ML20196F945

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Rev 7 to AP-1080, Refueling Canal Level Lowering
ML20196F945
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/19/1998
From: Wilson I
FLORIDA POWER CORP.
To:
Shared Package
ML20196F936 List:
References
AP-1080, NUDOCS 9812070166
Download: ML20196F945 (25)


Text

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RCLL. REV 07 (MC) AP-1080 l l

t REFUELING CANAL LEVEL LOWERING l l

1.0 ENTRY CONDITIONS E unexpected lowering of refueling canal level occurs.

THEN use this procedure.

2.0 IMMEDIATE ACTIONS NOTE There are no immediate actions for this procedure.

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Approved by MNP [.y do-Date'/////f/7[

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AP-1080 PAGE 1 of 25 RCLL 9812070166 981123

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. 3.0 FOLLOW-UP ACTIONS l

,e ACTIONS DETAILS V

3.1 Notify personnel of plant e STA conditions.

e Plant Operators i e Health Physics e NSM (evaluate plant conditions for potential entry into the Emergency Plan) e Refueling Area Supervisor 3.2 . E refueling activities are NOT in progress.

THEN GO T0 step 3.7 in l this procedure.

l E refueling canal level

'~'T 3.3 (V or SF pool level is lowering faster than fuel or components can be placed in a safe position.

THEN immediately evacuate the area.

3.4 Ensure fuel attached to e E irradiated fuel is suspended the Main Fuel Handling from Main Fuel Handling Bridge. <

Bridge is placed in a safe THEN notify bridge operator to position. place fuel in Rx vessel.

e E irradiated fuel can NOT be placed in the Rx vessel.

THEN notify bridge operator to place the fuel in an available upender and lower.

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. 3.0 FOLLOW UP ACTIONS (CONT *D)

ACTIONS DETAILS 3.5 Ensure comnenents attached e E irradiated fuel is suspended to the SF handling bridge from SF handling bridge.

are placed in a safe THEN notify bridge operator to position. return the fuel to the SF rack location it came from.

e E irradiated' fuel can NOT be returned to original location.

THEN notify bridge operator to i place the fuel in an available- l upender and lower.

3.6 Ensure components attached e E irradiated components are to the crane are placed in suspended from crane, safe position. AND in the canal.

THEN notify crane operator to place component in deep end.

e E component can NOT be placed in the deep end.

O THEN notiTy crane operator to suspend component inside Rx vessel above fuel.

O AP-1080 REV 07 (MC) PAGE 5 of 25 RCLL

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3.0 FOLLOW UP ACTIONS (CONT *D)

I rT ACTIONS DETAILS

'V NOTE RB pressure can affect fuel transfer canal level when fuel transfer ,

I tubes are open. l 3.7 Review plant parameters to e Observe all of the following levels:

determine source of leak. ,

AB sump I RB sump  ;

Refueling canal

__ BWST

_ _ SF pool RCS

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SW surge tank t t DC surge tank ,

L'H pit sumps 3.8 Determine if any recent e Evaluate all of the following activities may have caused causes:

the leak.

Valve stroking System venting or draining Changes in system alignment 3.9 Perform an inspection of e Notify PPO to PERFORh Enclosure 1.

possible leak sources in Potential Refueling Canal Leak RB and AB. Sources.

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. 3.0 FOLLOW UP ACTIONS (CONT *0)

ACTIONS DETAILS O

CAUTION Fuel transfer tube valves cannot be fully closed when fuel transfer carriage cables are connected. Damage to fuel transfer tube valves and carriage cables may result from over tightening.

3.10 E fuel transfer canal e SFV-119 " Fuel Transfer Tube Iso" level is lowering. (162 ft AB west end of SF pool)

THEN notify PPO to close fuel transfer tube valves e SFV-120 " Fuel Transfer Tube Iso" as far as possible. (162 ft AB west end of SF pool) 3.11 E RCS.

QB DHR is sus)ected of being the leac source.

THEN GO TO AP-520. Loss of RCS Coolant or Pressure, beginning with Step 3.1 4 3.12 Jf leak is NOT in the RB.

THEN GO TO Step 3.21 in this procedure.

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3.0 FOLLOW UP ACTIONS (CONT'D) l ACTIONS DETAILS STATUS The leak has been determined to be in the RB.

3.13 Evacuate nonessential 1 Depress "RB EVACUATION" push personnel from the RB if button.

required.

2 Notify plant personnel over PA.

3 Repeat PA announcement.

3.14 E at any time a DHP is cavitating.

THEN stop the DHP, and GO TO AP-404 Loss of Decay Heat Removal, beginning with Step 3.1 3.15 E refueling canal level e Use any of the following sources: I is. lowering.

THEN consider-initiating BWST makeup to refueling canal.

RCBTs SF Pools BASTS l

l AP-1080 REV 07 (MC) PAGE 11 of 25 RCLL i

Applicable carry-over steps:

3.14 jf a DHP is cavitating. THEN stop the DHP and GO TO AP-404.

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3.0 FOLLOW UP ACTIONS (CONT *D) e ACTIONS DETAILS 3.16 Place RB sump pumps in

" PULL TO LOCK". WDP-2A WDP-2B i

3.17 IF RB equipment hatch is 1 Notify SPD to ensure purge heaters closed, are de-energized THEN stop the RB purge. (Unit 480V SWGR Room):

480V HEATING AUX BUS 3-3A "AHHE-16A. A RB Purge Heating Coil" 480V HEATING AUX BUS 3-4A "AHHE-16B. B RB Purge Heating Coil" 2 Ensure all main purge valves are

, closed:

( AHV-1C AHV-1B ,

AHV-1D AHV-1A 3 Ensure both RB purge supply fans are off:

AHF-6A AHF-6B 4 Ensure both RB purge exhaust fans are off:

AHF-7A AHF-7B

( 5 Notify Health Physics Supervisor that purge ventilation flow has g-) been lost.

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Applicable carry-over steps:

3.14 jf a DHP is cavitating. THEN stop the DHP and GO TO AP-404.

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3.0 FOLLOW UP ACTIONS (CONT *D) l ACTIONS DETAILS

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! 3.18 Ensure containment e E the equipment hatch is closure, removed.

THEN notify the NSM to install equipment hatch, e Notify PPO to ensure at least one personnel air lock door or a

temporary door is closed.

e Notify the NSM to initiate containment closure compensatory measures.

3.19 E refueling canal level e OP-404. Decay Heat Removal System is NOT lowering. Section 4.17. Filling The Fuel THEN GO T0 appropriate Transfer Canal: "A" DH System In '

procedure to restore Service. "B" DH System Recirc Of refueling canal level. BWST e OP-404. Decay Heat Removal System

Section 4.18. Filling The Fuel
l. Transfer Canal: "B" DH System In l

Service. "A" DH System Recirc Of BWST e OP-406. Spent Fuel Cooling System.

applicable section(s). i L

t 3.20 E refueling canal level -l

continues to lower.

l IHEN GO T0 step 3.28 in this procedure.

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.. . 3.0 FOLLOW UP ACTIONS (CONT'D)

ACTIONS DETAILS I 1 .\

l STATUS j

The leak has been determined to be in the AB.

i 3.21 Evacuate non essential 1 Depress "AB EVACUATION" push personnel from the AB if button.

required.

2 Notify plant personnel over PA. .

3 Repeat PA announcement. i i

3.22 E at any time DHP is

cavitating.

THEN stop DHP.

and GO TO AP-404. Loss of Decay Heat Removal, i beginning with Step 3.1 1

3.23 E SF pool liner or e GO T0 applicable section(s) of transfer tube has been OP-406. Spent Fuel Cooling Sys!2m. l determined to be the source'of leak.

THEN restore SF pool level l

3.24 E SF cooling system ng is the source of SFP-1A

l. THEN stop all SF pumps. SFP-1B L

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Applicable carry over steps:

3.22 JF a DHP is cavitating. THEN stop the DHP and GO TO AP-404.

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3.0 FOLLOW UP ACTIONS (CONT'0)

ACTIONS DETAILS 3.25 Notify PPO to ensure SF e Ensure closed SFV-82 "SF Cask supply to Cask Area is Area Iso" (143 ft AB) isolated and vented.

  • Ensure open SFV-90 "SF Cask Area Loop Seal Vent" (143 ft AB)

CAUTION SF pool may reach 190 F in s 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and may require 70 gpm makeup to maintain level.

NOTE Leakage from SF suction and discharge piping will stop at approximately 4 feet below normal level.

, 3.26 If SF cooling system e IE adequate volume exists in the

\ piping leak can not be BWST.

isolated. THEN GO TO OP-406. Spent Fuel AND SF pool level is System Cooling. Section 4.10.

lowering. Lowering SF Pool Level by THEN consider pumping the Diverting Purification Flow to volume above affected BWST.

piping to the BWST.

3.27 IE SF cooling system leak e GO T0 applicable section(s) of 1s isolated. OP-406. Spent Fuel Cooling System to AND a SF cooling path is restore:

av: e.l e .

Ibih i >tablish SF SF level to normal cooling and SF pool level.

SF cooling D

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Applicable carry-over steps:

3.22 lE a DHP is cavitating. THEN stop the DHP and GO TO AP-404.

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3'.0 FOLLOW UP ACTIONS (CONT *D)-

ACTIONS DETAILS

.O 3.28 IE leak can NOT be isolated.

OB level' continues to lower.

THEN contact TSC for further guidance and EXIT this procedure.

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+ 5.0 ENCLOSURE 1 POTENTIAL REFUELING CANAL LEAK SOURCES l

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I ACTIONS DETAILS ,

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1.1 Perform an inspection of e Visually inspect NI pull boxes i potential refueling canal (119 ft RB just inside personnel  !

leak sources in the RB. hatch).  ;

i e Visually inspect Fuel Transfer l Canal telltale drain line (124 i ft RB just outside A CFT Room). . l e Visually inspect Fuel Transfer i Canal telltale drain line (95 ft  !

RB by RB sump). j 1

e Visually inspect seal plate'for  !

rising air bubbles. j e Ensure Fuel Transfer Canal deep end drains are closed:

i SFV-83 " Fuel Transfer Canal Drain" (95 ft RB by RB sump)

SFV-84 " Fuel Transfer Canal Drain" L (95 ft RB by RB sump) e Vis ally inspect RCS and DHR sysi.em piping for leakage.

e Review local cold leg nozzle dam control panel if installed.

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I 5.0' ENCLOSURE 1 P0TENTIAL REFUELING CANAL LEAK SOURCES (CONT *D)  !

ACTIONS O DETAILS '

1.2 Perform an inspection of e Visually inspect SF cooling

! potential refueling canal system for leakage.

leak sources in AB.

e Visually inspect DHR system piping for leakage.

e Visually inspect SF pool liner' telltale drains (95 ft AB MVP cubicles).

e Visually inspect Transfer Tube telltale drains (119 ft AB by SFP air handlers).

e IE any telltale drains are flowing.

IHEN note each valve number.

and close all telltale drain valves.

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