ML20138K447

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Rev 2 to OI 115, SFP Svc Water Cooling Isolation for Maint
ML20138K447
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 01/25/1997
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20138K159 List: ... further results
References
OI-115, NUDOCS 9702180322
Download: ML20138K447 (18)
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Text

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' NUCLEAR POWER BUSINESS UNIT OI 115 OPERATING INSTRUCTIONS MINOR 4 Revision 2 4

SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997 i 6 MAINTENANCE Date RECORD DSS PROCEDURE VERIFIED CURRENT AND CHECKED FOR TEMPORARY CHANGES IF FIELD Operations Manager BY; DATE:  ;

1 1.0 PURPOSE To provide the requirements for isolating Service Water to the Spent Fuel Pool. This allows  ;

maintenance to be performed on the Service Water portion of the system which is common to l both SFP heat exchangers or which cannot be isolated without isolating Service Water to both heat exchangers.

2.0 REFERENCES

IR 96-006, NRC Inspection Report; NRC Commitment for Operations procedures PMT/QC )

reviews. l 3.0 PRECAUTIONS AND LIMITATIONS 3.1 The level of borated water in the Spent Fuel Pool should be maintained above the low level alarm setpoint. If at any time the low level alarm is attained, special consideration should be taken to assure a loss of suction for the pumps has not occurred.

3.2 During normal system operation, Service Water system pressure as read on PI-2844 and/or PI-2855 shall be maintained as shown on Attachment A of 01-70.

3.3 This test will be evaluating the heat up rate of the SFP with SW isolated. The heat up rate of the SFP need only be tested if fuel has been added to the SFP since the last time SFP heat up rate was tested.

3.4 Do not perform this procedure during dry cask or fuel handling operations in the SFP.

3.5 P-12A or B will be maintained running during this procedure IAW OP-8A. To maintain normal SFP temperature distribution.

l 3.6 When RE-220 is taken in/out of service, observe the requirements of TS 15.7.3, TS Table 15.7.3-1, and PBF-2068g.

4.0 INITIAL CONDITIONS i INITIALS 1

4.1 Initial SFP temperature must be 70-75 F.

9702180322 970210  ! Page1o m ENEE PDR ADOCK 05000301-P PDR '

,. NUCLEAR POWER BUSINESS UNIT. OI115 OPERATING INSTRUCTIONS MINOR Revision 2 SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997 MAINTENANCE INITIAL.S 4.2 SFP flow rate 1000-1100 gpm.

4.3 Normal operating level in the SFP ( 63-64 ft.).

4.4 W-33 A and B, SFP Supply Fans, available and NOT running.

4.5 The SFP Cooling System is aligned per CL-5C.

4.6 DSS permission to perform test.

DSS NOTE: If heat up rate test has already been performed since the last timefuel was added to thepool, transfer data to Attachment A andN/A allofsection 5.0.

5.0 SFP HEAT-UP RATE TESTING NOTE: IfP-12A is operating, perform section 5.1 and "N/A " section 5.2.

IfP-12B is operating, perform section 5.2 and "N/A " section 5.1.

5.1 P-12A. SFP Cooling Pumo. operatinn. >

aCAUTIONa SEE P&L 3.5 FOR STEP 5.1.1.

5.1.1 Verify shut SF-23, P-12 A/B SFP Pump Discharge Crossconnect.

5.1.2 Verify shut and remove the cap from SW-654, HX-13A SFP i HX Inlet Vent. '

5.1.3 Attach a hose to the piping downstream of SW-654, HX-13A

SFP HX Inlet Vent.

5.1.4 Route hose from SW-654 to the Ul or U2 Facade Sump.

  • CAUTIONa SEE P&L 3.6 FOR STEP 5.1.5.

5.1.5 Declare RE-220 out of service.

I 5.1.6 Shut SW-653, HX-13B SFP HX Inlet.

5.1.7 Verify shut SW-2930B, HX-13B SFP HX Outlet.

Page 2 of14 REFERENCE USE

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NUCLEAR POWER BUSINESS UNIT OI115 OPERATING INSTRUCTIONS MINOR Revision 2 SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997 MAINTENANCE ,

INITIALS l

5.1.8 Shut SW-2930A, HX-13 A SFP HX Outlet.

5.1.9 Shut SW-652, HX-13A SFP HX Inlet. I NOTE: If the vent draws air into the SWsystem, then shut SW-654, HX-13A SFP HXInlet Vent, and leave SW-654 shut.

5.1.10 Slowly open SW-654, HX-13A SFP HX Inlet Vent. j 5.1.11 Allow HX-13 A SW side to depressurize.

aCAUTIONa DO NOT ALLGW SFP TEMPERATURE TO RISE ABOVE 90 F DURING STEP 5.1.12.

5.1.12 Take data on the temperature rise of the SFP for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or any temperature limit is reached on Attachment A.

5.1.13 After data has been collected shut SW-654, HX-13 A SFP HX Inlet Vent.

5.1.14 Open SW-652, HX-13 A SFP HX Inlet.

5.1.15 Vent HX-13A by opening SW-654, HX-13A SFP HX Inlet Vent.

5.1.16 Shut SW-654, HX-13A SFP HX Inlet Vent.

5.1.17 Open SW-2930A, HX-13A SFP HX Outlet.

5.1.18 Disconnect the hose from the piping downstream of SW-654, HX-13A SFP HX Inlet Vent.

5.1.19 Cap SW-654, HX-13 A SFP HX Inlet Vent.

5.1.20 Open SW-653, HX-13B SFP HX Inlet.

aCAUTIONa SEE P&L 3.5 FOR STEP 5.1.21.

]

5.1.21 Position SF-23, P-12 A/B SFP Pump Discharge Crossconnect per DSS.

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NUCLEAR POWER BUSINESS UNIT OII15 OPERATING INSTRUCTIONS MINOR Revision 2 SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997 MAINTENANCE INITIALS

  • CAUTIONa SEE P&L 3.6 FOR STEP 5.1.22.

i 5.1.22 Return RE-220 to service.

5.2 P-12B. SFP Coolina Pumo. operating.

a aCAUTIONa SEE P&L 3.5 FOR STEP 5.2.1.

1 5.2.1 Verify shut SF-23, P-12 A/B SFP Pump Discharge

Crossconnect.

5.2.2 Verify shut and remove the cap from SW-655, HX-13B SFP HX Inlet Vent.

5.2.3 Attach a hose to the piping downstream of SW-655, HX-13B SFP HX Inlet Vent.

5.2.4 Route hose from SW-655 to the Ul or U2 Facade Sump. l l

[

  • CAUTION
  • SEE P&L 3.6 FOR STEP 5.2.5.  ;

5.2.5 Declare RE-220 out of service.

5.2.6 Shut SW-652, HX-13 A SFP HX Inlet.

5.2.7 Verify shut SW-2930A, HX-13A SFP HX Outlet.

I 5.2.8 Shut SW-2930B, HX-13B SFP HX Outlet. l 1

5.2.9 Shut SW-653, HX-13B SFP HX Inlet. I NOTE: Ifthe vent dntws air into the SWsystem, then shut SW-MS5, HX-13B SFP HXInlet Vent, and leave SW-655 skut.

4 5.2.10 Slowly open SW-655, HX-13B SFP HX Inlet Vent.

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5.2.11 Allow HX-13B SW side to depressurize.

Page 4 of14 REFERENCE USE o

NUCLEAR POWER BUSINESS UNIT OI115 ,

OPERATING INSTRUCTIONS MINOR l Revision 2 1 SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997

, MAINTENANCE INITIALS

  • CAUTIONa DO NOT ALLOW SFP TEMPERATURE TO RISE ABOVE 90 F DURING STEP 5.2.12.

5.2.12 Take data on the temperature rise of the SFP for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or any temperature limit is reached on Attachment A.

5.2.13 After data has been collected shut SW-655, HX-13B SFP HX Inlet Vent.

5.2.14 Open SW-653, HX-13B SFP HX Inlet.

5.2.15 Vent HX-13B by opening SW-655, HX-13A SFP HX Inlet Vent.

5.2.16 Shut SW-655, HX-13B SFP HX Inlet Vent. ,

1 5.2.17 Open SW-2930B, HX-13B SFP HX Outlet.

5.2.18 Disconnect the hose from the piping downstream of SW-655, HX-13B SFP HX Inlet Vent.

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5.2.19 Cap SW-655, HX-13B SFP HX Inlet Vent.

5.2.20 Open SW-652, HX-13 A SFP HX Inlet.

  • CAUTIONa SEE P&L 3.5 FOR STEP 5.2.21.

5.2.21 Position SF-23, P-12 A/B SFP Pump Discharge Crossconnect per DSS.

  • CAUTION
  • SEE P&L 3.6 FOR STEP 5.2.22.

5.2.22 Return RE-220 to service.

6.0 ISOLATION OF SW TO SFP COOLING FOR MAINTENANCE 6.1 Verify with reactor engineering that heat load in the pool is less than 7 x 10' Btu /hr.

6.2 Verify repair / modification procedures and equipment available prior to isolating system for maintenance. .

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NUCLEAR POWER BUSINESS UNIT 01115 OPERATING INSTRUCTIONS MINOR Revision 2 SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997 MAINTENANCE INITIALS ;

I 6.3 Verify with repair group that repairs are expected to be complete prior to reaching 100*F.

6.4 Verify repair / modification procedure has contingency actions in place to restore SFP cooling if SFP temperature reaches 100 F.

I 6.5 Verify a 10 CFR 50.59 screeningjevaluation for the contingency plan has 4

been approved.

6.6 Establish SFP temperature as close to 70 F as possible prior to isolating SW to the SFP.

6.7 Verify W-47, Drumming Area Supply Fan, running. <

6.8 Verify W-33 A and B, SFP Supply Fans, running.

6.9 Verify W-36 A and B, SFP Exhaust Fans, running.

6.10 Verify shut and remove the caps from the following valves:

SW-663 HX-13 A/B SFP HX Return Vent SW-646 HX-13 A/B SFP HX Return Header Vent SW-658 HX-13 A/B SFP HX Return Vent SW-656 HX-13A SFP HX Outlet Drain SW-657 HX-13B SFP HX Outlet Drain SW-654 HX-13A SFP HX Inlet Vent SW-655 HX-13B SFP HX Inlet Vent SW-651 HX-13 A/B SFP HX Supply Vent 6.11 Attach a drain hose to the following valves and route it to the U1 or U2 Facade Sump:

SW-646 HX-13 A/B SFP HX Return Header Vent SW-658 HX-13 A/B SFP HX Return Vent SW-656 HX-13 A SFP HX Outlet Drain SW-657 HX-13B SFP HX Outlet Drain I SW-654 HX-13A SFP HX Inlet Vent SW-655 HX-13B SFP HX Inlet Vent Page 6 of14 REFERENCE USE

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NUCLEAR POWER BUSINESS UNIT OI115 OPERATING INSTRUCTIONS MINOR Revision 2 SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997

a. MAINTENANCE INITIALS NOTE: Thefollowing step willplace RE-220 00S (See P&L 3.6).

6.12 Shut SW-668, HX-13A/B SFP HX Return RE-220/SG-4456 Outlet.

6.13 Shut SW-666, HX-13A/B SFP HX Return RE-220 Inlet 2nd OffIsolation.

l NOTE: Thefollowing step willisolate SWcooling to the SFP HX's.

6.14 Isolate cooling to SFP heat exchangers.

6.14.1 Shut SW-650, HX 13 A/B SFP HX Supply 6.14.2 Take data and complete Attachment B.

6.14.3 Monitor SFP temperature using Attachment C.

6.15 Verify open SW-652, HX 13 A SFP HX Inlet.

6.16 Verify open SW-653, HX 13B SFP HX Inlet.

6.17 Verify open SW-2930A, HX-13 A SFP HX Outlet. l 6.18 Verify open SW-2930B, HX-13B SFP HX Outlet. j l

6.19 Verify open SW-660, HX-13 A/B SFP HX Return Throttle, if possible. j i

6.20 Verify open SW-661, HX-13 A/B SFP HX Return Throttle, if possible. I aCAUTION* IF CW WATERBOX ALARMS OR VACUUM CONTROL l TANK LOW VACUUM ALARMS DURING THE ,

FOLLOWING STEP, IMMEDIATELY SHUT SW-651. l 6.21 Open SW-651, HX-13 A/B SFP HX Supply Vent for 5 minutes to allow l the residual SW to be vacuum dragged to the SW return header. I 6.22 Shut SW-651, HX-13 A/B SFP HX Supply Vent.

6.23 Shut SW-664, HX-13 A/B SFP HX Return Isolation.

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Page 7 of14 REFERENCE USE g

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, NUCLEAR POWER BUSINESS UNIT OI115 l OPERATING INSTRUCTIONS MINOR Revision 2 SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997 ,

/k MAINTENANCE l

INITIALS l
  • CAUTIONa AIR MAY LEAK PAST SW-664 WHEN OPENING SW-651 IF SW-664 IS NOT LEAK TIGHT. CHECK FOR ,

AIR INFILTRATION WHEN OPENING SW-651 AND I INFORM DSS IF SW-664 IS LEAKING BY. I 6.24 Open SW-651, HX-13A/B SFP HX Supply Vent.

6.25 Open SW-663, HX-13 A/B SFP HX Return Vent. i 6.26 Open the following valves to the SW piping to allow the SW to drain to the Ul or U2 Facade Sump:

SW-646 HX-13 A/B SFP HX Return Header Vent SW-658 HX-13 A/B SFP HX Return Vent i SW-656 HX-13A SFP HX Outlet Drain l

SW-657 HX-13B SFP HX Outlet Drain  !

SW-654 I HX-13A SFP HX Inlet Vent j

SW-655 HX-13B SFP HX Inlet Vent 6.27 Make a copy of the completed Attachment B and give it to the appropriate Maintenance Planner for inclusion in their work package.

NOTE: Return the SFPSW Cooling to service as soon as possiblepaying particular attention to the times calculatedin Attachment B.

7.0 RESTORATION OF SW TO THE SFP HEAT EXCHANGERS  !

7.1 Shut the following valves:

SW-663 HX-13 A/B SFP HX Return Vent SW-646 HX-13 A/B SFP HX Return Header Vent SW-658 HX-13 A/B SFP HX Return Vent SW-656 HX-13A SFP HX Outlet Drain SW-657 HX-13B SFP HX Outlet Drain I 4

SW-654 HX-13A SFP HX Inlet Vent SW-655 HX-13B SFP HX Inlet Vent SW-651 HX-13 A/B HX Supply Vent Page 8 of14 REFERENCE USE

, NUCLEAR POWER BUSINESS UNIT 01115 OPERATING INSTRUCTIONS MINOR Revision 2 o

SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997 MAINTENANCE INITIALS NOTE: Ifany of the valves listedin step 7.2 are removedfor maintenance, ensure thepressure boundaries are intact and annotate as such. If they are not removedfor maintenance, the valves shall be open.

7.2 Verify open/ flanged the following valves:

SW-652 HX-13A SFP HX Inlet O/Boundanes Intact SW-653 HX-13B SFP HX Inlet O/ Boundanes intact SW-2930A HX-13A SFP HX Outlet O/ Boundanes intact SW-2930B HX-13B SFP HX Outlet O/ Boundanes Intact SW-660 HX-13 A/B SFP HX Return Throttle O/ Boundanes intact l SW-661 HX-13A/B SFP HX Return Throttle O/ Boundanes intact l 7.3 Remove the cap on SW-673, HX-13A/B SFP HX Return PI-2950 Test Connection.

7.4 Attach a hose to SW-663, HX-13 A/B SFP HX Return Vent.

7.5 Route SW-663 vent hose to the U1 or U2 Facade Sump.

7,6 Slowly crack open SW-650, HX-13A/B SFP HX Supply.

7.7 When SW pressure on PI-2950 stops rising, fully open SW-650.

7.8 Completely vent off the air in the SFP Heat Exchanger SW lines through the following valves:

SW-654 HX-13A SFP HX Inlet Vent SW-655 HX-13B SFP HX Inlet Vent SW-673 HX-13 A/B SFP HX Return PI-2950 Test Conn SW-663 HX-13 A/B SFP HX Return Vent SW-646 HX-13 A/B SFP HX Return Header Vent SW-658 HX-13 A/B SFP HX Return Vent Page 9 of14 REFERENCE USE

NUCLEAR POWER BUSINESS UNIT OI115 OPERATING INSTRUCTIONS MINOR Revision 2 SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997 MAINTENANCE INITIALS 7.9 Verify shut and capped the following valves:

SW-648 RE-220 Downstream Drain SW-649 RE-220 Upstream Drain SW-662 RE-220 Outlet Drain 7.10 Verify open the following valves:

SW-665 RE-220 Inlet First OffIsolation SW-666 RE-220 Inlet Second OffIsolation SW-667 RE-220 Outlet First OffIsolation SW-668 RE-220 Outlet Second OffIsolation

, 7.11 Annotate which SFP HX, HX-13 A/B will be in standby, if neither will be in standby, NA this step.

HX-13A HX-13B NOTE: Steps 7.12 and 7.13 allow any residual air in the SWlines that could not be manually vented to be ewept to the SWreturn header.

Waterbar low level and/or vacuum control tank low vacuum alarms may be received if alarms are received, shut SW-664 until alarms are clear andproceed with Step 7.12.

7.12 Slowly open SW-664, HX-13 A/B SFP HX Return Isolation.

NOTE: Thefollowing step may be marked N/A if valve has been removed fwm the systemfor maintenance.

7.13 Wait 5 minutes then shut the standby SFP HX outlet MOV ( see step 7.11).

SW-2930A SW-2930B NOTE: Ensure SFPflow and SWflow are lined up to the same SFP HX (fIX-13) to cooldown the SFP.

7.14 Control SFP temperature IAW OP-8A using the appropriate throttle valve SW-660 or SW-661.

Page 10 of14 REFERENCE USE t

NUCLEAR POWER BUSINESS UNIT OI115 OPERATING INSTRUCTIONS MINOR Revision 2 o SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997 MAINTENANCE INITIALS l PMT 7.15 Verify RE-220 has sample flow as seen in SG-4456, RE-220 Outlet Sightglass.

7.16 Declare RE-220 back in service using P&L 3.6.

7.17 Remove hoses, as applicable, and cap the following valves:

SW-654 HX-13A SFP HX Inlet Vent l

SW-655 HX-13B SFP HX Inlet Vent i l

SW-656 HX-13A SFP HX Outlet Drain SW-657 HX-13B SFP HX Outlet Drain SW-673 HX-13A/B SFP HX Return PI-2950 Test Conn SW-658 HX-13 A/B SFP HX Return Vent SW-646 HX-13 A/B SFP HX Return Header Vent SW-663 HX-13 A/B SFP HX Return Vent 7.18 Secure W-33 A and B, SFP Supply Fans.

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Page11of14 REFERENCE USE

, NUCLEAR POWER BUSINESS UNIT OI 115 OPERATING INSTRUCTIONS MINOR Revision 2 SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997

, MAINTENANCE Attachment A d

Step 5.1.12 Condition Time TIC-635 Heat Up Rate

( "F ) ( Note 1 )

EM Service Water Secured ,;

+30 minutes [ "E P

=-

+3 hours _g

+4 hours

+5 hours l E h ms l l Step 5.2.12 L

l Tirpe l Condition TIC-635 Heat Up Rate j

('F) ( Note 1 )

Service Water Secured

+30 minutes

+1 hour

+2 hours

+3 hours

+4 hours j

+5 hours l l

+6 hours l l l Note 1: HUR = (#' ' }

(hf h.)  :

HUR = Heat up rate

t. = Initial temperature when SW secured (TIC-635)
tr = Final temperature (TIC-635) -

h.= Initial time when SW secured (hours) hr = Final time (hours)

, , Page 12 of 14 REFERENCE USE.

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, NUCLEAR POWER BUSINESS UNIT OIi15 OPERATING INSTRUCTIONS MINOR Revision 2 SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997

/~ MAINTENANCE Attachment B Sle_p_6.14.2 Condition Titac/Date TIC-635

( t. )*F SW-650 shut Temperature Condition Rise Heat Up Rate Hours Date/ Time

(*F) { from Attach. A) (Note 1) (Note 2)

(Nees 3)

Time to 100*F (100- t. ) =

(Maes 4)

Time to 120*F (120 t,) =

Time to complete contingencies 20 (Nm O

Time to 145'F (145-t. ) =

i i

l NOTE 1: Hours until temperature is reached is calculated by:

Temperature Rise Hours = Heatup Rate i

NOTE 2: Date and Time is calculated by adding the hours calculated in Note 1 to the Date/ Time that SW-650 was shut.

NOTE 3: Time to 100 *Fis the estimated time allowed to perform maintenance.

. NOTE 4: Time to 120 *Fis the estimated time allowed to complete contingency actions to i

return SFP cooling. Contingencies should be expected to be completeprior to reaching 120*F. "*

NOTE 3: Time to 145 *Fis the estimated timeprior to exceeding the highest allowed SFP tengperature.

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, NUCLEAR POWER BUSINESS UNIT OI115 OPERATING INSTRUCTIONS MINOR Revision 2 l

' I SFP SERVICE WATER COOLING ISOLATION FOR January 25,1997

,,_ MAINTENANCE Attachment C Date/ Time TIC-635 Date/ Time TIC-635 Date/ Time TIC-635 Note 1 (*F) (Note 1) ('F) (Note 1) (*F) i t

l i

6 i

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l 4

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l NOTE 1: Temperatures should be taken about every two hours, but at a minimum ofonce every four hours. i i

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Page 14 of14 REFERENCE USE

NUCLEAR POWER BUSINESS UNIT . ORTINDEX U1 OPERATIONS REFUELING TESTS Revision 185 January 31,1997 INDEX -
UNIT 1.

\

BIENNIAL

' PROCEDURE REVISION EITECTIVE REVIEW NUMBER- PROCEDURE TITLE NUMBER DATE DATE ORT INDEX A Completion Status Index...................................... 10 I 06/09/95 12/21/92 ORT 3 Safety Injection Actuation with Loss of Engineered Safeguards AC .................................. 26 C 08/02/93 08/02/93 ORT 3 APP C Review of ORT 3 Test Results.................. .............. 6 I 04/29/93 04/29/93 ORT 3A U1 Safety injection Actuation with Loss of .

Engineered Safeguards AC, Unit 1...................... 30 C . 04/12/% 04/04/96 ORT 3B Safety Injection Actuation with Loss of Engineered Safeguards AC .................................. 28 . C 04/03/95 04/03/95 ORT 3C U1 Auxiliary Feedwater System and AMSAC Actuation, Unit 1................ ..................... ............... 0 C 04/12/96 04/12/ %

~ [ ORT 4 Main Turbine Mechanical Overspeed Trip Device... 9 C 01/31/97 03/04/96

. ORT 6 Containment Spray Sequence Test.......................... 15 R 02/12/96 02/12/96 ORT 7 Operation of Backdraft Dampers .............................. 8 R 02/13/95 02/22/93

ORT 9 Fwy&dion for Integrated Leak Rate Test............... 13 R 03/19/93 03/19/93 ORT 9 APP A Component Cooling to and from IPIA(P15,17)...... 5 R 03/19/93 03/19/93 ORT 9 APP B Component Cooling to and from IPIB(P16,18)...... 5 R 03/19/93 03/19/93 ORT 9 APP C Hot Leg Sample.......................................(P28A)...... 5 R 03/02/93 03/02/93 ORT 9 APP D Pressurizer Liquid Sample ......................(P28B)...... 5 R 03/02/93 03/0263' .

ORT 9 APP E Pressurizer Steam Space Sample.............(P28C)...... 5 R 03/02/93 03/02/93 i ORT 9 APP F RMW to Containment ............................. (P30C)...... 3 R 03/02/93 03/02/93 ORT 9 APP G Nitrogen to SI Accumulators...................(P14C)...... 3 R 03/12/93 03/12/93' i ORT 9 APP H Instrument Air Supply.............................(P33A) ..... 9 R 03/05/93 03/05/93

j. ORT 9 APP I Instrument Air Supply.............................(P33B)...... 8 R 03/26/90 03/26/90
ORT 9 APP J "A" Steam Generator Sample..................(P34B)...... 4 R 03/26/90 03/26/90
ORT 9 APP K "B" Steam Generator Sample..................(P34C)...... 4 R 03/26/90 03/26/90 i

ORT 9 APP L Steam Generator B Blowdown...................(P50)......R6 03/12/93 03/12/93 OR)! 9 APP M Steam Generator A Blowdown...................(P51)...... R 6 03/05/93 03/05/93 ORT 9 APP N Nitrogen to PRT........................................ (14A)...... 5 R 03/26/90 03/26/90 .-

i ORT 9 APP O Reactor Coolant Pump Seal Return............(P11)......1 R 03/26/90 03/26/90 $

ORT 9 APP P Demineralized Water Supply to O Containment ......... .................... ........(P 12A)...... 2 R 07/14/93
  • 07/14/93 - <1 ORT 9 APP R Sample Line from PRT to Oas Analyzer - - -

' ..............................................................(P34A)......2 R 03/02/93 03/02/93

- ORT 9 APP S Sample Line from RCDT to Gas Analyzer i

.. ...... ...... ... ..... .............. .... ...... .. ... ... (P3 4D). ... .. 2 R 03/02/93 03/02/93

. ORT 9 APP T Heat Steam to Containment........................(P52)...... R- 03/26/90 1 03/26/90

[ f ORT 9 APP U Containment Condensate Retum................(P53)...... R 03/12/93 2 03/12/93

  • Indicates leak testing done with test rig located outside of containment.

C = Continuous Use R = Reference Use (T-Temporary Change) Page1of4 I = Information Use V .

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NUCLEAR POWER BUSINESS UNIT ORTINDEX UI OPERATIONS REFUELING TESTS Revision 185 January 31,1997 INDEX UNIT I BIENNIAL PROCEDURE REVISION EFFECTIVE REVIEW NUMBER PROCEDURE TITLE NUMBER DATE DATE ORT 9 APP V Train A Spray System Containment Isolation Valves.......................................(P54)...... 3 C 06/09/95 03/12/93 ORT 9 APP WTrain B Spray System Containment Isolation valves....... ................................(P5 5)...... 2 R 03/12/93 03/12/93 ORT 9 APP X 1 RE-211 and 212 Supply ............................ (X1)...... 3 R 12/05/94 03/19/93 ORT 9 APP Y 1 RE-211 and 212 Retum............................. (X2)...... 3 R 12/05/94 03/22/93 ORT 9 APP Z Component Cooling to and from iHX-4, Excess Letdown Heat Exchanger......................... . 1 R 03/22/93 03/22/93 ORT 9 CL-1B Containment Integrity Checklist for an ILRT........... 5 R 03/22/93 03/22/93 ORT 10 Recovery from Integrated Leak Rate Test........ ......1I R 03/19/93 03/19/93 ORT 11 Check Valve Stroke Test ........................................... 4 R 03/25/93 03/25/93 ORT 12 Fuel Transfer Tube Flange Seal ................................ 8 C 09/20/96 10/21/93 ORT 13 Equipment Hatch Flange Seals ................................. 9 C 02/22/95 02/22/93 ORT 15 Fuel Manipulator and Fuel Transfer System 1 Ch ecko ut . . . .. .. .. .. . . . . . . . . . .. . ... .. . . . .. . . . . ... .. .. . . . . . .. ...R. .. . . 10/02/95

. .. I 6 01/17/94 ORT 17 Containment Integrated Leak Rate Test.................... 0 C 03/19/93 03/19/93 ORT 18 ORT 19 ORT 20 ORT 21 l ORT 22 ORT 23 ORT 24 SI Test Line CIVs Leckage Test ... .................... ...... 2 C 03/10/95 12/05/94 ORT 25 RCDT and Cavity Drain...............................(P9).... 13 C 01/16/95 01/16/95 ORT 26 Letdown Line ....... .....................................(P 10)..... I 1 C 02/22/95 02/07/94 ORT 27 Reactor Coolant Pump Seal Return............(P11)..... I 1 C . 02/22/95 01/16/95 ORT 28 Demineralized Water Supply to r Containment .........................................(P 12A)..... I 1 C 10/25/96 10/28/93 -

ORT 29 Permanent Test Connection .... ..............(P12B)...... 2 C 01/09/97 01/09/97 ORT 30 C RCDT To Vent Header............................ (P12C)..... I 1 02/06/95 02/06/95  ;

ORT 31 Nitrogen Supply to the Pressurizer '

Relief Tank...........................................(P14 A)..... I 1 C 01/31/97 04/29/93

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ORT 32 Nitrogen to the SI Accumulators.............(P14C)....12 C 03/22/96 07/15/93 CORT 33 Post-Accident Containment Vent System-Retum ...................................... (P25 C).... 15 C 02/22/95 07/16/93 ORT 34 Nonnal Charging Line ...............................(P26)...... 9 C 09/22/95 09/22/95 ORT 35 Hot Leg Sample Line .................. ...........(P28A).... 13 C 10/02/95 11/30/93 ORT 36 Pressurizer Liquid Sample Line..............(P28B)...... 9 C 02/24/95 11/30/93

  • Indicates leak testing done with test rig located outside of containment.

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NUCLEAR POWER BUSINESS UNIT ORTINDEX U1 OPERATIONS REFUELING TESTS Revision 185 l

January 31,'1997 i / UNIT 1  ;

,( BIENNIAL

i. PROCEDURE REVISION EFFECTIVE REVIEW ,
NUMBER PROCEDURE TITLE NUMBER DATE DATE ORT 37 Pressurizer Steam Space Sample Line....(P28C)....10 C 02/24/95 -11/30/93 i ORT 38 ORT 39 Seal Injection to 1 P-1 A ...........................(P29A).... 10 C 02/22/95 02/15/93 -
ORT 40 Seal Injection to 1 P-1 B ........................... (P29B).... 12 C 02/22/95 02/22/93
- ORT 41 Pennanent Test Connection ....................(P30A)...... 4 C 01/09/97 01/09/97 ORT 42 RMUW to Containment ......... ...............(P30C).... 13 C 02/06/95 02/06/95  ;

' ORT 43 Containment Sampling Line....................(P31B)...... 8 C 02/13/95 02/22/93 q

  • ORT 44 Post-Accident Containment Ventilation

! System - Vent ....................................... (P31 C).... 14 C 02/24/95 01/16/95

. ORT 45 .

ORT 46 Auxiliary Charging Line ............. ..........(P32C).... 12 C 09/22/95 09/22/95

' ORT 47 Instmment Air Supply.............................(P33 A).... 13 C 02/06/95 02/06/95  !

  • ORT 48 Instrument Air Supply.............................(P33B).... 12 C 02/06/95 02/06/95 *
  • ORT.49 - Service Air Supply to Containment ........(P33C)....1 I C 02/24/95 04/29/93 l ORT 50 PRT to Gas Analyzer Sample Line .........(P34A)...... 9 C 01/31/97 11/30/93 ORT 51 Steam Generator A Sample Isolation......(P34B)...... 6 C 02/24/95 02/24/95 <

, ORT 52 Steam Generator B Sample Isolation......(P34C)...... 6 C 02/06/95 02/06/95 ORT 53 Reactor Coolant Drain Tank to Gas l Analyzer .................................. ............. (P34D)...... 7 C 01/16/95 01/16/95 F ORT 54 Steam Generator B Blowdown........ ..........(P50)....10 C 02/24/95 12/13/94 ORT 55 Steam Generator A Blowdown...................(P51)...... 9 C 02/24/95 12/13/94

- ORT 56 Heating Steam to Containment ..................(PS2)...... 7 C 02/13/95 02/22/93

, ORT 57 Containment Condensate Retum................(P53)...... 9 C 06/09/95 08/15/94 i ORT 58 C 02/24/95 1 Containment Test Connection.............. .....(P56)...... 9 02/22/93

  • ORT 59 Train A Spray System CIV Leakage Test...............17 C 01/31/97 12/05/94
  • ORT 60 . Train B Spray System CIV Leakage Test...............19 C 01/31/97 05/21/93
  • ORT 61 Sump A Drain to Auxiliary Building

, S ump .... . .. ... . .... . . .. . .. .... . . . . . .. . . . .. ... ....... .. .. .. . (P 71 C 7 )...... 02/24/95 02/24/95  ;

ORT 64 ORT 65 RE-211 and 212 Supply ........ ..................(PX1).... 12 C 02/24/95 02/22/93 j RE-211 and 212 Retum.............................(PX2)..... I 8 C 02/24/95 12/21/93 4

  • ORT 66A Containment Pressum.. ..........................(P31 A).... 10 C 02/13/95 ' '

02/13/95

.* ORT 66B Containment Pressure.............................. (P14B)...... 6C 02/13/95- 02/13/95 - - -

  • ORT 66C -

Containment Pressure..............................(P32A)...... 6 C 02/13/95 02/13/95

, ORT 67. Component Cooling Water to and from the Excess Letdown Heat

_ Exchanger - Refueling Shutdown .....(P19, 20).... 15 C 01/31/97 08/02/93

. ORT 68 Component Cooling Water to and

' from PI A - Refueling Shutdown.......(P15,17).... 17 C 03/10/95 07/16/93

  • Indicates leak testing done with test rig located outside of containment.

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NUCLEAR POWERBUSINESS UNIT ORTINDEX Ul OPERATIONS REFUELINO TESTS Revision 185 knuary 31,1997 INDEX UNIT 1 BIENNIAL PROCEDURE REVISION EFFECTIVE REVIEW NUMBER PROCEDURE TITLE NUMBER DATE DATE ORT 69 Component Cooling Water to and from IP-1B - Refueling Shutdawn ...(P16,18)....16 C 03/10/95 08/02/93 ORT 70 l ORT 71 Electrical Penetration Leak Test......... .......(P58)...... 7 C 01/31/97 02/13/95 ORT 72 Electrical Penetration Leak Test...........(P21,22)...... 8 C 01/25/97 02/13/95 ORT 73 Electrical Penetration Leak Test.................(P28)...... 8 C 01/25/97 02/13/95 ORT 74

  • ORT 75 Mechanical Penetration Leak Test (P50,51,52,53) . 8 C 02/13/95 02/13/95

' ORT 76 Mechanical Penetration Leak Test .............(P58)...... 6 C 02/13/95 02/13/95

  • ORT 77 Mechanical Penetration Leak Test.............(P57)...... 6 C 02/13/95 02/13/95

' ORT 78 Mechanical Penetration Leak Test.(P71,70,69)...... 7 C 02/13/95 02/13/95

  • ORT D Mechanical Penetration Leak Test ....................... .... 6 C 02/24/95 10/24/91
  • ORT I > Mechanical Penetration Leak Test.(P29,13,27)...... 8 C 02/13/95 02/13/95 CORT 1 Mechanical Penetration Leak Test .(P37, 38, 36, 40,48,45,44,46)...... 5 C 02/13/95 02/13/95
  • ORT 82 Mechanical Penetration Leak Test .(P47,43,39, 35, 55, 54, 5, 6)...... 4 C 02/13/95 02/13/95 CORT 83 Mechanical Penetration Leak Test.(P15,16,17, F 18,10,11)...... 7 C 02/13/95 02/13/95 .
  • ORT 84 Mechanical Penetration Leak Test.(P8,7,9,22)..... 7 C 02/13/95 02/13/95 W

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  • Indicates leak testing done with test rig located outside orcontainment.

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