ML20138K251
| ML20138K251 | |
| 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-530A, NUDOCS 9702180078 | |
| Download: ML20138K251 (34) | |
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! LEAKAGE RE. . DUCTION AN.D PREV. ENTIVE .- yJanuary 31[1997.
1 i , ,hMAINTENANCE g PROGRAM TEST OF THE TRAIN 4W~" '
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, iTo ditectland quantify Nakage'froin the components comprising the high head safety injection .j ij f and residual heat removal l systems'.. ;j w,
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,. [1.2 3This test is J iart of the' program to evaluate the integrity ofpost-accidem recovery systems j
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g g;,g: frequency, quantified ' seat leakage testing of valves ISI-854A, IRH-706A, and? ,
- ; dlSC-959 as required by ASME Boiler and Pressure Vessel Code,Section XI, " Rules for ~
- Inspection of Nuclear Power Plant Components."-
e 't g; !!.5 F ;This procedure fulfills.the 40-month functional pressure test requirements for Class 2 j
LS ',,, . HHSI and RHR piping'in accordance with ASME Section XI and PBNP Pressure Test 1 Program. ..
I y 9, J L2.01 REFERENCES > y
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- 32.1s LEDS Nuclear Report, " Leakage Reduction and Preventive Maintenance Program at Point Beach NuclearP Q"
.m ' ympwgwn lant," dated 07-24-80 og 4
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L 2.2 1 EDS Nuclear, "High Pressure Safetp Injection System Leakage Test," TMI-02, dated k $p l'
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? NUCLEAR POWER @USINESS UNIT ' IT 530A'
.4 " INSERVICE TESTS; L ~ '
MAJORi ' '
~
~ Revision 2f d W : LEAKAGE REDUCTION AND PREVENTIVE : January 31; 1997 - A
. MAINTENANCE PROGRAM TEST OF THE TRAIN :l
j iUNIT 1 > j m , ,
y
[2.4; 1 Technical Soecifications:
~
L 2;4.11 ITabIc 1f4'1-2, Item 22 (
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,i.(i2;4.2i 15.4.4.IV.A.1.(a):, '
- 2.4.3 i .15:4.4.IV.A 2 : '
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<2.5: : 01-65, " Post-Maintenance Pressure Testing" !
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NUREG-0578, It'em 2.1.6.a, " Leakage Reduction and Preventive Maintenance Program" O w i2.6 l
2.7 ..IR 96-006, NRC Inspection Report; NRC Commitment for Operations procedures - !
PMT/QC reviews. ' ' I i
3.0 PRECAUTIONS 1
?3.1- . IF THERE IS ANY PROBLEM IN PERFORMING THIS TEST, IMMEDIATELY. 1
~ NOTIFY THE DUTY SHIFT SUPERINTENDENT. - OPERATION OF THIS j EQUIPMENT IS A TECHNICAL SPECIFICATION REQUIREMENT. i a :
13.2 Liquids leaking from various components of the HHSI or RHR systems will be mildly
- radioactice, and appropriate health physics practices should be observed.
- 3.3 Hydro pumps
1 3.3.1- ' Hydro pump skids must be prevented from rolling (i.e; wheels chocked, brakes
~
7 !
locked, chained to wall, etc.) to minimize the risk ofRHR piping damage in a ' iI seismic event.
- .};
.3.3.2
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When a hydro pump is connected to a radioactive liquid system, ms*atain the ,f ,
test point valve shut until hydro pump pressure is established, e.ad shut the test ,y4' point valve before securing the hydro pump on depressuriring, to prevent - --
contamination of the hydro hose (s) and pump.
33.4 L ' IPI-974, SI pump suction pressure gauge shall be isolated during this test, as it is outside
. the test boundary, n . .
'.5? :
LHSI pump suction pressure will be read on~ the installed gauges in the No. 2 lower
' pipeway on EL 8', -
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Page 2 of34 '. -
CONTINUOUS USE .
e .
),*,
NUCLEAR POWER BUSINESS UNIT IT 530A ,
INSERVICE TESTS MAJOR .
Revision 2 !
! . LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
, MAINTENANCE PROGP.AM TEST OF THE TRAIN s A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 - 1 i
f Date RECORD E DSS' PROCEDURE VEMnED CURRENT M.D CHECKED FOR TEMPORARY CHANGES IF FIE1.D COPIES REQtERED. USE PBF406 1AW NP 1.24 AND DO MZI COMPLETE THIS BLOCK BY: DATE:
1.0 PL%"OSE i
To detect and quantify leakage from the components comprising the high head safety injr On and residual heat removal systems.
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 of post-accident recovery systems outside containment as required by Technical Specification Table 15.4.1-2(22).
1.3 To hydrostatically test, inspect and measure leakage from components of the RHR system l p
V including intersystem leakage as required by Technical Specification 15.4.4.IV.A. I.(a) and 15.4.4.IV. A.2.
l I
I i
1.4 Refueling frequency, quantified seat leakage testing of valves ISI-854A, IRH-706A, and' l ISC-959 as required by ASME Boiler and Pressure Vessel Code,Section XI, " Rules for l
Inspection of Nuclear Power Plant Componer ts."
1.5 This procedure fulfills the 40-month functianal pressure test requirements for Class 2 i HHSI and RHR piping in accordance with ASME Section XI and PBNP Pressure Test Program.
~
2.0 REFERENCES
2.1 EDS Nuclear Report, " Leakage Reduction and Preventive Maintenance Program at Point Beach Nuclear Plant," dated 07-24-80 2.2 EDS Nuclear, "High Pressure Safety Injection System Leakage Test," TMI-02, dated 12-17-80 .
2.3 P& ids 2.3.1 110E017, Sheets 1 and 2 SIS 2.3.2 110E018, Sheet 1 Aux Coolant System 9702t80078 9702tO t Page1of34 CONTINUOUS USE PDR ADOCK 0500 P -
NUCLEAR POWER BUSINESS UNIT IT 530A INSERVICE TESTS MAJOR )
Revision 2 l LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 2.4 Technical Specifications:
2.4.1 Table 15.4.1-2, Item 22 1
2.4.2 15.4.4.IV. A.1.(a) l l
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 THIS TEST, IMMEDIATELY g NOTIFY THE DUTY SHIFT SUPERINTENDENT. OPERATION OF THIS T 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.
1 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 ofRHR piping damage in a seismic event.
4 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 IPI-974, SI pump suction pressure gauge shall be isolated during this test, as it is outside the test boundary.
3.5 LHSI pump suction pressure will be read on the installed gauges in the No. 2 lower pipeway on El. 8'. g
, W Page 2 of 34 CONTINUOUS USE e e
1 NUCLEAR POWER BUSINESS UNIT IT 530A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
( MAINTENANCE PROGRAM TEST OF THE TRAIN Q] A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 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 s25 minutes when solely on mini-recire flow.
Measured mini-recire flow is 110 gpm. Minimum total flow for continuous operation is 225 gpm.
3.8 Limit the run time of the LHSI pumps to s30 minutes when solely on mini-recire 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 HHSIis aligned per CL-7A.
O 4.3 Standby emergency power shall be available to the 4160 V safeguards buses 1 A05,1 A06, 2A05, 2A06, or 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 IFE-659 of the HHSI high flow recirc line.
4.4.2 IFE-660 of the LHSI high flow recirc line.
4.5 An RWP is available, including entry into containment.
5" 4.6 If a 40-month functional pressure test is required, then:
4.6.1 Pre-test data of Attachments F and G are completed.
4.6.2 The QTS inspector is notified of the test.
4.6.3 The ANII inspector is notified of the test.
v Page 3 of 34 CONTINUOUS USE
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NUCLEAR POWER BUSINESS UNIT IT 530A 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 1 INITIALS 4.7 The following equipment is available:
4.7.1 Stopwatch 4.7.2 Graduated 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 IRH-VI, IP-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 pumps 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 ISI-829A so that a spill of RWST water does not occur from vent valve ISI-V23.
4.11 Permission to Perform Test 3
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 Page 4 of 34 CONTINUOUS USE 4 5 '
e
I NUCLEARPOWER BUSINESS UNIT IT 530A )
INSERVICE TESTS MAJOR ;
Revision 2 l
- LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
- ('g MAINTENANCE PROGRAM TEST OF THE TRAIN Q A HHS! AND RHR SYSTEMS (REFUELING)
UNIT I ~
INITIALS 5.0 SEAT LEAKAGE TEST OF RHR TRAIN KVALVES NOTE: bieps 51 through 36 may beperformed concurrently.
5.1 Alignment of Primary Samolina System NOTE: Notify U1 Control Operator and Chemistry ofintent to secure thefailedfuel monitor (IRE-199)for the duration of Section LO.
5.1.1 Isolate the hot leg sampling system by shutting ISC-955, 966C and 956C.
5.1.2 Shut 1SC-968, common sample return isolation.
5.1.3 Verify shut 1SC-951,153,966A and 966B, pressurizer sample valves.
O 5.1.4 Verify shut 1SC-959 and 990, RHR sample valves.
5.1.5 Verify open 1SC-958A, RHR root sample valve.
5.1.6 l
Open ISC-965C and 971 to provide a valve leak-off path to the l sample sink.
5.1.7 Notify Chemistry that the primary sample system is aligned for a leak test and must not be altered without the test directors i permission. ,'!
5.2 Alione ofRHR f *down System '
1 i
5.2.1 Verify shut 1SF-821 A and IRH-715D, refueling cavity
~
purification system cross-connects.
l 5.2.2 Attach a Tygon tube to IRH-D13 and route the tube to an elevation greater than the highest point within the boundary of i IRH-715C,715D and 1CV-369A. Secure the Tygon in place to act as a system overflow vent. l O -
i Page 5 of 34
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1 . . . ~ . - - - ,
. NUCLEAR POWER BUSINESS UNIT IT 530A 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 1 INITIALS 5.2.3 With 1RH-715C open, crack open IRH-D13 to fill / prime the leak detection hose until it overflows into a container, then shut IRH-715C firmly and shut IRH-D13.
5.3 Nicnment of Local RHR Samole System 5.3.1 Verify shut IRH-705 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 1RH-705 and 712.
5.4 dignment of RHR High Flow Test Line 5.4.1 Verify IRH-706A&B, test line isolation valves, are shut firmly.
5.4.2 Attach a Tygon tube to IRH-V16 and route the tube to an elevation greater than the highest point within the boundary of IRH-706A&B and 742. Secure the Tygon in place to act as a system overflow vent.
NOTE: This procedure assumes that the IFE-660 orifice is installed and the blank is removed Otherwise thefill and vent of the test line will need to be modified byfilling through 1RH-706A or B.
5.4.3 With all test line vents and drains shut, partially open IRH-742 and 742B.
5.4.4 Crack open IRH-V16 to fill / prime the test line and leak detection hose until it overflows into a container, then shut IRH-742 and 742B firmly.
5.4.5 Fully open IRH-V16. Measure and record a stabilized baseline leak rate, if any, at IRH-V16. Baseline leakage =
seem 5.4.6 Shut IRH-V16.
h Page 6 of 34 CONTINUOUS USE e
NUCLEAR POWEREUSINESS UNIT IT 530A t INSERVICE TESTS MAJOR Revision 2 '
LEAKAGE REDUCTION AND PREVENTIVE . January 31,1997 -
MAINTENANCE PROGRAM TEST OF THE TRAIN
()g
-\' ~ A HHSI AND RHR SYSTEMS (REFUELING) t UNIT 1 ^
INITIALS f
5.5 Alimiment of Sorav system ;
i 5.5.1- Attach a Tygon tube to the swagelock tee at ISI-848J and j route the tube to an elevation greater than the highest point !
within the boundary of ISI-870A, 871 A, 860A and 860B.
Secure the Tygon in place to act as a system overflow vent.
5.5.2 Crack open 1 SI-848J to prime the leak detection hose until it overflows into a container, then shut ISI-848J.
l 5.6 Venting RHR to HHSI Pioing ,
5.6.1 Route tubing to floor drain from 1RH-Vl9, RHR Train A test line high point vent.
5.6.2 Crack open IRH-Vl9 and vent piping until a steady stream of I water is apparent, then shut and cap 1RH-Vl9. l O
i
.. 1
. t
._ .;o... J n su-i i
Page 7 of 34 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN l I
A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 INITIALS
- CAUTIONa AS RHR SYSTEM PRESSURE IS INCREASED TO TEST PRESSURE, THE LEAK-OFF POINTS AT 1RH-D13 AND 1RH-V16 MUST BE MONITORED TO PREVENT LEAK-OFF CONTAINER OVERFILLING.
- CAUTIONa IF A UNIT 1 SAFEGUARDS OR REACTOR l PROTECTION ACTUATION OCCURS AT ANY l TIME DURING PERFORMANCE OF THE REMAINDER OF THIS PROCEDURE SECTION:
- 1) VERIFY OPEN ISI-856A AND ISI-870A.
- 2) VERIFY IP-10A AND IP-14A CONTROL SWITCHES TO AUTO.
- 3) IF IICP-666A IS IN PROGRESS, DIRECT ;
I&C PERSONNEL TO RESTORE 1RH-624 TO FULLY OPERATIONAL STATUS AND INFORM CONTROL ROOM WHEN COMPLETE.
- 4) SHUT IRH-V1 AND SECURE THE HYDRO P U M P. l 5.7 Enter LCO for Train A RHR, if required, and notify I&C that IICP-666A may commence.
5.8 Place the IP-10A RHR pump control switch in PULLOUT.
a
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, Page 8 of 34 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530A 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 1 INITIALS ,
1 i
5.9 Verify the following valves shut, to isolate the test volume:
5.9.1 Outside Containment 1SI-851 A 1P-10A sump "B" suction MOV ISI-856A IP-10A RWST suction MOV t ISI-852A LHSI Core Deluge MOV ---
ISI-871A RHR to IP-14A suction MOV 1RH-720 RHR Return to RCS MOV '
1RH-823A 1P-10A suction drain ;
1RH-713A IHX-11 A/B inlei crossconnect i IRH-716D 1HX-11 A/B outlet crossconnect j ISI-857A RHR to IP-15A suction manualisol ,
IRH-704A 1P-10A loop suction manual isolation
- CAUTIONa WHEN 1RH-703 IS SHUT, THERE IS NO THERMAL RELIEF PROTECTION FOR TRAIN A OF RHR UNTIL THE HYDRO PUMP IS ix VALVED IN AT 1RB-V1. THE HYDRO PUMP
' OPERATOR SHOULD QUICKLY PROCEED 1
) WITH STEPS 5.10 THROUGH 5.12 AFTER i 1RH-703 IS SHUT.
5.9.2 Inside Containment 1RH-703 RHR to letdown manualisolation ICV-133(fail air) RHR to letdown HCV 5.10 Shut IRH-VI, then disconnect the suction gauge tubing at IRH-VI and ..
connect the hydro hose to the welded reducer at IRH-V1. '
5.11 :
With IRH-VI shut, operate the hydro pump per appropriate part of OI-65
, to raise discharge pressure to 100 psig. - d' 5.12 Open IRH-VI and raise test volume pressure per 01-65 to 350 (+25, -0) psig as indicated on IPI-628. -
~O .
Page 9 of 34 CONTINUOUS USE,
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i
, NUCLEAR POWER BUSINESS UNIT IT 530A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE Januay 31,1997 !
MAINTENANCE PROGRAM TEST OF THE TRAIN A HHS1 AND RHR SYSTEMS (REFUELING)
UNIT 1 INITIALS 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 Waikdown piping and components, and record leakage to atmosphere on Attachment B.
5.13.2 Total input pumping rate in seem 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.
1 AH =
inches AT =
minutes 1PI-628 =
psig i
5.13.3 ISC-959 leak rate determination '
- a. Measure the base line leak rate at ISC-971, if any. Base line leakage seem
- b. Open 1SC-990 and measure ISC-959 leakage at valve ISC-971 = seem
- c. When leak rate measurement of ISC-959 is complete, shut 1SC-990,965C and 971.
5.13.4 1RH-715C leak rate determination ..
- b. When leak rate measurement of IRH-715C is complete, shut IRH-D13.
O; I
1 l
. Page 10 of 34 CONTINUOUS USE I
~ NUCLEAR POWER BdSINESS UNIT IT 530A I
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 1 INITIALS ,
, 5.13.5' 1RH-706A leak rate determination. !
l
'a. Open IRH-V16 and record leak rate through IRH-706A at
- 1RH-V16 = scem 4-
l b. When leak rate measurement for IRH-706A is complete, !
l shut IRH-V16. t 5.13.6 Quantify the following leakage rates: ;
- -i
- a. 1P-10A seal leakage = seem l
j b. IRH-705/712 leakage at Local Sample Sink = seem !
J
.[
f .
i e 5.14 Calculate the bounday valve leak rate as follows:
,,__(5.13.3.a)secm - (5.13.3.a) scem = 1SC-959 secm ;
(5.13.4.a) 1RH-71SC sccm j (5.13.5.a)scem - (5.4.5) sccm = 1RH-706A scem ,
(5.13.6.a) IP-10A Seal seem
- 1RH-705/712 seem 3
(5.13.6.b)
Boundary total (sum of above leak rates) scem
+
5.15 Calculate the leak rate attributable to ISI-856A and 1RH-823A using the ;..e 3
followmg.
--g
- a.:
[
s 5.15.1 cc AH 946 g x AT = 946 x = =-Ge a-l AH from Step 5.13.2 AT '
5.15.2 (5.15.1) total leakage - (5.14) Boundary Total Leakage =
.. ISI-823A/856A Valve Leakage
~
Page11of34 CONTINUOUS USE
NUCLEARPOWER BUSINESS UNIT IT 530A 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 1 INITIALS 5.16 Boundary Valve Leakage to Atmosphere 5.16.1 Verify IRH-V14 shut, then open IRH-V14A to protect gauge IPI-657 from overpressurization.
5.16.2 Open IRH-715D.
5.16.3 Slowly open IRH-715C to pressurize the piping up to 1SF-821 A and ICV-369A.
5.16.4 Open ISC-959 to pressurize piping up to ISC-990.
5.16.5 Record leakage to atmosphere for components listed on Attachment C.
5.16.6 If 40-month pressure test is required, notify QTS /ANI to begin inspection, and record data required by Attachment G.
5.17 151-871 A Seat Leakage Test 5.17.1 Enter the LCO for Train A Spray system, if required.
5.17.2 Place the IP-14A control switch in PULLOUT.
5.17.3 Shut ISI-870A.
5.17.4 Open ISI-848J and measure ISI-871 A leak rate at l
ISI-848J = secm. J 5.17.5 Shut ISI-848J. l 5.18 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), perform Attachment H troubleshooting.
1 Page 12 of 34 CONTINUOUS USE
NUCLEAR POWERBUSINESS UNIT IT 530A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31, M7 pg MAINTENANCE PROGRAM TEST OF THE TRAIN ,
V A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 1
INITIALS NOTE: Although the target testpressure is 350 psigfor seat leakage measurement of1SI-854A, the minimum acceptablepressure is 100 psig as indicated by 1PI-628. If1PI-628 pressure stabilizes at
<100psig after opening ISI-856A, then record the maximum l l achievable hydropump dataper Step 5.19 andin addition, perform the specialtest ofAttachment A.
5.19 Electrically open ISI-856A, then operate the hydro pump to restore test l volume pressure to 350 (+25, -0) psig and record as in Step 5.13.2.
AH = inches l AT = minutes IPI-628 = psig _
5.20 Shut IRH-VI, then secure, depressurize and disconnect the hydro pump, per 01-65.
O oI tat !
5.21 Reconnect the suction gauge tubing at IRH-VI and leak check by 1 momentarily opening 1RH-V1. '
5.22 Determine baseline leak rate for ISI-871 A by opening ISI-848J and' I measuring leak rate at ISI-848J = seem 5.23 Shut ISI-848J.
5.24 Open ISI-870A. /
9 5.25 Place IP-14A control switch to AUTO. /
5.26 End LCO for Train A Spray.
5.27 Verify open 1SI-856A. /
5.28 Place IP-10A control switch to AUTO. /
5.29 Verify IICP-666A is complete and end LCO for Train A RHR, if required.
O -
4
, Page 1,3 of34 CONTINUOUS USE
NUCLEAR POWERCUSINESS UNIT IT 530A 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 1 INITIALS 5.30 Position the following:
5.30.1 ISC-968 OPEN 5.30.2 ISC-966C OPEN 5.30.3 ISC-955 OPEN 5.30.4 ISC-959 SHUT 5.30.5 1RH-715D SHUT 5.30.6 1RH-715C SHUT 5.30.7 1CV-133 SHUT (AIR ON) /
5.30.8 1RH-703 LOCKED OPEN /
5.31 Notify UI Control Operator and Chemistry thra the failed fuel monitor (IRE-109)is realigned for operation.
5.32 Com'plete the test data sheet section for seat leakage rates of IP-10A suction valves.
5.33 Remove all tygon tubmg installed for this test and reinstall caps at all connection points.
6.0 lki
~
TRAIN A LHSI/HHSI " PIGGYBACK" TEST j
6.1 Pre-Test System Alinnment/ Verification O
6.1.1 Verify the valve position of the following: POSITION ISI-897A SI test line isolation AOV Gag Open ISI-897B SI test line isolation AOV Gag Open IRH-742A RHR to RWST low flow Shut 1S1-828 Ul blender to Ul RWST Shut ISF-811 P-33 to U1 RWST Shut IWL-1729 RCDT pump to Ul RWST Shut 1SI-876A 1P-15A mini-recirc Open Page 14 of 34 CONTINUOUS USE e
- . = - . . .-- .- .
1 NUCLEAR POWER BUSINESS UNIT IT 530A j INSERVICE TESTS MAJOR l Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN O A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 INITIALS 6.1.2 Verify oil level in 1P-15A at or above one-half sightglass.
Contact the DSS for the type of oil required. ;
1 6.1.3 Verify proper oil level in the thrust bearing housing of IP-10A.
Contact the DSS for the type of oil required.
l 6.1.4 Verify a primed solid condition of the HHSI high flow test line:
- a. Verify ISI-829A, B, and D shut.
- b. Open ISI-V23, test line high point vent, to a container and observe no leakage of ISI-829A, B, and D at static head.
I
- c. Crack open ISI-829C&D to fill the test line until a solid l stream is observed at ISI-V23, then shut firmly ISI-829C&D. <
l
- d. Ifleakage persists at ISI-V23, then verify shut ISI-829A&B.
- e. Record backgr.ound leak rate at iSI-V23, if any. l SCCM '
- f. Shut ISI-V23.
I 4
a l
l 1
t e
.,, , Page 15 of 34 CONTINUOUS USE
NUCLEARPOWERBUSINESS UNIT IT 530A INSERVICE TESTS MAJOR l Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING) <
UNIT 1 '
INITIALS i 6.2 HHSI Train A Leakane Test
- CAUTIONa IF A SAFEGUARDS ACTUATION OR A REACTOR PROTECTION SYSTEM ACTUATION SHOULD OCCUR ON UNIT I WHILE PERFORMING THIS TEST, THEN IMMEDIATELY PROCEED TO STEP 6.2.27.
RECOVER SYSTEMS PER STEPS 6.2.27 THROUGH 6.2.37, THEN TERMINATE THIS TEST.
6.2.1 Unlock and open IRH-742, high flow test line RWST isolation.
6.2.2 Position IRH-742B, high flow test line FCV, to 32% open position (~1000 gpm). l 6.2.3 If IFE-660 blank was removed and orifice installed for this test, then fill and vent the high flow test line until water issues at IRH-V16 and V17 high point vents. Otherwise N/A this step.
6.2.4 Enter LCO for Train A RHR, if required.
6.2.5 Place IP-10A control switch to PULLOUT.
NOTE: Steps 6.2. 6 and 6.2. 7 provide a second barrier to leakage of letdown water to av snmonitoredRWSTshouldICV-133 and/or 1RH-702 leak by the seat during the test.
6.2.6 Shut the following valves:
,[
- a. 1RH-716A,1HX-11 A outlet isolation ~We
- b. IRH-714A, bypass FCV outlet isolation
~
Page 16 of 34 CONTINUOUS
'USE .
NUCLEAR POWERBUSINESS UNIT IT 530A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 f] MAINTENANCE PROGRAM TEST OF THE TRAIN Q A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 INITIALS 6.2.8 Unlock and open IRH-706A, high flow test line inlet isolation.
6.2.9 Verify open ISI-856A, IP-10A RWST suction MOV.
6.2.10 Verify 1P-10A discharge pressure at <50 psig per 1PI-628.
6.2.11 Align 1PI-653 A, IP-10A suction pressure gauge, for service:
- a. Shut IRH-VI A, IPI-653 A vent.
- b. Open IRH-VI, suction gauge root isolation.
- c. Open IRH-VIB, IPI-653A inlet isolation.
6.2.12 Stan IP-10A.
g
- CAUTION
- MONITOR AND VERIFY IP-10A SUCTION PRESSURE IS >0 PSIG PER IPI-653A ANY11ME FLOW IS CHANGED.
6.2.13 Verify IP-10A suction pressure is >0 psig.
6.2.14 Position IRH-742B for a test line flow of 600 50 gpm per l IFIT-660.
i NOTE: Idennfy in remarks section any leakage o$servedfrom the pung or mechanicalseals. 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 ofoverheating.
6.2.16 Enter LCO for Train A HHSI, if required.
6.2.17 Place IP-15A control switch to PULLOUT.
O .
, i Page 17 of 34 ~ CONTINUOUS USE G
NUCLEAR POWER BUSINESS UNIT IT 530A 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 I INITIALS 6.2.18 Shut ISI-896A, IP-15A suction MOV.
6.2.19 Slowly open ISI-857A, low head to high head crossconnect, to full open.
6.2.20 Visually inspect the shaft seals of IP-15A. Collect, measure, and time any observed leakage. Record required data of Attachment D, Section 1.0.
- CAUTIONa DO NOT SECURE 1P-10A WITHOUT FIRST '
SECURING IP-15A OR A TOTAL LOSS OF IP-15A SUCTION MAY OCCUR, RESULTING IN PUMP DAMAGE. IF IP-10A POWER IS LOST FOR ANY REASON, THEN IMMEDIATELY SECURE IP-15A.
. NOTE: Reference P&L 3.7.
6.2.21 Start IP-15A.
6.2.22 Open 1 SI-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 ISI-V23.
6.2.23 With ISI-829A shut, collect and record ISI-829A leakage to atmosphere on Attachment E.
O Page 18 of 34 CONTINUOUS USE
i NUCLEAR POWER BUSINESS UNIT IT 530A
-INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 p
MAINTENANCE PROGRAM TEST OF THE TRAIN j
\ A HHSI AND RHR SYSTEMS (REFUELING) >
UNIT 1 l INITIALS NOTE: The IP-15A SIpump must run 10 minutes at testpressure {
prior to start ofinspectionfor Attachment F. ;
i 6.2.24 For a 40-month test, perform the following substeps. ;
Otherwise N/A this step. ;
i
i
- b. Adjust ISI-829C for a test line flow of 250125 gpm per :
IFIT-659. !
f
- c. Unlock and shut ISI-876A, IP-ISA mini-recire isolation '
valve. i
- d. Record pressure achieved and laWon start data on Attachment F.
O 6.2.25 Visually inspect the shaft seals of IP-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 ( amponents
- valve
! stems and body to bonnetjoints, pipe flanges / orifices, vent and j drain plugs / caps, instrument line fittings / gauges listed on i j Attachment E. Collect, measure, time, and record observed '
l.
a-leakage Record data on A**ehmaat E. ..,;.T
- i 1
- 6.2.27 When all data is completed, including A"achment F for -
- 40-month tests, secure IP-15A and place control switch to 4 PULLOUT.
i 6.2.28 Secure IP-10A and place control switch to PULLOUT.
}
- 6.2.29 Red lock open ISI-876A. Lock No. /
l
- O .
Page 19 of 34 CONTINUOUS USE a
g-w , w- ,.-e
NUCLEAR POWER BUSINESS UNIT IT 530A 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 1 INITIALS 6.2.30 Red lock shut:
- a. ISI-829A Lock No. /
- b. ISI-829D Lock No. /
- c. 1RH-742 Lock No. /
6.2.31 Shut ISI-857A. /
6.2.32 Open ISI-896A, IP-15A suction MOV. /
6.2.33 Place IP-15A control switch to AUTO. /
6.2.34 Exit LCO for Train A HHSI, if required.
6.2.35 Remove IP-10A suction gauges from service: i
- a. Shut IRH-V1. _
- b. Open IRH-VI A.
)
- c. Shut IRH-VlB.
6.2.36 Position the following:
- a. Red lock shut IRH-706A. Lock No. / *
'y \
- b. Red lock open IRH-733A. Lock No. / M i
7,
- c. Red lock open IRH-716A. Lock No. /. - ___l
- d. Open IRH-714A. /
6.2.37 Place 1P-10A control switch to AUTO. /
6.2.38 Exit LCO for Train A RHR,if required.
Page 20 of 34 CONTINUOUS USE 6
g 4
NUCLEAR POWERBUSINESS UNIT IT 530A '
INSERVICE TESTS MAJOR Revision 2 !
i
. LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 q MAINTENANCE PROGRAM TEST OF THE TRAIN
~ A HHSI AND RHR SYSTEMS (REFUELING) l UNIT 1 ,
INITIALS t 7.0 ACCEPTANCE CRITERIA ' l 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.
t 8.1- Comparison with allowable ranges of test values and analysis of deviations complete.
O 8.2 Any requirements for corrective action?
Yes No If yes, give details in the remarks section and MWR No. '
8.3 Data analyzed. By Date .
Remarks:
"f e
.=- .- d 9
Page 21 of 34 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530A 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 1 TEST DATA SHEET 1.0 Valve Seat Leakage NOTE: Allleak rates arein secm.
NOTE: Column A data isinformation only.
Column B data is applicable to TechnicalSpecifications and NUREG 0578.
Col A Col B 1.1 1SI-856A and IRH-823A (Reference Step 5.15) 1.2 ISI-854A (Reference Step 5.19 and Attachment A)
AH 946$x m AT
946 x = seem minus Boundary leakage (Step 5.14)
or Attachment A = gpm 1.3 ISC-959 (Reference Step 5.14) =
1.4 1RH-715C (Reference Step 5.14) =
i 1.5 1RH-705 and 712 (Reference Step 5.14) =
1.6 iRH-706A (keference Step 5.14) = -
.l l.7 ISI-871 A (Reference Steps 5.17 and 5.22) 1 (Step 5.17) scem -(Step 5.22) seem = - =
~ '
Page 22 of 34 CONTINUOUS USE r -
NUCLEAR POWER BUSINESS UNIT IT 530A
~ INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 p MAINTENANCE PROGRAM TEST OF THE TRAIN
\ A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 l
ATTACHMENT A i
Seat Leakane Test of ISI-854A Usinn P-33 l l
} NOTE: This test is required when the seat leakage of151554A ecceeds the 4
punping rate ofthe hydro pung and test system pressureper JPI-628 is
<100psigperStep 5.19.
i INITIALS
! 1.0 Shut IRH-VI, then secure the hydro pump. ,
t
3.0 _ Align P-33 for Unit 1 RWST recirc (Refer to U1 PC-25) at 20 gpm per FI-636 by l throttling with ISF-811.
1
- e 4.0 - Verify IRH-701 shut, then open ISF-819 and verify FI-636 flow remains at 20 gpm. ^
l 3 i 5.0 Shut IRH-709A and 733A.
F 6.0 Open 1RH-704A to ~25% open and allow flow at FI-636 to stabihze. 4 7.0 Record the following data: !
P-33 flow per FI-636 gpm.
P-33 pressure per PI-651 psig Test volume pressure per IPI-628 psig I a
n 8.0 Shut ISF-819 and IRH-704A.
[
q -
.,.-.x~
J 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
- j Test volume pressure per IPI-628 psig i
r i
Page 23 of 34 CONTINUOUS USE ;
NUCLEAR POWERBUSINESS UNIT IT 530A i INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 l
MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1
)
Attachment A ;
INITIALS 10.0 Open IRH-733A and 709A, then return P-33 to previous status or as directed by the DSS when the testing is complete.
I1.0 Calculate ISI-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 l
O I
i
^
- l-
- i 1
l
. 9 Page 24 of 34 CONTINUOUS USE
NUCLEARPOWER BUSINESS UNIT IT 530A INSERVICE TESTS MAJOR Revision 2
. LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 i' MAINTENANCE PROGRAM TEST OF THE TRAIN Q. A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 i l t
ATTACHMENT B Leakage Rate :
Component ID Component Descriotion (sccm) l 1P-10A RHR Pumo Cubicle IRH-823A IP-10A suction low point drain i 1RH-V10 - IP-10A seal supply vent 1 1RH-V11 IP-10A seal heat exchanger inlet vent IRH-71ID IP-10A sealleak telltale Flange IP-10A seal RO flange l 1RH-711 A IPT-628 root valve l IP-10A Pump seals I
., PAB General Area South. El -19' IPT-628 IP-10A discharge pressure transmitter i
Unit 1 RHR Pineway I
- 1RH-710A IP-10A discharge check valve
- IRH-709A IP-10A discharge isolation 1RH-713A IP-10A discharge cross-connect 1SI 85l A IP-10A "B" sump suction MOV ISI-851C Pressure equalizer for ISI-851 A 1RH-715A 1HX-11 A inlet isolation 1RH-D2 IHX-11 A interpass drain i- 1RH-D3 1HX-11 A interpass drain .
1RH-D4 IHX-11 A interpass drain 4
PAB General Area South. El -5'
_y IHX-11 A discharge TCV 1RH-716A IHX-11 A outlet isolation
. lRH-716D IHX-11 A outlet cross-connect 1RH D8. .--
1HX-11 A outlet drain _ . -
j j
PAB General Area South. El 8'0" 1RH-705 RHR local sampleisolation 1RH-711C 1P-10A seal water supply 4 IFT-626 Train "A" RHR flow transmitter j
th g 1 Page 25 of 34 - CONTINUOUS USE l 0
I NUCLEAR POWER BUSINESS UNIT IT 530A i INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING) l UNIT 1 l
Attachment B l
~
Leakage Rat j Comoonent ID Comoonent Description (secm)
Lower Piceway #2 1RH-VlB IPI-653A root valve 1RH-VI A 1PI-653A bleed-off for seat leakage of IRH-VlB 1RH-VIC 1PI-654A root valve IPI-654A IP-10A RHR suction pressure indication ISI-856A IP-10A RWST suction MOV ISI-854A IP-10A RWST suction check i 1RH-712 RHR local sample isolation l 1SC-958 RHR sample system isolation l 1RH-714A RHR heat exchanger bypass isolation l 1RH-714B RHR heat exchanger bypass isolation 1RH-626 RHR heat exchanger bypass FCV ISC-958A RHR pump discharge sample isolation IRH-VI {
IPI-653A and 654A root valve j 1RH-704A 1P-10A RCS loop suction isolation lRH-717A {
IFT-626 high pressure root valve 1RH-717B IFT-626 low pressure root valve 1FE-626 Train "A" RHR flow orifice 1RH-733 A IP-10A mini-recire isolation '
1RH-706A IP-10A high flow test line isolation IRH-706B IP-10B high flow test line isolation '
1RH-D14 High flow test line drain IRH-V16 High flow test line vent 1RH-D15 High flow test line drain 4 1RH-742B High flow test line flow control 1RH-890C RH-742 RHR return thermal release IFE-660. High flow test line orifice flange >
1RH-662A IFIT-660 high side root - ~ ~ ~ ~ - -
IRH-662B IFIT-660 low side root IFIT-660 High flow test line flow indicator transmitter PB Train "A" RHR discharge containment penetration -
Containment Sorav and S1 Pumo Area ISI-871 A Train "A" RHR/CS cross-connect MOV 1SI-857A Train "A" RHR/SI cross-connect isolation .
Other miscellaneous system components Page 26 of 34 CONTINUOUS USE 8 g $
a
NUCLEARPOWER BUSINESS UNIT IT 530A >
- INSERVICE TESTS MAJOR Revision 2 -
LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 !
MAINTENANCE PROGRAM TEST OF THE TRAIN ,
! V(~'s ' A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 ATTACHMENT C Leakage Rate
- Comoonent ID Comoonent Descriotion (secm) - ,
i Lower Pineway #2
- 1RH-V14 IPI-657 isolation valve Unit 1 Samole Room
- 1SC-960A RHR sample check valve
'
- ISC-990 RHR sample sink isolation i l
PAB General A' rea South. El -5' I
- 1SF-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.
'?
, 94
, m:
k,t s;4 l
( ,
Page 27 of 34 CONTINUOUS USE e' ,
NUCLEAR POWER BUSINESS UNIT IT 530A 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 1 ATTACHMENT D 1P-15A PUMP SEAL LEAKAGE & 1SI-829A SEAT LEAKAGE 1.0 EEAL LEA.K RATE WITH IP-15A SECURED IP-10A Discharge Pressure Per IPI-628 = psig cdcollected seconds Leak Rate = (cc collected /sec)(60 sedmin) = SCCM 2.0 1SI-829A SEAT LEAK RATE IP-15A Discharge Pressure per IPI-923 = psig cdcollected seconds Leak Rate = (cc collected /sec)(60 sedmin) = SCCM Background Leak Rate (Step 6.1.4.e) = SCCM 3.0 SEAL LEAK RATE WITH IP-15AOPERATING IP-10A Discharge Pressure Per IPI-628 = psig
- l IP-15A Discharge Pressure Per IPI-923 =
psig cc collected seconds Leak Rate = (cc collected /sec)(60 sedmin) = SCCM Page 28 of 34 CONTINUOUS USE O e e e
NUCLEAR POWERBUSINESS UNIT IT 530A l r INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
'p MAINTENANCE PROGRAM TEST OF THE TRAIN Q A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 3-
, ATTACHMENT E p TRAIN A ATMOSPHERIC LEAKAGE LEAKAGE RATE COMPONENT DESCRIPTION- (SCCM) ,
Components Located in Containment Sorav/SI Pumo Aren 1St857A RHR/SI crossconnect.... . .. ... .. ... . . . . . . . . . . . . . . . . . . . ... .
- Flange 1P-1SA suction flange.. . . . . .. .... .. . . . . . . . . . . . .... ...
ISI-DIO 1P-15A discharge line drain. .. . . . . . . . . . . . . . . . . . . . . . . . . .
Flange IP-15A dischargH'ange -.- - ~. . . - . _ . - _ . - . ~ . .
1SI 881 A 1PT-923 root valve.. ... . .. . . . . . . . . . . . . . . . . . . . . . . . . .
1PT-923 1P-1SA discharge pressure transmitter. .. ..... .. ..... . . ... . . . . .
1SI-889A 1P-15A discharge check valve........................................... .... ...... ..
1SI-888A 1P-IS A discharge isolation ....... .. ....... .......... ...................... .... ....
p 1SI-829A 1P-1 SA&B SI pumps discharge crossconnect...............................
(
lSI-891 A 1 P-1 SA mini-recire check valve.. ...... . . ......... ............... .. . .... . ..
1SI-829B 1P-15A&B SI pumps discharge crossconnect..... .. ..... .... .. .. . . .
1SI-V23 HHSI high flow test line vent. . ... ..
1SI D32 HHSI high flow test line drain.. . . . . . . . . . . . . . . . . . . .
IFI-659 HHSI high flow test line orifice flange.. . . .
1SI-663B IFI-659 high side isolation. . . . . . . . ..
IFI-659 High side sensing line., . . . . . . . . . . . . . . . . . . . .
MISC Other miscellaneous system components .... .... . ... ..... . .. ..... .. ...
Comoonents LoentM in Pineway No. 4 1SI-D13 SI Train A discharge line drain..................... ......................... ......... 'l 1SI-848A 1 FI-925 LP root valve .. . . . . .. . . . . . . . . . . .. .... . ... . .. . . .. . . . . .. ... . . . . . .. . . . . . . . . N 1SI-848B '
1 FI-925 HP root valve . . . ... . . . ... . . .. . . .. .. .. .... . . . . ...... ... . . . . . . . . .. . .. . .. . . . . .
- 1FE-925 ~
SI Train A flow orifice . . . .. . . .. . . . ... . . .. .. .. .......... . ....... . .... . .. . .. .. . . .
lFT-925 SI Train A flow transmitter.. .............................
1SI-866A SI Train A discharge MOV. .. . . . . . . . . . . . . . . . . . . . . . . . . . .
MISC Other miscellaneous system components. .. ....... .. . ... . ..... . .. . .
I IP-10A discharge pressure, IPI-628 psig IP-15A discharge pressure, IPI-923 psig . .
i i
Page 29 of'34 _ CONTINUOUS USE
NUCLEAR POWERBUSINESS UNIT IT 530A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PRCGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 ATTACHMENT F HHSI 40-MONTH INSERVICE PRESSURE TEST PRE-TEST DATA Record calibration dates for:
1PI-923 1PI-940 Record RWST Level per ILI-972 %
IT-34A Accumulator Level per ILI-938 %
TEST DATA Train A Test pressure achieved:
IPI-923 psig Time 10-minute hold / Inspection started: I IPI-923 psig Time i
Inspection completed: -
IPI-923 psig Time IT-34A SI ACCUMULATOR ~
Inspection started:
IPI-940 psig Time Inspection completed:
IPI-940 psig Time
- 1 Page 30 of 34 CONTINUOUS USE e
NUCLEAR POWER BUSINESS UNIT IT 530A INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
UNIT I 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 i leakage through boundary valves.
/
Test Director Date ,
i QTS Reference Report Number:
i
,r i
i a
1 i
1.
l
.?!
.h
- \
j '
.6 )
-:3
+
a#
--. . .=-:= n l
i 1
l 4
Page 31 of 34 CONTINUOUS USE
i i
NUCLEARPOWER BUSINESS UNIT IT 530A l INSERVICE TESTS MAJOR Revision 2 i LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 {
MAINTENANCE PROGRAM TEST OF THE TRAIN A HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 i
ATTACHMENT G RHR TRAIN A 40-MONTH FUNCTIONAL PRESSURE TESI PRE-TEST DATA Record calibration dates for:
IPI-628 TEST DATA Test pressure achieved '
IPI-628 psig Time 10-minute hold / Inspection started IPI-628 psig Time Inspection completed IPI-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 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.
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Test Director Date QTS Reference Report Number:
Page 32 of 34 CONTINUOUS USE e 9
NUCLEARPOWER BUSINESS UNIT IT 530A 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 1 l l
i ATTACHMENT H ;
TROUBLESHOOTING TRAIN A RHR LEAKAGE >l.5 nal/hr l1 1; Firmly SHUT the following valves:
1RH-713A,1HX-11 A/B Inlet Crossconnect ~
. IRH-713B,1HX-11 A/B Inlet Crossconnect ,
IRH-716C,1HX-11 A/B Outlet Crossconnect i 1RH-716D, lHX-11 A/B Outlet Crossconnect IRH-823 A, IP-10A Suction Drain -
- 1SI-857A, IP-15A Suction from RHR I ISI-851C, Interdisc thermal release isol for ISI-851 A
- 1. Station a dedicated operator whose duties will be to shut IRH-V2 and secure the f
Train B hydro pump _in the event of a Unit I reactor protection or safeguards i actuation.
l
- 3. Shut IRH-V2, disconnect the suction pressure gauge tubing at IRH-V2 and connect a Haskal hydro pump at IRH-V2.
- 4. With 1RH-V2 shut, operate the second hydro pump per 01-65 to raise discharge pressure to 100 psig. j i
- 5. Open IRH-V2 and raise Train B RHR pressure to between 325 and 350 psig, not to exceed 350 psig, as read at IPI-629. I
- 6. Adjust Unit I letdown pressure to beween 325 and 350 psig, not to exceed 350 psig, as read at IPI-135.
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,.- =-?
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Page,33 of34 CONTINUOUS USE O .
NUCLEAR POWER BUSINESS UNIT IT 530A I
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 1 Attachment H l i
NOTE: Ensure measurements are taken on the Train A hydropump.
- 7. Measure and record total Train A RHR input pumping rate (as in Step 5.13.2)
AH = inches AT = minutes 1PI-628 = psig AH Totalinput = 946 x = 946 x = seem AT
- 8. Restore Unit I letdown pressure to normal per DSS.
- 9. Shut IRH-V2 and secure the Train B hydro pump.
- 10. Reconnect the suction pressure gauge tubing and leak check by momentarily opening 1RH-V2. (The dedicated operator may be released at this point.)
9
- 11. Depressurize Train B RHR:
- a. Open IRH-V2 and crack open iRH-V2B.
- b. When Train B RHR is depressurized, as indicated on IPI-629, shut IRH-V2 and IRH-V2B.
- 12. Open 1SI-851C and retum to procedure Step 5.19.
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, . Page 34 of 34 CONTINUOUS'USE
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