ML20040A975
| ML20040A975 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/12/1980 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20040A967 | List: |
| References | |
| NUDOCS 8201230024 | |
| Download: ML20040A975 (14) | |
Text
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EXHIBIT 11 PACIFIC GAS AND ELECTRIC COMPANY DEPAP.TMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2
" ".,, _, !m.,7" EMERGENCY OPERATING PROCEDURE.NO. OP-22 2-'.
" ~ ' ' ~
TITLE:
EMERGENCY SHUTDOWN SCOPE This procedure covers placing the reactor in the safe shutdown condition i
following an event (such as fire) that renders the normal emergency shutdown systems and equipment inoperable.
Since the exact circu= stances of the inci-dent cannot be predicted ahead of time, this procedure is rather general and suggests different ways and means of accomplishing the goal.
It is not con-sidered that a LOCA or other major accident occurs simultaneously.
SYMPTOMS The symptoms for an accident of this type could be practically unlimited.
They will depend on the initiating event and will include such things as loss of indication on operating or standby equipment, annunciation of i
spurious conditions and possible overcurrent or other relay action.
AUTOMATIC ACTIONS The automatic actions which take place will depend on the source and magni-tude of the initiating event.
They could,. howe,ver, include such things as:
1.
Turbine-Generator trip (V
2.
,O g
i 3.
Diesel cenerator start i
1
-A.
4.
Transfer to startup power
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5.
Actuation of sprinkler or deluge system Mj'M,gs=i:e 6
g 6.
Actuation of Cardox system g
y 7.
Control room ventilation transfer OBJECTIVES 1.
To assure the reactor is shutdown (tripped) and is borated to -the cold Xe free condition.
2.
To establish a heet sink for the reactor.
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PAGE 1
0F _l]__
REVISION O
DATE an2/80 APPROVAL
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8201230024 820114
'T SUPERINTENDENT DATE PDR ADOCK 05000275 G
DIABLO CANYON POWER PLANT UNIT N05.1 AND 2 EMERGENCY OPERATING PROCEDURE NO. OP-22 TITLE:
EMERGENCY SHUTDOWN I
s DNEDIATE OPERATOR ACTIONS ACTIONS COMMENN 1.
Regardless of whether the reactor has tripped, take the following actions:
a.
Detemi.ie the cause or source of the incident (fire, water, high enerqy line break, etc.).
b.
Take all possible actions to limit the consequences of the incident.
This may include such things as deenergizing equipment, load centers or buses, securing equipment or lines and draining tanks.
c.
Detemine the extent of the damage and the consequences of this damage in terms of equipment operability.
d.
Make an assessment of the. potential damage and consequences if the situation cannot be readily con-trolled.
e.
If the possibility exists that re-dundant safeguarcs or shutdown systems may be affected or if they are affected, trip the reactor.
SUBSEOUENT OPERATOR ACTIONS Once it has been determined that the redundant normal shutdown and cooldown systems are inoperable, the following general actions should be taken.
First and most important is to get the reactor shutdown.
Cooldown~should then be initiated by any means possible.
It is essential to get water igto the steam generators for a heat sink and to insure natural circulation or the primary coolant.
ACTIONS COMMENTS 1.
Declare this event an alert and carry
,c.,
i l
out.the instructions given in
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Appendix 2 of the Emergency Proce-dures (Notification of Offsite Per-i l
sonnel In The Event of An Emergency).
PAGE_.2 0F ll REVISION O
DATE 4/12/80
LTC$EF@WMFlMMOORhnBWG65.11 MD 2
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EMERGEllCY OPERATIfiG PROCEDURE 110. OP-22 TITLE:
gr.1ERGEliCY_SHUTDOWri ACTIOils COMMErlTS 2.
Shutdown the reactor.
a.
Trip the reactor in the normal manner from the control room.
b.
Check all rods inserted and reactor power decreasing rapidly.
c.
Shutdown both control rod drive MG sets.
d.
Check both reactor trip breakers and both bypass breakers open and rack them out.
3.
Borate the reactor to the cold xenon free shutdown condition.
It is highly desirable to get the reactor borated as soon as possible since conditions may deteriorate to where the heat tracing systmn is ineffective and boration bec mes difficult to accomplish.
Any of the following boration paths may be uti-lized as appropriate or necessary:
a.
liormal baration thrcugh the blender to the suction of the charging pumps.
b.
Emergency boration - refer to Emergency Operating Procedure OP-6 for details and various cl:ernate flow paths.
c.
Boration through the normal charg-c.
If power is not available, ing path with the charging pump these valves can be operated taking suction from the RWST.
manually.
1)
Open the charging pump suction i
valves from the RWST (8805A'& B).
l 2)
Close the nonnal suction valves from the VCT (LCV-ll23 & C).
,e i'
3)
If suction from the RWST cannot be achieved by gravity, it is possible to cbtain suction from the RWST by running an RHR pump l
and opening valve 8804A.
P. AGE 3
0F 11 REVISI0t1 0
DATE 4/12/80
l DIABLO Cnin0N POWER PLANT UNIT tiOS.1 AND 2 EMERGEtiC7 OPERATItiG PROCECURE NO. 22 TITLE:
EMERGE!1CY SHUTDOWN
_x ACTIONS COMMENTS d.
Boration from the BIT with the charging pump taking suction from the RWST.
1)
Proceed as in Step 3 above.
2)
Open the BI.T inlet valves (8803A & B).
3)
Open the BIT outlet valves (8801A & B).
e.
Boration with the charging pump e.
Uscd as last resort due to RCP seal taking suction directly from a consideration.
boric acid storage tank.
1)
This assumes that no boric transfer pump is available.
2)
Open the emergency borate valve (8104).
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3)
Check open all valves in the flow path frem the boric acid tanks to the emergency borate valve.
4)
Close the VCT oui.iet valves (LCV-112B&C).
NOTE:
This is necessary in ord3r to reduce the suction header pressure to a point where gravity flow from the boric acid storage tanks is possible.
5)
Reduce charging pump flow to match the maximum suction flow anc not cavitate the pumps.
All of the above boration methods recuire at least one charging Oumd to be in s ervic e.
If all charging pumps are inoperable, maintain the reactor in the hot condition.
Do not attempt to reduce reactor pressure to the point where the safety injection pumps are usable at this time.
8
,c.i FAGE 4 0F 11 REVISION O
DATE 4/12/80 m
easmagerigkvMgFl;42L3f_DLMT UNIT NOS.
1 AND 2 EMERGENCY OPERAT!NG PROCEDURE NO. OP-22 TITLE:
EMERGENCY SHUTDOWN COMMENTS 4.
Establish a Heat Removal Mechanism from the Steam Generators If condenser steam dump is a.
available it should be used.
Handjacks on 40% steam dumps a.
can be used if normal control is unavailable.
b.
With the reactor and turbine tripped the 35% atmospheric dump valves are unavailable.
The 10% atmospheric dump valves c.
should be available and should be used as the heat removal mechanism.
d.
If instrument air is lost, the 10%
valves will control off back up N2, If back up N2 is lost, control the valve operation using back up air via toggle switch on VB-3.
Cooldown capability is severely e.
limited with only the safety valves available for heat removal and if 10% steam dumps can't be opened using Step 4 then the 10% steam dump valves should be manually opened using, the handjack to provide a controlled heat removal mechanism.
5.
Establish a Feedwater Supply to the Steam Generators, If the motor driven auxiliary feedwater a.
pumps are operabia, use them to feed the generators.
If necessary, use the handjack to throttle the feedwater flow control valves.
Valves are spring 3
open, EH oil pressure to close.
i b.
If the motor driven pumps are inoperable,
, use the turbine driven pump.
Its flow control valves can be operated manually, if necessary.
,r.i t
l FAGE 5 0F 11 REVISION O
DATE j/l2/80 i
m
EMERGEliCY OPERATING PROCEDURE ?!0.
OP-22 5
TITLE:
EMERGEliCY SHUTDOWN COMMEi4TS 1.
If the speed control circuit for the turbine is inoperable, the speed can be controlled manually at t.he turbine governor.
2.
The motor sperated steam supply valves to the turbine can be opened manually if necessary.
3.
If the turbine speed control 3.
It may be necessary to disconnect l
system fails completely, the the governor valve linkage prior governor valve can be blocked to blocking the valve open.
open using the exposed linkage and speed can be manually controlled by manipulatino the thrcttle stop valve manually.
4.
The turbine is designed to operate j
with steam supply pressure as low as 100 psig, but with reduced power output. The steam generator level should be built up to SC-60% while steam pres'sure is high so tnat the reduced flow -
rates at lower steam pressure can be tolerated during the cool-down.
5.
The turbine driven pump can be utilized to cool the plant all the way down to the point where the RHR system can be placed in s ervi ce.
6.
With AF4 pumps available cooldown can ce accomplished nrovided there is suffient water availaL',e to the AP4 pumps, If the condensate tank is lost, the a.
fire tank can be lined up for suction.
The suction valves can be manually i
opened if required.
b.
The raw water reservcir can be lined up to the AR4 pumps via the make up water header.
O 2/80 PAGE 6 0F 11 REVISION DATE
(
r EMERGENCY OPERATING PROCEDURE NO. OP-22 TITLE: EMERGENCY SHUTDOWN COMMENTS c.
If the reservoir line is lost, line up the emergency pump at the reservoir and use the emergency hose to the condensate tank or M. U. Water header.
7.
If condenser vacuum has been maintained, 7.
It may.be necessary to reset the it is possible to use the main feedwater feedwater isolation signal.
pumps in conjunction with the condensate /
booster pumps to supply the steam generators.
a.
A condensate / booster pump set is ecuired to supply suction to the nain feed pump.
b.
Normal AC power must be available to the turbine high pressure lube oil pumps in order to latch the turbine and open the valves.
c.
Either the hand speed changer or the governor valve positioner may be used to control turbine speed.
d.
With the main unit tripped, only the high pressure steam supply
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will be available.
The LP governor valves will be wide open before the HP governor valve starts to open.
e.
in the event of an extreme emergency with the condenser unavailable, block the low vacuum trip, break the casing rupture disk and attempt to run the turbine with exhaust to atmosphere.
f.
Once the steam generator pressure J
has been reduced to les: than 8
600 psig, the condensate / booster pump sets can be used to feed water directly by pumping through the idle feed pumps.
Using the feed water regulating valves for control.
F-l i
l PAGE 7 0F 11 REVISION O
DATE 4/12/,80
EMERGENCY OPERATIflG PROCEDURE NO. OP-22 TITLE: EMERGENCY SHUTDOWN CCMMENTS 8.
Primary System Cooldown Considerations It is es:ential to maintain circulation
.of the reactor coolant to remove decay.
heat.
If a reactor coolant pump is operable, it should be kept running.
However, if all the coolant pumps are lost it is essential'to maintain natural circulation.
Verify natural circulation per Emergency Procedure OP-23.
NOTE:
Natural circulation is caused by providing heat addition in one part of the system (decay heat frem the core) and heat removal in another part of the' system (steam removal from the generators).
Natural circulation is better just after a trip when the decay heat is greater and it can be improved by increasing the heat removal rate.
Natural circulation can be prevented by format on of a steam bubble in the i
tubes or by loss of heat removal capabili ty.
Primary system pressure and temperature should be monitored to insure that saturation conditions are not reached.
Also circulation may stop if the steam generator secondary side temperature exceeds-the primary side temperature.
In part 5 above the varicus baration a.
methods were discussed.
All of these methods require that a charging pump be operable.
If all three chargiiig pumps are inoperable, the goal beccmes to get the primary system pressure reduced to where a safety injection pump can be used for boration (less than 1500 psig).
j b.
Check all pressurizer heaters deenergi;ed.
c.
Without any reactor coolant pumps O '!
or charging pumps there is no pressurizer spray available so i
pressure must be reduced by other means.
l l
PAGE 8 0F 11 REVISION 0
DATE 4/12/80 e
l mp29f9MmnM90@In;WAW W/Annsg. ObMrs l
. EMERGENCY OPEPATING PROCEDURE NO. OP-22 TITLE: EMERGENCY SHUTDOWN C0tNENTS d.
Pressure can be reduced due to d.
If all control rods inserted (or l
shrinkage c.aused by ' cooling the with one stuck out) the amount o crimary system.
Reducing the reactivity added by this tempera.
primary system temperature to decrease will not be sufficient less than 510*F will produce a niake tne reactor critical, pressure of less than 1500 psig and pennit boration by the safety injection pumps taking suction i
fro'a the RWST.
i e.
If it appears that the
'e.
This method is used because the charging pumps may become PORV's have no throttle capabili(
inoperable, it may be necessary to blow down the primary system in order to get the pressure l
down to 1500 psig as quickly as possible.
1)
Select one power relief valve for use and close its motor operated stop valve.
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- 2) Open the power relief valve.
3)
Initiate blowdown slowly by opening the stop valve until l
flow is detected then place l
the control switch in the 1
STOP posi, tion.
- 4) Once flow has stabilized and if the PRT pressure and temperature are in control the stop valve can be opened further in small increments.
5)
When pressure has been reduced 5)
Verify closure by position india to less than 1500 psig, close lights and discharge pipe tempea the reTief valve and the el ements.
power operated relief valve.
i f.
Start a safety injection pump with suction frem the RWST.
Eorate to the cold, xenon free condition.
g.
If boration is slow, continue. to '
cool down until the accumulator pressure is reached.
Allow one accumulator at a time to discharge into the system to assist in baration.
PAGE 9
0F.11 REVISION 0
DATE 4/12/80
EMERGEf;CY OPERATItfG PROCEDURE i;0. OP-22 TITLE: EMERGEllCY SHUTD0Wii pMMEliTS 9.
RHR System Operation.
a.
When primary system pressure and a.
The following steps also apply if
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temperature have been reduced to the initiating event occurred with 390 psig and 350*F place the RHR the RHR system in service.
system in service to remove heat from the primary system.
b.
If the RHR system is not available or if its required support systems (component cooling and auxiliary salt water) are not available, proceed as follows.
1)
Continue to use the steam dump system to reduce RCS temperature down to 212*F.
2)
Continue to add feedwater to the steam generators.
3)
In order to col down below 212*F, some kind of liquid release must occur since boiling will not occur.'
4)
Open the blowdown valves on each steam generator all the way.
The bicwdown stream will provide a liquid heat' removal path.
5)
If the blowdown flow is not large enough to provide adequate heat removal, increase the feedwater flow and start filling the steam generators, 6)
The addition of this cold water 3
has a heat removal effect, i
7)
Continue filling until water enters the main steam line.
Line up all drains to bypass the traps and go directly to
,r.:
the condenser.
This will
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provide an additional flow path.
PAGE 10 0F 11 REVISION 0
DATE 4/12/80
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EMERGENCY OPERATING PROCEDURE NO. OP-22 TITLE:
EMERGETT.Y S.JTDOWil APPENDIX 7 EMERGENCY PROCEDURE WOTIFICATION INSTRUCTIONS 1.
When this emergency procedure has beeti activated and upon direction from the Shift Foreman proceed as follows:
a.
Notify the Plant Superintendent and Supervisor of Operations or their designated alternates.
b.
Designate this event an Alert.
Notify those agencies given in General Appendix 2 of the Emergency Procedures (Notification of outside ager.:ies in the event of an emergency.
c.
Within one hour notify the NRC Operations Center using the red phone in the control room.
Gather sufficient information from all sources prior to calling so that the phone call is meaningful.
Notify the NRC that your call is pursuant to 10 CFR Part 50.72, (Notification of Significant Events).
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l FAGE 11 0F 11 REVISION 0
DATE 4/12/80
t "*73 m
._.a co 4
e UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD _
)
)
In the Matter of
)
PACIFIC GAC AND ELECTRIC COMPANY
)
Docket Nos. 50-275 O.L.
)
50-323 0.L.
)
(Diablo Canyon Nuclear Power Plant, Unit Nos. 1 and 2)
)
)
CERTIFICATE OF SERVICE BROWN I hereby certify that copies of " GOVERNOR EDMUND G.
RESPONSE TO S'lMMARY DISPOSITION MOTIONS FILZD BY STAFF AND PACIFIC GAS AND ELECTRIC COMPANY" have JR.
to the following on January 14, 1982 by U.S. Mail, first class, except as otherwise noted.
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$1 N
IA Mr. Thomas Moore, Chairman Atomic Safety and Licensing Appeal Board q) 51982 > =-
U.S. Nuclear Regulatory Commission
-d dMi 2
W:shington, D.C. '
0%ni M.SlC!E'4 20555 Dd"d L"~'
Dr.
W. Reed Johnson
'S Atomic Safety and Licensing Appeal Board q)
_a U.S. Nuclear Regulatory Commission g3 Washington, D.C.
205:5 Dr. John H.
Buck Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Chairman Atomic Safety and Licensing Appcal Panel U.S. Nuclear Reculatory Commission
, Washington, D.C.
20555 John F. Wc! f, Esq., Chairman (*)
Atomic Safety and Licensing Board Nuclear Regulatory Commission U.S.
Washington, D.C.
20555 l
e -.
Mr. Glenn O. Bright
(*)
Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Dr. Jerry R. Kline (*)
Atomic Safety and Licensing Board Panel
-U.S. Nuclear Regulatory Commission Washington, D.C.
20555 William J. Olmstead, Esq.
Edward G. Ketchen, Esq.
Office of Executive Legal Director BETH 042 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Secretary U.S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTENTION:
Docketing and Servf.ce Section Mrs. Elizabeth Apfelberg 1415 Cozadera San Luis Obispo, California 93401 Janice E.
Kerr, Esq.
J 4
Public Utilities Commission l
5246 State Building 350,McAllister Street San Francisco, California 94102 Mrs. Raye Fleming 19 20 Mattie Road -
Shell Beach, California 93449 Mr. Frederick Eissler Scenic Shoreline Preservation Conference, Inc.
4623 More Mesa Drive Santa Barbara, California 93105 Mr. Gordon Silver Mrs. Sandra A.
Silver 1760 Alisal Street San Luis Obispo, California 93401 Joel R.
Reynolds, Esq.
John R.
Phillips, Esq.
Center for Law in the Public Interest 10951 West Pico Boulevard Third Floor Los Angeles, California 90064 Bruce Norton, Esq.
Norton, Burke, Berry & Junck 3216 North Third Street, Suite 300 Phoenix, Arizona 85012
Philip A.
- Crane, Jr.,
Esq.
F.
Ronald Laupheimer, Esq.
Richard F.
Locke, Esq.
Pacific Gas and Eldctric Company P.O.
Box 7442 San Francisco, California 94106 David S.
Fleischaker, Esq.
P.O.
Box 1178 j
Oklahoma City, Oklahoma 73101 Arthur C. Gehr, Esq.
Snell & Wilmer 3100 Valley Bank Center l
Phoenix, Ari zona 85073 Mr. Richard B. Hubbard i
MHB Technical Associates 1723 Hamilton Avenucy Suite K San Jose, California 95125 Mr. Carl Neiberger Telecram Tribune
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l P.O.
Box 112 l
San Luis Obispo, California 93402 1
Byron i. Georgiou, Esq.
Legal Affairs Secretary Governor's Office State Capitol Sacramento, California 95814 g7 uj' c /.
' O.wt1sar
'(JA &!?m h %
Dawrence Coe Lanpher/
i HILL, CHRISTOPHER AND PHILLIPS, P.C.
l 1900 M Street, N.W.
Washington, D.C.
20036 January 14, 1982
(*) By messenger on January 14, 1982 I
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