ML20054J971

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Offnormal Event Procedure 05-1-02-II-1, Shutdown from Remote Shutdown Panel,Safety-Related, Revision 11
ML20054J971
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 06/14/1982
From:
MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20054J949 List:
References
05-1-02-II-1, 5-1-2-II-1, NUDOCS 8206300251
Download: ML20054J971 (11)


Text

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PLANT OPERATIONS MANUAL i

Volume 05 05-1-02-11-1 Section 02 Revision:

11 Date: 6-14-82 OFF-NORMAL EVENT PROCEDURE SHUTDOWN FROM THE REMOTE SHUTDOWN PANEL SAFETY RELATED Prepared:_. _.;-- k l-(

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Reviewed:

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Nuclear Plant Quality Superinterfdent n'ical ' Review Approved:

Ohw Opergtons perinten n Concurrence:

((p p-As sis' t Plant Man e

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List of Ef fective Pages:

Page:

1-10 List of TCN's Incorporated:

Revision TCN No.

10 None 11 None I

8206300251 820625 l

PDR ADOCK 05000416 l

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' GRAND GULF NUCLEAR STATION'

'0FF NORMAL EVENT PROCEDURE

Title:

Shutdown From The Remote ;No.:

05-1-02-11-1

Revision:

11 lPage:

1 l

Shutdown Panel l

l 1.0 PURPOSE / DISCUSSION 1.1 The purpose of this procedure is to provide instructions for shutting down the plant from outside the control room and bringing the plant to a cold shutdown condition from the remote shutdown panel.

1.2 This procedure will interface with the Emergency Plan.

1.3 The following assumptions and initial conditions are considered to be prerequisites for the implementation of this procedure:

1.3.1 An unsafe condition exists in the control room.

This condition may be caused by fire, chlorine or other toxic gas, high airborne activity, or other emergency.

The Shift Supervisor / Shift Superintendent will have evaluated the possibility of remaining in the control room with breathing apparatus and will order evacuation only if necessary.

~s 1.3.2 If time permits, the RCIC System will be manually initiated prior to evacuation.

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773t3 The emergency AC buses are energized"from' their normal power-No loss of off-site power is considered after the start' sources.

of the emergency that precipitates this procedure.

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~T' 1.3.4 DC power is supplied from at least one plant DC power source to each system or component required for remote shutdown.

1.3.5 All support systems are in normal lineups, operating normally, and continue to operate normally throughout this evolution.

1.3.6 Nothing abnormal occurs which would cause reactor plant deterioration such that immediate operator action would be required upon reaching the remote shutdown panel.

i Placing the Mode Switch in Shutdown will immediately put the plant.

in a hot shutdown condition.

While the MSIV's are o i

reactor feed pumps (with the aid of the RCIC system) pen, the will continue l

to feed water to the reactor vessel thereby preventing a Low Level j

2 (-41.6"), containment and auxiliary building isolation, and subsequent loss of vital plant systems.

The main condenser will remain in service while the main steam bypass valves control r

reactor pressure and remove sensible and decay heat.

In the event the MSIV's close and/or the low level trip point is reached, HPCS, RCIC, and the safety-relief valves will all function to I

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' GRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

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Title:

Shutdown From Tha Remote No.:

05-1-02-11-1 Ravision:

11 Page:

2 Shutdown Panel l

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$i control reactor level and pressure.

The operator at the remote shutdown panel will take control of the RCIC system and, as necessary, the safety-relief valves to control level, pressure, and.cooldown rate ~until the RHR system can be placed in the j

shutdown cooling mode.

The operator will also startup the Standby

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Service Water system and the RHR system in the suppression pool i

cooling mode.

One control rod drive pump will be used to maintain rod drive cooling and augment the RCIC system, and will be available to maintain level after RCIC has been secured.

4 f'

This procedure contains abbreviated portions from the appropriate S0l's and considers the Off-Normal condition of operation with a minimum of controls and instrumentation.

2.0 SYMPTOMS 2.1 Any unsafe situation such as fire, toxic gas, high airborne activity or other condition which, in the opinion of the Shift Supervisor / Shift ?

Superintendent, requires. evacuation of the control room.

3.0 AUTOMATIC ACTIONS 7

t t

NOTE'

1. _

These automatic actions will be a result of the-Immediate Operator Actions 4T taken in 4.0.

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3.1 With the Mode Switch in SHUTDOWN,.the MSIV's will not close on low main steam line pressure. -

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p-m 3.2 If the MSIV's do not close, the main feed pumps will continue to feed the

' vessel, recovering the inventory lost during the shrink following the scram, and will continue to feed the vessel until they and the main J

turbine trip at +54.9" or until reactor pressure. decreases below that j

required to drive the feed pumps.

3.3 i ~ ~ ~

Reactor pressure will be controlled by the main steam bypass valves ag long as it remains above the bypass valve setpoint.

l 3.4 If vessel level reaches -41.6", HPCS and RCIC start and inject water into the vessel.

The HPCS injection valve and RCIC steam supply and injection l

valves will close at 53.5".

n

GBAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

Title:

Shutdown From The Remote No.:

05-1-02-11-1 Revision:

11 jPege:

3 l

Sh'tdown Panal I

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3.5 If the MSIV's close, the safety-relief valves will function as necessary to maintain reactor pressure, the main steam bypass valve pressure control and reactor feed pump vessel feed functions will be lost, and the main condenser will no longer be available as a consequential heat sink.

4.0 IMMEDIATE OPERATOR ACTIONS 4.1 The Shift Supervisor / Shift Superintendent makes the decision to evacuate the control room and designates which operators are to man the remote shutdown panels.

4.2 The Control Room Operator will perform the following before leaving the control room:

4.2.1 Place the Reactor Mode Switch in the SHUTDOWN position.

4.2.2 Verify all control rods are fully inserted.

/

4.2.3 Manually initiate the RCIC system if time permits.

4.3 If necessary, the plant _may_.le scrammed from ou.tside.the. control. rg e as

' Fo'llows:

NOTE This will also initiate a Group I Isolation as well as the Scram.-

4.3.1 At panel IC71-P001 open these breakers:

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CB-4A Neutron Monitoring CB-6A Neutron Monitoring 4.3.2 At panel IC71-P002 open these breakers:

CB-4B Neutron Monitoring CB-6B.

Neutron Monitoring

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5.0 SUBSEQUENT ACTIONS

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5.1 Proceed to implement the Emergency Plan as directed by the Shift Supervisor / Shift Superintendent.

NOTE All controls and indications are located on the remote shutdown panels 1H22-P150 and 1H22-P151 unless otherwise indicated.

5.2 The RCIC system may have shutdown on high reactor level.

The system will (steam supply and injection valve will open) if level 2 is restart reached.

However, the system should be manually re-started after the high level has cleared by re-opening the RCIC STM SPLY TO RCIC TURB E51-F045 and verifying the RCIC INJ SHUT 0FF VLV E51-F013 re-opens.

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-m CftAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

Title:

Shutdown From The Remote No.:

05-1-02-11-1 Revision:

11 Page: 4 Shutdown Panel 5.3 If at any time the RCIC TURBINE trips, reset the trip as follows:

4

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5.3.1 Place the RCIC TURE TRIP /THROT VLV E51-C002 XFER SWITCH in the

{

EMER position.

' " 5 '. 3. 2 Close RCIC TURB TRIP /THROT VLV E51-C002 I

5.3.3 _ Place the. RCIC FLO CONT IN MANUAL and run the controller to ~ '

minimum.

5.3.4 Reopen RCIC TURB TRIP /THROT VLV E51-C002.

Check RCIC Turbine status lights on panel 1H22-P150 to see that turbine is reset.

5.4 Control reactor level by controlling RCIC speed with RCIC FLO CONT.

Observe reactor level on the shutdown panel while attempting to maintain i

vessel level near the normal range of 33" to 40".

5.5 Verify locally that the main turbine / generator has tripped and the t

f bypass valves are operating as necessary to control reactor pressure.

+

5.6 Ensure at least one CRD_ pump _is running to cool, driv.e mechanisms ang.to, i

~~ ~~ assist in level control.

5.7 The HPCS pump may be running, recirculating on minimum flow from the CST to the suppression pool.

The pump will inject water to the vessel if level falls below -41.6".

The.HPCS injection valve will close, returning the pump to recirculation flow, at +53.5".

Observe CST level and suppression pool level.

The.HPCS and RCIC suctions will automatically shift from the CST to the suppression pool at a CST level of l'2" or a suppression pool level of 18'7".

Minimize water transfer from the CST to the suppression pool through the RCIC and HPCS minimum flow lines.

5.8 Commence suppression pool cooling as follows:

5.8.1 Select RHR loop A or B for suppression pool cooling mode.

(Loop A j

is preferable since Loop A allows for discharge to radwaste).

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5.8.2 Verify SSW system A(B) in operation, supplying the RHR heat

~exchangers to be.used for supp. pool cooling.

If SSW is not supplying the RHR heat exchangers, start up SSW as follows:

l Open SSW Loop A(B) RTN TO CLC TWR A(B) (P41-F005) A(B) a.

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b.

Start SSW PMP A(B) P41-C001 A(B) c.

Open SSW PMP A(B) DISCH VLV P41-F001 A(B)

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GjtAND GULF NUCLEAR STATION

'0FF-NORMAL EVENT PROCEDURE

'l

Title:

Shutdown From The Remote, No.:

05-1-02-11-1 Revision:

11 lPage:

5 l

l Shutdown Panel l

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d.

Start (Loop A) SSW CLG TWR FAN A P41-P003A, and SSW CLC TWR 1

FAN B P41-C003B, or (Loop B) SSW CLC TWR FAN C P41-C.003C, and SSW CLG TWR FAN D P41-C003D.

Observe SSW SYS A(B) FLOW indication Approx.

7900 GPM.

e.

5.8.3 Place the following RHR transfer switches in the EMER position: -

t-a.

.SHUTDN CLG SUCT VLV E12-F006B XFER SWITCH b.

SUPP POOL SUCT VLV E12-F004B XFER SWITCH t

c.

RHR HX INL VLV E12-F047B XFER SWITCH d.

RHR HX INL VLV E12-F047A XFER SWITCH e.

SUPP POOL SUCTION VLV E12-F004A XFER SWITCH

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f.

SHUTDN CLG SUCT VLV E12-F006A XFER SWITCH 4

5.8.4 Open or check open,.thg_following valves,

RHR PUMP A(B) SUCT FM SUPP POOL 812-F004A(B) a.

b.

RHR HX A(B) INL VLV E12-F047A(B) e.

i c.

RHR HX A(B)'0UTL VLV E12-F003A(B)

-c 1;

-d.

RHR HX A(B) BYP VLV E12-F048A(B)-

9 5.8.5 - Start RHR PMP A(B) E12-C002A(B).

i 5.8.6 Open RHR A(B) RTN TO SUPP POOL E12-F024A(B).

Observe RHR SYS A(B)

FLO indication approx. 7450 GPM i

..5.8.7 Close RHR HX A(B) BYP VLV E12-F048 A(B)

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5. 8. 8 Adjust RHR A(B) TEST RTN TO SUPP POOL E12-F024A(B) to maintain RHR SYS A(B)'FLO at about 7450 gpm.

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_ GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

Title:

Shutdown From The Rtmote No.:

05-1-02-11-1 Rsvision:

11 Page:

6 Shutdown Psnal 5.8.9 Continue to monitor suppression pool temperature and level, and

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ADJUST RHR flow to maintain temperature less than 120*F.

5.9 Reduce reactor pressure by manually operating the safety / relief valves as follows:

5.9.1 While observing reactor pressure and level, open a safety / relief valve to depressurize slowly while maintaining vessel level above

+20".

I Close the safety / relief valve and observe reactor pressure and 5.9.2 level.

Allow time for level and pressure to stabilize, then open a different safety / relief valve as in Step 5.9.1 above.

l 5.9.3 Continue to operate safety / relief valves as per the two preceeding steps.

If core decay heat is low enough such that pressure is not rising, allow the reactor to'depressurize without operating relief valves.

Close safety / relief valves if vessel level drops to f*

+20".

5.9.4 Plot vessel cooldown_sn'the time vs temp,erature. graph acqompanying '


" ~ this procedure. Convert vessel preffure to the corresponding temperature using the saturated steam data (Table 1).

Maintain the cooldown rate not greater than 100*F/ hour.

5.9.5 Control vessel level and pressure using a combination of safety / relief valve operation ahd m'anual RCIC speed control.

5.9.6 Closely monitor suppression' pool' temperature and level during the

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depressurization operation.

5.10 Depressurize the reactor to 125 psig or less.

5.11 Verify all safety / relief valves are closed.

5.12. Raise vessel level to +45 to +50" and then shutdown the RCIC system and place it in standby as follows:

(Ref.

SOI 04-1-01-E51-1).

i 5.12.1 Reduce RCIC Flow to approx. 100 GPM.

5.12.2 close RCIC INJ SHUTOFF VLV E51-F013.

5.12.3 Close RCIC TURB TRIP /THROT VI.V E51-C002.

C,RAi[DCULFNUCLEARSTITION

'0FFtibRkLEVENTPROCEDURE I

Title:

Shutdown From The Remote No.:

05-1-02-11-1 Revision:

11 Page:

7 Shutdown Panel 5.12.4 Verify E51-F019 closed.

I 5.12.5 Stop RCIC GL SEAL COMPR E51-C002-2A.

5.12.6 Close E51-F046.

5.13 Place the RHR loop that is not in suppression pool cooling service in the shutdown cooling mode as follows:

i 5.13.1 Verify the SSW system A(B) in operation supplying RHR heat exchangers to be used for shutdown cooling.

If SSW is not i

supplying the RHR heat exchangers, start up the SSW system as per Steps 5.8.2a through 5.8.2.e of this procedure.

(Ref. SOI 04-01-1-P41-1.

5.13.2 Close or check closed the folleving valves to prevent draining reactor water to the suppresr, ion pool or to the RHR loop in suppression pool cooling mode.

RHR PMP A(B) SUCT FM SHUTDN CLG E12-F006 A(B) (for the loop in a.

suppression yoo kcooling).

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b.

RHR PUMP A(B) SUCT FM SUPP POOL 112-F004 A(B) (For the loop t'o be placed in shutdown cooling).

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W 5.13.3 For the RHR loop to be placed in shutdown cooling, open 'tHR PMP i.-

A(B) SUCT'FM SHUTDN CLC E12-F006 A(B).

j CAUTION 1

The opening of RHR SHUTDN CLG INBD SUCT VLV E12-F009 and RHR s i

SHUTDN CLG OUTBD SUCT VLV E12-F008 vill allow reactor water to fill the RHR suction piping thereby lowering vessel level.

5.13.4 Fill and vent the RHR suction line as follows:

Check RHR SHUTDN CLG INBD SUCT VLV E12-F009 closed.

N s.

b.

Open RHR SHUTDN CLG OUTBD SdCT VLV E12-F008.

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c.

Open suction line manual vent valves: E12-F001 and E12-F002 (between E12-F008 and F009) c.

Unlock and open fill line isolation valve E12-F020.

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C, RAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE 7igle:

Shutdown From The Remote No..

05-1-02-11-1 Revision:

11 Page: 8 Shutdown Penal j

d.

When suction line is full and water issues from the vent line, close E12-F001, F002 and close and lock E12-F020.

5.13.5 Open the breaker for the minimum flow valve (1E12-F064A or 1E12-F064B) for the RHR pump to be placed in shutdown cooling (Breakers 52-153151 for F064A, 52-163114 for F064B).

To circumvent the potential for draining reactor water to the suppression pool at low RRR Flows.

5.13.6 Open or check open.RHR HX A(B) BYPASS VLV E12-F048 A(B).

I' 5.13.7 Close RHR RX A(B) INL VLV E12-F047 A(B) and RHR RX A(B) OUTL VLV E12-F003A(B).

5.13.8 Open RHR SHUTDN CLG INBD SUCT VLV E12-F009.

5.13.9 Start RHR PMP A(B) and immediately throttle open RHR A(B) SHUTDN RTN TO FW E12-F053 A(B) to achieve a stable flow of 2000-4000 gpm i

as read on the RHR SYS A(B) FLO meter.

1

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1 5713r10 When RHR flow is stable place the hfft exchanger 'into service ast l

follows:

a.

Open RHR RX A(B) INL VLV E12-F047A(B) b-Open RHR HX'A(B)'0UTL VLV E12-F003A(B)

Throttle RHR RX A(B) BYP VLV E12-F048A(B) and, as c.

necessary, RHR RX A(B) OUTL VLV E12-F003A(B) to control reactor cooldown rate.

Do not allow RHR flow to drop below 1000 GPM.

5.13.11 Minimize reactor cooldown rate since actual temperature indication

{

is not available at the remote shutdown panel.

2-5.13.12 Maintain shutdown cooling and suppression pool cooling operation

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until control room accessibility is restored.

l 5.13.13 Once access to the control room is regained, enter the appropriate EP or S01 as conditions dictate.

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GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

Title:

Shutdown From The RemotejNo.:

05-1-02-11-1 l Revision:

11 [Page:

9 l

Shutdown Panel l

l l

l TABLE I Saturated Steam Temperature Table Temp (*F)

Press (psig)

Temp (*F)

Press (psig)

Temp (*F)

Press (psig) 560 1118 416 281 276 31 556 1083 412 268 272 28 552 1048 408 256 268 26 548 1013 404 244 264 23 544 980 400 232 260 20 540 948 396 221 256 18 536 916 392 211 252 16 532 885 388 200 248 14 528 855 384 190 244 12*

524 826 380 181 240 10 520 798 516

~ 770

~-376 172

,.236.

.8 372 163 232

  • 7*

512 743 368._

154 228 5

508 71G 364 146 224 3

504 691 360 138 -

220 2

500 666 356 130 216 1

496 642 352 123 212 0

492 618 348 116 488 595 344 109 484 573 340 103 480 551 336 97 476 530 332 91 472 510 328 85 468 490 3 24.....

80 464 471 320 460 452 75 i

316 70 456 434 312 65 452 416 308 60 448 399 304 56 Note:

Pressures are approxi-444 383 300 52 mate values.

Accurate 440 367 to + 2 psig.

296 48 436 351 292 45 Source:

1976 ASME STEAM 432 336 288 41 TABLES 428 321 284 37 424 307 280 34 420 294

GRM3D GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

. *. -.l

Title:

Shutdown Froa The Remote No.:

05-1-02-11-1 R2 Vision:

11 Pego:

10 l

Shutdown Penal l

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