ML20138K290
| ML20138K290 | |
| 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-535A, NUDOCS 9702180125 | |
| Download: ML20138K290 (35) | |
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR l Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
'p MAINTENANCE PROGRAM TEST OF THE TRAIN y/ A HHSI AND RHR SYSTEMS (REFUELING) l UNIT 2 :
Date RECORD +
DSS PROCEDM MMED CNEN CWMOR1MORARMMGES F MrlD '
COPIES REQUIRED USE PBFM6 1AW NP 1.24 AND DoliQI COMPLETE TICS BLOCK BY: DA"II: !
1.0 PURPOSE '
To detect and quantify leakage from the components comprising the high head safety injection and residual heat removal systems.
l 1.1 This test is part of the Leakage Reduction and Preventive Maintenance Program required !
by NUREG-0578, Item 2.1.6a.
1.2 This test is part of the program to evaluate the integrity ofpost-accident recovery systems outside containment as required by Technical Specification Table 15.4.1-2(22).
l.3 To hydrostatically test, inspect and measure leakage from components of the RHR system Q including intersystem leakage as required by Technical Specification 15.4.4.IV.A.I.(a) and U 15.4.4.IV. A.2.
1.4 Refueling frequency, quantified seat leakage testing of valves 2SI-854A,2RH-706A, and ;
2SC-959 as required by AShE Boiler and Pressure Vessel Code,Section XI, " Rules for '
Inspection of Nuclear Power Plant Components."
1.5 This procedure fulfills the 40-month functional pressure test requirements for Class 2 HHSI and RHR piping in accordance with ASME Section XI and PBNP Pressure Test Program.
2.0 REFERENCES
I' 2.1 EDS Nuclear Report, " Leakage Reduction and Preventive Maintenance Program at Point i Beach Nuclear Plant," dated 07-24-80
. ~ . _ _
2.2 EDS Nuclear, "High Pressure Safety Injection System Leakage Test," TMI-02, dated 12-17-80 I
O .
Qg21gggg[ $80 1 Page,1 o 35 ,,' CONTINUOUS USE, P
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN ,
A HHSI AND RHR SYSTEMS (REFUELING) )
UNIT 2 2.3 PAIQ3 l 2.3.1 Il0E035, Sheets 1 and 2 SIS 2.3.2 110E029, Sheet 1 Aux Coolant System 2.4 Technical Soecifications:
2.4.1 Table 15.4.1-2, Item 22 2.4.2 15.4.4.IV.A. I.(a) 2.4.3 15.4.4.IV. A.2 2.5 01-65, " Post-Maintenance Pressure Testing" 2.6 NUREG-0578, Item 2.1.6.a, " Leakage Reduction and Preventive Maintenance Program" 2.7 IR 96-006, NRC Inspection Report; NRC Commitment for Operations procedures PMT/QC reviews.
3.0 PRECAUTIONS 3.1 IF THERE IS ANY PROBLEM IN PERFORMING TIIIS TEST. IMMEDIATELY NOTIFY THE DUTY SIIIFT SUPERINTENDENT. OPERATION OF THIS ,
EQUIPMENT IS A TECHNICAL SPECIFICATION REQUIREMENT.
3.2 Liquids leaking from various components of the HHSI or RHR systems will be mildly radioactive, and appropriate health physics practices should be observed. .
3.3 Hydro pumps:
3.3.1 Hydro pump skids must be prevented from rolling (i.e; wheels chocked, brakes locked, chained to wall, etc.) to minimize the risk of RHR piping damage in a seismic event.
3.3.2 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) and pump. .
3.4 2PI-974, SI pump suction pressure gauge shall be isolated during this test, as it is outside the test boundary.
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l NUCLEAR POWER BUSINESS UNIT IT 535A i
, INSERVICE TESTS MAJOR l l
Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 3 MAINTENANCE PROGRAM TEST OF THE TRAIN I A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 3.5 LHSI pump suction pressure will be read on the installed gauges in the No. 3 lower pipeway on El. 8'. !
3.6 If, at any time, RHR or SI pump suction pressure is less than the NPSH required, this test must be discontinued until the problem is corrected. The SI pump must not be operated without the associated RHR pump operating and the associated low head to high head crossconnect open.
3.7 Limit the run time of the HHSI pumps to $25 minutes when solely on mini-recirc flow.
Measured mini-recirc flow is 110 gpm. Minimum total flow for continuous operation is 225 gpm. I 3.8 Limit the nm time of the LHSI pumps to s30 minutes when solely on mini-recirc flow (design flow rate of 150 gpm). Minimum total flow for continuous operation is 520 gpm.
INITIALS 4.0 INITIAL CONDITIONS 4.1 RHR is aligned for LHSI per CL-7A 4.2 HHS! is aligned per CL-7A.
4.3 Standby emergency power shall be available to the 4160 V safeguards buses 1 A05,1 A06,2A05, 2A06, g the component (s) to be tested is/are in the same train that is out of service.
4.4 The orifice is installed in:
4.4.1 2FE-659 of the HHSI high flow recirc line.
4.4.2 2FE-660 of the LHSI high flow recirc line.
4.5 An RWP is available, including entry into containment.
4.6 If a 40-month functional pressure test is required, then:.
4.6.1 Pre-test data of Attachments E and O are completed.
(g h 4.6.2 The QTS inspector is notified of the test. -
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR i Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS 4.6.3 The ANII inspector is notified of the test.
4.7 The following equipment is available:
4.7.1 Stopwatch 4.7.2 T.rraduated cylinder in ml or cc 4.7.3 Leakage collection apparatus for 3 collection points 4.7.4 Pressure test gauge for 350 psig 4.8 A PAB qualified auxiliary operator with no other duties has been assigned to assist in performing this test.
4.9 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.
4.10 A SRO has conducted a briefing with all personnel involved in this test.
This briefing consists of:
4.10.1 The possibility of exceeding design flow of the RHR p! amps since both the RHR full flow recirc line and the SI pump full flow recirc line will be in operation.
4.10.2 Exercise caution when conducting the leak check of 2SI-829A so that a spill of RWST water does not occur from vent valve 2SI-V23.
4.11 Permission to Perform Test .
The conditions required by this test are consistent with required plant i
conditions, including equipment operability. Permission is granted to '
perform this test.
l DSS Time Date l
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 >
q MAINTENANCE PROGRAM TEST OF THE TRAIN y/ A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 '
INITIALS 5.0 SEAT LEAKAGE TEST OF RHR TRAIN A VALVES NOTE: Sreps 51 through 56 may beperformed concurrently.
5.1 Alignment of Primary Samoling System NOTE: Notify U2 Control Operator and Chemistry ofintent to secure ,
thefailedfuelmonitor (2RE-199)for the duration of Section LO.
5.1.1 Isolate the hot leg sampling system by shutting 2SC-955, 966C and 956C.
5.1.2 Shut 2SC-968, common sample return isolation.
5.1.3 Verify shut 2SC-951,953,966A and 966B, pressurizer sample '
valves.
O 5.1.4 Verify shut 2SC-959 and 990, RHR sample valves.
5.1.5 Verify open 2SC-958A, RHR root sample valve.
5.1.6 Shut 2SC-938, HX-14C, RC hot leg out to high rad sample system.
5.1.7 Open 2SC-965C and 971 to provide a valve leak-off path to the sample sink.
5.1.8 Notify Chemistry that the primary sample system is aligned for a leak test and must not be altered without the test directors permission.
5.2 Alinnment of RHR Letdown System 5.2.1 Verify shut 2SF-821 A and 2RH-715D, refueling cavity purification system cross-connects.
C Page 5 of 35 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 )
MAINTENANCE PROGRAM TEST OF THE TRAIN l A HHSI AND RHR SYSTEMS (REFUELING) l UNIT 2 INITIALS l 5.2.2 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.
5.2.3 With 2RH-715C open, crack open 2RH-D13 to fill / prime the leak detection hose until it overflows into a container, then shut 2RH-715C firmly.
5.2.4 Measure background leakage from 2RH-715C then shut 2RH-D13. Baseline leakage = seem _ , ,
5.3 Alignment of Local RHR Samole System 5.3.1 Verify shut 2RH-705, 705A and 712, local sample valves.
5.3.2 Verify the sample tubing is open to the local sample sink to act as leak-off collection point for seat leakage of 2RH-705, 705A and 712. )
1 5.4 A_lienment of RHR High Flow Test Ling 5.4.1 Verify 2RH-706A&B, test line isolation valves, are shut firmly. !
5.4.2 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 onfice is installed and the blank is removett Otherwise thefill and vent of the _
test line will need to be modified byfilling through 2Ril-706A or B.
5.4.3 With all test line vents and drains shut, partially open 2RH-742 and 742B.
5.4.4 Crack open 2RH-V16 to fill / prime the test line and leak detection hose untilit overflows into a container, then shut -
2RH-742 and 742B firmly. I I
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 '
O MAINTENANCE PROGRAM TEST OF THE TRAIN Q A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS 5.4.5 Fully open 2RH-V16. Measure and record a stabilized baseline leak rate, if any, at 2RH-V16.
Baseline leakage = seem '
5.4.6 Shut 2RH-V16.
5.5 Alignment of Soray system 5.5.1 Attach a Tygon tube to the Swagelock tee at 2SI-848J and l
route the tube to an elevation greater than the highest point within the boundary of 2SI-870A, 871 A, 860A and 860B.
Secure the Tygon in place to act as a system overflow vent.
5.5.2 Crack open 2SI-848J to prime the leak detection hose until it overflows into a container, then shut 2SI-848J. '
5.6 Ventine RHR to HHSI Piping 5.6.1 Route tubing to floor drain from 2RH-VS, RHR Train A test line high point vent.
5.6.2 Crack open 2RH-V5 and vent piping until a steady stream of water is apparent then shut 2RH-V5.
5.6.3 Install the digital pressure gauge at 2RH-V5 and open 2RH-V5.
=ms (3
V .
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1 NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS
- CAUTION
- AS RER SYSTEM PRESSURE IS INCREASED l TO TEST PRESSURE, THE LEAK-OFF POINTS AT 2RH-D13 AND 2RH-V16 MUST BE ,
MONITORED TO PREVENT LEAK-OFF l CONTAINER OVERFILLING.
- CAUTION
- IF A UNIT 2 SAFEGUARDS OR REACTOR PROTECTION ACTUATION OCCURS AT ANY TIME DURING PERFORMANCE OF THE REMAINDER OF THIS PROCEDURE SECTION:
- 3) IF 2ICP-666A IS IN PROGRESS, DIRECT I&C PERSONNEL TO RESTORE 2RH-624 TO FULLY OPERATIONAL STATUS AND INFORM CONTROL ROOM WHEN COMPLETE.
- 4) SHUT 2RII-VI AND SECURE THE HYDRO PUMP.
5.7 Enter LCO for Train A RHR, if required, and notify I&C that 2ICP-666A may commence.
5.8 Place the 2P-10A RHR pump control switch in PULLOUT.
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 '
A MAINTENANCE PROGRAM TEST OF THE TRAIN
.Q A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS 5.9 Verify the following valves shut, to isolate the test volume:
5.9.1 Dutside Containment 2SI-851 A 2P-10A sump "B" suction MOV 2SI-856A 2P-10A RWST suction MOV 2SI-852A LHSI Core Deluge MOV 2SI-871A RHR to 2P-14A suction MOV 2RH-720 RHR Return to RCS MOV 2RH-823A 2P-10A suction drain l
2RH-713A O 2RH-716D 2HX-11 A/B inlet crossconnect 2HX-11 A/B outlet crossconnect l
2SI-857A RHR to 2P-15A suction manualisol 2RH-704A 2P-10A loop suction manual isolation :
aCAUTIONa WHEN 2RH-703 IS SHUT, THERE IS NO THERMAL RELIEF PROTECTION FOR TRAIN A OF RHR UNTIL THE HYDRO PUMPIS ,
VALVED IN AT 2RH-V1. THE HYDRO PUMP OPERATOR SHOULD QUICKLY PROCEED WITH STEPS 5.10 THROUGH 5.12 AFTER 2RH-703 IS SHUT. -_
5.9.2 Inside Containment 2RH-703 RHR to letdown manualisolation 2CV-133(fail air) RHR to letdown HCV Page 9 of 35 CONTINUOUS USE 4 $
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 ;
INITIALS l
I 5.10 Shut 2RH-VI, then disconnect the suction gauge tubing at 2RH-V1 and connect the hydro hose to the welded reducer at 2RH-V1.
5.11 With 2RH-V1 shut, operate the hydro pump per appropriate part of 01-65 l to raise discharge pressure to 100 psig.
5.12 Open 2RH-VI and raise test volume pressure per 01-65 to 350 (+25, -0) psig as indicated on 2PI-628, and record pressure on digital pressure indicator. psig NOTE: To save time, thefollowing leakage measurements should be determined concurrently.
5.13 Maintain a stable test pressure for 10 minutes, then quantify the following:
5.13.1 Walkdown piping and components, and record leakage to atmosphere on Attachment B.
NOTE: RHR system pressure should indicate approximately the same pressure as step 5.12 as read on digitalpressure indicator prior to taking AH and ATreadings.
5.13.2 Total input pumping rate in scem 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 -
IPI-628 =
PsiB O
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 O MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS 5.13.3 2SC-959 leak rate determination
- a. Measure the base line leak rate at 2SC-971, if any.
Base line leakage scem
5.13.4 2RH-715C leak rate determination
- a. Open 2RH-D13 and record 2RH-715C leak rate at 2RH-D13 = sccm above leakage - (Step 5.2.4 leakage) = 2RH-715C leakage
5.13.5 2RH-706A leak rate determination
'2RH-V16 = scem l
5.13.6 Quantify the following leakage rates:
- a. 2P-10A seal leakage = seem
- b. 2RH-705/705A/712 leakage at Local Sample ^ Sink = secm (q
g -
Page,1,1 of 35 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TEETS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS 5.14 Calculate the boundary valve leak rate as follows:
(5.13.3b)secm - (5.13.3a) seem = 2SC-959 seem (5.13.4a) 2RH-715C seem (5.13.5a)scem - (5.4.5) scem = 2RH-706A seem (5.13.6a) 2P-10A Seal seem (5.13.6b) 2RH-705/712 scem Boundary total (sum of above leak rates) scem 5.15 Calculate the leak rate attributable to 2SI-856A and 2RH-823 A using the following:
946 x = 946 x =
(from 5.13.2) l 5.15.2 (5.15.1) total leakage - (5.14) Boundary Total Leakage =
2SI-823A/856A Valve Leakage
- =
5.16 Boundary Valve Leakage to Atmosphere 5.16.1 Verify 2RH-V14 shut, then uncap the test connection for 2PI-657 to protect gauge 2PI-657 from overpressurization.
5.16.2 Open 2RH-71SD.
5.16.3 Slowly open 2RH-715C to pressurize the piping up to -
5.16.4 Open 2SC-959 to pressurize piping up to 2SC-990.
5.16.5 Record leakage to atmosphere for components listed on Attachment C. ,
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 A MAINTENANCE PROGRAM TEST OF THE TRAIN (j A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS 5,16.6 If 40-month pressure test is required, notify QTS /ANI to begin ,
inspection, and record data required by Attachment G.
5.17 2SI-871 A Seat Leakage Test 5.17.1 Enter the LCO for Train A Spray system, if required.
l 5.17.2 Place the 2P-14A control switch in PULLOUT.
5.17.3 Shut 2SI-870A.
5.17.4 Open 2SI 848J and measure 2SI-871 A leak rate at 2SI-848J = secm.
t 5.17.5 Shut 2SI-848J. '
5.13
- 7 When inspection / data collection per Attachments B, C and G (ifrequired)
!( is complete, evaluate Train A RHR Tech Spec leakage, and if>l.5 gal /hr (95 secm), perfonn Attachment H troubleshooting. !
NOTE: RilR system pressure should indicate approximately the same pressure as step 5.12, as read on the digitalpressure indicatorprior to taking All and ATreadings.
4 NOTE: Although the target testpressure is 350psigfor seat leakage measurement of2SI-854A, the minimum acceptablepressure is 100 psig as indicated by 2PI-628. If2PI-628 pressure stabilizes at
<100psig after opening 2SI-856A, then record the maximum ~
achiemble hydropump dataper Step 19 andin addirian, perform the specialtest ofAttachment A.
5.19 Electrically open 2SI-856A, then operate the hydro pump to restore test volume pressure to 350 (+25, -0) psig and record as in Step 5.12.2.
AH =
inches AT =
minutes 2PI-628 =
psig Page 13 of35
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS
- CAUTIONa THERE IS NO THERMAL RELIEF PROTECTION FOR TRAIN A RHR WHILE 2RH-703 AND 2CV-133 ARE SHUT. SO POSITION 2RH-703 AND 2CV-133 PER STEPS 5.30.7 AND 5.30.8 AT THIS TIME, WHILE PROCEEDING WITH THE FOLLOWING STEPS.
5.20 Shut 2RH-VI 5.20.1 Secure and disconnect hydro pump per 01-65.
5.20.2 Depressurize test volume to RWST by opening 2RH-706A and 2RH-742A per 01-65.
5.20.3 Shut 2RH-706A /
5.20.4 Shut 2RH-742A l PMT 5.21 Reconnect the suction gauge tubing at 2RH-V1 and leak check by momentarily opening 2RH-V1.
5.22 Determine baseline leak rate for 251-871 A by opening 2SI-848J and measuring leak rate at 2SI-848J = scem 5.23 Shut 2SI-848J.
5.24 Open 2SI-870A. /
5.25 Place 2P-14A control switch to AUT 5. / _
5.26 End LCO for Train A Spray. ._
5.27 Verify open 2SI-856A. /
5.28 Place 2P-10A control switch to AUTO. /
5.29 Verify 21CP-666A is complete and end LCO for Train A RHR, if required.
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 l Q MAINTENANCE PROGRAM TEST OF THE TRAIN l Q A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS l I
5.30 Position the following:
l l
5.30.1 2SC-968 OPEN 5.30.2 2SC-966C OPEN 5.30.3 2SC-955 OPEN 5.30.4 2SC-959 SHUT !
l 5.30.5 2RH-715D SHUT j
5.30.6 2RH-715C SHUT l 5.30.7 2CV-133 /
SHUT (AIR ON) 5.30.8 2RH-703 LOCKED OPEN /
5.30.9 2RH-V5 SHUT / CAPPED
)
l 5.30.10 2PI-657 Test connection CAPPED 5.31 Notify U2 Control Operator and Chemistry that the failed fuel monitor (2RE-109)is realigned for operation.
5.32 Complete the test data sheet section for seat leakage rates of 2P-10A suction valves.
9 5.33 Remove all tygon tubing installed for this test and reinstall caps at all connection points.
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS 6.0 TRAIN A LHSI/HHSI "PIGGYB ACK" TEST 6.1 Pre-Test System Alienment/ Verification 6.1.1 Verify the valve position of the following: POSITION 2SI-897A SI test line isolation AOV Gag Open 2SI-897B SI test line isolation AOV Gag Open 2RH-742A RHR to RWST low flow Shut 2SI-828 U2 blender to U2 RWST Shut 2SF-811 P-33 to U2 RWST Shut 2WL-1729 RCDT pump to U2 RWST Shut 2SI-876A 2P-1SA mini-recirc Open 6.1.2 Verify oil level in 2P-15A at or above one-half sightglass.
Contact the DSS for the type of oil required.
l 6.1.3 Verify proper oil level in the thrust bearing housing of 2P-10A.
l Contact the DSS for the type of oil required.
l 6.1.4 Verify a primed relid condition of the HHSI high flow test line: I
- a. Verify 2SI-8.3A, B, and D shut.
\
)
, B, and D at static head. I
- c. Crack open 2SI-829C&D to fill the test line until a solid stream is observed at 2SI V23, then shut firmly 2SI-829C&D. , 1 O
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN
. Q,G A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS
- e. Record background leak rate at 2SI-V23, if any.
SCCM
, f. Shut 2SI-V23.
6.2 IlliSI Train A Leakane Test 4
- CAUTIONa IF A SAFEGUARDS ACTUATION OR A REACTOR PROTECTION SYSTEM
- ACTUATION SHOULD OCCUR ON UNIT 2 WHILE PERFORMING THIS TEST, THEN IMMEDIATELY PROCEED TO STEP 6.2.25.
RECOVER SYSTEMS PER STEPS 6.2.25 s THROUGH 6.2.35, THEN TERMINATE THIS
( TEST.
6.2.1 Unlock and open 2RH-742, high flow test line RWST isolation.
6.2.2 Position 2RH-742B, high flow test line FCV, to 32% open position (~1000 gpm).
- 6.2.3 If 2FE-660 blank was removed and orifice installed for this test, t
then fill and vent the high flow test line until water issues at 2RH-V16 and V17 high point vents. Otherwise N/A this step.
6.2.4 Enter LCO for Train A RHR, ifrequired.
6.2.5 Place 2P-10A control switch to PULLOUT. .
O .
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING) I UNIT 2 INITIALS NOTE: Steps 6.2.6 and 6.2. 7 provide a second barrier to leakage of letdown water to an unmonitored RWSTshould 2CV-133 and/or 2RH-702 leak by the seat during the test 1 1
6.2.6 Shut the following valves:
- a. 2RH-716A,2HX-1I A outlet isolation 1
6.2.8 Unlock and open 2RH-706A, high flow test line inlet isolation.
1 6.2.9 Verify open 2SI-856A,2P-10A RWST suction MOV.
6.2.10 Verify 2P-10A discharge pressure at <50 psig per 2PI-628.
l 6.2.11 Align 2PI-653 A, 2P-10A suction pressure gauge, for service:
- c. Open 2RH-V1B,2PI-653A inlet isolation.
6.2.12 Stan 2P-10A.
- CAUTION
- MONITOR AND VERIFY 2P-10A SUCTION PRESSURE IS >0 PSIG PER 2PI-653A ANYTIME FLOW IS CHANGED. I 6.2.13 Verify 2P-10A suction pressure is >0 psig.
6.2.14 Position 2RH-742B for a test line flow of 600 50 gpm per 2 FIT-660.
Page 18 of 35 , CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535A '
INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN
( A HHSI AND RHR SYSTEMS (REFUELING) '
UNIT 2 INITIALS NOTE: Identufy in remarks section any leakage observedfrom the pump or mechanical seals. Also include amount (seals wet, dropsper minute, etc.), color, and any other comments.
6.2.15 Check the pump and mechanical seals for leakage, unusual noise, and evidence of overheating.
6.2.16 Enter LCO for Train A HHSI, if required.
6.2.17 Place 2P-15A control switch to PULLOUT.
6.2.18 Shut 2SI-896A,2P-15A suction MOV.
6.2.19 Slowly open 2SI-857A, low head to high head crossconnect, to full open.
- 6.2.20 Visually inspect the shaft seals of 2P-15A. Collect, measure, and time any observed leakage. Record required data of Attachment D, Section 1.0.
- CAUTIONa DO NOT SECURE 2P-10A WITHOUT FIRST SECURING 2P-15A OR A TOTAL LOSS OF 2P-15A SUCTION MAY OCCUR, RESULTING IN PUMP DAMAGE. IF 2P-10A POWER IS LOST FOR ANY REASON, THEN IMMEDIATELY SECURE 2P-ISA.
NOTE: Reference P&L 3.6. < '1 6.2.21 Start 2P-15A.
6.2.22 Open 2SI-V23 to a container and when a stable leak rate, if any,
~ ~ ~
is observed, quantify the leakage over time and record the required data of Attachment D, Section 2.0. Then shut and cap 2SI-V23.
6.2.23 With 2SI-829A shut, collect and record 2SI-829A leakage to atmosphere on Attachment E.
+O .
Page 19 of 35 CONTINUOUS USE 1
9 g,
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING) i UNIT 2 l INITIALS NOTE: The 2P-15A Sipump must run 10 minutes at testpressure prior to start ofinspectionfor Attachment F.
6.2.24 For a 40-month test, perform the following substeps.
Otherwise N/A this step.
- b. Adjust 2SI-829C for a test line flow of 250 25 gpm per 2 FIT-659.
l Unlock and shut 2SI-876A,2P-15A mini-recirc isolation c.
valve.
- d. Record pressure achieved and inspection start data on ,
Attachment F.
6.2.25 Visually inspect the shaft seals of 2P-15A. Collect, measure, and time any observed leakage. Record required data of Attachment D, Section 3.0.
6.2.26 Visually inspect the piping system and components: valve stems and body to bonnet joints, pipe flanges / orifices, vent and drain plugs / caps, instrument line fittings / gauges listed on ,
Attachment E. Collect, measure, time, and record observed leakage. Record data on Attachment E.
6.2.27 When all data is completed, including Attachment F for 40-month tests, secure 2P-ISA and place control switch to PULLOUT.
6.2.28 Secure 2P-10A and place control switch to PULLOUT.
6.2.29 Red lock open 2SI-876A. Lock No. /
O Page 20 of 35 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 f] MAINTENANCE PROGRAM TEST OF THE TRAIN V A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 INITIALS 6.2.30 Red lock shut:
- a. 2SI-829A Lock No. /
- b. 2SI-829D Lock No. /
- c. 2RH-742 Lock No. /
6.2.31 Shut 2SI-857A. /
6.2.32 Open 2SI-896A,2P-15A suction MOV. /
6.2.33 Place 2P-15A control switch to AUTO. /
l 6.2.34 Exit LCO for Train A HHSI, if required.
6.2.35 Remove 2P-10A suction gauges from service:
- a. Shut 2RH-V1.
- b. Open 2RH-VI A.
- c. Shut 2RH-VlB.
6.2.36 Position the following:
- a. Red lock shut 2RH-706A. Lock No. / ,
- b. Red lock open 2RH-733A. Lock No. /
- c. Red lock open 2RH-716A. Lock No. / . . . - -
- d. Open 2RH-714A. /
6.2.37 Place 2P-10A control switch to AUTO. /
O V
Page 21 of 35 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING) !
UNIT 2 INITIALS 6.2.38 Exit LCO for Train A RHR,if required.
7.0 ACCEPTANCE CRITERIA Leakage criteria of the Leakage Reduction and Preventive Maintenance Program are used to evaluate the leakage from safety injection system components to atmosphere. Total leakage from all post-accident system (not just safety injection system) components, located in a specific area of the plant, is limited by Criterion 1 or Criterion 2. Total post-accident system leakage from all areas of the plant is limited by Criterion 3. Thus, acceptance of these test results require their evaluation together with the results of the other post-accident system leakage tests.
8.0 ANALYSIS TO BE COMPLETED BY THE OPERATIONS MANAGER OR HIS REPRESENTATIVE.
8.1 Comparison with allowable ranges of test values and analysis of deviations complete.
8.2 Any requirements for corrective action?
Yes No If yes, give details in the remarks section and MWR No.
I 8.3 Data analyzed. By Date Remarks:
l Page 22 of 35 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR ~ i Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 p MAINTENANCE PROGRAM TEST OF THE TRAIN (j A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 TEST DATA SHEET 1.0 Valve Seat Leakage 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-823A (Reference Step 5.15) 1.2 2SI-854A (Reference Step 5.19 and Attachment A) 946fx = 946 x = sccm O minus Boundary leakage (Step 5.14) = '
I or Attachment A = gpm 1.3 2SC-959 (Reference Step 5.14) =
1.4 2RH-715C (Reference Step 5.14) =
1.5 2RH-705, 705A and 712 (Reference Step 5.14) =
i 1.6 :
2RH-706A (Reference Step 5.14) =
1.7 2SI-871 A (Reference Steps 5.17 and 5.22)
(Step 5.17) seem -(Step 5.22) seem = - =
Ci
'V .
Page 23 of 35
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 j MAINTENANCE PROGRAM TEST OF THE TRAIN l A HHSI AND RHR SYSTEMS (REFUELING) l UNIT 2 i ATTACHMENT A l
Stat Leakace Test of 2SI-854A Usine P-33 NOTE: This test is required when the seat leakage of 2SI-854A etceeds the pumping rate of the hydropump and test systempressureper 2PI-628 is
<100psigper Step S.19.
INITIALS 1.0 Shut 2RH-VI, then secure the hydro pump.
2.0 Secure SFP recire or Unit 1 RWST recire (Refer to Ul PC-25A, Part 1), ifin operation 3.0 Align P-33 for Unit 2 RWST recire (Refer to U2 PC-25) 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 Shut 2RH-709A and 733A.
6.0 Open 2RH-704A to ~25% open and allow flow at FI-636 to stabilize.
7.0 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 8.0 Shut 2SF-819 and 2RH-704A.
9.0 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 10.0 Open 2RH 733A and 709A, then return P-33 to previous status or as directed by the DSS when the testing is complete.
- Page 24 of 35 CONTINUOUS USE 90
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NUCLEAR POWER BUSINESS UNIT '
IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 O MAINTENANCE PROGRAM TEST OF THE TRAIN h A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 i Attachment A INITIALS 11.0 . Calculate 2SI-854A seat leakage as P-33 flow in Step 7.0 minus P-33 flow in Step 9.0 = gpm. Record this leakage on the test data sheet, Step 1.2.
12.0 Return to procedure step 5.20.
l
- O n
]
4 4
I l
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NUCLEAR POWER BUSINESS UNIT IT S35A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN ,
A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 ATTACHMENT B Comoonent ID Comoonent Descriotion Leakage Rate (scem) 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 Flange 2P-10A seal RO flange 2RH-711 A 2PT-628 root valve 2P-10A Pump seals PAB General Area South. El -19' 2PT-628 2P-10A discharge pressure transmitter Unit 2 RHR Pineway 2RH-710A 2P-10A discharge check valve 2RH-709A 2P-10A discharge isolation 2RH-713 A 2P-10A discharge cross-connect 2SI-851 A 2P-10A "B" sump suction MOV 2SI-851C Pressure equalizer for 2SI-851 A 2RH-71SA 2HX-11 A inlet isolation 2RH-D2 2HX-11 A interpass drain 2RH-D3 2HX-11 A interpass drain 2RH-D4 2HX-11 A interpass drain 2RH-D1 2P-10A&B discharge crossconnect PAB General Area South. El -5' 2RH-624 2HX-11 A discharge TCV 2RH-716A 2HX-1I A outlet isolation 2RH-716D 2HX-11 A outlet cross-connect -
2RH-D8 2HX-11 A outlet drain 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-V5 Train A RHR to SI and spray suction line vent PAB General Area South. El 8'0" 2RH-705 RHR local sampleisolation 2RH-711C 2P-10A seal water supply 2FT-626 Train "A" RHR flow transmitter Page 26 of,35 CONTINUOUS USE a g e
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
/G MAINTENANCE PROGRAM TEST OF THE TRAIN Q A HHSI AND RHR SYSTEMS (REFUELING)
, UNIT 2 Attachment B
_Cpmponent ID Comoonent Descriotion Leakage Rate (secm)
Lower Pioeway #3 2RH-VIB 2PI-653A root valve 2RH-V1A 2PI-653A bleed-off for seat leakage of 2RH-VIB 2RH-VIC 2PI-654A root valve 2PI-654A 2P-10A RHR suction pressure indication 2SI-856A 2P-10A RWST suction MOV 2SI-854A 2P-10A RWST suction check 2RH-712 RHR local sample isolation 2SC-958 RHR sample system isolation
- 2RH-714A RHR heat exchanger bypass isolation 2RH-714B RHR heat exchanger bypass isolation 2RH-626 RHR heat exchanger bypass FCV 2SC-958A RHR pump discharge sampleisolation .
2RH-VI 2PI-653A and 654A root valve 2RH-704A 2P-10A RCS loop suction isolation 2RH-717A 2FT-626 high pressure root valve V 2RH-717B 2FT-626 low pressure root valve 2FE-626 Train "A" RHR flow orifice 2RH-733A 2P-10A mini-recirc isolation 2RH-706A 2P-10A high flow test line isolation 2RH-706B 2P-10B high flow test line isolation 2RH-D14 High flow test line drain 2RH-V16 High flow test line vent 2RH-V17 High flow test line downstream vent 2RH-D15 High flow test line drain 2RH-742B High flow test line flow control 2RH-890C .!
RH-742 RHR return thermal release ~'
2FE-660 High flow test line orifice flange 2RH-662A i 2 FIT-660 high side root j
2RH-662B 2 FIT-660 low side root -
2 FIT-660 l High flow test line flow indicator transmitter P8 ,
Train "A" RHR discharge containment penetration Containment Sorav and S1 Pumo Area '
2SI-871 A Train "A" RHR/CS cross-connect MOV 2SI-857A Train "A" RHR/SI cross-connect isolation i 0
O Other miscellaneous system components Page 27 of 35 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 _
ATTACHMENT C Component ID Comoonent Description Leakage Rate (secm)
' Lower Pineway #3
- 2RH-715C RHR letdown isniain
- 2RH-D13 RHR letdown drain
- 2CV-369A RHR letdown isolation ,
- 2RH-715D Refueling cavity purification isolation
- 2RH-V14 2PI-657 isolation valve Unit 2 Sample Room
- 2SC-960A RHR sample check valve
- 2SC-990 RHR sample sink isolation PAB General Area South. El .1' '
- 2SF-821 A P-33 cavity purification discharge isolation Other miscellaneous system components Total Leak Rate
- Inspect and record leakage after system is pressurized, i.e. Step 5.16, O
Page 28 of 35 CONTINUOUS USE 9 .
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN y/ A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 ATTACHMENT D 2P-15A PUMP SEAL LEAKAGE & 2SI-829A SEAT LEAKAGE 1.0 SEAL LEAK RATE WITH 2P-15A SECURED 2P-10A Discharge Pressure Per 2PI-628 = psig cc/ collected seconds Leak Rate = (cc collected /sec)(60 sec/ min) = SCCM 2.0 2SI-829A SEAT LEAK RATE i
2P-15A Discharge Pressure per 2PI-923 = psig cc/ collected seconds j
Leak Rate = (cc collected /sec)(60 sec/ min) = SCCM Background Leak Rate (Step 6.1.4.e) = SCCM 3.0 SEAL LEAK RATE WITH 2P-15A OPERATING 2P-10A Discharge Pressure Per 2PI-628 = psig
{
2P-15A Discharge Pressure Per 2PI-923 = psig cc collected seconds ,-
Leak Rate = (cc collected /sec) (60 sec/ min) = SCCM Page 29 of 35 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 ATTACHMENT E TRAIN A ATMOSPHERIC LEAKAGE LEAKAGE RATE COMPONENT DESCRIPTION (SCCM)
Comnonents Located in Containment Sorav/SI Pumn Area 2SI-857A RHR/SI crossconnect.. . . . . . . . . . .. ... .
2SI 896A 2P-15A suction MOV ... . . . . . .. ..
Flange 2P-1SA suction flange. . . . . . . . .. .
2SI D10 2P-15A discharge line drain.. . . . . . . . . . . . .
Flange 2P-15A discharge flange.. . . .. . . . . . . . . . . . .
2SI881A 2PT-923 root valve . . . .. . . .. . . .
2PT-923 2P-15A discharge pressure transmitter.. . ...
2SI-803A 2PI-913A root valve.. . . .. . . . . . ..
2SI-889A 2P-1SA discharge check valve.... ............ .. . ..........
2SI-888A 2P-1SA discharge isolation............. . . . . . . . . . . . . . . . . . . . .
2SI-829A 2P-15A&B SI pumps discharge crossconnect.. .. ...
2SI-891 A 2P-1SA mini-recire check valve... ....... . .... . ... . . . .
2SI-829B 2P-15A&B SI pumps discharge crossconnect . ..
2SI-V23 HHSI high flow test line vent . .. .
2SI-D32 HHSI high flow test line drain . . .
2FI-659 HHSI high flow test line orifice flange.
2SI-663B 2FI-659 high side isolation .
2F1-659 High side sensing line.
MISC Other miscellaneous system components.. . .
2SI-663A 2FI-659 low side isolation .. . . . . . . .
2SI-V22 HHSI high flow test line vent . . . . . . . . . . . . . .
2St.D28 HHSI high flow test line drain. . . . . . . . . . . . . . . . . . . . . . .
Components Located in Pineway No. 4 2SI-D13 SI Train A discharge line drain .. .. . .. . . . . . . . . . . . . .
2SI-848A 2FI-925 LP root valve .. .. . . . . . . . . ...
2SI-848B 2FI-925 HP root valve . . . .
2FE-925 SI Train A flow orifice . . . . .
2FT-925 SI Train A flow transmitter . . . . . . . . . ...
2SI-866A SI Train A discharge MOV .. ..
MISC Other miscellaneous system components.. .. . .
2P-10A discharge pressure,2PI-628 psig .
2P-15A discharge pressure,2PI-923 psig Page 30 of'35
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NUCLEAR POWER BUSINESS UNIT IT 535A I INSERVICE TESTS MAJOR Revision 2 i LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
,Q MAINTENANCE PROGRAM TEST OF THE TRAIN (j A HHSI AND RHR SYSTEMS (REFUELING) j UNIT 2 ATTACHMENTE HHSI 40-MONTH INSERVICE PRESSURE TEST PRE-TEST DATA Record calibration dates for:
2PI-923 2PI-940 l
l Record RWST Level per 2LI-972 %
j
- 2T-34A Accumulator Level per 2LI-938 %
TEST DATA Train A 1
Test pressure achieved:
2PI-923 psig Time 10-minute hold / Inspection staned:
l 2PI-923 psig Time Inspection completed: '
2PI-923 4
psig Time 2T-34A SI ACCUMULATOR ~~
Inspection started:
2PI-940 psig Time Inspection completed:
N 2PI-940 psig Time Page 3) of 35 CONTINUOUS USE
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NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 ACCEPTANCE CRITERIA The test is considered acceptable if the pressure retaining piping and components within the test boundary withstand the test pressure without loss of structural integrity.
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:
O 1
o- w -s.m Page 32 of 35 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 535A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAfNTENANCE PROGRAM TEST OF THE TRAIN k A HHSI AND RHR SYSTEMS (REFUELING) j UNIT 2 ATTACHMENT G RHR TRAIN A 40-MONTH FUNCTIONAL PRESSURE TEST 4
PRE-TEST DATA Record calibration dates for:
2PI-628 TEST DATA.
Test pressure achieved f 2PI-628 psig Time 10-minute hold / Inspection staned 2PI-628 psig Time Inspection completed 2PI-628 psig Time ACCEPTANCE CRITERIA The functional pressure test is considered acceptable if the pressure retaining piping and components withstand the test pressure without loss ofstructuralintegrity. -
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:
O Page 33 of35
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NUCLEAR POWER BUSINESS UNIT IT 535A l
INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 i MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING) j UNIT 2 l
1 INITIALS )
ATTACHMENT H TROUBLESHOOTING TRAIN A RHR LEAKAGE >1.5 cal /hr 1.0 Firmly SHUT the following valves:
2RH-713 A, 2HX-11 A/B Inlet Crossconnect !
2RH-713B, 2HX-I I A/B Inlet Crossconnect 2RH-716C,2HX-11 A/B Outlet Crossconnect i l
2RH-716D,2HX-11 A/B Outlet Crossconnect i
2RH-823A,2P-10A Suction Drain '
2SI-857A,2P-ISA Suction from RHR i
2SI-85 iC, Interdisc thermal release isol for 2SI-851 A 2.0 Station a dedicated operator whose duties will be to shut 2RH-V2 and secure the Train B hydro pump in the event of a Unit 2 reactor protection or safeguards actuation.
3.0 Shut 2RH-V2, disconnect the suction pressure gauge tubing at 2RH-V2 and connect a Haskal hydro pump at 2RH-V2.
4.0 With 2RH-V2 shut, operate the second hydro pump per 01-65 to raise discharge pressure to 100 psig.
5.0 Open 2RH-V2 and raise Train B RHR pressure to between 325 and 350 psig, not -
to exceed 350 psig, as read at 2PI-629.
6.0 Adjust Unit 2 letdown pressure to between 325 and 350 psig, not to exceed .
350 psig, as read at 2PI-135.
O Page 34 of 35 CONTINUOUS USE
. NUCLEAR POWER BUSINESS UNIT it525A INSERVICE TESTS MAJOR l Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 O MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 2 '
Attachment H INITIALS NOTE: Ensure measurements are taken on the Train A hydropump.
7.0 Measure and record total Train A RHR input pumping rate (as in step 5.13.2)
AH =
inches AT =
minutes 2PI-628 =
psig AH Totalinput = 946 x A T " ## * " #""
8.0 Restore Unit 2 letdown pressure to normal per DSS.
9.0 Shut 2RH-V2 and secure the Train B hydro pump.
10.0 Reconnect the suction pressure gauge tubing and leak check by momentarily opening 2RH-V2. (The dedicated operator may be released at this point.)
11.0 Depressurize Train B RHR
12.0 Open 2SI-851C and return to procedure step 5.19.
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