakage measurement of 2SI-854A, the minimum acceptablepressure is 100 psig as indicated by 2PI-628. If2PI-628 pressure is <100psig, then record the maximum achievable hydropump data per Step 4. 9 and in addition, perform the special test ofAttachment A.
a 4.9 Electrically open 2SI-856A, then operate the hydro pump to restore test
{
volume pressure to 350 (+25, -0) psig and record as in Step 4.8.1.
AH =
inches AT =
minutes 3
2PI-628 =
psig 4
, NOTE: Duringperformance of this test a hydraulic lock may occur between 2RH-704A and check valve 2RH-718A. Prior to depressurizing test volume, this may be avoided by slowly cracking open 2RH-704A prior to depressurizing test volume.
O 4.10 When the leak rate measurements are completed:
4.10.1 Shut 2RH-V1, then secure, depressurize and disconnect the hydro pump.
l PMT 4.10.2 Reconnect the suction gauge tubing at 2RH-VI and leak check i
by momentarily opening 2RH-V1.
4.10.3 Open 2RH-733A to depressurize the test volume and leave open.
4.10.4 Open 2RH-709A.
4.10.5 Position 2SI-856A and 2RH-704A per the direction of the DSS.
4 l PMT 4.10.6 Test run 2P-10A to verify operability.
4.11 End LCO for 2P-10A, if required.
O a
Page 5 of 29 CONTINUOUS USE ,
I NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM j (REFUELING) UNIT 2 !
TNITIALS !
l 4.12 Complete the test data sheet section for seat leakage rates of 2P-10A l suction valves.
5.0 SEAT LEAKAGE TEST OF 2P-10B SUCTION VAL'ES 5.1 Initial Conditions 5.1.1 The RHR system is aligned per CL-7A or 7B.
5.1.2 The RCS is:
- a. In the process of cooldown per OP-3C with decay heat removal via the RC loops and steam generators and RCS temperature is between 500 F and 350 F, or i
- b. In a refueling shutdown condition with the refueling czvity l flooded and upper internals removed, or
- c. In the process of heatup per OP-1 A with decay heat removal via the RC loops and steam generators and RCS temperature is between 350 F and 500 F.
5.1.3 A pressure test gauge for 350 psig is available.
5.1.4 A Haskal hydro pump is availab e on the El 8' of the PAB with hydro hose to connect to 2RH-V2,2P-10B suction gauge isolation, and a rule to measuse reservoir water level.
5.1.5 A graduated cylinder in cc or ml for leak rate measurement is available.
a w-s-5.1.6 An RWP is available.
5.1.7 The "B" train of RHR/Lo-head SI may be taken out of service.
Page 6 of 29 CON.TINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 ;
( MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 l
INITIALS 5.1.8 Permission to Perform Test The conditions required by this test are consistent with required !
plant conditions including equipment operability. Permission is granted to perform this test.
DSS Time Date NOTE: Prior to takingpump out ofservice, ensure 2P-10B has runfor
~5 min. toflush test volume isolation salves. l 5.2 Enter LCO for 2P-10B, if required.
5.3 Place the 2P-10B RHR pump control switch in " Pull-out."
5.4 Isolate the test volume by shutting the following valves:
( 2SI-851B 2P-10B sump "B" suction MOV 2SI-856B 2P-10B RWST suction MOV 2RH-704B 2P-10B loop suction manual isolation 2RH-733B 2P-10B mini-recirc isolation 2RH-823B 2P-10B suwon drain 2RH-709B 2P-10B discharge manualisolation 5.5 Shut 2RH V2, then disconnect the suction gauge tubing at 2RH-V2 and
' connect the hydro hose to the welded reducer at 2RH-V2.
5.6 With 2RH-V2 shut, operate the hydro pump per OI-65, Part 3 to raise -
discharge pressure to 100 psig.
- 5.7 Open 2RH-V2 and raise test volume pressure per OI-65 to i
350 (+25, -0) psig per 01-65 as indicated by 2PI-629.
i i
i i-i i
i Page 7 of 29 CONTINUOUS USE !
, l . . . ;
4 l
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NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS 5.8 Maintain a stable test pressure for 10 minutes, then quantify the following:
NOTE: To save time, thefollowing leakage measurements should be determined concurrently.
5.8.1 Total input pumping rate in sccm by accurately measuring the pump reservoir draw down over a suitable period of time.
Minimum run time for measurement is 15 minutes unless a high ,
pumping rate (>1"/ minute)is experienced. Measure the change in inches (AH) in reservoir level over a corresponding time ,
interval (AT)in minutes and record.
i AH = inches l
AT =
minutes '
2PI-629 =
psig 5.8.2 Quantify the leak rate at the seal of 2P-10B and record.
2P-10B seal leak rate = scem 5.8.3 Calculate the leak rate attributable to 2SI-856B and 2RH-823B using the data of Steps 5.8.1 and 5.8.2.
1 AH 946 CC-x = 946 x =
total sccm in AT total seem - 2 P-10B seal = valve leakage
= scem
- . Page 8 of 29 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 r MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS l NOTE: Although the target testpressure is 350psigfor seat leakage measurement of251-854B, the minimum acceptablepressure is
. 100psig as indicated by 2PI-629. If2PI-629 pressure is <100psig, i then record the maximum achievable hydropump data per Step S.9 i
andin addition, perform the specialtest ofAnachment B.
5.9 Electrically open 2SI-856B, then operate the hydro pump to restore test volume pressure to 350 (+25, -0) psig and record as in Step 5.8.1.
AH =
inches
, AT =
minutes j 2PI-629 =
psig NOTE: During performance of this test a hydraulic lock may occur between 2RH-704B and check valve 2RH-718B. Prior to depressuri:ing test volume, this may be amided by slowly cracking open 2RH-704B prior to depressurizing test wlume.
1 1
O 5.10 When the leak rate measurements are completed:
[ 5.10.1 Shut 2RH-V2, then secure, depressurize and disconnect the hydro pump.
l PMT 5.10.2 Reconnect the suction gauge tubing at 2RH-V2 and leak check 4
by momentarily opening 2RH-V2.
5.10.3 Open 2RH-733B to depressurize the test volume and leave open.
4
, 5.10.4 Open 2RH-709B.
5.10.5 Position 2SI-856B and 2RH-704B per the direction of the DSS.
l f.MI ~
, 5.10.6 Test run 2P-10B to verify operability.
5.11 End LCO for 2P-10B, if required.
O -
Page 9 of 29 CONTINUOUS USE 8
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS 5.12 Complete the test data sheet section for seat leakage rates of 2P-10B suction valves.
6.0 SEAT LE AKAGE TEST OF 2SF-818. 819. 2SC-959. 2RH-705. '/06A. 706B.
712 AND 715C
- CAUTIONa TEST SECTION 6.0 MUST BE COMPLETED PRIOR TO ANY RCS CLEANING OPERATIONS WITH THE RHR SYSTEM IN OPERATION, SUCH AS CAMP-I10, LN ORDER TO MINIMIZE EXPOSURE TO TEST PERSONNEL.
NOTE: Ifperforming RHR Boundary Leak TestperSection 7.0 in conjunction with this test, perform Steps starting at 6. 7 and 7.2 concurrently.
6.1 Initial Conditions 6.1.1 The RCS is solid and on RHR with RCS temperature <200 F.
6.1.2 The RCS is capable of being pressurized to 350 psig. I 6.1.3 The RHR system is aligned per CL-7B.
6.1.4 Normalletdown system is available.
6.1.5 The SFP purification system may be secured.
6.1.6 A graduated cylinder in cc or ml for leak rate measurement is available.
6.1.7 An RWP is available.
6.1.8 Permission to Perform Test The conditions required by this test are consistent with required plant conditions including equipment operability. Permission is DSS granted to perform this test.
Time h
Date Page 10 of 29 CONTINUOUS USE e
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 p MAINTENANCE PROGRAM TEST OF THE '
(') RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS NOTE: Steps 6.2 through 6.6 may beperformed concurrently.
6.2 Alienment ofPrimary Samoline System 6.2.1 Isolate the hot leg sampling system by shutting 2SC-955, 966C and 956C.
6.2.2 Verify shut 2SC-951, 953, 966A and 966B, pressurizer sample valves. If 2SC-951 & 966A were open for pressurizer degas, then notify Control that pressurizer degas is secured for this procedure.
6.2.3 Verify shut 2SC-959 and 990, RHR sample valves.
6.2.4 Shut 2SC-968, common sample return isolation.
6.2.5 Verify open 2SC-958A, RHR root sample valve.
6.2.6 Open 2SC-965C and 971 to provide a valve leak-off path to the sample sink. ,
1 6.2.7 Notify Chemistry that the primary sample system is aligned for a leak test and must not be altered without the test directors permission.
6.3 Alianment of RHR Letdown System 6.3.1 Ifletdown is from the RHR system via 2RH-715C and '
2CV-369A, then shift to any other letdown mode or combination and shut 2CV-369A.
6.3.2 Verify shut 2SF-821 A and 2RH-715D, refueling cavity purification system cross-connects.
6.3.3 Attach a Tygon tube to 2RH-D13 and route the tube to an elevation greater than the highest point within the boundary of 2RH-715C, 715D and 2CV-369A. Secure the Tygon in place to act as a system overflow vent.
(./
Page 1,1 of 29 CONTINUOUS USE
IT 535 l NUCLEAR POWER BUSINESS UNIT INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS 6.3.4 With 2RH-715C open, crack open 2RH-D13 to fill / prime the I leak detection hose until it overflows into a container, then shut l 2RH-715C firmly and shut 2RH-D13 as a leak-off path. l 6.4 Alignment of RHR Suction Makeuo Line 6.4.1 Verify shut 2SF-819, makeup system isolation valve.
6.4.2 Attach a Tygon tube to 2SF-819B and route the tube to an elevation greater than the highest point within the boundary of 2SF-819 and 819A. Secure the Tygon in place to act as a system overflow vent.
6.4.3 Align the SFP purification to supply the head required to fill / prime the Tygon tube, then open 2SF-819A.
6.4.4 Crack open 2SF-819B to fill / prime the leak detection hose until it overflows into a container, then shut 2SF-819A and open g
fully 2SF-819B.
6.4.5 Secure P-33, refueling water circ pump, if operating.
64.6 Isolate the SFP purification system by shutting:
SF-795 P-33 discharge to U6 SF-27 P-12A&B discharge to U6 SF-812A SFP purification returnisolation 6.5 Alignment ofLocal RHR Samole System 6.5.1 Verify shut 2RH-705 and 712, local sample valves.
6.5.2 Verify the sample tubing is open to the local sample sink to act as leak-off collection point for seat leakage of 2RH-705 and 712.
O Page 12 of 29 CONTINUOUS USE
i NUCLEAR POWEREUSINESS UNIT IT 535 i INSERVICE TESTS MAJOR Revision 12 l LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 p MAINTENANCE PROGRAM TEST OF THE i
RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 j INITIALS I 6.6 Alignment of Hinh Flow Test Line 6.6.1 Verify 2RH-706A&B, test line isolation valves, are shut firmly. ,,_
6.6.2 Attach a Tygon tube to 2RH-V16 and route the tube to an elevation greater than the highest point within the boundary of 2RH-706A&B and 742. Secure the Tygon in place to act as a system overflow vent.
NOTE: Thisprocedure assumes that the 2FE-660 orifice is installed ;
and the blank is removed Otherwise thefill and vent of the test line will need to be modified byfilling through 2RH-706A or B.
6.6.3 With all test line vents and drains shut, partially open 2RH-742 and 742B.
(' 6.6.4 Crack open 2RH,V16 to fill / prime the test line and leak detection hose until it overflows into a container, then shut 2RH-742 and 742B firmly.
6.6.5 Measure and record a stabilized baseline leak rate, if any, at 2RH-V16. Baseline leakage = sccm "CA UTION* AS RHR SYSTEM PRESSURE IS INCREASED TO TEST PRESSURE, THE LEAK-OFF POINTS AT 2RH-D13, 2RH-V16 AND 2SF-819B MUST BE MONITORED TO PREVENT LEAK-OFF CONTAINER OVERFILLING.
NOTE: Steps 6. 7 and 6.8 ofthisprocedure are common with Steps 7.2 and 7.3 ofSection 7.0.
6.7 Raise RCS system pressure to >350 psig and maintain stable pressure for the duration of the test.
O V '
Page 13 of 29 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS 6.8 After 10 minutes at test pressure, collect and record the seat leakage rate for the following valves:
NOTE: RHR system walkdown andleakage to atmosphere measurements per Section 7. 0 of this procedure should be performed concurrently.
6.8.1 Measure and record a baseline leak rate, if any, at 2SC-971.
Baseline leakage = seem 6.8.2 Open 2SC-990, then measure the seat leak rate of 2SC-959 at ;
sample valve 2SC-971. j 2SC-959 leakage = secm l 6.8.3 When leak rate measurement of 2SC-959 is complete, then shut 2SC-990,965C and 971. . ,
NOTE: Ifpressurit.er degas is to be resumed, reference OP-5D, Section C and reopen 2SC-968, 951 and 966A. Throttle degasflow with 2SC-965Afor aflow rate of 0.5-1.0 GPMper i 2F1-90.1.
6.8.4 Open 2RH-D13, allow leakage to strbilize, then collect and record leak rate of 2RH-715C at 2RH-D13 = seem 6.8.5 When leak rate measurement of 2RH-715C is complete, then l shut 2RH-D13 and remove the leak-off Tygon tube.
6.8.6 Record leak rate of 2RH-705 and 712 at the local sample
~
sink = seem 6.8.7 Open 2RH-V16, allow leakage to stabilize, then collect and record seat leakage rate of 2RH-706A&B at 2RH-V16= scem 6.8.8 When leak rate measurement of 2RH-706A&B is complete, then shut 2RH-V16, remove the Tygon tube and cap 2RH-V16.
Page 14 of 29 CONTINUOUS USE 9
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS 6.8.9 Verify open 2SF-819B, then record leak rate of 2SF-818 and 819 at 2SF-819B = seem 6.8.10 When leak rate measurement of 2SF-818 and 819 is complete, then shut 2SF-819B and remove the leak-off Tygon tube.
6.9 Align the Followine Valves for System to Atmosobere Leakage Measurement 6.9.1 Verify 2RH-V14 shut, then uncap the test connection for 2PI-657 to protect gauge 2PI-657 from overpressure.
6.9.2 Open 2RH-715D.
6.9.3 Slowly open 2RH-715C to pressurize the piping to 2SF-821 A and 2CV-369A.
6.9.4 Verify 2RH-742, 742A and 742B shut, then partially open 2RH-706A to pressurize the piping to 2RH-742B.
6.9.5 Open 2SC-959 to pressurize the piping to 2SC-990.
6.10 Complete the test data sheet section for ses leakage rates ofvalves tested in this section.
O .
Page 15 of 29 CONTINUOUS USE
i NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR j Revision 12 l
LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS 7.0 RHR BOUNDARY LEAK TEST aCAUTIONa TEST SECTION 7.0 MUST BE COMPLETED PRIOR TO ANY RCS CLEANING OPERATIONS WITH Tile RHR SYSTEM IN OPERATION, SUCH AS CAMP-110, IN ORDER TO MINIMIZE EXPOSURE TO TEST PERSONNEL.
NOTE: This test and the valve leakage test ofSection 6.0 should be performed concurrently.
7.1 Initial Conditions 7.1.1 The RCS is solid and on RHR with RCS temperature <200 F.
7.1.2 The RCS is capable of being pressurized to 350 psig.
7.1.3 The RHR system is aligned per CL-7B.
7.1.4 Graduated cylinders in cc or ml for leak rate measurement are i available. !
1 7.1.5 An RWP is available.
l 7.1.6 If this test is being utilized to fulfill 40-month functional pressure test requirements, then:
- a. The QTS inspector is notified of the test.
- b. The ANIIis notified of the test.
- c. The pretest data of Attachment D is completed.
7.1.7 !
Permission to Perform Test l
The conditions required by this test are consistent with required plant conditions including equipment operability. Permission is i
granted to perform this test.
I DSS Time _ Date I
l Page 16 of,29 CONTINUOUS UFE
- l
NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 O MAINTENANCE PROGRAM TEST OF THE (RESIDUAL REFUELING) UNIT HEAT 2 REMOVAL SYSTEM INITIALS 7.2 _ Raise RCS pressure to >350 psig and maintain stable pressure for the duration of the test. For a 40-month test, record test pressure achieved data on Attachment D.
7.3 After 10 minutes at test pressure, visually inspect the piping system and components (heat exchanger tubesheet joints, pump seals, valve stems and body to bonnet joints, pipe flanges / orifices, vent and drain plues/ caps, instrument line fittings / gauges) listed in Attachment C. Collect and .: cord all visible leakage to atmosphere in secm. For a 40-month test, record Attachment D data.
7.4 When the leak test data and Attachment C data are complete, including Attachment D if applicable, 7.4.1 Shut 2RH-715D.
7.4.2 Install the cap on the test connection for 2PI-657.
O 7.4.3 Position 2RH-715C and 2CV-369A per the direction of the DSS.
7.4.4 Red lock shut 2RH-706A. Lock No.
7.4.5 Shut 2SC-959.
7.4.6 Total the individual component leakages of Attachment C in scem and record on Attachment C.
Page 17 of29 CONTINUOUS US.E
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NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LiiAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 Leakage criteria of the Leakage Reduction and Preventive Maintenance Program are used to evaluate leakage from residual heat removal system components to atmosphere. Total leakage from all post-accident system components located in a specific area of the plant is limited by Criterion 1 or Criterion 2. The total post-accident system leakage from all areas of the plant is limited by Criterion 3. Thus, acceptance of these test results requires their evaluation together with the results of the other post-accident system leakage tests.
8.2 Valve through-leakage should not exceed 30 cc/hr per inch of valve diameter. This is only to be used as a guideline, and may be changed to be consistent with the "as-low-as-practicable" philosophy.
8.3 The maximum allowable leakage from the RHR system components (which includes valve stems, flanges and pump seals) shall not exceed two gallons per hour per Technical Specification 15.4.4.IV.B.
9.0 ANALYSIS TO BE COMPLETED WITIIIN 96 IIOURS BY OPERATIONS MANAGER OR IIIS REPRESENTATIVE.
9.1 Comparisons with allowable ranges of test values and analysis of deviations complete.
9.2 Any requirements for corrective action? '
Yes No (Ifyes, give details in the remarks section.) ~
9.3 Data analyzed by Time and date Remarks:
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NUCLEAR POWER BUSINESS UNTT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE Januay 31,1997 l c MAINTENANCE PROGRAM TEST OF THE
( RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS l l
TEST DATA SHEET 1.0 Valve Seat Leakane 1
NOTE: Allleak rates arein secm.
NOTE: Column A data is information only. Column B data is applicable to TechnicalSpecifications and NUREG 0578.
Col A Col. B 1.1 2SI-856A and 2RH-823 A (Reference Step 4.8.3) 1.2 2SI-854A (Reference Step 4.9 and Attachment A)
C 946 - x = 946 x = sccm in AT minus 2P-10A seal leak (Step 4.8.2) = .
(
or Attachment A = gpm l 1.3 2SI-856B and 2RH-823B (Reference Step 5.8.3) 1.4 2SI-854B (Reference Step 5.9 and Attachment B)
C 946 - x = 946 x = seem in AT minus 2P-10B seal leak (Step 5.8.2) =
or Attachment B = gpm 1.5 2SC-959 (Reference Steps 6.8.1 and 6.8.2) l Corrected leak rate = Step 6.8.2 minus 6.8.1 = '
1.6 2RH-715C (Reference Step 6.8.4) =
1.7 2RH-705 and 712 (Reference Step 6.8.6) =
t 1.8 2RH-706A&B (Reference Step 6.8.7) = .
1.9 2SF-818 and 819 (Reference Step 6.8.9) =
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NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS ATTACHMENT A Seat Leakage Test of 2SI-854A Usine P-33 NOTE: This test cannot beperformedifRHR is operating in the DHR mode and 2RH-701 cannot be shut.
NOTE: This test is required when the seat leakage of 2SI-854A exceeds thepumping rate ofthe hydro pump and test system pressureper 2PI-628 is <100psigper Step 4.9.
1.0 Shut 2RH V1, then secure the hydro pump.
2.0 Secure SFP recirc or Unit 1 RWST recire, ifin operation.
- 3.0 Align P-33 for Unit 2 RWST recire at 20 gpm per FI-636 by throttling with
, 2SF-811.
4.0 Verify 2RH-701 shut, then open 2SF-819 and verify FI-636 flow remains at 20 gpm.
5.0 Open 2RH-704A to ~25% open and allow flow at FI-636 to stabilize.
6.0 Record the following data:
P 33 flow per FI-636 gpm P-33 pressure per PI-651 psig Test volume pressure per 2PI-628 _ ___ psig 7.0 Shut 2SF-819 and 2RH-704A.
8.0 When P-33 flow has stabilized, record the following data:
P-33 flow per FI-636 gpm P-33 pressure per PI-651 psig Test volume pressure per 2PI-628 psig l 9.0 Return P-33 to previous status or as directed by the DSS.
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NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 ATTACHMENT A INITIALS 10.0 Calculate 2SI-854A seat leakage as P-33 flow in Step 6.0 minus P-33 flow in Step 8.0 = gpm. Record this leakage on the test data sheet, Step 1.2.
I 1.0 Return to procedure step in effect of Section 4.0.
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NUCLEAR POWER BUflNESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGR AM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 INITIALS ATTACHMENT B Stat Leakage Test of 2SI-854 B Usine P-33 NOTE: This test cannot beperformed ifRHR is operating in the DHR mode and 2RH-701 cannot be shut.
NOTE: This test is required when the seat leakage of2SI-854B exceeds thepumping rate of the hydro pump and tes t system pressure per 2P1-629 is <100 psig per Step 5. 9.
1.0 Shut 2RH-V2, then secure the hydro pump.
2.0 Secure SFP recire or Unit 1 RWST recire, ifin operation.
3.0 Align P-33 for Unit 2 RWST recirc at 20 gpm per FI-636 by throttling with 2SF-811.
4.0 Verify 2RH-701 shut, thea open 2SF-819 and verify FI-636 flow remains at 20 gpm.
5.0 Open 2RH-704B to ~25% open and allow flow at FI-636 to stabilize.
6.0 Record the following data:
P 33 flow per F1-636 gpm
. P-33 pressure per PI-651 psig 4
Test volume pressure per 2PI-629 psig 7.0 Shut 2SF-819 and 2RH-704B.
8.0 When P-33 flow has stabilized, record the following data:
P-33 flow per FI-636 gpm P-33 pressure per PI-651 psig Test volume pressure per 2PI-629 psig 9.0 Return P-33 to previous status or as directed by the DSS.
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1 NUCLEAR POWER BUSINESS UNIT IT 535 I INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE 8
RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 ATTACHMENT B INITIALS 10.0 Calculate 2SI-8548 seat leakage as P-33 flow in Step 6.0 minus P-33 flow in Step 8.0 = gpm. Record this leakage on the test data sheet, Step 1.4.
I 1.0 Retum to procedure step in effect of Section 5.0.
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NUCLEAR POWER BUSINESS UNIT IT 535 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 ATTACHMENT C Leakage Rate Component ID Comoonent Descriotion (secm) 2P-10A RHR Pumo Cubicle 2RH-823A 2P-10A suction low point drain 2RH-V10 2P-10A seal supply vent 2RH-VI1 2P-10A seal heat exchanger inlet vent 2RH-71 ID 2P-10A sealleak telltale Flange 2P-10A seal RO flange 2RH-711 A 2PT-628 root valve 2P-10A Pump seals PAB General Area South. El. -19'3" 2PT-629 2P-10B dh; charge pressure transmitter 2PT-628 2P-10A discharge pressure transmitter 2P-10B RHR Pumo Cubicic 2RH-823B 2P-10B suction low point drain 2RH-711F 2P-10B sealleak telltale 2RH V12 2P-10B seal supply vent 2RH-V13 2P-10B seal heat exchanger inlet vent Flange 2P-10B seal RO flange 2RH-71IB 2PT-629 root valve 2P-10B Pump seals -
Unit 2 RHR Pineway 2RH-710A 2P-10A discharge check valve -~'
2RH-709A 2P-10A discharge isolation 2RH-713A 2P-10A discharge cross-connect 2RH-D1 2P-10A&B discharge cross-connect drain -
2RH-713B 2P-10B discharge cross-connect 2RH-709B 2P-10B discharge isolation 2RH-710B 2P-10B discharge check valve 2SI-851 A 2P-10A "B" sump suction MOV ,
2SI 851C Pressure equalizer for 2SI-851 A 2SI-851B 2P-10B "B" sump suction MOV Page 24 of 29 CONTINUOUS USE
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NUCLEAR POWER BUSINESS UNIT IT 535 l INSERVICE TESTS MAJOR Revision 12 l LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 l MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 '
ATTACHMENT C Leakage Rate Component ID Component Description (sccm) .
Unit 2 RHR Pineway(Cont.)
i 2SI-851D Pressure equalizer for 2SI-851B 2RH-715A 2HX-11 A inlet isolation 2RH-D2 2HX-11 A interpass drain 2RH-D3 2HX-11 A interpass drain i 2RH-D4 2HX-11 A interpass drain '
2RH-715B 2HX-11B inlet isolation 2RH-D5 2HX-1IB interpass drain ;
2RH-D6 2HX-IlB interpass drain '
2RH-D7 2HX-11B interpass drain PAB General Area south. El -5'3"
/ 2RH-624 2HX-11 A discharge TCV 2RH-625 2HX-IIB discharge TCV 2RH-716A 2HX-11 A outlet isolation 2RH-716B 2HX-1IB outlet isolation 2RH-716C 2HX-llB outlet cross-connect 2RH-716D 2HX-11 A outlet cross-connect 2RH D8 2HX-11 A outlet drain 2RH-V7 Train "B" RHR to S1 and spray suction line vent (above HR-36) 2RH-V6 Train "A" RHR to SI and spray suction line vent 2RH-D11 Train "A" RHR to SI and spray suction line drain 2RH-D12 ~,'
Train "B" RHR to SI and spray suction line drain 2RH-V5 Train "A" RHR to SI and spray suction line vent PAB General Area South. El. 8'0" ~-
2RH-705 RHR local sample isolation 2RH-711C 2P-10A seal water supply 2RH-711E 2P-10B seal water supply 2FT-626 Train "A" RHR flow transmitter 2FT-928 Train "B" RHR flow transmitter 2RH-V4 Train "B" RHR to SI and spray suction line vent (above 2RH-742)
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l NUCLEAR POWER BUSINESS UNIT IT 535 l INSERVICE TESTS MAJOR Revision 12 ;
LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM l (REFUELING) UNIT 2 ATTACHMENT C Leakage Rate Component ID Comoonent Description (sccm)
Lower Pineway #3 2RH-VlB 2PI-653A root valve 2RH-VIA 2PI-653A bleed-off for seat leakage of 2RH-VIB 2RH-VIC 2PI-654A root valve 2RH-V2B 2PI-653B root valve 2RH-V2A 2PI-653B bleed-off for seat leakage of 2RH-V2B 2RH-V2C 2PI-654B root valve 2PI-654A 2P-10A RHR suction pressure indication 2PI-654B 2P-10B RHR suction pressure indication 2SI-856A 2P-10A RWST suction MOV 2SI-856B 2P-10B RWST suction MOV 2SI-854A 2P-10A RWST suction check 2SI-854B 2P-10B RWST suction check 2RH-712 RHRlocal sample isolation 2SC-958 RHR sample system isolation 2RH-714A RHR heat exchanger bypass isolation 2RH-7148 RHR heat exchanger bypass isolation 2RH-626 RHR heat exchanger bypass FCV 2SC-958A RHR pump discharge sample isolation 2RH-VI 2PI-653A and 654A root valve 2RH-V2 2PI-653B and 654B root valve 2RH-704A 2P-10A RCS loop suction isolation 2RH-704B 2P-10B RCS loop suction isolation l
2RH-718A 2P-10A RCS loop suction check 2RH-718B 2P-10B RCS loop suction check 2RH-717A 2FT-626 high pressure root valve 2RH-717B 2FT-626 low pressure root valve !
2FE-626 Train "A" RHR flow orifice --
2RH-848F 2FT-928 high pressure root valve 2RH-848E 2FT-928 low pressure root valve 2FE-928 Train "B" RHR flow orifice 2SF-819 RHR loop suction makeup isolation 2RH-733A 2P-10A mini-recire isolation 2RH-733B 2P-10B mini-recirc isolation P7 Loop suction containment penetration P8 .
Train "A" RHR discharge containment penetration P22 l Train "B" low head SI containment penetration !
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. NUCLEAR POWER BUSINESS UNIT IT 535 ;
INSERVICE TESTS MAJOR Revision 12
- LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
- MAINTENANCE PROGRAM TEST OF THE i y RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) LNIT 2 I
ATTACHMENT C Leakage Rate Component ID Component Description (sccm)
Containment Sorav and SI Pumo Area 2SI-871A Train "A" RHR/CS cross-connect MOV .
2SI-871B Train "B" RHR/CS cross-connect MOV '
] 2SI-857A Train "A" RHR/SI cross-connect isolation 2SI-857B Train "B" RHR/SI cross-connect isolation :
Lower Pipeway #3 i i *2SC-959 RHR sample system AOV
. *2RH-706A 2P-10A high flow test line isolation .
4
- 2RH-706B 2P-10B high flow test line isolation
- *2RH-D14 High flow test line drain ,
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- 2RH-V16 High flow test line vent l
- 2RH-890C RH-742 RHR return thermal release
{ *2FE-660 High flow test line orifice flange
- 2RH-662A FIT-660 high side root
- 2RH 662B 2 FIT-660 sensing line isolation
- 2 FIT-660 High flow test line flow indicator !
i *2RH-715C RHR letdown isolation '
i *2RH-D13 RHR letdown drain
- 2CV-369A RHR letdown isolation
- 2RH-715D Refueling cavity purification isolation
- 2RH-V14 2PI-657 isolation valve i
, Unit 2 Samnle Room
- 2SC-960A RHR sample check valve
- 2SC-990 RHR sample sink isolation
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NUCLEAR POWER BUSINESS UNTr IT 535 l INSERVICE TESTS MAJOR l Revision 12 i LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 ATTACHMENT C Leakage Rate Comoonent ID Component Descriotion (secm)
PAB General Area South. El -5'3"
- 2SF-821 A P-33 cavity purification discharge isolation Other miscellaneous system components (specify in Remarks)
Total Leak Rate l
- Inspect and record leakage after system is pressurized; i.e., Step 6.9 is completed.
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NUCLEAR POWER BUSINESS UNIT IT 535 -
INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE ' January 31,1997 MAINTENANCE PROGRAM TEST OF THE (m RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) UNIT 2 ATTACHMENT D 40-MONTH FUNCTIONAL PRESSURE TEST PRETEST DATA Record calibration dates for:
~ TEST DATA Test pressure achieved:
2PI-628 psig 2PI-629 psig Time 10-Minute hold / Inspection started:
2PI-628 psig 2PI-629 psig Time l
Inspection completed:
2P,.I-628 psig 2PI-629 psig Time ACCEPTANCE CRITERIA The functional pressure test is considered acceptable if the pressure retaining piping and components I withstand the test pressure without loss of structural integrity.
Additionally, the test is considered acceptable if there is no leakage from the system other than controlled leakage or leakage through boundary valves.
Test Director Date QTS Reference Report Number:
Remarks:
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