ML20138K294

Rev 3 to IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) Unit 2

ML20138K294
Person / Time
Site:	Point Beach
Issue date:	01/31/1997
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
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References
RTR-NUREG-0578, RTR-NUREG-578 IT-535B, NUDOCS 9702180135
Download: ML20138K294 (33)

Text

i NUCLEAR POWER BUSINESS UNIT IT535B INSERVICE TESTS MAJOR Revision 3 -

LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B s

)

' HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 Date RECORD DSS Pnocem vmrna cuantwr AuD el<textD ron iturOnanv enswots ir ritto COPIts REQUIRED. USC P8r 0026iIAW NP l.2 4 AND dog COMPLITE TliiS BLOCL BY:

DATE:

l 1.0 PURPOSE i

To detect and quantify leakage from the components comprising the high head safety injection I

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.

I 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 1.3 To hydrostatically test, inspect and measure leakage from components of the RHR system including intersystem leakage as required by Technical Specification 15.4.4.IV.A.I.(a) j and 15.4.4.IV.A.2.

1.4 Refueling frequency. quantified seat leakage testing of valves 2SI 854B,2RH-706B, as required by ASME Boiler and Pressure Vessel Code,Section XI, " Rules for litspection of j

Nuclear Power Plant Components."

}

1.5 This procedure fulfills the 40-month functional pressure test requirements for Class 2 HHS1 and RHR piping in accordance with ASME Section XI and PBNP Pressure Test l

Program.

2.0 REFERENCES

2.1 EDS Nuclear Report, " Leakage Reduction and Preventive Maintenance Pwp-o 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&lDs 2.3.1 110E035, Sheets 1 and 2 SIS

'2.3.2 Il0E029, Sheet 1 Aux Coolant System 4

9io2teot35 97o210 Page1of31 CONITNUOUS USE.

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1 NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 2.4 Technical Snecifications:

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 0165, " Post-Maintenance Pressure Testing" 2.6 NUREG-0578, Jtem 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 PERFORMINO THIS TEST,IMMEDIATELY NOTIFY THE DUTY SHIFT SUPERINTENDENT. OPERATION OF THIS EQUIPMENTIS 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.

j 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.

3.5 LHS1 pump suction pressure will be read on the installed gauges in the No. 3 lower pipeway on El. 8'.

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NUCLEAR POWER BUSINESS UNIT IT535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 G

MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 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 cross-connect open.

3.7 Limit the run time of the HHSI pumps to $25 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.

4 INITIALS 4.0 INITIAL CONDITIONS 4

4.1 RHR is aligned for LHSI per CL 7A i

4.2 HHSIis aligned per CL 7A.

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 2FE-659 of the HHSI high flow recire line.

4.4.2 2FE-660 of the LHSI high flow recire line.

4.5 An RWP is available, including entry into containment.

4.6 If a 40-month functional pressure test is required, then:

4 4.6.1 Pre-test data of Attachments E and F are completed.

~

4.6.2 The QTS inspector is notified of the test.

m 4.6.3 The ANII inspector is notified of the test.

4.7 The following equipment is available:

O V

4.7.1 Stopwatch Page 3 of 31 CONTINUOUS USE e

NUCLEAR POWER BUSINESS UNIT IT535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS 4.7.2 Graduated cylinderin ml or cc i

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 2RH-V2,2P-10B 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 recire line will be in operation.

4.10.2 Exercise caution when conducting the leak check of 2SI-829B so that a spill of RWST water does not occur from vent valve 2SI-V23.

4.11 Permission to Perform Test i

The conditions required by this test are consistent with required plant conditions, including equipment operability. Permission is granted to perform tids test.

DSS Time Date i

5.0 SEAT LEAKAGE TEST OF RHR TRAIN B VALVES i

5.1 Alienment of RHR Hich Flow Test Line 1

5.1.1 Verify 2RH-706A&B, test line isolation valves, are shut firmly.

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NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR i

Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 i -

MAINTENANCE PROGRAM TEST OF THE TRAIN B

!\\

HHSI AND RHR SYSTEMS (REFUELING)

[

UNIT 2 INITIALS I

5.1.2 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 ovedlow vent.

i l

NOTE:

This procedure assumes that the 2FE-660 orifice is installed

]

and the blank is removed. Otherwise thefill and vent ofthe test line will need to be modified byfdling through 2RH-706A or B.

1 5.1.3 With all test line vents and drains shut, partially open 2RH-742 4

and 742B.

5.1.4 Crack open 2RH-V16 to fill / prime the test line and leak detection hose until it overflows into a container, then shut 2RH-742 and 742B firmly.

l 5.1.5 Fully open 2RH-V16. Measure and record a stabilized baseline 4

leak rate, if any, at 2RH-V16.

Baseline Leakare =

seem j

5.1.6 Shut 2RH-V16.

I i

5.2 Alienment of Sorav system i

5.2.1 Attach a Tygon tube to the swagelock tee at 2SI-848K and 6

route the tube to an elevation greater than the highest point within the boundary of 2SI-870B,871B,860C and 860D.

Secure the Tygon in place to act as a system overflow vent.

3 5.2.2 Crack open 2SI-848K to prime the leak detection hose r.rttii ';

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overflows into a container, then shut 2SI-848K.

5.3 Ventinn RHR to HHS1 Pinine i

e 5.3.1 Route tubing to floor drain from 2RH-V4, HX-1113 RHR HX supply to Si and spray vent.

O 7

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NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31.1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS 5.3.2 Crack open 2RH-V4 and vent piping until a steady stream of water is apparent, then shut 2RH-V4.

5.3.3 Install the digital pressure gage at 2RH-V4 and open 2RH-V4.

• CAUTION

• AS RHR SYSTEM PRESSURE IS INCREASED TO TEST PRESSURE, THE LEAK-OFF POINT AT 2RH-V16 MUST BE MONITORED TO PREVENT LEAK-OFF 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:

1) VERIFY OPEN 2SI-856B AND 2SI-870B.

9l

2) VERIFY 2P-10B AND 2P-14B CONTROL SWITCHES TO AUTO.

3) IF 2ICP-666B IS IN PROGRESS, DIRECT I&C PERSONNEL TO RESTORE 2RH-625 TO FULLY OPERATIONAL STATUS AND INFORM CONTROL ROOM WHEN RESTORATION IS COMPLETE.

j

4) SHUT 2RH-V2 AND SECURE THE IIYDRO PUMP.

NOTE:

NotifyISIinspector that 40 month inspection willtakeplace at Step 5.10.1, ifrequired.

5.4 Enter LCO for Train B RHR, if required, and notify I&C that 2ICP-666B may commence.

5.5 Place the 2P-10B RHR pump control switch in PULLOUT.

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NUCLEAR POWER BUSINESS UNIT IT535B INSERVICE TESTS-MAJOR r

Revision 3 -

LEAKAGE REDUCTION AND PREVENTIVE January 31,1997

- MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS

,5.6 Verify the following valves shut, to isolate the test volume:

2SI 851B 2P-10B sump "B" suction MOV 2SI-856B 2P-10B RWST suction MOV 2SI 852B LHSI Core Deluge MOV 2SI-871B RHR to 2P-14B suction MOV 2RH-720 RHR Retum to RCS MOV 2RH-823B 2P-10B suction drain i

2RH-713B 2HX-11B/A inlet crossconnect i

2RH-716C 2HX-11B/A outlet crossconnect 2SI-857B RHR to 2P-15B suction manualisol

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2RH-704B 2P-10B loop suction manual isolation 5.7 Shut 2RH-V2, then disconnect the suction gauge tubing at 2RH-V2 and connect the hydro hose to the welded reducer at 2RH-V2.

5.8

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With 2RH-V2 shut, operate the hydro pump per appropriate part of OI 65 to raise discharge pressure to 100 psig.

5.9 Open 2RH-V2 and raise test volume pressure per OI 65 to 350 (+25, -0) psig as indicated on 2PI-629, and record pressure on digital pressure indicator, psig 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 begin inspection, and record data required by Attachment F.

5.10.2 Walkdown piping and components, and record leakage to atmosphere on Attachment B.-

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NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHS! AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS NOTE:

RHR system pressure should indicate approximately the same pressure as Step 5.9 as read on the digitalpressure indicator prior to taking AH and ATreadings.

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 2RH-706B leak rate determination 9

Open 2RH-V16 and record leak rate through 2RH-706B at a.

2RH-V16 =

scem

b. When leak rate measurement for 2RH-706B is complete, shut 2RH-V16.

5.10.5 Quantify 2P-10B seal leakage =

seem 5.11 Calculate the boundary valve leak rate as follows:

(5.10.4.a)scem -

(5.1.5) seem =

2RH-706B secm (5.10.5) 2P-10B Seal seem Boundary total (sum of above leak rates) sccm O

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NUCLEAR POWER BUSINESS UNIT IT 535B

- INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 C

MAINTENANCE PROGRAM TEST OF THE TRAIN B

(~

HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS 5.12 Calculate the leak rate attributable to 2SI-856B and 2RH-823B using the following:

0" 946 Ex

= 946 x total seem

=

in AT 5

total seem - 5.11 = 2SI-856B/823B valve leakage

=

scem 5.13 2SI-871B Seat Leakage Test 5.13.1 Enter the LCO for Train B Spray system, if required.

5.13.2 Place the 2P-14B control switch in PULLOUT.

(mj) 5.13.3 Shut 2SI-870B.

5.13.4 Open 2SI-848K and measure 2SI-871B leak rate at 2SI-848K = seem 5.13.5 Shut 2SI-848K.

5.14 When inspection / data collection per Attachment (s)B and F (if required) is complete, evaluate Train B RHR Tech Spec leakage, and if>l.5 gal /hr (95 secm), perform Attachment O troubleshooting.

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NUCLEAR TOWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS NOTE:

RHR system pressure should indicate approximately the same pressure as Step S.9 as read on digitalpressure indicatorprior to taking Alland ATreadings.

NOTE:

Although the target test pressure is 350psigfor seat leakage measurement of2SI-854B, the minimum acceptablepressure is 100 psig as indicated by 2PI-629. If2PI-629 pressure stabilizes at

<100psig after opening 251-856B, then record the maximum achievable hydro pump data per Step 5.15 and in addition, perform the specialtest ofAttachment A.

5.15 Electrically open 2SI-856B, then operate the hydro pump to restore test volume pressure to 350 (+25, -0) psig and record as in Step 5.10.3.

AH inches

=

AT minutes

=

IPI-629 psig

=

5.16 When inspection / data collection of Attachments B and F (if required) is complete. shut 2RH.V2.

5.16.1 Secure and disconnect the hydro pump per 0165.

5.16.2 Depressurize test volume per 0165 by opening 2RH-706B and 2RH-742A.

5.16.3 Shut 2RH-706B.

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5.16.4 Shut 2RH-742A l

PMT

~~~

5.17 Reconnect the suction gauge tubing at 2RH-V2 and leak check by momentarily openin5 RH-V2.

i 2

5.18 Determine baseline leak rate for 2SI 871B by opening 2SI-848K and measuring leak rate at 2SI-848K =

seem 5.19 Shut 2SI 848K.

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' NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 -

MAINTENANCE PROGRAM TEST OF THE TRAIN B

y HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 1

INITIALS 5.20 Open 2SI-870B.

'5.21 Place 2P-14B control switch to AUTO.

/

5.22 End LCO for Train B Spray.

5.23 Verify open 2SI-856B.

5.24 Place 2P-10.8 control switch to AUTO.

/

5.25 Verify 2ICP-666B is complete and end LCO for Train B RHR, if required.

i j

5.26 Shut 2RH-V4. Disconnect digital pressure gage, then cap 2RH-V4.

e 5.27 Complete the test data sheet section for seat leakage rates of 2P-10B suction valves.

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!V 5.28 Remove and store all tygon tubing installed for this test.

6.0 TRAIN B LHSI/HHSI " PIGGYBACK" TEST j

6.1 Pre-Test System Alienment/ Verification n

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 RWSTlow 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-876B 2P-1SB mini-recirc Open 6.1.2 Verify oil level in 2P-15B at or above one-half sightglass.

Contact the DSS for the type of oil required.

4 6.1.3 Verify proper oil level in the thrust bearing housing of 2P-10B.

fg

-V Contact the DSS for the type of oil required.

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NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS 6.1.4 Verify a primed solid condition of the HHSI high flow test line:

a.

Verify 2SI-S29A, B, and D shut.

b. Open 2SI-V23, test line high point vent, to a container and observe no leakage of 2SI-829A, B, and D at static head.

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.

d. Ifleakage persists at 2SI-V23, then verify shut

{

2SI-829A&B.

Record background leak rate at 2SI-V23, if any.

e.

SCCM f.

Shut 2SI-V23.

6.2 HHSI Train B Leakane Test

• CAUTION

• IF A SAFEGUARDS ACTUATION OR A REACTOR PROTECTION SYSTEM ACTUATION SHOULD OCCUR ON UNIT 2 WHILE PERFORMING THIS TEST, THEN IMMEDIATELY PROCEED TO STEP 6.2.26 RECOVER SYSTEMS PER STEPS 6.2.26 THROUGH 6.2.38, 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).

O Page 12 of 31 CONTINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3

' LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B O'

HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS 6.2.3 If 2FE-660 blank was removed and orifice installed for this test, 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 B RHR, if required.

6.2.5 Place 2P-10B control switch to PULLOUT.

f 6.2.6 Shut 2RH-733B,2P-10B mini-recire isolation.

6.2.7 Unlock and open 2RH-706B, high flow test line inlet isolation.

6.2.8 Verify open 2SI-856B,2P-10B RWST suction MOV.

j 6.2.9 Verify 2P-10B discharge pressure at <50 psig per 2PI-629.

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6.2.10 Align 2PI-653B,2P-10B suction pressure gauge, for service:

a. Shut 2RH-V2A,2PI-653B vent.

l

b. Open 2RH-V2, suction gauge root isolation.

i

c. Open 2RH-V28,2PI-653B inlet isolation.

6.2.11 Start 2P-10B.

• CAUTION

• MONITOR AND VERIFY 2P-10B SUCTION PRESSURE IS >0 PSIG PER 2PI-653B ANYTIME FLOW IS CHANGED.

6.2.12 Verify 2P-10B suction pressure is >0 psig.

6.2.13 Position 2RH-742B for a test line flow of 600 ISO gpm per 2 FIT-660.

l 0

j C

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NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS NOTE:

Identify in remarks section any leakage observedfrom the pump or mechanicalseals. Also include amount (seals wet, 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 2P-15B control switch to PULLOUT.

6.2.17 Shut 2SI-896B,2P-15B suction MOV.

6.2.18 Slowly open 2SI-857B, low head to high head cross-connect, to full open.

6.2.19 Visually inspect the shaft seals of2P-15B. Collect, measure, and time any observed leakage. Record required data of Attachment C, Section 1.0.

• CAUTION

• DO NOT SECURE 2P-10B WITHOUT FIRST SECURING 2P-15B OR A TOTAL LOSS OF 2P-15B SUCTION MAY OCCUR, RESULTING IN PUMP DAMAGE. IF 2P-10B POWER IS LOST FOR ANY REASON, THEN IMMEDIATELY SECURE 2P-15B.

NOTE:

Reference P&L 3.7.

6.2.20 Start 2P-1SB.

6.2.21 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 C Section 2.0. Then shut and cap 2SI-V23.

6.2.22 With 2SI-829B shut, collect and record 2SI-829B leakage to atmosphere on Attachment D.

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NUCLEAR POWER BUSINESS UNIT IT535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997

/7 MAINTENANCE PROGRAM TEST OF THE TRAIN B h

HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS NOTE:

The 2P-15B 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.

Open 2SI-829B, open and backseat 2SI-829D, HHSI high a.

flow test line isolation valves.

b. Adjust 2SI-829C for a test line flow of 250 25 gpm per 2 FIT-659.

Unlock and shut 2SI-876B,2P-15B mini-recire isolation c.

valve.

d. Record pressure achieved and inspection start data on

/

Attachment E.

6.2.24 Visually inspect the shaft seals of 2P-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 bonnetjoints, pipe flanges / orifices, vent and drain plugs / caps, instrument line fittings / gauges listed on 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 2P-15B and place control switch to PULLOUT.

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6.2.27 Secure 2P-10B and place control switch to PULLOUT.

6.2.28 Red lock open 2SI-876B. Lock No.

/

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NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHS1 AND RHR SYSTEMS (REFUELING)

UNIT 2 INITIALS 6.2.29 Red lock shut:

2SI-829B Lock No.

/

2SI-829D Lock No.

/

2RH-742 Lock No.

/

6.2.30 Shut 251-857B.

/

6.2.31 Shut 2SI-829C.

6.2.32 Open 2SI-896B,2P-15B suction MOV.

/

6.2.33 Place 2P-15B control switch to AUTO.

/

6.2.34 Exit LCO for Train B HHSI, if required.

6.2.35 Remove 2P-10B suction gauges from service:

a.

Shut 2RH-V2.

b. Open 2RH-V2A.

I l

l

c. Shut 2RH-V2B.

6.2.36 Red lock shut 2RH-706B. Lock No.

/

i 6.2.37 Red lock open 2RH-733B. Lock No.

/

6.2.38 Place 2P-10B control switch to AUTO.

/

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6.2.39 Exit LCO for Train B RHR,if required.

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NUCLEAR POWER BUSINESS UNIT IT535B INSERVICE TESTS MAJOR 1

Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997

^

g MAINTENANCE PROGRAM TEST OF THE TRAIN B

-(Q HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 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 I 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.

1.

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.

s a

8.2 Any requirements for corrective action?

i Yes No i

If yes, give details in the remarks section and MWR No.

8.3 Data analyzed.

By Date 1

e Remarks:

~

f b

Page 17 of 31 CONTINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 TEST DATA SHEET 1.0 Valve Seat Leakace NOTE:

Allleak rates arein secm.

NOTE:

Column A data is information only. Column B data is applicable to TechnicalSpecifications andNUREG 0578.

Col. A Col. B 1.1 2SI-856B and 2RH-823B (Reference Step 5.12) 1.2 2SI-854B (Reference Step 5.15 and Attachment A) 0" 946$x

= 946 x

=

seem m

AT minus Boundary leakage (Step 5.11) =

or Attachment A =

gpm 1.3 2RH-706B (Reference Step 5.11) =

l l

)

h Page 18 of 31 CONTINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3

. LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 n

MAINTENANCE PROGRAM TEST OF THE TRAIN B J

4 HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 i

A'ITACHMENT A Seat Leakace Test of 2SI-854B Usinn P-33 NOTE:

This test is required when the seat leakage of2SI-854B exceeds the pungping rate ofthe hydro pungp and test systempressureper 2PI-629 is

<100psigperStep 5.16.

INITIALS 1.0 Shut 2RH-V2, then secure the hydro pump.

2.0 Secure SFP recire or Unit 1 RWST recire (Refer to UI 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.

O 4.0

. Verify 2RH-701 shut, then open 2SF-819 and verify FI-636 flow remains at 20 gpm.

5.0 Shut 2RH-709B and 7338.

6.0 Open 2RH-704B 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-629 psig 8.0 Shut 2SF-819 and 2RH-704B.

9.0

. When P-33 flow has stabilized, record the following data:

P-33 flowper FI-636 gpm P-33 pressure per PI-651 psig Test volume pressure per 2PI-629 -

psig 10.0 Open 2RH-733B and 709B, then return P-33 to previous status or as directed

.. by the DSS when the testing is complete.

Page 19 of 31 QONTINUOUS USE O

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NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31.1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 Attachment A

~

INITIALS

-11.0 Calculate 2SI-854B 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 5.15.

O 4

Page 20 of 31 CONTINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997

/

MAINTENANCE PROGRAM TEST OF THE TRAIN B HHS! AND RHR SYSTEMS (REFUELING)

UNIT 2 ATTACHMENT B Leakage Rate Component ID Component Description (sccm) 2P-10B RHR Pumn Cubicle 2RH-823B 2P-10B suction low point drain 2RH-V12 2P-10B seal supply vent 2RH V13 2P-10B seal heat exchanger inlet vent 2RH-711F 2P-10B seal leak telltale Flange 2P-10B seal RO flange 2RH-71IB 2PT-629 root valve 2P-10B Pump seals PAB General Area South. El. -19' 2PT-629 2P-10B discharge pressure transmitter Unit 2 RHR Pineway 2RH-710B 2P-10B discharge check valve 2RH-709B 2P-10B discharge isolation 2RH-713B 2P-10B discharge cross-connect 2SI-851B 2P-10B "B" sump suction MOV 2SI-851D Pressure equalizer for 2SI-851B 2RH-715B 2HX-1IB inlet isolation 2RH D5 2HX-11B interpass drain

~~

2RH-D6 2HX-11B interpass drain 2RH-D7 2HX-1IB interpass drain V

Page 21 of 31 CONTINUOUS USE 0

4 4

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r NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 Attachment B Leakage Rate Component ID Comnonent Descrintion (secm)

PAB General Area South. El. -5' 2RH-625 2HX-1IB discharge TCV 2RH-716B 2HX-11B outlet isolation 2RH-716C 2HX-11B outlet cross-connect PAB General Area South. El. 8' 2RH-V7 Train B RHR to SI and spray suction line vent (above HR-36) 2RH-D12 Train B RHR to SI and spray suction line drain 2RH-71IE 2P-10B seal water supply 2FT-928 Train B RHR flow transmitter 2RH-V4 Train B RHR to SI and Spray suction line vent (above 2RH-742)

I ower Pinewav #3 2RH-V2B 2PI-653B root valve 2RH-V2A 2PI-653B bleed-off for seat leakage of 2RH-V2B 2RH-V2C 2PI-654B root valve 2PI-654B 2P-10B RHR suction pressure indication 2SI-856B 2P-10B RWST suction MOV 2SI-854B 2P-10B RWST suction check 2RH-V2 2PI-653B and 654B root valve 2RH-704B 2P-10B RCS loop suction isolation 2RH-848F 2FT-928 high pressure root 2RH-848E 2FT-928 low pressure root 2FE-928 Train B RHR flow orifice 2RH 733B 2P-10B mini-recire isolation Page 22 of 31 CONTINUOUS USE l

' NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE -

January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B O

HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 Attachment B

~

Leakage Rate Component ID Component Descrintion (sccm)

Lower Pineway #3 (continued) 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 i2RH-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 thennal micase

(

2FE 660 High flow test line orifice flange 2RH-662A 2 FIT-660 high side root 2RH-662B 2 FIT-660 low side root 2 FIT-660 High flow test line flow indicator transmitter l

P22 Train B RHR discharge containment penetration

\\

Containment Sorav and S1 Pumn Area 1

L l

2SI-871B Train B RHR/CS cross-connect MOV l

2SI-857B Train B RHR/SI cross-connect isolation i

Other miscellaneous system components '

l l

l l

~

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NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 ATTACHMENT C 2P-15B PUMP SEAL LEAKAGE & 2SI-829B SEAT LEAKAGE 1.0 SEAL LEAK RATE WITH 2P-15B SECURED 2P-10B Discharge Pressure Per 2PI-629 =

psig cc/ collected seconds Leak Rate = (ce collected /sec)(ci0 sec/ min) =

SCCM 2.0 2SI-829B SEAT LEAK RATE 2P-158 Discharge Pressure per 2PI-922 =

psig cc/ collected seconds O

Leak Rate = (ce collected /sec)(60 sec/ min) =

SCCM Background Leak Rate (Step 6.1.4.e) =

SCCM 3.0 SEAL LEAK RATE WITH 2P-15B OPERATING 2P-10B Discharge Pressure Per 2PI-629 =

psig 2P-15B Discharge Pressure Per 2PI-922 =

psig cc collected seconds Leak Rate = (ce collected /sec)(60 sec/ min) =

SCCM O

Page 24 of 31 CONTINUOUS USE 4

NUCLEAR POWER BUSINESS UNIT IT535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 A

MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 ATTACHMENT D TRAIN B ATMOSPHERIC LEAKAGE LEAKAGE RATE COMPONENT DESCRIPTION (SCCM)

Components Located in Containment Sorav/SI Pumo Area 2SI 857B RHR/SI crossconnect...................................................

2SI-8968 2 P-15 B s ucti on M O V....................................................

Flange 2P-15 B suction flange...................................................

2SI D9 2P-15B discharge line drain............................................

j Flange 2 P-15 B discharge flange.................................................

2SI-881B 2 PT-922 roo t val ve...........................................................

2PT-922 2P-15B discharge pressure transmitter............................

2SI-803B 2PI-913 B root valve.........................................................

2SI-889B 2P-1 SB discharge check valve.........................................

(v,)

2SI-888B 2P-15B discharge isolation..............................................

2SI 829A 2P-15A&B SI pumps discharge crossconnect.................

2SI-891B 2P-15B mini recirc 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.....................................

2F1-659 HHS! high flow test line orifice flange.........................

2SI-663B 2F1-659 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........................................

2SI-D28 HHSI high flow test line drain.........................................

l p.

Page 25 of 31 CONTINUOUS USE.

NUCLEARl'OWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHSI AND RHR SYSTEMS (REFUELING)

UNIT 2 Attachment D LEAKAGE RATE COMPONENT DESCRIPTION (SCCM)

Components Located in Pineway No. 4 2SI-848C 2FI-924 LP root valve....................................................

2SI 848D 2 FI-924 HP root val ve...................................................

2FE-924 SI Train B flow orifice..........................................

2FT-924 SI Train B flow transmitter........................................

2SI-866B SI Train B discharge MOV........................................

MISC Other miscellaneous system components.......................

2SI-D20 2P-15B SI pump discharge drain...................................

2SI-D21 2P-15B SI pump discharge drain...............................

i 2P-10B discharge pressure,2PI-629 psig 2P-15B discharge pressure,2PI-922 psig Page 26 of 31 CONTINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 i

LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 i

e' MAINTENANCE PROGRAM TEST OF THE TRAIN B

(]T HHSI ANDRHRSYSTEMS(REFUELING) s i

UNIT 2 ATTACHMENT E HHSI 40-MONTH INSERVICE PRESSURE TEST PRE-TEST DATA Record calibration dates for:

2PI-922 2PI-936 Record RWST Level per 2LI-972 2T-34B Accumulator Level Per 2LI-934 TEST DATA Irain B ph Test pressure achieved:

0 2PI-922 psig Time 10-minute hold / Inspection started:

i 2PI-922 psig Time i

Inspection completed:

2PI-922 psig Time 2T-343 SI ACCUMULATOR 1

Inspection started:

-1 1

2PI-936 psig Time Inspection completed:

p 2PI-936 psig - Time l

LJ Page 27 of31 CONTINUOUS USE 9

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NUCLEAR POWER BUSINESS UNIT IT535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MATNTENANCE PROGRAM TEST OF THE TRAIN B HHU AND RHR SYSTEMS (REFUELING)

UNIT 2 Attachment E ACCEPTANCE CRITERIA The' test is considered acceptable if the presrtre retaining piping and components within the test boundary withstand the test pressure without loss of structural integrity.

The test is considered ecceptable if there is no leakage from the system other than controlled leakage or leakage through boundary valves.

/

Test Director Date QTS Reference Report Number G

+

Page 28 of 31 CONTINUOUS USE 9

NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 3

MAINTENANCE PROGRAM TEST OF THE TRAIN B (Q

HHS1 AND RHR SYSTEMS (REFUELING)

UNIT 2 ATTACHMENT F RHR TRAIN B 40-MONTH FUNCTIONAL PRESSURE TEST PRE-TEST DATA Record calibration dates for:

2PI-629 TEST DATA Test pressure achieved:

2PI-629 psig Time 10-minute hold / Inspection started:

r1 V

2PI-629 psig Time Inspection completed:

2PI-629 psig Time ACCEPTANCE CRITERIA The functional pressure test is considered acceptable if the pressure retaining piping and components

,. I withstand the test pressure without loss of structural integrity.

Additionally, the test is considered acceptable if there is no leakage from the system other than controlled leakage or leakage through boundary valves.

/

Test Director Date QTS Reference Report Number:

Page,2,9 of 31 CONTINUOUS USE 8

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NUCLEAR POWER BUSINESS UNIT IT 535B INSERVICE TESTS MAJOR Rerision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE TRAIN B HHS1 AND RHR SYSTEMS (REFUELING)

UNIT 2 ATTACHMENT G TROUBLESHOOTING TRAIN B RHR LEAKAGE >1.5 gal /hr INITIALS 1.

Firmly SHUT the following valves:

2RH-713A,2HX-11 A/B Inlet Crossconnect 2RH-713B,2HX-11 A/B Inlet Crossconnect

~

2RH-716C,2HX-11 A/B Outlet Crossconnect 2RH-716D,2HX-11 A/B Outlet Crossconnect 21Ui-823B,2P-10B Suction Drain 2SI-857B, 2P-1JB RHR Suction 2SI 851D, Interdisc thermal release isol for 2SI-851B 2.

St&n a dedicated operator whose duty will be to shut 2CV-133 in the event of a Unit 2 reactor protection or safeguards actuation.

3.

Open 2CV-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 2PI-628.

NOTE:

Ensure measurements are taken on the Train B hydro pump.

5.

Measure and record total Train B RHR input pumping rate (as in Step 5.10.3)

AH inches

=

i AT

=__

minutes 2PI-629 =

psig Totalin;vit = 946

• x

= 946 x __

=

seem m

AT 6.

Shut 2CV-133, secure dedicated operator for 2CV-133 and restore Unit 2 letdown h

system and pressure to normal, per DSS.

Page 30 of 31 CON.TINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT 535B r

INSERVICE TESTS MAJOR t

Revision 3 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997

_ym MAINTENANCE PROGRAM TEST OF THE TRAIN B

f(

HHSI AND RHR SYSTEMS (REFUELING)

~

UNIT 2 INITIALS I

7.

Depressurize Train A RHR:

a.

Open 2RH-VI and crack open 2RH-V1B.

b.

When Train A RHR is depressurized, as indicated on 2PI-628, shut f

2RH-V1 and 2RH-VIB.

8.

Open 251-851D and return to procedure step 5.15.

REMARKS:

,O

()

I 1

' (J

\\

+

Page 31 of 31 CONTINUOUS USE

NUCLEARPOWERBUSINESSUNIT OPINDEX OPERATINGPROCEDURES Revision 127 January 31,1997 INDEX BIENNIAL PROCEDURE I

REVISION EFFECTIVE REVIEW NUMBER PROCEDURE TITLE NUMBER DATE DATE OP-1 A Cold Shutdown to Low Power Operation............. 57 R 10/02/96 11/20/95 OP1B Reactor Startup................................................ 2 7 C 12/09/96 04/22/96 OP-1B APP A Estimated Rate Position Calculation..................... 6 I 05/24/96 09/18/92 OP1C Low Power Operation to Normal Power Operati on........................................................ 5 6 R 01/10/97 10/13/95 OP-2A Normal Power Operation.................................... 25 I T 10/13/95 10/13/95 OP-2A APP. A Operation at Restricted Power Level...................1 I T 09/20/94 06/03/94 OP-3A Normal Power Operation to Low Power Operati on....................................................... 3 7 R 03/29/96 09/29/95 OP3B Reactor Shutdown........................................ 23 C 01/10/97 11/08/94 OP-3B APP. A Shutdown Margin Calculation............................. 5 I 05/24/96 12/02/93 OP3C Hot Shutdown to Cold Shutdown.................. 66 R 12/20/96 08/21/95 OP-4A Filling and Venting Reactor Coolant System...... 42 R 03/29/96 05/13/94 OP48 Reactor Coolant Pump Operation..................... 30 R 12/13/96 11/03/95 OP-48 APP. A Starting Reactor Coolant Pumps When Defeating Degraded Voltage Relays is Necessary............. 0 R 11/13/95 11/13/95 OP-4C Pressurizer ReliefTank Operation......................13 C 01/08/96 04/07/95 OP 4D Part 1 Draining the Reactor Coolant System to a CVCS q

HUT Without Entering Reduced Inventory....... 46 R 01/31/97 06/12/95 U/

OP-4D Part 2 Draining the Reactor Coolant System to a CVCS HUT Into Reduced Inventory........................ 2 C 06/12/95 06/12/95 OP-4D Pan 3 Drainir.g the Cavity and Reactor Coolant System With Fuel in the Vessel..............

.......4 R

08/30/96 06/12/95 OP-4D Part 4 Draining the Cavity and Reactor Coolant System With No Fuel in the Vessel.....

.4 R

08/30/96 06/12/95 OP 4D Part 5 Draining the Reactor Coolant System to a CVCS HUT Without Entering Reduced Inventory and Without Draining Steam Generator Tubes........... I R 01/31/97 03/29/96 OP-4F Reactor Coolant System Reduced Inventory Requirements............................................... 12 C 01/22/96 11/03/95 OP-5A Reactor Coolant Volume Control......................... 29 R 08/30/96 08/30/ %

OPSB Blender Operation / Dilution /Boration................... 12 R 12/09/96 12/09/ %

OPSD Primary System Chemical Addition and Control. 30 R 12/13/96 06/12/95 OP-5E Establishing and Securing Excess Letdown.......... 3 R 01/08/96 01/08/96 OP-6A Operation of Component Cooling System..........19 R

09/13/96 07/08/94 OP-7A Placing Residual Heat Removal System in Operation...................................................... 3 3 C 08/30/96 12/21/93 OP-7B Removing Residual Heat Removal System From Operation.............................................. 24 C 11/13/95 06/21/93

/O V

(T - Temporary Change)

C = Continuous Use Page1of2 R = Reference Use I = Information Use

..e

NUCLEARPOWER BUSINESSUNIT OPINDEX OPERATING PROCEDURES Revision 127 January 31,1997 INDEX BIENNIAL PROCEDURE REVISION EFFECTIVE REVIEW NUMBER PROCEDURE TITLE NUMBER DATE DATE OP-8A Spent Fuel Pool Cooling Water System Operati on...............,........................................ 14 R T 12/04/95 12/04/95 OP-9A Liquid Waste Process System Operation..............19 R 08/07/96 02/04/94 l OP 9C Containment Venting and Purging....................... 38 R 01/31/97 07/26/96 OP9D Discharge of Gas Decay Tank (s).......................... 13 R 01/10/97 01/10/97 OP-10E Discharge of B CVCS HUT.................................... 5 R 07/19/93 03/23/93 OP-11 A Emergency Diesel Generator G-01 (G-02)........... 27 R 10/13/95 06/10/94 OP-11B Emergency Diesel Generator G-03 (G-04)........... 4 R 10/13/95 10/11/94 OP-13 A Secondary Systems Stanup.................................. 45 R 09/07/93 09/07/93 OP-13B Secondary Systems Shutdown........................... 5 R 08/21/95 11/06/92 O

O (T - Temporary Change)

C = Continuous Use Page 2 of 2 R = ReferenceUse I = Information Use

,