ML20138K255
| ML20138K255 | |
| 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-530B, NUDOCS 9702180082 | |
| Download: ML20138K255 (28) | |
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D N,MINSERVICE TESTS ? '3-
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t ;l t To detect and q.uantify leakage from the components comprising the high head safety mjection 1
,g i.and ' residual heat removal systems.
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.s fj} Q 'M ti; ? This' test is part'of the Leakage Reduction and Preventive
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- by NUREG-0578, Item 2.1.6a.
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j 1~.2 d 6This. test is part of the program to evaluats ths integrity' of post-accident recovery systems outside centainment as required by Technical Sp+incation Table 15.4.1-2. ' 22).
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"013 iTo hydrostaticallyltest, inspect and measure leakage from components of the RHR system 8
including ist p n leakage as required by Technical Sparheian 15 4 4 IV A I ( )...a and t
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i 15.4.4.IV.A.2/
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1,4 iR' e' fueling frequency, quantified seat leakage testing ofvalves ISI-854B, IRH-706B, as 3
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frequirsd by ASME Boiler and Pressure Vessel Code, Section 'XI, " Rules for Inspection of -
~ Nuclear Power Plant Components,"
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- This procedure fulfills the 40-month functional pressure test requirements for Class 2 y
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! HHSI and RHR piping in accordance with ASME Section XI and PBNP Pressure Test Program.
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' 42.05 REFERENCES
'dT
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- o 22'.D D EDS Nuclear Report, " Leakage Pa%'d Preventive Maintenance Program at Pu f!
/ -
._ Beach N_uclear Plant," dated 07-24-80
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tj;s[4 A ' f 2.2 L iEDS Nuclear, "High Pressure Safety Injection System Leakage Test," TMI-02, dated :
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W J12-17-80'-
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Mi 9702180082 970210 PageIof28-
- CONTINUOUS USE -
PDR ADOCK 05000301
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",? NUCLNARPOWERCUSINESS UNITc T
IT 530B!
? INSERVICE TESTS
- MAJOR.
! Revision 2 -
/LEAKAGN REDUCTION AND PREVENTIVE,
- January 31,21997 i
+
MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING) -
iUNIT 1 l
s (2.41 i Technical Soccifications:-
~
- 2.4.1 ~
i Table 15:4.1-2, Item 22
- 2A.21
':15.4.4.IV.A.I.(a) ;
.i e
2.4.31
' 15.4.4.IV.A'2
- 2.52 L 01-65, " Post-Maintenance Pressure Testing"'
g y
' " 12'.6 L NUREG-0578, item 2.1.6.a, " Leakage Reduction and Preventive Maintenance Program" l
4 32.7- ' IR 96-006, NRC Inspection Report; NRC Commitment for Operations procedures
'PMT/QC reviews.-
i
, 3.0..
' PRECAUTIONS-c
' 3.1..
IF THERE IS ANY PROBLEM IN PERFORMING'THIS TEST, IMMEDIATELY
- y
- NOTIFY THE DUTY SHIFT SUPERINTENDENT.: OPERATION OF THIS
~. EQUIPMENT IS A TECHNICAL SPECIFICATION REQUIREMENT.
3.2.
Liquids leaking from various components of the HHSI o' RHR systems will be mildly r
radioactive, and appropriate health physics practices should be observed.
3.3 Hydro Pumps:
3.3.1 Hydro pump skids must be prevented frem rolling (i.e, wheels chocked, bral,
3_
locked, chained to wall, etc.) to minimize the risk of RHR piping damage i-j' seismic event.
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3.3.2 When a hydro pump is connected to a radioactive liquid system, maintain the
/3 i
. test point valve shut until hydro pump pressure is established, and shut the test f
point valve before securing the hydro pump on depressurizing, to prevent contamination of the hydro hose (s) and pump.
3.4 :
> 1PI-974, SI pump suction pressure gauge shall be isolated during this test, as it is outside the test boundary.
1, 43.5; LHSI pump suction pressure will be read on the installed gauges in the No. 2 lower
} pipeway on El.' 8'.-
)
P 1 age 2 of28 CONTINUOUS USE ar
NUCLEARPOWER BUSINESS UNIT IT 530B.
. INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
{Q y
MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 i
l Date RECORD DSS PROCEDURE vEiunED CURRENT AND CHECKED FOR TEMPORARY CHANGES !F FIELD COPR3 REQUIRED. USE PBF-0026 IAW NP !.24 AND DO EQI COMPLETE THIS BLOCK BY:
DATE:
i l.0, PURPOSE l
l To detect and quantify leakage from the components comprising the high head safety injection
- 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.
j 1
1.2 This test is part of the program to evaluate the integrity of post-accident recovery systems i
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 G
including intersystem leakage as required by Technical Speci6 cation 15.4.4.IV.A.I.(a) and 15.4.4.IV.A.2.
1.4 Refueling frequency, quantified seat leakage testing of valves 1SI-854B, IRH-706B, as required by ASME Boiler and Pressure Vessel Code,Section XI, " Rules for Inspection of j
Nuclear Power Plant Components."
e 1.5 This procedure fulfills the 40-month functional pressure test requirements for Class 2 I'HS1 and RHR piping in accordance with ASME Section XI and PBNP Pressure Test Program.
I
2.0 REFERENCES
I 4
2.1 EDS Nuclear Report, " Leakage Reduction and Preventive Maintenance Program at Point Beach Nuclear Plant," dated 07 24-80
_l 2.2 EDS Nuclear, "High Pressure Safety Injection System Leakage Test," TMI-02, dated 12-17 80 1
2.3 P& ids
!O 2.3.1 110E017, Sheets I and 2 SIS 2.3.2 110E018, Sheet 1 Aux Coolant System 9702180082 970210 Page1of28 CONTINUOUS USE PDR ADOCK 05000301 P
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NUCLEAR POWERBUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 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 OI-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 NOTIFY THE DUTY SHIFT 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 ofRHR 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 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 i
pipeway on El. 8',
Page 2 of 28 CONTINUOUS USE
NUCLEAR POWERBUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 4
'p MAINTENANCE PROGRAM TEST OF THE TRAIN B l
.G HHSI AND RHR SYSTEMS (REFUELING)
~
UNIT 1 i
3.6-If, at any time, RHR or SI pump suction pressure is less than the NPSH required, this test l
must be discontinued until the problem is corrected. The SI pump must not be operated l
l without the associated RHR pump operating and the associated low head to high head i
crossconnect open.
1 3.7 Limit the run time of the HHSI pumps to s25 minutes when solely on mini-recire flow.
i j
Measured mini-recire flow is 110 gpm. Minimum total flow for continuous operation is l
225 gpm.
1 t
3.8 Limit the run time of the LHSI pumps to s30 minutes when solely on mini-recirc flow (design flow rate of 150 gpm). Minimum total flow for contmuous operation is 520 gpm.
t i
j INITIALS j
4.0 INITIAL CONDITIONS 1
' 4.1 RHRis aligned for LHSI per CL-7A 4.2 HHSIis aligned per CL-7A.
4.3 Standby emergency power shall be available to the 4160 V safeguards buses I A05, I 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:
1-4.4.1 IFE-659 of the HHSI high flow recirc line.
i 4.4.2 IFE-660 of the LHSI high flow recirc line.
- ~
4.5 An RWP is available, ' cluding entry into containment e
m
- 4.6 If a 40-month functional pressure test is required, then:
^"
-l 4.6.1 Pre-test data of Attachments E and F are completed.
i 1
4.6.2 The QTS inspector is notified of the test.
4.6.3 The ANII inspector is notified of the test.
O Page 3 of 28 CONTINUOUS USE i
)
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT I INITIALS 4.7 The following equipment is available:
~
4.7.1 Stopwatch 4.7.2 Graduated cylinderin ml or cc 4.7.3 Leakage collection apparatus for 2 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-V2, IP-10B suction gauge isolation, and a rule to measure reservoir waterlevel.
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-829B so that a spill ofRWST water does not occur from vent valve ISI-V23.
l-4.11 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.
i DSS Time Date 5.0 SEAT LEAKAGE TEST OF RHR TRAIN B VALVES 5.1 Alienment of RHR High Flow Test Line 5.1.1 Verify IRH-706A&B, test line isolation valves, are shut firmly.
Page 4 of 28 CON.TINUOUS USE 0
9 4
e e
-NUCLEAR POWER BUSINESS UNIT.
IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
,;q MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
. UNIT 1 INITIALS i
5.1.2 At'ach a Tygon tube to IRH-V16 and route the tube to an elevation greater than the highest point within the boundary of 1RH-706A&B and 742. Secure the Tygon in place to act as a system overflow vent.
NOTE:
This procedure assumes that the 1FE-660 onfice is installed and the blank is removed Othawise thefill and vent ofthe a
test line will need to be modsfied byfilling through 1RH-706A orb.
5.1.3 With all test line vents and drains shut, partially open IRH-742
{
and 742B.
j 5.1.4 Crack open IRH-V16 to fill / prime the test line and leak l
detection hose until it overflows into a container, then shut j;
1RH-742 and 742B firmly.
5.1.5 Fully open IRH-V16. Measure and record a stabilized baseline leak rate, if any, at IRH-V16.
Baseline Leakage =
scem 4
5.1.6 Shut IRH-V16.
5.2 Alignment of Sorav system 5.2.1 Attach a Tygon tube to the swagelock tee at ISI-848K and route the tube to an elevation greater than the highest point within the boundary of ISI-870B, 871B, 860C and 860D.
J. <
Secure the Tygon in place to act as a system overflow vent.
I 5.2.2 Crack open ISI-848K to prime the leak detection hose until it overflows into a container, then shut 1SI-848K.
j
' 5.3.
Ventino RHR to HHSI Pininn 5.3.1 Route tubing to floor drain from 1RH-V4, HX-1IB RHR HX supply to SI and spray vent.
5.3.2 Crack open IRH-V4 and vent piping until a steady stream of -
water is apparent, then shut and cap 1RH-V4.
Page 5 of 28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANC5 PROGRAM TEST OF THE TRAIN B HHSI AND RER SYSTEMS (REFUELING)
UNIT 1 INITIALS aCAUTIONa AS RHR SYSTEM PRESSURE IS INCREASED TO TEST PRESSURE, THE LEAK-OFF POINT AT 1RH-V16 MUST BE MONITORED TO PREVENT LEAK-OFF CONTAINER OVERFILLING.
- CAUTIONa IF A UNIT 1 SAFEGUARDS OR REACTOR PROTECTION ACTUATION OCCURS AT ANY TIME DURING PERFORMANCE OF THE REMAINDER OF THIS PROCEDURE SECTION:
- 1) VERIFY OPEN ISI-856B AND ISI-870B.
- 2) VERIFY IP-10B AND IP-14B CONTROL SWITCHES TO AUTO.
- 3) IF IICP-666B IS IN PROGRESS, DIRECT I&C g
PERSONNEL TO RESTORE 1RH-625 TO W
FULLY OPERATIONAL STATUS AND INFORM CONTROL ROOM WHEN RESTORATION IS COMPLETE.
- 4) SHUT 1RH-V2 AND SECURE THE HYDRO PUMP.
5.4 Enter LCO for Train B RHR, if required, and notify I&C that IICP-666B may commence.
5.5 Place the IP-10B RHR pump control switch in PULLOUT.
Page 6 of.28
, CONTINUOUS 'USE
- NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
.O MAINTENANCE PROGRAM TEST OF THE TRAIN B i
()
hHSI AND RHR SYSTEMS (REFUELING)
UNIT 1
}
INITIALS i
5.6 Verify the following valves shut, to is61ste the test volume:
ISI-851B IP-108 sump "B" suction MOV 1SI-856B IP-10B RWST suction MOV l
ISI-852B LHSI Core Deluge MOV
[
ISI-871B RHR to IP-14B suction MOV i
IRH-720 RHR Return to RCS MOV i
1RH-823B IP-10B suction drain i
IRH-713B lHX-1IB/A inlet crossconnect 1RH-716C IHX-1IB/A outlet crossconnect l
1SI-857B RHR to 1P-ISB suction manualisol l
1RH-704B IP-10B loop suction manual isolation 5.7 Shut 1RH-V2, then disconnect the suction gauge tubing at IRH-V2 and connect the hydro hose to the welded reducer at IRH-V2.
5.8 With 1RH-V2 shut, operate the hydro pump per appropriate part of OI-65 to raise discharge pressure to 100 psig.
5.9 Open IRH-V2 and raise test volume pressure per 01-65 to 350
(+25, -0) psig as indicated on 1PI-629.
NOTE:
To save time, thefollowing leakage measurements should be determined concurrently.
5.10 Maintain a stable test pressure for 10 minutes, then quantify the following:
5.10.1 If 40-month pressure test is required, notify QTS /ANI to begia ia&Jon, and record data required by #+-w F.
5.10.2 Walkdown piping and components, and record leakage to atmosphere on Attachment B.
" - = " -
O Page 7 of 28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B 1
HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 INITIALS 5.10.3 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.
AH inches
=
AT minutes
=
IPI-629 Psig
=
5.10.4 1RH-706B leak rate determination
- a. Open IRH-V16 and record leak rate through IRH-706B at IRH-V16 = _
seem
- b. When leak rate measurement for 1RH-706B is complete, 9 {l shut IRH-V16.
i 5.10.5 Quantify 1P-10B sealleakage =
seem 5.11 Calculate the boundary valve leak rate as follows:
(5.10.4.a)sccm -
(5.1.5) seem =
IRH-706B scem j
(5.10.5)
IP-10B Seal scem Boundary total (sum of above leak rates) scem 5.12 Calculate the leak rate attributable to ISI-856B and IRH-823B using the following:
946 x
= 946 x totalsccm
=
total seem 5.11
= 1SI-856B/823B valve leakage
=
sCCm O
Page 8 of 28 CONTINUOUS USE
- 9
NUCLEAR POWERBUSINESS UNIT IT 530B l
INSERVICE TESTS MAJOR Revision 2 4
LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
<f'
. MAINTENANCE PROGRAM TEST OF THE TRAIN B l
(
HHSI AND RHR SYSTEMS (REFUELING) 1-
' UNIT 1 INITIALS l
5.13 ISI-871B Seat Leakage Test l
5.13.1 ~
Enter the LCO for Train B Spray cystem, if required.
l t
5.13.2 Place the IP-14B control switch in PULLOUT.
l 5.13.3 Shut ISI-870B.
l I
5.13.4 Open ISI-848K and measure ISI-871B leak rate at 1SI-848K =
scem i
j 5.13.5 Shut ISI-848K.
4 5.14 When inspection / data collection per Attachment (s) B and F (ifrequired) is l
complete, evaluate Train B RHR Tech Spec leakage, and if >l.5 gal /hr (95 secm), perform Aweh===' G troubla=haating l
NOTE:
Although the target testpressure is 350psigfor seat lack ge A
measurement ofISI-854B, the minimum acceptablepressure is 100 psig as indicated by 1PI-629. If1PI-629 pressure stabilizes at
<100psig after opening 1S1-856E, then record the maximum
[
achievable hydro pump data per Step 5.15 and in addition, perform l
the specialtest ofAttachment A.
5.15 Electrically open ISI-856B, then operate the hydro pump to restore test volume pressure to 350 (+25, -0) psig and record as in Step 5.10.3.
^
AH inches
=
g AT
=
mmutes IPI-629 psig
=
5.16 When ianae' ion / data collection of Attachments B and F (if required) is
~~
complete, shut IRH-V2, then secure, depressurize and disconnect the hydro pump, per 01-65.
I l
f.MI i'
5.17 Reconnect the suction gauge tubing at IRH-V2 and leak check by
[
momentarily opening 1RH-V2.
5.18. Determine baseline leak rate for 1SI-871B by opening 1SI-848K and measuring leak rate at 1SI-848K =
. sccm.
N I
Page 9 of 28 CONTINUOUS USE
NUCLEAR POWER @USINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 INITIALS 5.19 Shut ISI-848K.
'5.20 Open ISI-870B.
5.21 Place IP-14B control switch to AUTO.
5.22 End LCO for Train B Spray.
5.23 Verify open 1SI-856B.
5.24 Place IP-10B control switch to AUTO.
5.25 Verify llCP-666B is complete and end LCO for Train B RHR, ifrequired.
5.26 Complete the test data sheet section for seat leakage rates of IP-10B suction valves.
5.27 Remove and store all tygon tubing installed for this test.
6.0 TRAIN B LHSI/HHST " PIGGYBACK" TEST 6.1 Pre-Test System Alignment / Verification 6.1.1 Verify the valve position of the following:
POSITION ISI-897A SItestlineisolation AOV Gag Open ISI-897B SI test line isolation AOV Gag Open IRH-742A RHR to RWSTlow flow Shut 151-828 U1 blender to UI RWST Shut ISF-811 P-33 to UI RWST Shut 1
1WL-1729 ISI-876B
_RCDT pump to UI RWST Shut IP-15B mini-recire Open 6.1.2 Verify oil level in IP-15B at or above one-half sightglass.
Contact the DSS for the type of oil required.
6.1.3 Verify proper oil level in the thrust bearing housing of IP-10B.
Contact the DSS for the type of oil required.
Page 10 of 28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR
-l Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 l
O MAINTENANCE PROGRAM TEST OF THE TRAIN B Q
HHSI AND RHR SYSTEMS (REFUELING)
UNIT I INITIALS i
1 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 stream is observed at ISI-V23, then shut firmly ISI-829C&D.
- d. Ifleakage persists at ISI-V23, then verify shut ISI-829A&B.
- e. Record background leak rate at ISI-V23, if any.
SCCM f.
Shut ISI-V23.
6.2 HHSI Train B Leakane Test
- CAUTIONa IF A SAFEGUARDS ACTUATION OR A REACTOR PROTECTION SYSTEM ACTUATION SHOULD OCCUR ON UNIT I WHILE PERFORMING THIS TEST, THEN i
IMMEDIATELY PROCEED TO STEP 6.2.26.
RECOVER SYSTEMS PER STEPS 6.2.26 THROUGH 6.2.37, THEN TERMINATE THIS
..I 3
TEST.
32
~$
6.2.1 Unlock r.nd open IRH-742, high flow test line RWST isolation.
6.2.2 Position 1RH-742B, high flow test line FCV, to 32% open position (-1000 gpm).
f O
G Page11 of28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 INITIALS 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 B RHR. if required.
6.2.5 Place IP-10B control switch to PULLOUT.
6.2.6 Shut 1RH-733B, IP-10B mini-recire isolation.
6.2.7 Unlock and open IRH-706B, high flow test line inlet isolation.
6.2.8 Verify open 1SI-856B, IP-10B RWST suction MOV.
6.2.9 Verify IP-10B discharge pressure at <50 psig per IPI-629.
6.2.10 Align IPI-653B, IP-10B suction pressure gauge, for service:
a.
Shut 1RH-V2A, IPI-653B vent.
- b. Open IRH-V2, suction gauge root isolation.
- c. Open IRH-V23, IPI-653B inlet isolatior..
6.2.11 Start IP-10B.
- CAUTIONa MONITOR AND VERIFY IP-10B SUCTION PRESSURE IS >0 PSIG PER IPI-653B ANYTIME "k
FLOW IS CHANGED.
6.2.12 Verify IP-10'B suction pressure is >0 psig.
Page 12 of 28 CONTINUOUS USE
'4
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 fs MAINTENANCE PROGRAM TEST OF THE TRAIN B i
HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 INITIALS 6.2.13-Position IRH-742B for a test line flow of 600 50 gpm per l
IFIT-660.
NOTE:
Identify in remarks section any leakage observedfrom the pump or mechanicalseals. Also include amount (seals wet, l
dropsper minute, etc.), color, and any other comments.
6.2.14 Check the pump and mechanical seals for leakage, unusual noise, and evidence of overheating.
6.2.15 Enter LCO for Train B HHSI, if required.
6.2.16 Place IP-15B control switch to PULLOUT.
6.2.17 Shut ISI-896B, IP-ISB suction MOV.
l 6.2.18 Slowly open ISI-857B, low head to high head crossconnect, to O
full open.
6.2.19 Visually inspect the shaft seals of 1P-15B. Collect, measure, and time any observed leakage. Record required data of Attachment C, Section 1.0.
- CAUTIONa DO NOT SECURE IP-10B WITHOUT FIRST SECURING IP-15B OR A TOTAL LOSS OF IP-15B SUCTION MAY OCCUR, RESULTING IN i
PUMP DAMAGE. IF IP-10B POWER IS LOST FOR ANY REASON, THEN IMMEDIATELY
.M SECURE IP-15B.
NOTE:
Reference P&L 3.7.
6.2.20 Start IP-15B.
i 6.2.21 Open 1SI-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 C, Section 2.0. Then shut and cap i
.p 1SI-V23.
Q 1
Page 13 of 28 CONTINUOUS USE
.U
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 INITIALS 6.2.22 With ISI-829B shut, collect and record ISI-829B leakage to atmosphere on Attachment D.
NOTE:
The IP-1SB SIpump must run 10 minutes at testpressure prior to start ofinspectionfor Attachment E 6.2.23 For a 40-month test, perform the following substeps.
Otherwise N/A these substeps.
a.
Open ISI-829B, open and backseat ISI-829D, HHSI high flow test line isolation valves.
- b. Adjust ISI-829C for a test line tiow of 250 $25 gpm per IFIT-659.
- c. Unlock and shut ISI-876B, IP-ISB mini-recire isolation valve.
- d. Record pressure achieved and inspection start data on Attachment E.
6.2.24 Visually inspect the shaft seals of IP-15B. Collect, measure, and time any observed leakage. Record required data of Attachment C, Section 3.0.
6.2.25 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 or.
Attachment D. Collect, measure, time, and record observed leakage. Record data on Attachment D.
6.2.26 When all data is completed, including Attachment E for 40-month tests, secure IP-15B and place control switch to PULLOUT.
6.2.27 Secure IP-10B and place control switch to PULLOUT.
6.2.28 Red lock open ISI-876B. Lock No.
/
Page 14 of 28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT
. IT 530B INSERVICE TESTS MAJOR
' Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 OUNIT1 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
INITIALS 6.2.29 Red lock shut:-
ISI-829B Lock No.
/
ISI-829D Lock No.
/
1RH-742 Lock No.
/
6.2.30 Shut 1SI-857B.
/
6.2.31 Open ISI-896B, IP-ISB suction MOV.
/
6.2.32 Place IP-ISB control switch to AUTO.
/
6.2.33 Exit LCO for Train B HHSI, if required.
6.2.34 Remove IP-10B suction gauges from service:
1' r.
O s
- a. Shut IRH-V2.
- b. Open IRH-V2A.
- c. Shut IRH-V2B.
6.2.35 Red lock shut IRH-706B. Lock No.
/
7 6.2.36 Red lock open IRH-733B. Lock No.
/
7,.
~
.ys 6.2.37 Place IP-10B control switch to AUTO.
/
((,
n 6.2.38
_ Exit LCO for Train B RHR, ifrequired.
22 O
V Page 15 of 28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT I INITIALS 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 dwiatic. ns complete.
8.2 Any requirements for corrective action?
Yes No If yes, give details in the remarks section and MWR No.
51. 3 Data analyzed.
By Date Remarks:
- l
.(
w Page 16 of 28 CONTINUQUS USE 9
0 8
e
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
/*
MAINTENANCE PROGRAM TEST OF THE TRAIN B
~(,
. IRISI AND RHR SYSTEMS (REFUELING)
UNIT 1 TEST DATA SHEET 1.0 Valve Seat Leakage l
NOTE:
Allleak rates arein secm.
NOTE:
Column A data is information only. Column B data is applicable to Technical Specifications and NUREG 0578.
t Col A Col. B 1.1 ISI-856B and IRH-823B (Reference Step 5.12) i 1.2 ISI-854B (Reference Step 5.15 and Attachment A) cc AH 946
= 946 x _
gx T
=
seem n.inus Boundary leakage (Step 5.11) =
O or Attachment A =
gpm 1.3 1RH-706B (Reference Step 5.11) =
. ~.
l l
\\
d Page 17 of 28 CONTINUOUS USE
i NUCLEAR POWER BUSINESS UNIT IT530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 i
ATTACHMENT A Seat Leakace Test ofISI-854B Usine P-33 NOTE:
This test is required when the seat leakage ofISI-854B exceeds the pumping rate of the hydropump and test systempressureper JPI-629 is
<100psigper Step S.16.
INITIALS 1.0 Shut IRH-V2, then secure the hydro pump.
2.0-Secure SFP recire or Unit 2 RWST recire (Refer to U2 PC-25A, Part 1), ifin operation.
3.0 Align P-33 for Unit 1 RWST recirc (Refer to Ul PC-25) at 20 gpm per FI-636 by throttling with ISF-811.
4.0 Verify IRH-701 shut, then open ISF-819 and verify FI-636 flow remains at 20 bpm.
5.0 Shut IRH-709B and 733B.
6.0 Open IRH-704B to ~25% open and allow flow at FI-6% to stabilize.
l 7.0 Record the following data:
P-33 flow per FI-636 gpm
)
P-33 pressure per PI-651 psig
- j Test volume pressure per IPI-629 psig 8.0 Shut ISF-819 and IRH-704B.
)
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 IPI-629 psig 10.0 Open IRH-733B and 709B, then return P-33 to previous status or as directed by the DSS when the testing is complete.
Page 18 of 28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B q
HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 Attachment A INITIALS 11.0 Calculate ISI-854B seat leakage as P-33 flow in Step 7.0 niinus 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 5.15.
4 I (J
\\..
4 1
4 g.
J:
..;s O
r J
LJ Page,1,9 of 28 CONTINUOUS USE u
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B 1
HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 ATTACHMENT B Leakage Rate Comnonent ID Component Descriotion (secm) i IP-10B RHR Pumo Cubicle IRH-823B IP-10B suction low point drain IRH-V12 IP-10B seal supply vent IRH-V13 IP-10B seal heat exchanger inlet vent IRH-71IF IP-10B sealleak telltale Flange IP-10B seal RO flange 1RH-711B 1PT-629 root valve 1P-10B Pump seals PAB General Area South. El -19' 1PT-629 IP-10B discharge pressure transmitter Unit i RHR Piceway l
1RH-710B IP-10B discharge check valve 1RH-709B 1P-10B discharge isolation 1RH-713B 1P-10B discharge cross-connect ISI-851B IP-10B "B" sump suction MOV ISI-851D Pressure equalizer for ISI-851B 1RH-715B lHX-1IB inlet isolation IRH-D5 IHX-1IB interpass drain 1RH-D6 IHX-1IB interpass drain 1RH-D7 IHX-1IB interpass drain PAB General Area South. El -5' 1RH-625 IHX-1IB discharge TCV 1RH-716B 1HX-1IB outlet isolation 1RH-716C IHX-1IB outlet cross-connect PAB General Area South. El 8' i
1RH-711E' 1P-10B seal water supply IFT-928 Train B RHR flow transmitter 1RH-V4
)
Train B RHR to SI and Spray suction line vent (in ovrhd of
. seal wtr return filter cubicle) 1 Page 20 of 28 CONTINUOUS USE i
-NUCLEARPOWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 7'y MAINTENANCE PROGRAM TEST OF THE TRAIN B V
HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 Attachment B i
Leakage Rate Comoonent ID Comoonent Descriotion (sccm)
Lower Pineway #2 1RH-V2B 1PI-653B root valve IRH-V2A IPI-653B bleed-off for seat leakage of IRH-V2B IRH-V2C IPI-654B root valve IPI-654B IP-10B RHR suction pressure indication 1SI-856B 1P-10B RWST suction MOV ISI-854B 1P-10B RWST suction check
=IRH-V2 IPI-653B and 654B root valve 1RH-704B IP-10B RCS loop suction isolation 1RH-848F IFT-928 high pressure root IRH-848E 1FT-928 low pressure root IFE-928 Train B RHR flow orifice IRH-733B 1P-10B mini-recirc isolation IRH-706A IP-10A high flow test line isolation s
1RH-706B IP-10B high flow test line isolation 1RH-D14 High flow test line drain
- IRH-V16 High flow test line vent IRH-D15 High flow test line drain 1RH-742B High flow test line flow control IRH-890C RH-742 RHR return thermal release IFE-660 High flow test line orifice flange 1RH-662A IFIT-660 high side root 1RH-662B IFIT-660 low side root IFIT-660 High flow test line flow indicator transmitter P22 Train B RHR discharge containment penetration Containment Sorav and SI Pumo Area
_.__ i.-
ISI-871B Train B RHR/CS cross-connect MOV ISI-857B Train B RHR/SI cross-connect isolation Other miscellaneous system components
/O
'A.)
Page 21 of 28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHS1 AND RHR SYSTEMS (REP"-"NG)
UNIT 1 ATTACHMENT C IP-15B PUMP SEAL LEAKAGE & 1SI-829B SEAT LEAKAGE 1.0 SEAL LEAK RATE WITH IP-15B SECURED 1P-10B Discharge Pressure Per IPI-629 =
psig cdcollected seconds Leak Rate = (cc collected /sec)(60 sedmin) =
SCCM 2.0 1SI-829B SEAT LEAK RATE IP-ISB Discharge Pressure per IPI-922 =
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-15B OPERATING IP-10B Discharge Pressure Per IPI-629 =
psig IP-ISB Discharge Pressure Per IPI-922 =
psig cc collected seconds Leak Rate = (cc collected /sec) (60 sedmin) =
SCCM Page 22 of 28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
(~
MAINTENANCE PROGRAM TEST OF THE TRAIN B i
HHSI AND RHR SYSTEMS (REFUELING) i UNIT 1 j
ATTACHMENT D 1
TRAIN B ATMOSPHERIC LEAKAGE LEAKAGE RATE COMPONENT DESCRIPTION (SCCM)
Comnonents Located in Containment Sorav/SI Pumo Area 1SI-857B RHR/SI crossconnect......
ISI-896B IP-15B suction MOV.......
Flange 1P-15B suction flange...........
ISI-D9 IP-ISB discharge line drain...
Flange IP-15B discharge flange......
1SI-881B 1PT-922 root valve.............
1PT-922 1P-ISB discharge pressure transmitter...
!SI-889B 1P-15B discharge check valve...........................
)
1SI-888B 1 P-1 SB discharge isolation.....................................................
1SI-829A IP-15Aa.B SI pumps discharge crossconnect............................
/
1SI-891B 1 P-1 SB mini-recirc check valve.............................................
i ISI-829B IP-15A&B SI pumps discharge crossconnect...
ISI-V23 HHSI high flow test line vent..
1SI-D32 HHSI high flow test line drain..
IFI-659 HHSI high flow test line orifice flange.
i 1SI-663B 1FI-659 high side isolation.
IF1-659 High side sensing line.
MISC Other miscellaneous system components....
i Comoonents Located in Pineway No. 4 I
,.3 i 1SI-848C 1 FI-924 LP root valve.........................................................
1SI-848D 1 FI-924 HP root valve..............................................................
3.u>
IFE-924 S1 Train B flow orifice..........................................................
& i
...3 1FT-924 SI Train B flow transmitter....
'~
lSI-866B SI Train B discharge MOV....
MISC Other miscellaneous system components.....
I 1P-10B discharge pressure, IPI-629 psig IP-ISB discharge pressure, IPI-922 psig V
Page 23 of 28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 ATTACHMENT E HHSI 40-MONTH INSERVICE PRESSURE TEST PRE-TEST DATA Record calibration dates for:
1PI-922 1PI-936 Record RWST Level per ILI-972 IT-34B Accumulator Level Per IL1-934 TEST DATA Train B Test pressure achieved:
IPI-922 psig Time 10-minute hold / Inspection started:
IPI-922 psig Time Inspection completed:
IPI-922 psig Time l
IT-34B SI ACCUMULATOR Inspection started:
7..
IPI 936 psig Time Inspection completed:
IPI-936 psig Time i
I I
Page 24 of,28 CON.TINUOUS USE
.A
NUCLEAR POWER BUSINESS UNIT IT 530B' INSERVICE TESTS MAJOR Revision 2 i
LEAKAGE REDUCTION AND PREVENTIVE January 31,1997
('
MAINTENANCE PROGRAM TEST OF THE TRAIN B
(
HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 Attachment E 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 (D
%)
^
t,
.i Page 25 of 28 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 ATTACHMENT F RHR TRAIN B 40-MONTH FUNCTIONAL PRESSURE TEST PRE-TEST DATA Record calibration dates for:
1PI-629 TEST DATA Test pressure achieved:
IPI-629 psig Time 10-minute hold / Inspection started:
IPI-629 psig Time Inspection completed:
IPI-629 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.
/
Test Director Date QTS Reference Report Number:
O Page 26 of 28
. CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2
' LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 f^g MAINTENANCE PROGRAM TEST OF THE TRAIN B
!Q HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 ATTACHMENT G TROUBLESHOOTING TRAIN B RHR LEAKAGE >1.5 eal/hr D TITIALS 1.
Firmly SHUT the following valves:
1 RH-713 A,1HX-I I A/B Inlet Crossconnect IRH-713B, lHX-11 A/B Inlet Crossconnect IRH-716C,1HX-11 A/B Outlet Crossconnect 1RH-716D,1HX-II A/B Outlet Crossconnect 1RH-823B, IP-10B Suction Drain ISI-857B, IP-ISB RHR Suction ISI-851D, Interdisc thermal release isol for ISI-851B 2.
Station a dedicated operator whose duty will be to shut 1CV-133 in the event of a Unit I reactor protection or safeguards actuation.
3.
Open 1CV-133 to pressurize Train A RHR to letdown line pressure.
4.
Raise letdown pressure to between 325 and 350 psig, not to exceed 350 psig, as read at IPI-628.
NOTE:
Ensure measurements are taken on the Train B hydropump.
i 5.
Measure and record total Train B RHR input pumping rate (as in Step 5.10.3)
AH inches
=
AT minutes
=
1PI-629 =
psig cc MI-Total input =946 5x y = 946 x
=
sccm
. Os v
i Page 27 of 28 CONTINUOUS USE
- 4
NUCLEAR POWER BUSINESS UNIT IT 530B INSERVICE TESTS MAJOR Revision 2 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)
UNIT 1 i
Attachment G INITIALS 6.
Restore Unit I letdown pressure to normal per DSS.
i 7.
Depressurize Train A RHR-Open IRH-VI and crack open IRH-VlB.
a.
b.
When Train A RHR is depressurized, as indicated on IPI-628, shut 1RH-VI and IRH-VIB.
8.
Open ISI-851D and return to procedure Step 5.15.
REMARKS:
s O'
1
't f
gy i
Page 28 of 28 CONTINUOUS'USE
- l 1