change 2 to 'loss of low pressure injection sys.'loss of low pressure injection system...

Form 34731 (RS8)

Duke Power Company (1)ID No. AP/3/A/1700/07

PROCEDURE PROCESS RECORD Change(s) . to

0 Incorporated

PREPARATION (2) Station OCONEE NUCLEAR STATION

(3) Procedure Title LOSS OF LOW PRESSURE INJECTION SYSTEM

(4) Prepared By Date g / 9 (5) Reviewed By -4- )$.2 Date J

Cross-Disciplinary Review y N/R

(6) Temporary Approval (if necessary)

By (SRO) Date

By Date

(7) Approved By 7~~Date ~

(8) Miscellaneous

Reviewed/Approved By Date ..

Reviewed/Approved By Date

(9) Comments (For procedure reissue indicate whether additional changes, other than previously approved changes, are included. Attach additional pages, if necessary.) Additional Changes Included. M Yes

(10) Compared with Control Copy Date

(11) Requires change to FSAR not identified in 1 OCFR50.59 evaluation? O Yes If "yes", attach detailed explanation. 3 No

Completion (12) Date(s) Performed

(13) Procedure Completion Verification

O Yes O N/A Check lists and/or blanks property initialed, signed, dated or filled in N/A or N/R, as appropriate?

O Yes O N/A Usted enclosures attached?

O Yes O N/A Data sheets attached, completed, dated and signed?

O Yes O N/A Charts, graphs, etc. attached and properly dated, identified and marked?

O Yes O N/A Procedure requirements met?

Verified By Date

(14) Procedure Completion Approved Date

(15) Remarks (attach additional pages, if necessary)

910725008B 910715 PDR ADOCK 05000287 P PDR

Unit 3 Page i

LOSS OF LOW PRESSURE INJECTION SYSTEM AP/3/A/1700/07

TABLE OF CONTENTS

Page

CASE A: Failure Of One Train Of The LPI System During ECCS Operation

1.0 Purpose 1

2.0 Symptoms 1

3.0 Automatic Systems Actions 1

4.0 Immediate Manual Actions 2

5.0 Subsequent Actions 3

CASE B: Loss Of Low Pressure Injection System During Decay Heat Removal

1.0 Purpose 9

2.0 Symptoms 9

3.0 Automatic Systems Actions 9

4.0 Immediate Manual Actions 10

5.0 Subsequent Actions 11

6.0 Enclosures

6.1 Establishing RB Containment Closure 25

6.2 East Penetration Room Valve Checklist 33

6.3 West Penetration Room Valve Checklist 37

6.4 Miscellaneous Valve Checklist 40

6.5 Elapsed Time Until Core Boiling, Core

Uncovery, and Core Damage Following Loss

of DHR Capability 41

OCONEE NUCLEAR STATION


CASE A

Failure Of One Train Of The LPI System During ECCS Operation

1.0 Purpose

This case of this procedure provides the actions necessary following failure of one train of the LPI System during ECCS operation to restore flow to both LPI Hdrs, if possible.

2.0 Symptoms

* "LP INJECTION LOOP A FLOW HIGH/LOW" statalarm

(3SA-3, C-8)

* "LP INJECTION LOOP B FLOW HIGH/LOW" statalarm

(3SA-3, C-9)

* Failure of 3LP-17 ('3A' LP Injection) or

3LP-18*('3B' LP Injection) to "OPEN."

3.0 Automatic Systems Actions

None

Unit 3 Page 2 of 47


CASE A


Immediate Manual Actions

4.0 Immediate Manual Actions

NOTE Manual actions are required within 15 minutes of failure.

4.1 IF an LP Injection valve failed

to automatically open:

* 3LP-17 ('3A' LP Injection)

* 3LP-18 ('3B' LP Injection),

AND CANNOT be remotely operated,

* THEN send an Operator to open the valve(s)

manually.

4.2 IF an LPI pump failed to automatically start:

* '3A' LPI pump

* '3B' LPI pump,

THEN start the LPI pump.

Unit 3 Page 3 of 47


CASE A


Subsequent Actions

5.0 Subsequent Actions

5.1 Verify that the LPI System is lined up for ES conditions:

* REFER TO OP/3/A/1104/04, LOW PRESSURE INJECTION

SYSTEM.

5.2 IF an LPI pump fails to start

AND '3C' LPI pump is available,

THEN open the following valves:

* 3LP-6 ('3C' LPI Pump Suction ('A' Hdr))

* 3LP-7 ('3C' LPI Pump Suction ('B' Hdr))

5.2.1 IF the '3A' LPI pump is off,

THEN align the '3C' LPI Pump to 'A' header:

5.2.1.1 Open 3LP-9 ('3C' LPIP Disch to '3A' LPI

Hdr).

5.2.1.2 Start '3C' LPI Pump.

5.2.1.3 Throttle 3LP-12 ('3A' LPI Cooler Outlet

to establish = 3000 gpm flow in 'A'header.

Unit 3 Page 4 of 47


CASE A


Subsequent Actions

5.2.2 IF the '3B' LPI pump is off,

THEN align '3C' LPI Pump to 'B' header:

5.2.2.1 Open 3LP-10 Pump ('3C' LPIP Disch

To '3B' LPI Header).

5.2.2.2 Start '3C' LPI Pump.

5.2.2.3 Throttle 3LP-14 ('3B' LPI Cooler

Outlet)to establish = 3000 gpm flow in 'B' header.

5.3 IF only one LPI pump is operating,


* 3LP-9 ('3C' LPIP Disch to 'A' Hdr)

* 3LP-10 ('3C' LPIP Disch to 'B' Hdr).

5.3.1 Throttle the following valves to establish

1500 gpm in each Hdr:

* 3LP-12 ('3A' LPI Cooler Outlet)

* 3LP-14 ('3B' LPI Cooler Outlet).

Unit 3 Page 5 of 47


CASE A


Subsequent Actions

5.4 IF any LPI component required for normal ECCS

operation is inoperable,

* '3A' LPI pump

* '3B' LPI pump

* LPI ES valves

THEN attempt to repair the LPI system,

and

return LPI system to normal ECCS operation.

CAUTION 5.5: If only one LPI cooler is operable, the appropriate LPI and LPSW flows must be established through the operable cooler. This action ensures an adequate core cooldown rate and maintains RB environmental qualification criteria. This requirement is applicable immediately after swapping LPI pump suction from the BWST to the RB EMER Sump.

5.5 IF only one LPI cooler is operable

AND LPI Pump Suction is aligned to the RB

EMER Sump,


* 3LP-9 ('3C' LPIP Disch to 'A' Hdr)

* 3LP-10 ('3C' LPIP Disch to 'B' Hdr).

5.5.1 IF an LPI line break exists,

THEN send an operator to close the following

valve on the affected Hdr:

*3LP-11 ('3A' LPI Cooler Inlet)

* 3LP-13 ('3B' LPI Cooler Inlet).

Unit 3 Page 6 of 47


CASE A


Subsequent Actions

5.5.2 Verify two LPI pumps running.

5.5.3 IF '3A' cooler is operable,

THEN isolate the '3B' cooler:

* Close 3LP-13 ('3B' LPI Cooler

Inlet)

* Close 3LP-14 ('3B' LPI Cooler

Outlet),

AND throttle 3LP-12 ('3A' LPI Cooler

Outlet) to establish = 5000 to 5800

gpm.

5.5.3.1 Increase LPSW flow to the '3A' LPI Cooler to

=.5500 gpm:

* Throttle 3LPSW-405 ('3A' LPI Cooler Outlet Vlv).

5.5.4 IF '3B' cooler is operable,

THEN isolate the '3A' cooler:

* Close 3LP-11 ('3A' LPI .Cooler

Inlet)

* Close 3LP-12 ('3A' LPI Cooler

Outlet),

AND throttle 3LP-14 ('3B' LPI Cooler Outlet

to establish = 5000 to 5800 gpm.

Unit 3 Page 7 of 47


CASE A


Subsequent Actions

5.5.4.1 Increase LPSW flow to the '3B' LPI Cooler to

= 5500 gpm:

* Throttle 3LPSW-404 ('3B' LPI

Cooler Outlet Vlv).

5.6 IF one RB EMER Sump suction line is NOT operable:

* 3LP-19 ('3A' Rx Bldg Suction)

* 3LP-20 ('3B' Rx Bldg Suction),

AND LPI suction must be swapped to the RB EMER Sump

from the BWST,

THEN perform the following alignments:

5.6.1 Secure the following to provide adequate

NPSH for the LPI pumps:

* '3A' RBS Pump

* '3B' RBS Pump.

5.6.2 Open the following valves:

* 3LP-6 ('3C' LPI Pump Suction

('A' Hdr))

* 3LP-7 ('3C' LPI Pump Suction

('B' Hdr))

5.6.3 Open the operable valves:


* 3LP-20 ('3B' Rx Bldg Suction).

Unit 3 Page 8 of 47


CASE A

Failure Of one Train Of The LPI System During ECCS Operation

Subsequent Actions

5.6.4 Close the following valves:

* 3LP-21 ('3A' LPI BWST Suction)

* 3LP-22 ('3B' LPI BWST Suction).

5.6.5 Verify RBCUs operation:

* All RBCUs in "LOW" speed

* LPSW flow 1400 gpm to each RBCU.

END

Unit 3 Page 9 of 47


'CASE a

Loss Of Low Pressure Injection System During Decay Heat Removal

1.0 Purpose

This case of this procedure provides the actions necessary to reestablish core cooling following a loss of the LPI system during decay heat removal.

2.0 Symptoms

* "LP DECAY HEAT LOOP A FLOW LOW" statalarm

(3SA-3, A-8)

"LP DECAY HEAT LOOP B FLOW LOW" statalarm

(3SA-3, A-9) * RCS incore temperature increasing

* LP cooler outlet temperature increasing

* LPI pump(s) tripped

* "LP INJECTION PUMP A DIFF PRESS LOW" statalarm

(3SA-1, C-12)

0 '"LP INJECTION PUMP B DIFF PRESS LOW" statalarm

(3SA-1, D-12)

* 1"LP INJECTION PUMP C DIFF PRESS LOW" statalarm

(3SA-1, E-12)

* "ULTRASONIC RV LEVEL LOW" Statalarm

(3SA-14, A-5)

3.0 Automatic Systems Actions

None

III

Unit 3 Page 10 of 47


CASE B


Immediate Manual Actions

4.0 Immediate Manual Actions

4.1 IF LPI pump flow has degraded:

* LPI pump d/P < 130 psid

(3SA-1, C-12/D-12/E-12)

* "LPI Header Flow" < 1000 gpm/hdr

* "LPI pump amps" are fluctuating,

THEN trip the running LPI pump.



CASE B


Subsequent Actions

5.0 Subsequent Actions

5.1 Verify the LPI Decay Heat Removal valve lineup:

* REFER TO OP/3/A/1104/04, LOW PRESSURE

INJECTION SYSTEM.

NOTE 5.2 The accuracy of LT-5 "Reactor Level" is affected by RB and RCS pressure.

5.2 IF a loss of RCS inventory during LPI decay heat

removal has occurred,

THEN isolate possible leakage paths:

* Secure any draining of the RCS

* Secure LPI purification

and

initiate make up to the RCS:

* Ensure > 1% SDM.

5.2.1 IF the RCS is filled,

THEN maintain PZR level.



CASE B


Subsequent Actions

5.2.2 IF the RCS is drained

OR the RCS is open,

THEN make up to the RCS via the LPI System

from the BHUTs:

* REFER TO OP/3/A/1103/11,

DRAINING AND NITROGEN

PURGING OF RC SYSTEM.

5.2.3 IF makeup from the BHUTs CANNOT be

established,

THEN makeup to the RCS from the BWST:

5.2.3.1 Open one of the following valves:



5.2.3.2 WHEN RCS level > 10" as indicated by:

* LT-5 Gauge or Comp. Pt. A2103

* Hot Leg Level Comp. Pt. A2101

* Cold Leg Level Comp. Pt. A2102

THEN close the following valves:

* 3LP-21 ('3A' LPI BWST

Suction)

* 3LP-22 ('3B' LPI BWST

Suction).



CASE B


Subsequent Actions

NOTE 5.3 An LPI pump can experience cavitation if extended operation with < 800 gpm is allowed or adequate NPSH is not maintained.

5.3 IF the LPI pump did NOT experience

"cavitation,"

THEN start the STBY LPI pump.

5.4 IF all of the following conditions are true:

* Core cooling does NOT exist

* RCS is open

* Containment Integrity does NOT exist

THEN establish RB Containment Closure:

* REFER TO Enclosure 6.1 (Establishing

RB Containment Closure).

5.5 IF NO LPI pump is available,

THEN GO TO Step 5.9.



CASE B


Subsequent Actions

CAUTION 5.6 The RCS can overflow to the RB if the RCS is opened and an LPI flowpath is aligned from the BWST to the RCS.

5.6 IF the LPI pump has experienced "cavitation,"

THEN vent the LPI pumps:

5.6.1 Open one of the following valves:

3LP-21 ('3A' LPI BWST Suction)


5.6.2 Send an Operator to open the following valves:

* 3LWD-369 (LPI Pump '3A' Vent)

* 3LWD-373 (LPI Pump '3B' Vent)

* 3LWD-371 (LPI Pump '3C' Vent).

5.6.3 WHEN a solid stream of water is

visible in the sight glasses,





5.6.4 Start an LPI pump:

* IF NO LPI pumps are available,

* THEN GO TO Step 5.9.



CASE B


Subsequent Actions

5.6.5 Close the following valves:



5.6.6 Verify proper LPI pump parameters:

* LPI pump d/P > 130 psid

(3SA-1, C-12/D-12/E-12)

* "LPI Header Flow" > 1000 gpm/hdr

* "LPI Pump Amps" are stable.

5.7 IF the LPI pump(s) "cavitates" after venting,

THEN align LPI pump suction from the BWST and maintain

a stable core temperature:

* < 200aF if CETCs are available

* maintain RxV level on-scale if CETCs are NOT

available.

5.7.1 IF the RCS is closed,

AND system heat up and expansion has

resulted in deadheading of the

LPI pump(s):

* RCS pressure > 180 psig,

THEN depressurize the RCS to allow the LPI

pump(s) to discharge into the RCS:

* Open 3RC-4 (PZR Relief Block)

* Cycle 3RC-66 (PORV) to reduce RCS

pressure < 180 psig.



CASE B


Subsequent Actions

5.7.2 IF Containment Integrity does NOT exist,

AND the RCS is open,


* REFER TO Enclosure 6.1

(Establishing RB Containment

Closure).

5.7.3 Open the following valves:

-3LP-21 ('3A1 LPI BWST Suction)


5.7.4 Send an Operator to open the following valves:




5.7.5 WHEN a solid stream of water is visible in

the sight glasses,







CASE B

Loss Of Low Pressure Injection System During Decay Heat

Subsequent Actions

NOTE 5.7.6 The minimum flow for an LPI pump is 800 gpm. The

Operator may have to start and stop the LPI pumps to maintain an RCS inventory and to minimize RCS overflow to the RB.

5.7.6 Start an LPI pump:

IF NO LPI pump is available,

THEN GO TO Step 5.9.

5.8 IF a loss of RCS inventory during LPI decay

heat removal has occurred,

THEN initiate makeup to the RCS:

* Ensure > 1% SDM.

* IF the RCS is filled,

THEN maintain PZR level.

* IF the RCS is drained,

OR the RCS is open,

THEN maintain > 10" as indicated on:

LT-5 Gauge or Comp. Pt. A2103

Hot Leg Level Comp. Pt. A2101

Cold Leg Level Comp. Pt. A2102

AND secure any draining of the RCS.

5.8.1 IF loss of inventory is due to a leak,

THEN determine the leak location,

and

isolate the leak, if possible.



CASE B


Subsequent Actions

5.8.2 IF Containment Integrity does NOT exist



* REFER TO Enclosure 6.1

(Establishing RB Containment

Closure).

5.8.3 IF the leak is on an LPI line,

THEN perform the following:

5.8.3.1 Stop the LPI pump discharging to the affected

header.

5.8.3.2 Isolate the affected header.

5.8.3.3 Align LPI pumps to the redundant header.

5.8.3.4 Start an LPI pump(s):

* Establish proper LPI flow rates:

* REFER TO OP/3/A/1102/10,

CONTROLLING PROCEDURE

FOR UNIT SHUTDOWN.



CASE B.


Subsequent Actions

5.8.4 IF the leak is in the RB,

AND the leak CANNOT be isolated,

THEN maintain RCS makeup,

and

maintain LPI decay heat removal flow.

CAUTION 5.8.4.1 Do not allow an LPI pump to "cavitate." The leak in the RB may not be large enough to maintain sufficient sump level for LPI pump NPSH.

5.8.4.1 WHEN RB level > 3.5 ft,

THEN swap LPI pump suction to the

RB EMER Sump:

Open the following valves:


* 3LP-20 ('3B' Rx Bldg Suction)

and

Close the following valves:

* 3LP-1 (LPI Return Block From

RCS)

* 3LP-2 (LPI Return Block)


* 3LP-22 ('3B' LPI BWST

Suction).



CASE B


Subsequent Actions

5.8.4.2 IF the RB level < 3.5 ft,

THEN cycle the LPI pump to allow

the RB level to reestablish

> 3.5 ft:

Maintain LPI pump NPSH.

NOTE 5.9 Inability to maintain core temperature < 200OF due to a sustained loss of LPI decay heat removal during shutdown conditionsmeets the criterion for an Alert condition. The TSC should be consulted whenever an alternate means of core cooling is required.

5.9 IF NO LPI decay heat removal is available,


5.9.1 IF the RCS is filled,

AND RCS can be pressurized,


5.9.1.1 Close the following valves:

* 3LP-1 (LPI Return Block From RCS)


* 3LP-3 (LPI Hot Leg Suction).



CASE B


Subsequent Actions

5.9.1.2 Align for HPI makeup from the BWST:

Open one HPI suction valve from the

BWST:

* 3HP-24 ('3A' HPI BWST Suction)

* 3HP-25 ('3B' HPI BWST Suction).

5.9.1.3 Start the '3A' or '3B' HPI pump.

5.9.1.4 Throttle 3HP-120 (RC Volume Control) to

establish a PZR level.

5.9.1.5 Establish RCS flow by one of the following:

* Increase RCS pressure above RCP NPSH

and

start one RCP:

* REFER TO OP/3/A/1103/06, RCP

OPERATION.

* Establish natural circulation.

5.9.1.6 Initiate FDW flow

and

establish proper SG level:

* 25" SUR with RCP

* 50% O.R. without RCP.



CASE B


Subseauent Actions

5.9.1.7 Maintain RCS cold leg temperature < 200 0 F:

* IF condenser vacuum exists,

THEN use the TBVs,

IF NOT,

THEN use the Atmospheric Dump

Valves:

* REFER TO EP/3/A/1800/01,

Enclosure 7.8 (Operation

of Atmospheric Dump

Valves).

5.9.1.8 IF primary to secondary heat transfer

CANNOT be established,

THEN establish RCS pressure at = 200

psig,

AND open the following valves to align

HPI pump suction from the LPI

system:

* 3LP-1 (LPI Return Block From

RCS)


* 3LP-3 (LPI Hot Leg Suction)

* 3LP-11 ('3A' LPI Cooler Inlet)

* 3LP-12 ('3A' LPI Cooler

Outlet)

* 3LP-15 ('3A' LPI to HPI and

RBS).



CASE B


Subsequent Actions

5.9.1.9 Limit HPI flow to 5 500 gpm with the

'3A' or '3B' HPI pump operating.

5.9.1.10 Establish primary to secondary heat transfer

as soon as possible since HPI flow alone may

have insufficient capacity to remove decay

heat.

CAUTION 5.9.2 The RCS can overflow to the RB if the RCS is opened and

makeup is initiated.

5.9.2 IF Containment Integrity does NOT exist



* REFER TO Enclosure 6.1 (Establishing RB

Containment Closure).

5.9.2.1 Align for HPI makeup from the BWST:

* Open one HPI suction valve from the

BWST:

* 3HP-24 ('3A' HPI BWST Suction)

* 3HP-25 ('3B' HPI BWST Suction).

5.9.2.2 Start the '3A' or '3B' HPI pump.

I.I



CASE B


Subsequent Actions

5.9.2.3 Throttle 3HP-120 (RC Volume Control):

* Maintain RxV level on scale if CETCs are

NOT available.

* Maintain RCS temperature < 200'F if

CETCs are available.

* Minimize RCS overflow to the RB.

5.9.3 IF the Fuel Transfer Canal is full,

THEN use the SF Coolers to maintain RCS

temperature:

* REFER TO OP/3/A/1104/06, SPENT FUEL

COOLING SYSTEM.

END



ENCLOSURE 6.1 Establishing RB Containment Closure

NOTE: The applicable steps of this enclosure must be performed concurrently, if possible, to ensure containment closure is established prior to core uncovery. Enclosure 6.5, elapsed time until core boiling, core uncovery, and core damage following loss of DHR capability, may be referenced to ensure appropriate resources are allocated to this task.

When the LPI system has been restored to the normal decay heat removal mode with RC system pressure and temperature within the desired range, containment closure activities may be halted.

1.0 Establish RB Containment Closure by instructing the Shift

Manager to make the following notifications:

1.1 Notify Mechanical Maintenance to close the following

components:

* RB equipment hatch

* All temporary RB penetrations

* All SG secondary side penetrations within

containment.

1.2 Notify I&E to close all RB instrument penetrations.

1.3 Verify with Performance that all RB electrical

penetrations are secure.

2.0 Evacuate the RB of all non-essential personnel.




3.0 Secure the RB purge:

3.1 Stop the RB purge fan.

3.2 Close:

3PR-1 (RB Purge Outlet)

3PR-2 (RB Purge Outlet)

3PR-3 (RB Purge Flow)

3PR-4 (RB Purge Inlet)

3PR-5 (RB Purge Inlet)

3PR-6 (RB Purge Inlet).

4.0 Send an Operator to close:

At least one door of the RB personnel hatch

At least one door of the RB emergency hatch.

4.1 IF electrical cables or hoses are routed through

the RB emergency hatch,

THEN notify the Shift Manager to remove obstructions

and close outer door.

5.0 Send Operators to establish RB Containment Closure.

* REFER TO: Enclosure 6.2 (East Penetration Room Valve

Checklist)

Enclosure 6.3 (West Penetration Room Valve

Checklist)

Enclosure 6.4 (Miscellaneous Valve

Checklist).




6.0 Establish RB Containment Closure from the control

room.

Close the following valves:

3RC-7 (PZR Sample Isolation)

3BS-1 ('A' Header RB Isolation)

3BS-2 ('B' Header RB Isolation)

3GWD-13 (Quench Tank Vent (Outside RB))

3FDW-103 (SG '3A' Shell Drain Block)

3FDW-104 (SG '3B' Shell Drain Block)

*__ 3FDW-106 (SG '3A' Sample Isolation)

3FDW-108 (SG '3B' Sample Isolation)

3PR-81 (H2 Sample Cont Isolation)




3LWD-1 (RB Normal Sump Isolation)

3CS-6 (Component Drn Pump Suction)

3HP-5 (Letdown Isolation).

7.0 IF seal return is NOT required for RCP operation,

THEN close 3HP-21 (RCP Seal Return Block).




8.0 IF warming line flow is NOT required,

THEN send an Operator to close 3HP-242 (Nozzle Warming

Stop Check, East Pent Rm, Pent #8).

9.0 IF RCS makeup is NOT supplied via the HPI injection

headers,

THEN isolate HPI injection:

9.1 Close the following valves:

'A' Header

____ 3HP-26 ('3A' HP Injection)

3HP-410 (3HP-26 Bypass)

'B' Header

3HP-409 (3HP-27 Bypass)

3HP-27 ('3B' HP Injection).

9.2 Send an Operator to close the following valves:

3HP-121 (RC Volume Control Outlet, East Pent

Rm,Pent #9)

3HP-122 (RC Volume Control Bypass, East Pent

Rm, Pent #9).




10.0 IF seal injection is NOT required for RCP operation

AND seal injection is NOT required for RCS makeup,

THEN send an Operator to close the following valves:

3HP-285 (Seal Supply to RCP 'Bl' Outside

Block, West Pent Rm, Pent #10) 3HP-286 (Seal Supply to RCP 'B2'Outside

Block, West Pent Rm, Pent #10).

11.0 IF the LPI recirculation mode is NOT aligned,


3LP-19 ('3A' Rx Bldg Suction) 3LP-20 ('3B' Rx Bldg Suction).




12.0 IF the RB radiation monitors are out-of-service,

THEN secure the sample pump:


3PR-8 (RB Radiation Monitor Inlet)

3PR-10 (RB Radiation Monitor Return Block).

13.0 IF CC is secured,

THEN close 3CC-8 (CC Return Penetration Outside Block).

14.0 IF the ILRT is in progress,

THEN notify Performance to isolate:

* Penetration #45 (ILRT Instrument Line)

* Penetration #51 (ILRT Pressurization Line).

15.0 IF EFDW is NOT required for DHR,

THEN send an Operator to close 3FDW-301 (SG '3A' Wet

Layup Recirc Inlet, East Pent Rm, Pent #50).




16.0 IF the RB Cooling Units are NOT in service,

THEN isolate LPSW:


3LPSW-16 ('3A' RBCU Inlet)

3LPSW-19 ('3B' RBCU & Aux Fan Clr Inlet)

3LPSW-22 ('3C' RBCU Inlet)

3LPSW-18 ('3A' RBCU Outlet)

3LPSW-21 ('3B' RBCU & RB Aux Fan Clr Outlet)

3LPSW-24 ('3C' RBCU Outlet)

16.2 Send an Operator to close the following valves:

3LPSW-241 (RBCU '3A' Outlet to 3RIA-31/35, East

Pent Rm, Pent #34)

3LPSW-258 (RBCU '3A' Outlet Test Connection, East

Pent Rm, Pent #34)

3LPSW-242 (RBCU '3B' Outlet to 3RIA-31/35, East

Pent Rm, Pent #35)

3LPSW-259 (RBCU '3B' Outlet Test Connection, East

Pent Rm, Pent #35)

3LPSW-243 (RBCU '3C' Outlet to 3RIA-31/35, East

Pent Rm, Pent #33)

3LPSW-257 (RBCU '3C' Outlet Test Connection, East

Pent Rm, Pent #33).

17.0 IF RCPs are NOT operating,

* AND the RB fire hose stations are NOT intact,


3LPSW-6 (RCP Coolers Supply)

3LPSW-15 (RCP Coolers Outlet).




18.0 IF all personnel using BA have evacuated the RB,

THEN send an Operator to close 3BA-271 (RB Header

Isolation, East Pent Rm, Pent #48).

19.0 IF IA pressure to the RB is lost,

THEN send an Operator to close 31A-90 (RB Header

Isolation, East Pent Rm, Pent #41).

END



ENCLOSURE 6.2 East Penetration Room Valve Checklist

1.0 Verify the following penetrations in the East Penetration Room

are isolated as follows:

* Penetration #18

3GWD-10 (QT Vent Penetration Vent) - CLOSED

3GWD-11 (QT Vent Penetration Vent) - CLOSED

* Penetration #9

3HP-123 (RC Loop 'A' Injection Pent. Vent) - CLOSED

3HP-124 (RC Loop 'A' Injection Pent. Vent) - CLOSED

* Penetration #8

3HP-237 (Aux PZR Spray Line Pent. Vent) - CLOSED

3HP-239 (Aux PZR Spray Line Pent. Drain) - CLOSED

3HP-243 (Nozzle Warming Pent. Vent) - CLOSED

3HP-245 (Nozzle Warming Pent. Drain) - CLOSED

3HP-419 (Aux Pzr Spray Check) - INTACT

* Penetration #7

3HP-68 (Seal Return Penetration Vent) - CLOSED

3HP-69 (Seal Return Penetration Drain) - CLOSED

* Penetration #6

3HP-36 (Letdown Penetration Vent) - CLOSED

3HP-37 (Letdown Penetration Drain) - CLOSED

01




* Penetration #2

3FDW-117 ('3A' SG Sample Pent. Vent) - CLOSED

3FDW-118 ('3A' SG Sample Pent. Drain) - CLOSED

* Penetration #23

3HP-202 (RCP 'A2' Seal Supply Pent. Vent) - CLOSED

3HP-204 (RCP 'A2' Seal Supply Pent. Drain) - CLOSED

3HP-209 (RCP 'Al' Seal Supply Pent. Vent) - CLOSED

3HP-211 (RCP 'Al' Seal Supply Pent. Drain) - CLOSED

3HP-390 (RCP 'Al' Seal Supply Check) - INTACT

*__ 3HP-454 (RCP 'A2' Seal Supply Check) - INTACT

* Penetration #22

3LPSW-144 (LPSW Return Pent. Drain) - CLOSED

3LPSW-145 (LPSW Return Pent. Vent) - CLOSED

3LPSW-146 (LPSW Return Pent. Test Gauge) - CLOSED

* Penetration #21

3LPSW-141 (LPSW Supply Pent. Drain) - CLOSED

3LPSW-142 (LPSW Supply Pent. Vent) - CLOSED

3LPSW-143 (LPSW Supply Pent. Test Gauge) - CLOSED

Penetration #15

3LP-44 ('A' Header Pent. Test) - CLOSED

3LP-17 ('A' LPI Injection) - INTACT




* Penetration #50

3FDW-130 (Aux FDW Header '3A' Pent. Vent) - CLOSED

3FDW-131 (Aux FDW Header '3A' Pent. Drain) - CLOSED

3FDW-39 ('3A' SG Emer Header Check) - INTACT

3FDW-317 (EFWP Disch to SG '3A' Check) - INTACT

3CCW-121 (Aux Service Water to SG '3A' Check) - INTACT

* Penetration #38

3CS-17 (QT Return Pent. Drain) - CLOSED

3CS-18 (QT Return Pent. Vent) - CLOSED

3CS-11 (QT Recirc Pent. Check) - INTACT

* Penetration #3

3CC-24 (Supply Hdr Pent. Isolation Check) - INTACT

* Penetration #61

3PR-25 (RB Sample Outlet Test) - CLOSED

* Penetration #46

3FW-64 (Booster Pump Header Pent. Block) - CLOSED

* Penetration #60

3PR-23 (RB Sample Inlet Pent. Test) - CLOSED

3PR-68 (Radiation Monitor Inlet Drain) - CLOSED

* Penetration #45 (Located between MFDW lines)

3LRT-25 (RB Pressure Line Outer Block) - CLOSED

3LRT-36 (LRT Block Valve) - CLOSED

3LRT-38 (LRT Outer Isolation) - CLOSED




* Penetration #20

3PR-27 (RB Purge Exhaust Pent. Test) - CLOSED

* Penetration #44

3CC-76 (CRD Cooling Pent. Outside Check) - INTACT

* Penetration #25

3FDW-46 ('3B' SG Normal Header Check) - INTACT

* Penetration #27

3FDW-247 (FDW Header '3A' Vent Block) - CLOSED

3FDW-37 ('3A' SG Normal Header Check Valve) - INTACT

2.0 Contact the control room for additional assignments prior to

exiting the penetration room.

01



ENCLOSURE 6.3 West Penetration Room Valve Checklist

1.0 Close the following valves located in the West Penetration Room:

* Penetration #59

3CF-7 (CF Bleed to Waste Holdup Tank) - CLOSED

3CF-19 (CF Sample Block) - CLOSED

* Penetration #58

3RC-49 (PZR Sample Pent. Vent) - CLOSED

3RC-50 (PZR Sample Pent. Drain) - CLOSED

3FDW-122 ('3B' SG Sample Pent. Vent) - CLOSED

___ 3FDW-123 ('3B' SG Sample Pent. Drain) -CLOSED

* Penetration #39

3CF-35 (CF Vent to Waste Gas Filter Block) - CLOSED

3CF-36 (CF Vent to Vent Hdr Block) - CLOSED

3CF-37 (CF Vent to Vent Hdr Pent.Vent) - CLOSED

3CF-41 ('B' CFT Pressure Gauge Block) - CLOSED

3HP-156 (CFT 'B' Fill) - CLOSED

3CA-29 (Boric Acid Supply to CFT '3B') - CLOSED

3N-131 (CFT 'B' Supply Check) - INTACT

* Penetration #56

3SF-60 (Canal Fill Pent. Block) - CLOSED

* Penetration #55

3DW-59 (Demin Header Pent. Isolation) - CLOSED




* Penetration #54

3CC-54 (Return Penetration Drain) - CLOSED

3CC-55 (Return Penetration Vent) - CLOSED

3CC-56 (Return Penetration Test) - CLOSED

* Penetration #10

3HP-216 (RCP 'B2' Seal Supply Pent. Vent) - CLOSED

3HP-218 (RCP 'B2' Seal Supply Pent. Drain) - CLOSED

3HP-223 (RCP 'Bl' Seal Supply Pent. Vent) - CLOSED

3HP-225 (RCP 'Bl' Seal Supply Pent. Drain) - CLOSED

Penetration #53

3CF-47 ('A' CFT Pressure Gauge Isolation) - CLOSED

3HP-155 (CFT 'A' Fill) - CLOSED

3CA-27.(Boric Acid Supply to CFT '3A') - CLOSED

3N-263 (Pent. Isolation LP Header) - CLOSED

3N-129 (CFT 'A' Supply Check) - INTACT

Penetration #52

3HP-149 (RC Loop 'B' Injection Pent. Vent) - CLOSED

3HP-150 (RC Loop 'B' Injection Pent. Drain) - CLOSED

* Penetration #19

3PR-29 (RB Purge Supply Pent. Test) - CLOSED




* Penetration #51

3LRT-17 (Pressurization Isolation) - CLOSED

2" Blind Flange Installed

3LRT-54 (Pressure Gauge Isolation) - CLOSED

* Penetration #16

3LP-43 ('B' Header Pent. Test). - CLOSED

3LP-18 ('3B' LP Injection) - INTACT

NOTE: If the Security enclosure is not open, assume 3FDW-442 is * intact.

* Penetration #17

3FDW-442 (EFDW to 'B' SG Outside Check) - INTACT

2.0 Contact the control room for additional assignments prior to exiting the penetration room.



ENCLOSURE 6.4 Miscellaneous Valve Checklist

1.0 Close the following valves located in Rm 82/83 (LPI Pump 'A' and

LP-19/20 Valve Rooms):

* Penetration #29

3CS-23 (Component Drain Header Pent. Drain) - CLOSED

3CS-25 (Component Drain Header Pent. Test) -CLOSED

* Penetration #36

3LP-66 ('3A1 Emergency Sump Line Drain) - CLOSED

3LWD-329 (LP-19 Valve Enclosure Drain) - CLOSED

* Penetration #37

3LP-65 ('3B' Emergency Sump Line Drain) - CLOSED

3LWD-330 (LP-20 Valve Enclosure Drain) -CLOSED

* Penetration #40

3LWD-99 (Emergency Sump Drain Pent. Block) - CLOSED

* Penetration #5

3RC-164 (Post Accident Sample Valve). - CLOSED



ENCLOSURE 6.5

Elapsed Time Until Core Boiling, Core Uncovery, and Core Damage Following Loss of DHR Capability

Assumptions

* Initial RCS/LPI Temperature = 140 0 F

* Upper SG Primary Handholes Removed To Vent RCS

* Worst Case Decay Heat (EOC)

* No Operator Action

Notes

1) "Prior To Refueling" curves-assume all fuel assemblies

in the core have experienced operation at power.

2) "After Refueling" curves assume approximately one third

of the core is new fuel.

3) Curves for "LT-5=-18" are applicable to incidents where

reactor vessel level has been reduced to the bottom of

the hot leg. Example: LPI line break.

Curves

Figure 1: Time To Core Boiling Prior To Refueling

Figure 2: Time To Core Uncovery Prior To Refueling

Figure 3: Time To Core Damage Prior To Refueling

Figure 4: Time To Core Boiling After Refueling

Figure 5: Time To Core Uncovery After Refueling

Figure 6: Time To Core Damage After Refueling



ENCLOSURE 6.5


Figure 1

Time to Core Boiling

1.7

40LT-5= 80"

I * * LT-5= 50"

* 0.400orLT-5= -18"v

L

1 00001

* 02

0 4 8 12 16 2 24

D eter Au



ENCLOSURE 6.5 Elapsed Time Until Core Boiling, Core Uncovery, and Core Damage

Following Loss of DHR Capability

Figure 2

Time to Core Uncovery Prrtb 1

12A

LT-5= 80"

40

I 9

o LT-5= 50 "

....- - L T-5 = -148"

*~~L5 o- - - - - -0 4 111122

A t

2M 0 LT-5= -18"

1AU

0A 0 4 8 12 16 3 24





Figure 3

Time to Core Damage

LT-5=80" 12A------- --40

I

LT-5=50"

A .. LT, 5 4100

10-*.. LT-5=14"

L OA -

LT-5 418

0 4. 6 12 16 x 24

D*dhr 9"-



ENCLOSURE 6.5


Figure 4

Time to Core Boiling

LT-5= 80"

g LT-5= 50"

L

0.4 212224.

0vd "



ENCLOSURE 6.5


Figure 5

Time to Core Uncovery asstang 1NOR5I

170

16A . LT-5= 80"

15- ---- 50

-145= 1

* ~~1* 7

2

- - -- - - - LT-5= 50"

11Am - - - - --

0A

-N - - - - -- LT-5= 14"

7m -

,5 .. -- - -

3A - LT-5= -18"

22 5

20 224 26 28.

ow d %W





Figure 6

Time to Core Damage

lii-- - ___ - - - - -- LT-5= 80"

LT-5= 50" 12A 16AU -- --- -

15A - LT-5= 50"

* 14A 3

o12A.3 LT-5= 14"

I

8A -* a a a3

'7A" 6A-- - LT-5= -18"1

4A.3 3

0 3 fl24 26N

change 2 to 'loss of low pressure injection sys.'loss of low pressure injection system...

Documents