Text

Public Version of Rev 0 to Emergency Plan Implementing Procedure EP OP-4A Re Loss of Electrical Power & Rev 0 to Procedure EP OP-4B Re Loss of All Ac Power
	ML20077B491
Person / Time
Site:	Diablo Canyon
Issue date:	04/07/1983
From:	Thornberry R; PACIFIC GAS & ELECTRIC CO.
To:	;
Shared Package
ML16340D609	List: ML20077B491;
References
	PROC-830407-01, NUDOCS 8307250156
	Download: ML20077B491 (105)
	v • d • e

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ATTACIMENT 1 Updates In This Subodttal Voltune 3A - -

Updated Table of Contents EP CP-4A Revision 0*

i EP (P-4B Revision 0* -

EP R-6 On-The-Spot Change IP R-7 On-The-Spot rhence IP M-1 On-The-Spot Change (2)

EP M-2 Oe-The-Spot Change EP M-6 On-The-Spot Change EP M-7 On-The-Spot Change EP G-3 On-The-Spot Change EP G-4 On-The-Spot Change t

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Procedures OP-4A and (P-4B replace Procechre OP-4 in its entirety.

8307250156 830719 PDR ADOCK 05000275 PDR F

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ATTAONENT 2 Iocation of Bradceted l Privacy / Proprietary Infomation '

t EP R-6 On-The-Spot m ange: Phone mmMrs on page 1 of 1 r

EP R-7 On 'Ibe-Spot Change: Phone numbers on page 1 of 1 EP M-1 On-The-Spot mane (4/18/83): Phone mmMrs on page 1 of 1 EP M-2 On-The-Spot Change: Phone mmMrs on page 1 of 1 l EP M-6 On-The-Spot Change: Phone numbers on page 1 of 1 i

EP G-3 On-The-Spot mange: Phone numbers on page 1 of 1 i

EP G-4 Orr-The-Spot Change: Phone numbers on all four pages t

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,.w.- -

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GRRENT EMEfGENCY PIAN 1Mammmo rROc-RES TABLE OF 00PTTENTS

" ,lume 3A ,

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TITLE REV OP-O Reactor Trip With Safety Injecticn 3 OP-1 Loss of Coolant Ace'ident 5 OP-2 Loss of Secondary Coolant ,

2 OP-3A Steam Gen Tube Failum 4 OP-3B Minor Steam Gen Tube Failum 1 j OP-4A Ioss of Electrical Power -

0 '

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OP-4B Ioss of All AC Power 0 OP-5 Reactor Trip Without Safety Injection 5 OP-6 Dnergency Boration 5 OP-7 Loss of Condenser Vacuum 2 OP-8 Control Roan Inaccessibility 5 OP-9 loss of Reactor Coolant Pump 3 OP-10 Ioss of Auxiliary Salt Water 2

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OP-11 Ioss of Component Cooling Water 2 OP-12 Malfunction of Auto Reactor Control 1

,O OP-12A

~ %dm Failure of a Control Bk to 2 Move in Auto OP-12B Cont Withdrawal of a Control Rod Bank 3

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OP-12C Cont Insertion of a Control Rod Bank 2 Olb12D Control Rod Pos Indication Sys Malfune 3 OP-12E Control Rod Misalignment 2 OP-12F Droppal Control Rod 2 OP-13 Malfunction of Reactor Press Control Systen 2 OP-14 Iligh Activity in Reactor Coolant 2 OP-15 loss of Feedwater 4 OP-16 Nuclear Instrumentation Malfuncticus 3 OP-17 Malfunction of RHR Systen 2 OP-18A loss of Charging O OP-18B Ioss of ikwl Letdown 0 OP-19 Malfunction of Reactor Makeup Control 2 l OP-20 Excessive Reactor Coolant Systen 2

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. TITLE -

REV l

[3 T-21 loss of A Coolant Loop RTD 2

_,.i OP-22 Bnergency Shutdown 1 OP-23 Natural Circulaticut of Reactor Coolant 2 l OP-24 Ioss of Contmimant Integrity 1 i OP-25 Tank Ruptures 1 OP-26 Excessive Feedwater Flor 1 CP Irradiated Fuel Damage .

1 OP-28 Startup of an Inactive Reactor Coolant Loop 1

- OP-29 - Excessive Load Increase 1 OP-30 Inadvertent Load Fuel Assly Inproper Pos 1 1 Systen Under Ftwquency

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OP-31

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OP-32 Rod Ejection 1 OP-33 Loss of Instrument Air- 1 OP-34 Generator Trip - Mill Ioad Rejection 1 Olb35 loss of Vital or Non-Vital Instr AC Sys , 1 OP-36 Turbine Trip 1 OF37 loss of Protection Systen Channel 1 i

OP-38 - Anticipated Transient Without Trip (A'ITT) - 3 OP-39 RCP Locked Rotor Accident 1 OP-40 Accidental Depressurization of PE Systen 1 OP-41 Hydrogen " Explosion" Inside Containment 1 OP-44 Gaseous Voids in the RCS 2 R-1 Per Injury (Rad Related) And/Or Overexp 9 R-2 Rel of Airborne Radioactive Materials 3 R-3 Re1 of Radioactive Liquids 3 R-4 High External Radiation 3 R-5 Radioactive Liquid Spill 3 R-6 Radiological Fire 5 R-7 Transnrtatim Accidents 2 M-1 Enployee Injury (Nonradiological) 9

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M-2 Nonenployee Injury or Illness (Third Party) 8 M-3 Chlorine Release 5 M-4 Earthquake 6 M-5 Tsimami Warning 5 M-6 Nonradiological Fire 7 M-7 Oil Spill ISO and Clean Up Procedure 4 M-8 Containnent Emergency Personnel Hatch 0 G-1 Emergency Classification and Dnergency Plan 3 Activation G-2 Establishment of the On-Site Emergency 3 Organi ratiort l G-3 Notification of Off-Site Organizations 2 G-4 Personnel Accountability and Assenbly 2 G-5 Evacuaticx1 of Nonessential Site Personnel 0 l

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PGsi3 Pacific Gas and Electric Company REVISION 0

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DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 2/24/83 OIABLO CANYON POWER PLANT UNIT Nots) 1 AND 2 PAGE 10F 27 EMERGENCY PROCEDURE TITLE: LOSS OF ELECTRICAL POWER APPROVED:

PLANT MANAGER M DATE SCOPE These instructions are provided to cover the possible candition of a loss of non vital and offsite AC power. In general this will occur on

. trip of a main generator coincident with loss of all startup power.

The reactor will trip cue tu the turbine generator trip if above 10%

power or will trip from loss of control rod drive M-G sets if below

- 10% power.

This procedure also addresses the added complication of an inoperable diesel genarator or loss of the swing diesel due to it being comitted to the other unit in the event of a Safety Injection in progress on the other unit.

) Loss of electrical power also results in the loss of all 4 RCP's, therefore this could be a severe ATWT (anticipated transient without trip), situation and should always be evaluated with this in mind.

SYMPTOMS

1. Turbine - generator trip

2. Reactor Trip if > P-7

3. 12 and 4KV undervoltage alarms 4 RCP trip alarms AUTOMATIC ACTIONS

1. Turbine - generator trip

2. Reactor trip is > P-7 ,

3. Steam Dump to condenser and 35% dump valves blocked.

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NUMBER EP OP 4A ,. m OfABLO CANYON POWER PLANT UNIT NO(S) i REVISICN O DATE 2/24/83 *d LOSS OF ELECTRICAL PCWER 7g t

i 4. Stcam ' generator 10*. dump valves open to maintain steam generator pressure at 1035 psig.

5. Turbine driven auxiliar/ feedwa'ert pump starti.

6. Diesel generators start, come up to rated speed and vo.itage and pick up the following Ibadt,

a. Vital 480V load centers.

. b. Centrifugal charging pumps. .

c. Component cooling water pumps.

- d. Auxiliary salt water pumps.

e. Motor driven auxiliary feedwater pumps '

f. Containmcnt fan coolers,(hi speed).

OBJECTIVES g

1. Restore vital power using emergency diesel generators.

2. Provide a RCS heat SINK by feeding and steaming all steam j - generators.

3. Ensure RCS subcooling by controlling RCS pressure, temperature and liquid inventory.

4 Maintain the core in a subcritical condition, j ACTION / EXPECTED RESPONSE RESPCNSE NOT OBTAINED l CAUTION: If SI actuation occurs at any time, immediately go to te OP-0, Reactor Trip with Safety Injection.

1. Verify icrediate : tions of 1; Perform the appropriate action EP CP-5, Reactor h ip are Manually.

coinpleted.

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1 AND 2 E OP-4A DIABLO CANYON POWER Pt. ANT UNIT NO(S)

/ OATE 2/24/83

' PAGE 3 OF 27 y7, LOSS OF ELECTRICAL POWER ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. Verify all 4KV vital busses 2. If no 4KV vital busses are energized. energized go to EP OP-48. If less than 3 4KV vital busses are energized and it is

, necessary to re-energize more than one 4KV bus from one diesel generator refer to Appendix B for guidance in re-energizing an additional 4KV vital but from one diesel generator.

. SUBSEOUENT ACTIONS

1. To limit an increasing RCS ,

pressure transient, manually OPEN the normal pressurizer spray valve PCV-445A & B

-- during the RCP coastdown.

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2. Reset Auto transfer feature on all vital busses NOTE: Auto transfer feature cannot be used on bus F if Diesel Generator 13 is supplying bus F on the other unit.

3. Verify the following minimum 3. Load them manually as required.

equipment has automatically loaded onto the 4KV vital busses.

a. Centrifugal Charging Pump

b. 3 CFCU (Hi Speed)

c. 2 CCW pumps

d. ASW pumps

e. Both AFW pumps

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NUMBER EP OP ~4A -

REVISION 0 DATE 2/24/83 d A 4 27 LOSS OF ELECTRICAL POWER riu ACTION / EXPECTED PESF0NSE RESPONSE NOT OBTAINED SUBSEQUENT ACTIONS blJTICN: Since RCP's are tripped RTD bypass temperature and

' ssociated interlocks will be inaccurate. Use wide range loop TD's and core thermocouples to determine RCS temperature.

4. Check RCS Average Temperature

a. Wide Range Temperature - a. Dump' steam:

Decreasing towards 547'F

1) Manually open steam generator 10". dumps.

_., b. Wide Range Temoerature -

LESS THAN 554*F

1) Verify feedwater flow 1) Manually close valve.

control valves - CLOSED 9

c. Temperature - STABILIZES AT c. STOP dumping steam. IF 3 547'F cooldown continues, TEE.1 close the main steam isolation valves.

5. Verify AFW flow on FI 157, 158, 159 & 160 (VB3),

a. Both motor driven AFW pumps a. START non-operating motor running, driven AFW pump.

b. Turbine driven pump steam b. Manually OPEN valve.

supply valve FCV-95 OPEN E 2 steam generator narrow range levels < 15".

c. AFW 1evel control valves c. Manually OPEN AFW 1evel OPEN and restoring steam control valves to recover generator level to narrow . steam generator level.

range indication.

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< DATE 2/24/83 PAGE 5 OF 27 LOSS OF ELECTRICAL POWER i

ACTION / EXPECTED RESPCNSE RESPONSE NOT OBTAINED

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l SUBSEOUENT ACTIONS

6. Check RCS Pressure:

a. Pressure - GREATER IHAN a. IF prassure less than 1850 1850 PSIG. psig THEN verify SI actuation and go to EP OP-0, REACTOR TRIP WITH SAFETY INJECTION.

IF pressure decreasing,

b. Pressure - STABLE OR b. i INCREASING. 'UTEN: 1

1) Verify pressurizer PORV's closed; if not, manually close.

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2) Transfer pressurizer

.,.. backup heaters Group 2

. . and 3 to the 480V vital i busses G and H per Operating Procedure A-4A and control RCS

- pressure as necessary,

c. Transfer pressurizer backup heaters Group 2 and 3 to the 480V vital busses G and H per Operating Procedure A-4A and control RCS pressure as necessary.

d. After the RCP coastdown, if pressurizer spray is required to control RCS pressure:

1) OPEN pressurizer auxiliary spray valves - -

CVCS-8145 and/or 8148.

NOTE: Table 5.7-1 of Section 5 of the Technical Specifications limits tne number of unheated auxiliary spray cycles if the spray water temperature and pressurizer water temperature differential is >320*F.

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REVISICN O '.

DATE 2/24/83

! PAGE 6 OF 27 LOSS OF ELECTRICAL POWER i Tn'LE:

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED SUBSEQUENT ACTIONS , .

2) Position the normal pressurizer spray valves PCV-455'A & 8, in MANUAL for desired .

RCS pressure control.

NOTE: Positioning PCV-455 A & B allows for some pressurizer spray

. oypass flow thus giving more FINE RCS pressure control.

7. Check Pressurizer Level:

a. Level - GREATER THAN 174 a. Verify letdown isolation, if not, manually isolate letdown.

b. Level - TRENDING TO 22% b. Manually control charging

. to restore pressurizer 'T?>

level, q;;y

c. Verify seal water. flow to c. Manually control charging the reactor coolant pumps. to restore adequate seal water flow to RCP's.

I CAUTION: Do not throttle AFW flow until water level is above top of U-Tubes. (59% WR)

8. Check Steam Generator Levels:

a. Level - IN NARROW RANGE. a. Continue filling steam generators until level is in narrow range.

b. Throttle AFW flow to maintain range level at 33%. . .

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1* ND 2 NUMBER EP OP-4A OtABLO CANYON POWER PLANT UNIT NO(S) rGASION 0

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DATE 2/24/83 1

pg1,; LOSS OF ELECTRICAL POWER ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED SUBSEOUENT ACTIONS CAUTION: Balance all steam generator pressures to <100 psi AP to prevent an inadvertent SI.

9. Check Steam Generator Pressures:

a. Steam Pressure - STEADY at a. Set each steam generator

<1035 psig 10% dump valve controller to maintain stable steam generator pressure at 1005 psig.

10. Verify Natural Circulation From Trending Values: .

a. Verify RCS subcooling by a. If 50*F subcooling can NOT

/~) observing greater than 50*F be verified:

s ,./ subcooling margin monitor (VB2).

1) Verify using core average thermocouple reading (pt. U0001) on the P-250 computer.

2) Increase dumping steam to establish 50*F subcooling.

b. Steam pressure - STABLE.

c. RCS hot leg temperature -

STABLE OR SLOWLY DECREASING.

d. Core exit TC's STABLE OR . -

SLOWLY DECREASING.

e. RCS cold leg temperature -

NEAR SATURATION TEMPERATURE FOR STEAM PRESSURE.

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! PAGE 8 0F 27 LOSS OF ELECTRICAL POWER 7,7 ,

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ACTION / EXPECTED RESNNSE RESRJNSE NOT OBTAINED SUBSE0 VENT' ACTIONS

11. If P-12 is activated take the following steps:

a. Place both steam dump interlock switches to the -

Bypass Interlock position

< (spring return). .

b. Block both trains of steam line safety injection circuit.

12. Monitor the NIS channels to verify continued subcritical status of the core.

a. When neutron flux has a. Manually re-energize source ,_,,

decreased below P-6, range detectors. /~^

10 10 amps in the O intermediate range, verify -

source range detectors re-energized.

b. Transfer a nuclear recorder to the source range scale.

13. Obtain RCS sample and determine i

the boron concentration.

( 14 Borate the RCS to the HOT Xenon j free condition as necessary.

' a. Borate RCS using BORATE a. Use methods described in

, MODE of RCS makeup system. EP OP-6 Emergency Borate i

! 15. Check the following l turbine-generator auxiliaries -

functioning properly. '

a. Turbine bearing oil pump running.

i OC0134 SII 5

1 AND 2 NUMBER EP OP-4A otAsLO CANYON POWER PLANT UNIT NO(S)

REVISION O

( DATE 2/24/83

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I LOSS OF ELECTRICAL POWER ACTION /. EXPECTED RESPCNSE RESPONSE NOT OBTAINED

.' SUBSEOUENT ACTIONS

b. OC air side seal oil pump running and maintain proper differential pressure.

16. Check the main feedwater pump .

turbine emergency DC lube oil pumps running and the feedwater *

. pumps on turning gear.

NOTE 1: Refer to Volume 9 of the Plant Manual to determine the length

. or time the plant can maintain " HOT STAND BY" based on condensate storage tank inventory, when using atmospheric steam dump valves for steam generator pressure control.

WTE 2: If the decision to initiate cooldown is made, it will be necessary to borate the reactor coolant to Cold Xenon free condition.

This process should be started as soon as possible to take advantage

) of the higher natural circulation flow rates.

17. Investigate the cause for the loss of power and try to restore normal AC power. .

a. From the 230KV Startup Power in accordance with OP J-3.

b. From the 500KV System in accordance with OP J-2.

c. If it appears that all sources of offsite power will be unavailable for a considerable length of time use Appendix C to energize the non-vital 480 Volt ~ '

busses with an operable diesel generator. This step should not be taken without the approval of the Plant Superintendent.

OC0134 9II

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PAGE 10 CF 27 LOSS OF ELECTRICAL POWER 7g g; I

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED SUBSEQUENT ACTIONS

18. When normal offsite power is 18. If normal offsite power'is not restored from either the 230 or restored and the plant must be 500KV system, start t.5e cooled down refer to following equipment in Appendix A.

accordance with the applicable .

operating procedure.

a. Air compressors. .

b. Control rod drive shroud coolers.

c. Service cooling water pumps.

d. Reactor coolant pumps.

,O.

e. Place the main turbine on t:J,)

the turning gear.

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f. If plant is to be cooled l -

l down:

1) AND a RCP is started, go to OP L-S Plant Cooldown From Minimum Load to Cold Shutdown.

2) If RCP's cannot be

started go to EP OP-23 l Natural Circulation.

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(- TITts: LOSS OF ELECTRICAL POWER APPENDIX A PLANT C00LDOWN ACTION / EXPECTED RESR71SE RESFCNSE NOT OBTAINED

1. Borate the RCS to the Cold Xenon free condition,'as necessa ry. ,

a. Borate RCS using BORATE a. Use methods described in EP QP-6 Emergency Borate.

MODE of RCS Makeup System.

b. Keep pressurizer heaters energized during boration.

c. Maintain pressure using auxiliary spray.

2. Verify Cold Shutdown baron -

concentration by sampling:

) .

-/ a. RCS hot leg

b. Pressurizer liquid b. Pressurizer liquid may not be the same concentration as the active portion of the RCS.

c. Letdown line

3. Line up the CVCS makeup control system for the new boron I

concentration and place the l system in AUTO, if desired.

4. Commence degassing the RCS consecutively with cooldewn to a hydrogen concentration of less than 5cc/Kg. Refer to OP B-1A:VIII. .

5. Verify that all Control Rod 5. Start all fans if possible.

Drive Mechanism cooling fans are in operation.

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DIABLO CANYON POWER PLANT UNIT NO(S) 1 ANO 2

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PAGE 120F 27 TIT 1E:

APPENDIX A ACTION / EXPECTED RESPCNSE . RESPONSE NOT C'BTAINED

6. Start RCS cooldown.

a. Maintain cooldown r' ate LESS THAN 25*F/hr. ,

b. Slowly increase rate of ,

. steam dump to start the . !

. cooldown.

CAUTION: When using the steam generator 10% dumps for cooldown, maintain steam generator pressures balanced to avoid an SI on steam generator differential pressure.

c. Verify Auxiliary Feedwater c. Manually throttle auxiliary

. System is automatically feedwater flow, as ;r; maintaining Steam Generator necessa ry. ?:-

Narrow Range level at 333.

d. Monitor the Condensate

- Storage Tank.

1) At LO-LO Level Alarm in the CST refer to Appendix A of EP OP-3A to shift CST suction to an alternate source.

7. Check RCS Hot Leg Temperature:

a. RCS hot leg temperature - a. CO NOT proceed until RCS LESS THAN 550*F. not jeg temperature is less, than 550*F.

8. Ccomence depressurizing the RCS to approximately 1865 psig: . .

a. If letdown is in service, a. If letdown NOT in service depressurize RCS using THEN use pressurizer pressurizer auxiliary PORV's.

spray.

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(/I PAGE 13 CF 27 LOSS OF ELECTRICAL POWER APPENDIX A ACTION /D@ECTEDRESPONSE RESPONSE NOT OBTAINED

9. When the reactor coolant system pressure decreases below the P-11 setpoint (1915 psig) block both trains of the pressurizer low pressure safety injection .

signal.

EAllTION: SI act.uation circuits will automatically unblock if RCS pressure increase above 1915 psig.

10. Maintain the following RCS conditions:

a. RCS pressure - about 1865 psig.

.b. Pressurizer level - about 22". .

. c. RCS cooldown rate - Less than 25'F/hr.

11. Verify RCS cooldown:

a. Core exit thermoccuples -

Trending down.

b. Wide Range hot leg RTD temperature - Tending down.

c. RCS subcooling on subcooling monitor (VB2) -

' increasing (minimum of 50*F).

NOTE: Thermocouple toggle switch on VB2 adjacent to subcooling monitor gives capability to monitor core subcooling margin or reactor vessel head region subcooling margin.

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NUMBER P OP-4A DIABLO CANYON POWEB PLANT UNIT NO(S)

DATE 2/24/83 V PAGE 14 OF 27 LOSS OF ELECTRICAL POWER TITLE:

APPENDIX A .

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

12. Depressurize I RCS as follows:

a. If all CROM fans are a. If all CRDM cooling fans running maintain 50*F are NOT available for subcooling. operatioh:

1) Maintain 200*F f subcooling until RCS pressure is 1200 psig.

, 2) Maintain RCS pressure at 1865 psig until RCS temperature is cooled down to 430*F.

b. If letdown in service, b. If letdown NOT in service, depressurize using then use pressurizer PORV's. o auxiliary spray. ;:

13. Continue RCS cooldown AND depressurization:

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a. Maintain cocidown rate -

LESS THAN 25'F/hr.

b. Maintain subcooling b. If the required subccoling requirements of step 12.a. cannot be maintained, STOP the depressurization anc reestablish the required subcooling.

c. Maintain the reactor ' "'

coolant system pressure-temperature relationship within the boundaries of the Plant Cooldown Curve, Vol. g of , ,

the Plant Manual.

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DIABLO CANYON POWER Pt ANT UNIT NO(S) R ON DATE 2/24/83

( PAGE 15 0F 27 I.- LOSS OF ELECTRICAL POWER TITLE:

APPENDIX A ACTION / EXPECTED RESPCNSE RESPONSE NOT OBTAINED 14 Verify NO voiding in Reactor 14. If voiding is suspected due to Vessel Eead Area. large variations in pressurizer level or RVLIS Plenum Range

<100%, THEN repressurize the RCS to collapse the void in the head area. Also refer to EP OP-44, Gaseous Voids In The ,

RCS. -

a. Pressurizer level RESPONSE NORMAL.

b. Reactor Vessel Level

Instrument Plenum Range (PAM PNL) indicating 100%.

s 15. If all CRDM fans are NOT in

') operation:

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a. Maintain RCS at 1200 psig while continuing to

. cooldown to 350*F.

b. Maintain 1200 psig for approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to Ellow the upper head to cool off to a temperature less than saturation for 400 psig (445'F) before continuing with the depressurization.

16. Check if SI system should be disabled:

a. RCS prassure - Less than a. DO NOT disable any SI 1000 psig but greater than. - system equipment if greater 700 psig. than 1000 psig.

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NUMBER POPdA .

DIABLO CANYCN PCWER PLANT UNIT NC(S)

DATE 2/24/83 s PAGE 16 CF ' 27 LOSS OF ELECTRICAL POWER APPENDIX A ACTION / EXPECTED RESPONSE RESf0NSE NOT OBTAINED

b. Average RCS temperature - b. DO NOT disable any SI LESS 350*F but RCS cold leg system equipment if Average temperature greater than RCS. temperature is greater 323*F. than 350'F.

c. Isolate SI accumulators. ,

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1) Close the isolation valves.

. 2) Rack out each isolation valve breaker.

d. Disable the safety injection pumps by opening

- the DC control power to the pump breaker. ,

pg

e. Disable the non-operating centrifugal c.harging pump by opening the DC control power to the pump breaker.

17. Open additional letdown orifices if necessary to maintain normal letdcwn flow.

18. Maintain adequate RCP Seal Injection Flow.

a. Adjust HCV-142, as necessary.

19. 'When system pressure has been reduced to approximately 400 psig, hold it constant at this value by reducing auxiliary , ,

spray flew and energizing the PZR heaters as necessary.

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OtABLO CANYCN POWER PLANT UNIT NO(S) ~' - *1 AND 2 NUW8ER EP OP-4 A REVISioPO

(- ( LOSS OF ELFCTRICAL POWER DATE PAGE 2/24/83 17 0F 27 TITLE:

APPENDIX A ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

20. When RCS hot leg temperature has been reduced to less than -

350*F and pressure is between 380-420 psig, place the RHR system in service recirculating ,

from hot leg 4 to the cold legs, in accordance with OP '

B-2:V RHR Place in Service -

During Plant Cooldown.

^

21. Prior to RCS hot leg temperature being reduced to 323*F ensure the pressurizer PORV's are providing low

pressure protection by verifying the Low Pressure Setpoint protection c/o switch O' is- CUT IN (VB2).

a. If the positive displacement reciprocating

- charging pump is operating:

1) Verify MOV's 8701 and 8702 are open.

2) Rack out their motor breakers.

22. Continue RCS cooldown to below l

200*F with RHR system.

CAUTION: Depressurizing the RCS before the entire RCS is below l 200-F may result in void formation in the system.

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NUMBER EP OP-4A OfABLO CANYON PCWER PLANT UNIT NO(S)

REVISICN O DATE 2/24/83 j LOSS OF ELECTRICAL POWER 7g g

, APPENDIX A

. ACTION / EXPECTED RESPCNSE RESPONSE NOT OBTAINED

23. Continue Cooldown of Inactive Portion of RCS:

a. Upper head region '- ALL a. IF fans NOT running, THEN CROM FANS RUNNING. IRI NOT depressuri:e RET--

until upper head cools to less than 200*F (approximately 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months after RHR system is placed

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in service).

b. Steam Generator U-Tubes - b. 00 NOT depressurize RCS CONTINUE DUMPING STEAM frcm . until steam generators have all steam generators until stopped steaming.

it is VERIFIED that they -

have stooped' steaming.

m

24. GO TO Operating Procedure L-5, . _

.-4

" Plant Cooldown From Minimum 'ia/

Load to Cold Shutdown", for centinued cooldown of the RCS to a cold shutdown condition using RHR forced cool down.

O G 6

.0C0134 ISI!

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DATE 2/24/83 PAGE 19 OF 27

( LOSS OF ELECTRICAL PCWER ,

. APPENDIX B

. ENERGIZING VITAL 4KV BUSSES WITH DIESEL GENERATOR SCOPE The purpose of this appendix. procedure is to make available a selected vital 4KV bus in the event its diesel generator is inoperable. This is accomplished by energizing the bus from an operable diesel generator. Since this is an extremely unusual situation and since we are cross connecting safety related trains, this procedure will only l be used when no other alternative means of power is aVailable and ONLY with the Plant Superintendent's permission.

. DISCUSSION This procedure deals with the situatio'n of the 4KV F vital bus being inoperable due to the 13 swing diesel generator being committed to the other Unit and considers the possibility of either 11 or 12 diesel generator of being inoperable. The procedure shall address energizing the 4KV F vital bus or another de-energized vital bus, G or H h depending on the second inoperable diesel generator. This. procedure is written in the Unit 1 perspective i.e., all bus and breaker numbers use Unit 1 designators.

Th! following is a list of the minimum number of essential components required for plant cooldewn with N0 safety injection.

a. 1 Centrifugal Charging Pump - 580KW

5. 1 Component Cooling Water Pump - ?23KW

c. 1 Auxiliary Saltwater Pump - 340KW

d. 3 Containment Fan Coolers - 660KW

e. 1 Auxiliary Feedwater Pump - 429KW

f. 1 Pressurizer Heater Group - 485KW

g. 2 480V Motor Centrol Cente'rs - 1033KW (MAX)

(,

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7g LOSS OF ELECTRICAL POWER i i

l APPENDIX B As a general guideline, in.this situation of trying to cooldcwn a unit on 1 diesel generator the Shift Foreman should attempt to only operate a centrifugal charging pump, component cooling water pump and the 480V motor control centers on a , continuous basis. He should attempt to cross connect with the other unit's auxiliary salt water system when possible if there is more power available. He should use the turbine driven auxiliary feedwater pump as much as possible and only operate the motor driven auxiliary feedwater pump, the containment fan coolers and the pressurizer heaters intermittently to maintain the plants critical parameters within the desired operating band, i

PROCEDURE '

1. Cutout the AUTO Transfer FCO's for 4KV busses and 12KV busses.

2. Depress all AUTO Transfer Reset Push Buttons. '

The Auto Transfer Reset will NOT reset and the BLUE light M:

N)TE NOT de-energize for the F bus if the 13 diesel generators is operating on the other Unit.

i

. 3. This step is only used to energize the 4KV F vital bus when the 13 diesel generator is operating on the other unit.

, a. Dispatch an Operator to the 4KV Bus F Switchgear Cubicle 7, to overvoltage relay 59HFG1/59HFG2

1) Remove the cover 1 2) Pull down on the 2 " RED" handled switches (Terminal 5 I

and 10).

b. THEN at the Main Control Board, depress the Auto Transfer Reset Push Button for the 4KV F vital bus. Notice the

" BLUE" light goes "OUT".

c. The Operator at the 4KV Sus F Switchgear may now return the

2 " RED" handled switches to their normal position and l replace the cover. - -

4. OPEN or verify OPEN all vital bus 4KV auxiliary feeder breakers, 52-HH-13, 52-HG-13 and 52-HF-13.

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DtABLO CANYON POWER PLANT UNIT NO(S)

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( PAGE 210F 27

[_ LOSS OF ELECTRICAL PCWER APPENDIX B

5. OPEN or verify OPEN all vital bus .4KV startup feeder breakers, 52-HH-14, 52-HG-14 and 52-HF-14.. ,

6. OPEN or verify OPEN startup feeder breaker to the vital busses F, G and H, 52-HG-15. ,

7. Cut in the FC0 to place all Diesel Generator Protection in service for the operating Diesel Generator.

8. OPEN or verify OPEN the 4KV to 480V bus feeder breaker,

a. If bus F is to be re-energized OPEN 52-HF-10. l

b. If bus G is to be re-energized OPEN 52-HG-10.

c. If bus H is to be re-energized OPEN 52-HH-10.

9. CLOSE the 4KV startup feeder breaker for the bus that will be supplying power to the inoperable bus,

a. If diesel generator 11 is operating CLOSE 52-HH-7.

b. If diesel generator 12 is operating CLOSE 52-HG-5.

bUTICN: IF THE DIEF'L GENERATOR APPEARS UNSTABLE DURING THE

FtriF0riMANCE OF STEP 10 OR AT ANY TIME BEYONO THIS POINT IN THE

PROCEDURE IMMEDIATELY OPEN STARTUP FEEDER BREAKER FOR THE INOPERABLE

,8US TO SEPARATE THE DIESEL.FROM THE INOPERABLE BUS. ,

10. CLOSE the 4KV startup feeder breaker for the inoperable bus.

a. If bus F is to be re-energized CLOSE 52-HF-14.

b. If bus G is to be re-energized CLOSE'52-HG-14

c. If bus H is to be re-energized CLOSE 52-HH-14 DUTICN: STATIONANOPERATORATT5iEVB4TOMONITORTHEDIESEL puitRATOR. IF AN SI SHOULD OCCUR IMMEDIATELY OPEN THE 4KV STARTUP

. FEEDER BREAKER FOR THE SUS WITH THE OPERABLE DIESEL GENERATOR TO PREVENT OVERLOADING THE OPERA 3LE DIESEL GENERATOR WHEN THE SI LOADS iSEQUENCE ON THE BUS. - -

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DATE 2/24/83 PAGE 22 0F 27 LOSS OF ELECTRICAL POWER 7,7 g APPENDIX B

11. CLOSE the 480V motor control. center feeder breaker.

NOTE: Evaluate the lead on the diesel generator prior to energizing each additional load to ensure its reserve capacity is not exceeded. As each additional load is added if the diesel overicads it may only be necessary to trip the last load added rather than tripping the entire bus,

a. If bus F was re-energized CLOSE 52-HF-10. -

b. If bus G was re-energized CLOSE 52-HG-10.

c. If bus H was re-energized CLOSE 52-HH-10.

12. START additional equipment necessary to restore the minimum

, systems needed for plant cooldown.

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N DIABLO CANYON POWER PLANT UNIT NO(S) .- 1 AND 2 .

E S ON EP OP-4A O

DATE PAGE 83

(. TITLE:

LOSS OF ELECTRICAL POWER 2

2 @3 27 4l APPENDIX C

. ENEliG!ZINGNON-VITAL 480VBUSSESWITHOIESELGENERATOR SCOPE -

l The purpose of this procedure is to make available selected non-vital l systems to lessen the restrictions on recovery until normal 0FF-SITE power is restored. This procedure deals with the situation when both Units are down and the some total of all power sources are the combined S emergency diesel generators. In this case one unit will be deprived of the swing diesel generator 13. The selected non-vital systems which are desired to be returned to service a're plant instrument air, service cooling water. CRDM shroud cooler fans, Turbine Generator lift pump and turning gear drive. 230KV and 500KV

. switchyard.

DISCUSSION This procedure deals with both units since the plant air compressors are pcwered from either unit and are normally cross connected such that it is coninon to both units. Therefore, the unit to which the s l swing diesel 13 is committed will be responsible for re-energizing the

~

compressed air system. Unit 1 is responsible to re-energize the 230 and 500KV switchyaro. Any additional loading will be done by Shift Foreman evaluation of remaining diesel generators capacity. This procedure is written in the Unit 1 perspective, i.e., all bus and breaker numbers use Unit 1 designators.

The following is a list of the minimum number of loads required for plant coolcown.

a. 1 Centrifugal Charging - 580KW

b. 1 Component Cooling Water - 323KW

c. 1 Auxiliary Salt Water - 340KW

d. -3 Containment Fan Coolers - 660KW

e. 1 Auxiliary Feedwater - 429KW

f. 1 Pressurizer Heater Group - 485KW

g. 2 480V Motor Control Centers - 1033KW (MAX)

'0C0134 23II .~ -

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TITLE. LOSS OF ELECTRICAL POWER l

APPENDIX C PROCEDURE . .

1. Determine which diesel generator will be used as source for the non-vital busses. .

a. On the Unit which has the 13 swing diesel generator available, transfer the maximum number of essential loads to the 4KV bus F and remove all non-essential loads from bus G.

l

b. On the Unit which does not have the 13 swing diesel ;

generator available, transfer the maximum number essential '

' loads to bus G and remove all non-essential loads from bus H.

2. Cut out the Auto Transfer FCO's for all 4KV busses and 12KV busses.

3. Depress all Auto Transfer Reset Push Buttons.

. m (OTE: The Auto Transfer Reset will NOT reset and the BLUE light wili NOT de-energize for the F bus iTTne 13 diesel generator is operatiiig on the other unit.

- 4 OPEN or verify OPEN all vital bus 4KV auxiliary feeder breakers,

. 52-HH-13, 52-HG-13 and 52-HF-13.

5. OPEN or verify OPEN all vital bus 4KV startup feeder breakers, 52-HH-14, 52-HG-14 and 52-HF-14

6. OPEN or verify OPEN startuo power to vital busses F, G, H, 52-HG-15.

7. OPEN or verify OPEN auxiliary feeder to 4KV busses 0 and E, 52-H'-2 and 52-HD-2.

8. OPE'N or verify OPEN startup feeder to 4KV busses 0 and E, 52-HE-3 and 52-HD-14

9. OPEN or verify OPEN startup transformer 12 feeder breaker j 52-HD-14

10. OPEN ALL 4KV feeder breakers to 480 voit busses on 4KV busses 0

and E -

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a OfABLO CANYON POWER PLANT UNIT NO(S) 1*AND 2 RE ON O

DATE 2 @ 83

((s.

\ TITLE. LOSS OF ELECTRICAL POWER PAGE 25 27 APPENDIX C

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11. Cut in the FC0 to place all Diesel Generator Protection in

. service for the Diesel Generator selected to power the non-vital busses.

12. Verify all Condensate / Booster pump stano-by switches are set in MANUAL.

13. Verify the Nash Vacuum pump is OFF and the No. 2 Heater Drip Pump is OFF. .

14 CLOSE the.startup feeder breaker to the vital bus.

. a. If Diesel Generator 11 is the non-vital bus power source CLOSE 52-HH-14.

b. If Diesel Generator 12 is the non-vital bus power source CLOSE 52-HG-14.

c. If Diesel Generator 13 is the non-vital bus power source CLOSE 52-HF-14.

'CAIJTION: If the diesel generator appears unstable during the !

performance of step 15 or at any time beyond this point in the i

procedure, imediately OPEN 52,HG-15 to separate the diesel from the:

pan-vitalsystem.

15. CLOSE startup power to vital busses F, G, H, 52-HG-15.

NOTE: There will be a short load surge on the Diesel Generator as the startup transformer 12 is energized.

16. CLOSE startup feeder to 4KV bus 0, 52-HE-3.

17. CLOSE startup feeder to 4KV bus E, 52-HM4

18. On the Unit which has the 13 swing diesel generator carrying the F vital bus energize the following 480V bosses.

WTE: Evaluate the load on the diesel generator prior to eFe71 9 zing each accitional load to ensure its reserve capacity is not exceeded. As each additional load is added, if the diesel generator overloads it may only be necessary to trip tne last load added rather than tripping the entire bus. . .-

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DC0134 25I1

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{ g[g /{fy83 7 TLE LOSS OF ELECTRICAL POWER APPENDIX C t

a. Energize non-vital bus.150 CLOSE 52-HD-6. ,

b. Energize non-vital bus 110 CLOSE 52-HD-10.

19. Return the instrument ' air system to service as per OP K-1.

20. Energize the 500K7 switchyard CLOSE 52-HE-7. '

a. Dispatch an Operator to the 500KV switchyard to verify CLOSED or CLOSE the local 4KV bus feeder breaker in the 500KV switchyard.

b. Operator should also verify 480V bus is energized and 500KV switchgear compressed air system is available.

c. Operator should verify 230KV yard 4KV bus is energized via i the emergency tie cable and its compressed air system is available. -

21. Additional loads such as CROM shroud coolers, turbine generator lift pump and turning gear drive may be made available and thair 480V busses energized at the discretion of the Shift Foreman,

dependent on diesel generator reserve capacity.

1

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TRIE: LOSS OF ELECTRICAL POWER

. APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS

1. When this . emergency procedure has been activated and upon

. direction from the Shift Foreman, proceed as folicws:

a. Designate this event a Notification of Unusual Event.

Notify plant staff and response organizations required for this classification by implementing Emergency Procedure G-2

" Establishment of the On-Site Emergency Organizations" and Emergency Procedure G-3 " Notification of Off-Site Organization" in accordance with Emergency Procedure G-1

" Accident Classification and Emergency Plant Implementation.

b. Designate this event an Alert _ if all of the vital busses (F, G and H) fail to be powered oy the apolicable diesel generator (step 4). Notify plant staff and response organizations required by EP G-2 and EP G-3 in accordance with IP G-1.

( ,) c. Designate this event a Site Area Emergency if AC pcwer cannot be restored to any vital bus (F G or H) by either Diesel Generators or off-site power within 15 minutes of the total loss. Notify plant staff and response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.

DC0134 271I

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NuusER 3DGs#3 Pacific Gas and Electric Company REVISICN O sp op.48 DATE DEPARTMENT OF NUCLEAR PLANT OPERATICNS 2/25/83 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 10F g1 EMERGENCY PROCEDURE TITLE: LOSS OF ALL AC POWER APPROVED:

PLANT MANAGER M DATE SCOPE -

This procedure is provided to cover the unlikely even,t of a loss of

, all AC power. In general this event is extremely unlikely since it would require the loss of all emergency diesel generators, a trip of the main generator coincident with a loss of all startup power and the

- 500KV system. The reactor will trip due to the turbine generator trip

, if above 10% power or will trip from loss of control rod drive M-G sets of below 10% power, therefore, the immediate actions of the Reactor Trip procedure or the Safety Injection procedure, if applicable will be completed upon entering this procedure.

SYMPTOMS

1. Control room standard lighting 0FF and backup emergency DC lighting ON.

2. Plant safeguards equipment do not energize.

3. All 12 and 4KV undervoltage alarms.

4. RCP trip. alarms. ,

AUTOMATIC ACTIONS

1. Turbine - generator trip.

2. Reactor trip.

3. Steam dump to condenser and 35% atmospheric cumps blocked.

l 4. Steam generator safeties may open to limit steam generator pressure to 1065 psig or steam generator 10% dump valves open to hold steam generator pressure at 1035 psig.

5. Turbine driven auxiliary feedwater pump starts.

l l . -

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. N DIABLO CANYCN POWER PLANT UNIT N0(S) 1'AND 2 R S ON ,m '

DATE 2/25/83 PAGE 2 OF 61 M#

mts: LOSS OF ALL AC POWER OBJECTIVES.

1. Minimize RCS inventory loss.

2. Provide a RCS heat sink by feeding and steaming all steam generators.

3. Maintain the core in a subcritical condition.

4. Restore AC power.

5. Recover the plant following restoration of AC power.

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ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAlf E

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IMMEDIATE ACTIONS

1. Verify the immediate actions of Reactor Trip or Safety Injection are completed.

CAUTION: WHEN POWER IS RESTORED TO ANY 4KV VITAL BUS GO TO STEP 15 AND EVALUATE PLANT RECOVERY OPTIONS.

~

IF AN SI SIGNAL EXISTS OR IF SI IS ACTUATED PRIOR TO RESTORTRG POWER, RESET THE S[TIGNAL.

ACTION /EXPECTcD RESPONSE RESPONSE NOT OBTAitED SUBSEOUENT ACTIONS

1. Attempt to Restore Power to Vital 4KV Bus.

a. Start any emergency diesel a. Start any emergency diesel generator. generator manually.

1) If the emergency diesel generator will not

~

start. Refer to OP J-6 Diesel Generator - Make Available to verify system lineup.

I CC0137 2II .

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k. - DATE i PAGE 3 OF 61 ints: LOSS OF ALL AC POWER ACTICA/ EXPECTED RESPONSE RESPONSE NOT OBTAINED SUBSEQUENT ACTIONS . .

b. Verify automatic loading of b. Manually load the the 4KV vital busses, safeguards equipment on the (Refer to Appendix A). 4KV vital busses (Refer to Appendix A). If the emergency dieseT generator cannot be loaded THEN manu111y trip the diesel.

c. If the 500KV system is

. available, refer to OP J-2, "TO BACKFEED NO. 1 UNIT AUXILIARIES FROM THE 500KV SYSTEM". ,

d. If Unit 2 12 KV startup bus is energized close crosstie .

,1 breaker (52-VU-11).

e. If AC Vital 4KV busses are restored, GO TO Step 15.

.f. If AC vital 4KV busses cannot be restored due to internal plant emergency such as a FIRE then:

1) Follow 'the appropriate General Emergency Procedure to combat the emergency while continuing with the subsequent steps of this procedure.

g. Dispatch an operator to the Vital 4KV bus switchgear. * ~

l 1

DC0137 3II

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DATE 2/25/83 PAGE 4 OF 61 TITLE: LOSS OF ALL AC POWER ACTION / EXPECTED RESPCesE RESPONSE NOT OBTAINED SUBSEOUENT ACTIONS

1) Open or check open the breakers to the-following equipment:

CC Pp 1-1 CC Pp 1-2 SI Pp 1-2 SI Pp 1-1 CFCU 1-1 RHR 1-1 ~ RHR 1-2 CFCU 1-2 CFCU 1-2 CFCU 1-4 CCW Pp 1-1 CFCU 1-5 CCW Pp 1-3 ASW Pp 1-1 CCW Pp 1-2 AFW Pp 1-2 APA Pp 1-1 ASW Pp 1-2 Cont. Spray Pp 1-2 Cont. Spray Pp 1-1

2) Open the DC control power to the above listed breakers and -

maintain communication 9,-

between the vital 4KV

bus switchgear and the control room.

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2. Verify RCS Isolation

a. Pressurizer PORVS - CLOSED a. If RCS pressure less than TJ35 psig. Then manually close PORVS.

b. Letdown isolated. b. Manually close letdown isolation valve.

1) CVCS 8149 A, B, and C 1) LCV-459 and LGV ,460....

CLOSED .

c. Excess letdown isolation valves closed.

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1) CVCS-8166 CLOSED

2) CVCS-8167 CLOSED DC0137 AII .

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k-OLABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 (h DATE 2/25/83 Tn1E: LOSS OF ALL AC POWER ACTION /EXPECTE) RESPONSE RESPONSE NOT OBTAINED SUBSE00ENT ACTIONS -

3. Place the following switches in CLOSED position and dispatch personnel to locally close valves to isolate RCP seals: -

a. MOV 8100 CLOSED ,

b. CVCS 8382 A&B CLOSED

. c. FCV-357 CLOSED

4. Verify Turbine Driven Auxiliary Feedwater Pump Running:

a. FCV ?5 OPEN a. Open FCV-95 Manually

b. Flow established to ALL 4 b. If AFW flow NOT verified, steam generators (VB-3) TREN Locally:

1) Check open or open FCV-37 and FCV-38

2) Check open or open:

a) Suction from CST MU-1-671 ,

b) Discharge header valves LCV-107, 108, 109 & 110 c) Manual valve alignment for AFW Pump 1-1.

5. Isolate the HOTWELL from the Condensate Storage Tank. ,

a. CN0-1-507 CLOSE's (Hotwell Makeup Isolation)

b. CND-1-509 CLOSED (Bypass) 4 DC0137 SIl G

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PAGE 6 CF61 TITLE; LOSS OF ALL AC POWER ACTION /EXPECTEDRESPONSE RESPONSE NOT OBTAINED SUBSE00ENT ACTIONS . .

6. Break Vacuum in the Main i Condenser. .

a. Dispatch personnel to open .

CND-1-506 (119' elev. south end of Main Condenser)

7. Check Steam Generator Isolation:

a. Main steam line isolation a. Manually close valves by valves - CLOSED going to close on the control switches (VB3).

b. Main steam line isolation b. Manually close valves by bypass valves - CLOSED going to close on the control switches (VB3).

c. Blowdown (OC) isolation c. Locally close the manual valves - CLOSED containment isolation valves.

8. Verify for Secondary Integrity.

a. All steam generator a. If pressure is 100 psig pressures approximately Tower in one steam equal (tzke into account generator as compared to steam generators 1-2 and the other isolate that 1-3 are supplying steam to steam generator (when the turbine driven making this decision auxiliary feedwater pump). consider any operator action that may have caused the low pressure condition).

1) Isolate AF4 flow to the faulted steam generator.

t DC0137 61I .

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2) Isolate the faulted steam generator supply -

l to the turbine driven AFW pump.

9. Verify for Primary to Secondary Integrity: -

a. Review chart recorder of a. If high, THEN continue with condenser air ejector . the procedure while trying

~

radiation monitor RE-15 to identify and isolate the since the start of the faulted steam generator.

" Loss of Power" event-NORMAL BACKGROUNO.

b. Review chart recorder of b. If any are high, THEN r . main steam monitors RE-71 cEntinue with the procedure '

\s / through 74 since the start while maintaining the 1 of the " Loss of Power" faulted steam generator event - NORMAL BACKGROUND isolated.

. on all. steam generators.

CAUTION: A FAULTED STEAM GENERATOR THAT IS ISOLATED SHOULO REMAIN ISOLATED THROUGHOUT FURTHER RECOVERY ACTIONS.

10. Check Non-Faulted Steam Generator Levels:

a. Narrow range level - a. If less than 33t THEN greater than 33%_. iiiaintain full AFf7 Tow until narrow range level is greater than 33%.

b. Manually control AFW flow b. If narrow range level in to maintain narrow range one steam generator level at 33%. continues to increase with AFW flow stopped.

THEN:

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PAGE 8 OF 61 TITLE; LOSS OF ALL AC POWER f

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. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED SUBSEQUENT ACTIONS

1) Isolate AF4 flow to the

- faulted steam generator.

2) Isolate faulted steam .

generator steam supply l to the turbine driven AFW pump.

11. Check Condensate Storage Tank i Level

a. CST level - gruter than

a. When CST level decreases to set. 10%, THEN switch to alternate APd pump water supply.

1) Verify a level in the- - O '

raw water storage

~

reservoir; then

. manually open FCV-436

~

(Reservoir supply to AFW pump). Allow the AFV pump to run during the transfer. Monitor I the AFW flow closely.

If APd flow is lost, trip AFW pump until the transfer is complete, then restart the pump.

2) If the raw water storage reservoir is

~' "

not available, go to

.- Appendix B (AFW Pumo

~

Suction Supply from Fire Water Tank

~

Precedure). Allow the i ,

AFd pumn to run during i

i

! CC0137 BII _

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DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 "hPOP-4B

( ) DATE 2/25/83 PAGE 9 OF61 I

ints: LOSS OF ALL AC POWER i ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED SUBSE0 VENT ACTIONS ,

the transfer. Monitor the AFW flow closely, if AFW flow is lost, trip AFW pump until the transfer is complete, then restart the pump.

NOTE: When the CST Lo

. Lo level alarm occurs, the operator has

~

approximately 20 minutes to perform Steps 1) or,2) above.

CAUTION: IN ORDER TO PREVENT INJECTION OF ACCUMULATOR NITROGEN INTO THE RCS AND TO PREVENT THE REACTOR CORE RETURNING 70

( ', '

CRITICALITY DUE TO MODERATOR TEMPERATURE EFFECTS, 00 NOT REDUCE RCS PRESSURE BELOW 365 PSIG OR CORE EXIT TdiFERATURE BELOW 440*F.

NOTE: The non-faulted steam generators should be depressurized as quickly as possible BUT in a controlled manner so that RCS pressure and temperature limits of the RCS cold down curve (Vol.

9 of the Plant Manual) are not violated.

NOTE: Continue on with Step 13 of the procedure after depressurization of non-faulted steam generators in Step 12 has been started.

m.-

12. Depressurize the Non-Faulted Steam Generators to Minimize RCS Inventory loss:

a. From the Control Room -

a .- If the steam generators 10%

( manually open and throttle dumps cannot be opened frem steam generator 10% dumps the control room, open and to reduce RCS pressure to throttle them locally.

370 psig.

l l

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NUMBER EP OP-48 ,

otAeLO CANYON POWER PLANT UNIT NO(S) l'AND 2' REVISION O ;

N 1 DATE 2/E5/83 -

PAGE 10 CF 61 s 1

TGLE. LOSS OF ALL AC POWER l 4

ACTION /EXPECitD RESPCNSE RESPONSE NOT OBTAINED SUBSEOUENT ACTIONS

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1) Station an operator at each local valve

, operator.

2) All local operators should be in communication with the control room where the cooldown will be controlled and monitored.

. NOTE: Ear protection required at the local valve station.

b. When RCS Pressure Decreases Below SI Setpoint 1850 osTo. (

1) Verify jg[ signal 1) Manually initiate 51 actuatea.

2) Reset jy[ signal,

c. Verify Phase A Containment c. Manually Close Phase A Isolation Valves Closed. Isolation Valves.

Refer to Postage Stamp Lights (VB1) Not In Alarm.

i

d. Manually control AFW flow d. If less than 10%, THEN:

te maintain steam generator narrow range level 33%.

1) Maintain full AFW flow until narrow range level is greater than 10%.

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'. PAGE 11 OF 61 :

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I LOSS OF ALL AC POWER TITLE: l I

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ;

SUBSEQUENT ACTIONS

2) Maintain steam generator levels above top of U-tubes (69% WR). IF NOT above U-tubes, TH E stop steam generator depressurization.

NOTE: Ear protection .

required at the local valve station.

b. When RCS Pressure Decreases Below SI Setpoint 1850 psio.

l 1) Verify SI signal 1) Manually initiate E.

y; actuated. . ;

2) Reset E signal.

l

c. Verify Phase. A Containment c. Manually Close Phase A l Isolation valves Closed. Isolation Valves.

Refer to Postage Stamp lights (VB1) Not In Alanu.

d. Manually control AFW flow d. If less than 10%, THEN:

to maintain steam generator narrow range level 33%.

1) Maintain full AFW ficw until narrow range level is greater than 10%.

, , 2) Maintain steam

, generator levels above top of U-5 Tubes (69% WR). IF NOT above U-tubes, TH E stop j steam generator l depressurization.

1 s ,

r :*

'~

! DC0137 11II I _

O T 1'AND 2' NUMBER EP OP-48 DIABLO CANYON POWER PLANT UNIT NO(S) F;EVISIONO .,

o4Tg 2/25/83 PAGE 12 OF 61 l TIT 1E: LOSS OF ALL AC POWER i

ACTION / EXPECTED PESPONSE PESPONSE NOT OBTAINED SUBSEQUENT ACTIONS

e. Manually throttle steam e. Locally throttle steam generators 10% dumps generator 10% dumps.

to maintain RCS pressure at 370 psig.

13. Check RCS Conditions During Secondary Cepressurization:

a. RCS pressure - greater than a. If less than 370 Dsig, THEN 370 psig, st'op steam generator

' depressurization and restore RCS pressure to

- 370 osig.

b. Core exit thermocouples *

b. If less than 440*F THEN ,

greater than 440*F. stop steam generator depressurization and restore RCS temperature to (7'N,

- greater than 440*F. q~b/

14. Check If Recovery Can Be Initiated:

a. At least one vital 4KV AC a. IF NOT restored, THEN Bus power restored. continue to controT ICS conditions and monitor plant stat'us:

1) Check status of auxiliary boration systems:

a) BIT temperature greater than 145'F.

b) SAST temperature greater than 145'F.

. n 4

DC0137 1211

" ^- _r- ,, , ,

i ,

N P OP-48 otAsLo CANYON PCWER PLANT UNIT N0(S) 1 AND'2

(.. g DATE pass 2/25/83 13 op 61 TITLE: LOSS OF ALL AC POWER i

ACTIO'N/ EXPECTED RESPONSE RESFONSE NOT OBTAINED SUBSEQUENT ACTION .

c) If auxiliary

. boration systems temperature less

. than 145'F consider methcos of reducing baron concentration:

(1) Draining tanks !

. to the :

auxiliary building sump.

(2) Diluting by ,

. adding water from the primary water

._x tanks via a !

('

portable 2 diesel powered fire pump.

2) Check status of spent fuel pool cooling.

a) Spent fuel pool level greater than 27 feet above Irradiated fuel.

l b) If spent fuel pool l . Tivel less than 27-feet above irradiated fuel, THEN dispatch

~ ~

personnel to fill spent fuel pool via the fire water '

system hose reel in the Fuel Handling Building.

/

_s' o DC0137 13I1 l ,

i .

s 1 . .

~

1 AND 2 NUMBER EP OP-4B otAaLO CANYON POWER PLANT UNIT NO(S) _s REVISION 0 DATE 2/25/83 "

PAGE 14 OF 61 TITLE: LOSS OF ALL AC POWER ACTIOWEXPECTED RESPONSE RESPONSE NOT OBTAlfED l SUBSEOUENT ACTION l

I

3) Return to Step 12 through 14 until power.

is restored.

15. Maintain Stable RCS Pressure While Calculating Recovery ~

Options.

16. Selected Recovery Options:

a. Check RCS subcooling a. If less than 35'F, then go greater than 35'F. to Appendix C, Loss of All AC Power Recovery

with SI-Required.

b. Check pressurizer level b. If less than 10% THEN go to greater than 10%.

Appendix C, Loss of All AC (~

Power Recovery with S_I, Required.

. c. Verify that SI components c. If SI components have NOT automatically nive automatically actuateo upon AC power actuated, THEN go to restoration. Appendix C, Loss of All AC Power Recovery with SI, I Required.

I d. If condition a, b, and c l

aFe satisfied, THEN go to Appendix 0, Loss of All AC Power Recovery Without SI, Required.

i l

\

DC0137 14II , -

t w--, ---t v--r- , ,~, -my-

7 .

N P OP-4B OtASLO CANYON PCWER PLANT UNIT NC(S) 1 AND 2

( DATE PAGE 2/25/83 15 op 61

(

Tm.E: LOSS OF ALL AC POWER APPENDIX A LOSS OF ALL AC POWER WITH SAFETY INJECTION EMERGENCY LOADING OF VITAL BUSSES

1. If the vital busses regain voltage prior to resetting the safety injection signal, the Vital busses wiTT~ automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.

2. If the vital busses regain voltage after the safety injection signal has been reset, load or verify loaded the equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that tne CFCU are running in Low Soeed. -

VITAL BUS VITAL BUS VITAL BUS F G H

/~ D/G 1-3 D/G 1-2 D/G 1-1

~

~ *MCC 1-F *FCC 1-G *MCC 1-H

CC Pp 1-1 *CC Pp 1-2 SI Pp 1-2 SI Pp 1-1

CFCU 1-2 RHR Pp 1-1 RHR Pp 1-2

CFCU 1-1 *CFCU 1-3 *CFCU 1-4

CCW Pp 1-1 *CFCU 1-5 *CCW Pp 1-3

ASW Pp 1-1 *CCW Pp 1-2 *AFW Pp 1-2

AFW Pp 1-1 *ASW Pp 1-2

Loading of Vital Bus when No Safety Injection.

e W 6

)

DC0137 1511

, T MSER P OP-48 otAsto CANYON POWER PLANT UNIT NC',5) 1'AND 2' DATE 2/25/83 -

PAGE 16 CF 61 in1E: LOSS OF ALL AC POWER

~

APPENDIX B AUXILIARY FEED PUMP SUCTION SUPPLY FROM FIRE WATER TANK The Operator has 20 minutes to perform this operation after the lo Lo level alarm on the condensate storage tank and before the AFW pumps lose suction. This provides sufficient time; however, the operator must not delay and must carry out the valve line up in order as written.

If the AFW pumps are being supplied from the raw water reservoir and a seismic event occurs with resultant loss of AFW suction and auxiliary i feedwater flow to the steam generators, the steam generators will boil dry in about 30 minutes. Under these conditions, it is especially important to expedite this procedure and reestablish AFW flow to the steam generators prior to the reactor losing its heat sink. .

ACTION Using the attached drawing, proceed to supply the AFW pumps suction from the nN fire water tank. Kj

~ 1. Close or verify closed MU-0-284 and MU-0-286.

2. Close or check closed MU-1-298.

3. Close or check closed MU-0-325.

4. Close or check closed MU-0-427.

5. Open FP-0-306 and FP-0-307.

5.- 'Natify the control room that the suction for the AFW pumps is now available from the fire water tank.

7. Locally open FCV 436 and 437.

8. Proceed to the auxiliary feedwater -

pumps and vent the pump casings if required to remove air.

\

r DC0137 ISIT -

r- =- +- - w

e

-4 0

. @ 5 c

3 m

ti Fire Water m 3 o

Tank

,~.f To H.U. y filters Sealed FP-0-4 f - 3 16 g 3 Open z1 -

n , 2 To fire Valve pen p $

P'89'S Suction 4 open 9 @

, Close HU-0-325 a

7 7 Close , s, STR L2 97 77-HU Raw Water llea -

4 From Raw Close 1-29t Water Reservoir >-- ,

HU-0-427 1 I A k n I Close F i' STR 98 H_ Package Boller F

H.U. Filter

/ ggj.0-Blowdown Bypass

! 286 i FCV-436 u -

AfW y.l-297 Sealed PPI -l 21 Open j open - Valye yamz Mh g,

FCV-437 y gom AFW ,1 fire Water Tank to @kg PP 1-2 s AFW Pump Sirction .$ osL l-3 open -

l l

NUMBER EP OP-4B DIABLO CANYCN POWER PLANT UNIT NO(S) 1 AN'O 2 -

RSVISION 0 3 OATE 2/25/83 ~'

PAGE 18 CF 61 TITLE; LOSS OF ALL AC POWER APPEN0!X C LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED ACTION / EXPECTED RFSPCNSE FESF0NSE BOT CBTAINED

1. Check Energized All Vital' 4 KV 1. If all vital 4 KV busses are Busses: not energized and it is necessary to energize an additional 4 KV vital bus from one diesel generator GO TO Appendix H.

NOTE: Appendix H shall not be useo without the Plant Superintendent's permission,

a. Bus Voltage - NORMAL a. If voltage low or frequency-tnstable,~THEN exercise, caution in loading

b. Bus Frequency - STABLE

2. Verify the following equipment 2. Manually load equipment as loaded on Vital 4KV AC Bus: necessary.

a. 480 volt busses (120 volts indicated on 480 volt vital busses F, G, and H; VB-4).

b. Battery chargers

c. Emergency lignting

d. Comunications

e. Dispat-h personnal to verify instrument AC inverters and busses return to service as per OP J-10. -

\

DC0137 1811 -

i .

DIABLO CANYON POWER PLANT UNIT NO(S) l'AND 2 [ONB

(.. DATE 2/25/83 19 OF 61 PAGE

( ring: LOSS OF ALL AC POWER

, APPENDIX C ACTION /EXPECTB ESPWSE RESPONSE NOT OBTAlh8

, f. AS it becomes necessary to load a piece of vital .

equipment that was defeated in step 1.g. of .

the main procedure, contact the operator at the vital 4KV switchgear to close the -

respective DC control power .

switch.

3. Return Auxiliary Salt Water System to service in accordance with OP E-5, if necessary.

4. Check RCP Sea! Isolation Status:

\

'~' a. Verify seal injection a .- If valves open, THEN check outside containment centrifugal charging pump isolation valves closed status:

(CVCS 8382 A & B Closed).

1) Jf pump running, THEN go to Step 5.

2) If pump NOT running, TiiEN manually close seal injection outside containment isolation valves.

(a) MOV-8100 CLOSED (b) CVCS-8382 A&B, CLOSED

~ ~ 3) 00 NOT startcharging.

centrifugal a pump during subsecuent recover steps until these valves are closed, UNLESS

( centrifugal charging l

pump essential for recover.

(,

w ._

DC0137 191I

1 AND 2 ' NUMBER EP OP-48 _,

CIABLO CANYON POWER Pt. ANT UNIT NO(S) g REVISION0 DATE 2/25/83 /

PAGE 20 op 61 mLE: LOSS OF ALL AC POWER

~

APPENDIX C ACTION / EXPECTED RESF0NSE RESPCNSE NOT OBTAIED

b. RCP thermal barrier CCW b. If valve is open, THEN return outside the . Trieck CCW pump status:

containment isolation valve closed, (FCV-357 CLOSED) 1) IF a.CCW pump is - "~

Enning, THEN go'to

. Step 5.

2) If NO CCW pumps are THEN close EnEng, FCV-357,TiTCV-357

~

cannot be closed, THEN close FCV-750, CCW return inside

, containment isolation

. valve.

5.* Verify SI Injection Mode Is /&-

RequireE Y

a. RWST level - greater than a. If RWST level less than 33%

33% TFIEN:

1) Verify containment sump level greater than 40%.

2) Manually align valves to establish recirculation mode.

Refer to Appendix E.

3) Manually lead the following safeguards components on the available 4KV Vital AC Busses:

(a) CCW pump (b) RHR Pump DC0137 20!I .

9

t .

1 i

l l

1 l'AND 2 NUMBER EP OP-48 DIABLO CANYON POWER PLANT UMT NO(S)

REMSON O

/ DATE 2/25/83

\ PAGE 21 OF 61 I rnts: LOSS OF ALL AC POWER APPENDIX C ACTION / EXPECTED RESPONSE RESF0NSE NOT OBTAINED (1) If RHR Pump fails to start go to Appendix G (RHR Train Failure)

'(c) Centrifugal Charging Pump (d) SI Pump (e) Containment Fan Cooler Units

4) Go To Step 8.

6. Manually Align Valves to

, Establish Injection Mode:

, :l .

a. Refer to Table 1 of this Appendix for valve list with desired position.

7. Manually load the following -

safeguards components on the tvailable 4KV Vital AC Busses.

Establish Injection Mode:

a. Centrifugal Charging Pumps

b. SI Pumps

c. If RCS pressure is less tnan~390 psig. THEN load RHR Pumps.

d. CCW Pumps .

i

(__ .

[ OC0137 21II i

l I

1

g 1.AND 2* NuuBER EP OP aB DIABLO CANYON POWER PLANT UNIT NO(S)

REVIS10N O DATE 2/25/B3 m PAGE 22 op 61 j M LE: LOSS OF ALL AC POWER APPENDIX C ACTION / EXPECTED PESFONSE RESPCNSE NOT OBTAINED

e. Containment Fan Cooler Units

f. Vital Ventilation F'nsa r

CAUTION: IF RCS PRESSURE DROPS TO 390 PSIG, THE RHR PUMP MUST BE i i

MANUALLY LOADED ON THE 4KTVITAL AC BUS TO SUPPLY WATER TO THE RCS.

8. Check If the Motor Driven AFW Pump SHould Be Loaded On the 4KV Vital AC Bus:

. a. Check non-faulted steam a. If,f less than 33"., THEN:

generator narrow range -

levels - greater than 33*.. 1) Manually load the motor / : .-

driven pump on the 4KV '

Vital AC Bus.

2) Control AFW flow to maintain narrow range '

level at 33%.

3) Go to Step 9.

b. Return the motor-driven AFW pump to service.

9. Check If Containment Spray Pump Should Be Loaded On the ..

Available 4KV Vital Bus:

a. Check containment pressure a. If pressure has gone above --'

has stayed below 22 psig. Tl psig, THEN:

-1) Verify available containment fan coolers running.

OC0137 22II l

~*

6 ,

1 AND 2 P OP-48 DIA8LO CANYON POWER Pt. ANT UNIT NC(S

( ' cATE 2/25/83 PAGE 23 op 61 I

m LE: LOSS OF ALL AC POWER APPENDIX C ACTION /EXPECTE RESPCNSE RESPWSE NOT OBTAINED

2) Verify containment

, isolation phase B actuated.

3) Verify containment spray signal actuated.

4) Reset containment spray

, 5) Check containment pressure (a) If less than 22 -

Es ig,0R cecreasing, THEN return containment 1 spray to service N...

but do not actuate containment spray.

(b) E greater than 22,

, psig and increasing, THEN establish required valve alignment and manually load containment spray pump on the 4KV Vital Bus.

6) Go to Step 10.

b. Return the containment spray pump to service.

CAUTICN: ESTABLISH RCP SEAL COOLING WITH CAUT-ION, IN ORDER TO PREVENT POTENTIAL INTRODUCTION OF STEAM INTO THE CCW SYSTEM AND THERMAL SHOCX TO THE RCP.

10. Establish RCP Seal Cooling, if necessarf. ._

OC0137 2311

, . - - - - , , - - - - , , , - - ----,--.---,--g

- - . , -- -,r-- - -- - , ,

a a 1'AND 2* N M ER WO otAsto CANYON POWER PLANT UNIT NO(S) __

DATE 2/25/83 ~,,

PAGE 24cp 51 m LE: LOSS OF ALL AC POWER APPENDIX C ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

a. Establish CCW flow to RCP thermal barriers: ,

1) Establish ,

communications between the Control Room and at FCV-357. -

2) Monitor RCP lower bearing temperature (TE 152,153,154,155).

3)

Manually FCV-357 (crack locally).open

4) Monitor ficw on FI-91 (PNL 185 locally at (.

FCV-357). Q

5) Increase ficw to the thermal barrier slowly reducing icwer bearing temperature (TE 152, 153, 154, 155) at a maximum rate of 1*F per min. until full thermal barrier flow is returned to normal.

b. Establish seal injection ficw to RCP's:

1) Wait until seal leak off water temperature (TE-148,146,132,and 125) has decreased to 23$'F. - -

2) Verify that Chem' cal and Volume Centrol System is available as n

DC0137 24!I .

/ .

otAst.O CANYON POWER PLANT UNIT NO(S) I'AND 2 NUMBER EP OP-48 REVISION 0 2/25/83

(' DATE prog 25 op 61 mLE. LOSS OF ALL AC POWER APPENDIX C

~

ACTION / EXPECT 8 RESKf6E RESPONSE f0T OBTAIh8

~

per OP B-1A:i, CVCS -

Prepare For Service with the exception of CVCS-8382 A&B closed. .

3) Crack open CVCS-8382 A or 8 as applicable. -

4) Carefully reestablish injection flow, reducing the lower bearing water temperature at a maximum rate of l'F per minute until the lower bearing water temperature is below 225'F.

5) Verify adequate seal

- leak off.

CAljTICN: 00 NOT START ANY RCP PRIOR TO A COMPLETE STATUS EVALUATION, IifiLI5T RCP START IS REQUIRED TO COMBAT AN INADEQUATE CORE GUCTliG SITUATION.

11. GO TO EP OP-0. Reactor Trip with Safety Injection, Subsequent Operator Actions ,

(Part A). '

l

(- ..

DC0137 251I

otAal.O cANYCN POWER PLANT UNIT NO(S) l'AND 2' fS CN -m oATE 2/25/83

PAGE 26 CF 61 TITLE: LOSS OF ALL AC POWER s

APPENDIX C TABLE 1 ,

'SI VALVE ALIGNMENT FOR INJECTION MODE

1. RWST TO CHG PPS (MOV-8805 A & B) ,

OPEN

2. VCT TO CHG PPS (LCV-112 B & C) CLOSED

3. NORMAL CHG LINE ISO (MOV-8107) CLOSED 4 NORMAL CHG LINE ISO (MOV-8108) CLOSED

5. BIT INLETS . (MOV-8803 A & B) OPEN

6. BIT OUTLETS (MOV-8801 A & B) OPEN

7. BIT TO BAST RECIRC ISO (SI-8870 A & B) CLOSED

8. BIT TO BAST RECIRC ISO (SI-8911) CLOSED

9. CHG PPS MINI FLOW (MOV-8105) CLOSED

. 10. CHG PPS MINI FLOW (MOV-8106) CLOSED

11. CCW HOR B MAX FLOW (FCV-360) OPEN

12. CCW HOR A MAX FLOW (ECV-366) OPEN

13. RWST TO SI PPS (MOV-8976) OPEN

14. SI PPS SUCTION (MOV-8923 A & B) OPEN

15. SI PPS TO COL,0 LEGS (MOV-8835) OPEN

16. SI PPS TO HOT LEGS (MOV-8802 A & B) CLOSED

17. SI PPS XTIE (MOV-8821 A & B) OPEN

18. SI PPS TO RWST (MOV-8'974 A & B) ~ OPEN

19. SI PPS XTIE TO ~

CHG PP SUCTION (MOV-8807 A & B) CLOSED

20. RWST TO RHR P'PS (MOV-8980) - -OPEN n

0C0137 26II ,

l i

OlABLO CANYON POWER PLANT UNIT NO(ST l'AND 2 hPOP-4B DATE 2/25/83

( PAGE 27 CF 61 TITLE: LOSS OF ALL AC POWER APPENDIX C TABLE 1 i SI VALVE ALIGNMENT FOR INJECTION MODE (Continued)

21. RHR PPS SUCTION (MOV-8700 A & B) ,

OPEN

22. SPRAY ADD TK OUT (MOV-8992) OPEN 23,. RHR HX 1 OUT (MOV-8992) OPEN

24. RHR HX 2 OUT (HCV-638) OPEN

25. RHR HX 1 & 2 TO COLD LEG (MOV-8809 A & B) OPEN

26. RHR HX 1 & 2 TO CHG PPS (MOV-8804 A & B) CLOSED

27. RHR HX 1 & 2 TO CONT SPRAY (MOV-9003 A & B) CLOSED U, 28. CNT SUMP TO RHR (MOV-8982 A & B) ,

CLOSED

~

29. RHR INJ TO LOOP 1 & 2 HOT LEG (MOV-8703) CLOSED

30. LOOP 4 TO RHR SUCTION (MOV-8701 & 8702) CLOSED e W k

.~

DC0137 27II

l NU DIABLO CANYON POWER PLANT UNIT NO(S) 1 At D 2 p )

ON '

DATE 2/25/83

, PAGE 2BOF 61 Tm LOSS OF ALL AC POWER .

APPENDIX D LOSSOFELECTRICALPOWERRECOVERYWITHOUT5IREQUIRED ACTION /DPECiG RESPONSE. RESPONSE NOT OBTAINED

~

1. CHECK Energized All Vital 4KV 1. If all vital 4KV busses are not AC Busses: energized and it is necessary to energize an additional 4KV but from one diesel generator GO .0 Appendix H.

NOTE: Appendix H shall not be used without the Plant Superintendent's permission.

a. Bus Voltage - NORMAL a. If Voltage Low or Frequency Vnstable, THEN exercise caution in loading equipment on the bus.

b. Bus Frequency - STABLE -

2. Verify The Following Equipment 2. Manually load equipment as

- . Loaded On Vital 4KV AC Busses: necessary.

a. 480 volt busses (120 volts indicated on 480 volt vital .

busses F, G, and H; VB-4)

b. Battery Chargers

c. Emergency lighting i

d. Comunications

e. Dispatch personnel to verify instrument AC inverters and busses returned te service as per -

OP J-10.

NOE: If a piece of vital equipment was defeated in step 1.g. of the ma Tri procedure, contact the operator at the Vital 4KV switchgear to close the respective CC control pcwer switch as it becomes necessary to load it on the 4KV bus. ~ -

s

. ./

~

OC0137 2SII

f ,

DIABLO CANYON POWER PLANT UNIT NO(S) l'AND 2 N DATE h[OMB 2/25/83

( PAGE 290F 61

k. TITLE: LOSS OF ALL AC POWER ,

APPENDIX 0

)

ACTION / EXPECTED RESPONSE RESI G SE NOT OBTAINED ;

3. Return Auxiliary Salt Water System to Service. ,

4. Check RCP Seal Isolation '

Status:

a. Verify seal injection a. E valves open, THEN check outside containment centrifugal charging pump isolation valves closed status:

(CVCS-8382 A & B CLOSED).

1) g pump running, THEN go to Step 5.

2) If pump NOT running, THEN maniIiT1y close

- seal injection outside containment isolation

. valves.

(a) MOV-8100 CLOSED (b) CVCS-8382 A&B CLOSED

3) 00 NOT start a

- centrifugal charging pump during subsequent recovery steps until these valves are closed, UNLESS centrifugal charging pump is essential for recovery.

b. RCP ttarmal barrier CCW b. If valve is coen, THEN return outside containment. . W eck CCW pump status:

isolation valve closed (FCV-357 CLOSED)

1) If a CCW oump is Enning, THEN go to Step 5.

DC0137 29II

. f NW8ER EP 0P-4B DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O ,m DATE 2/25/83 ;

PAGE 300F g1

{- TU1E: LOSS OF ALL AC POWER l

APPENDIX 0 ACTION / EXPECTED RESPONSE -

RESPONSE NOT OBTAINED

2) If NO CCW pumps are

. runr.ing THEN Close FCV-357.- 17 FCV-357 cannot be closed-THEN close FCV-750, CCW return inside containment isolation valve.

5. Verify or Manually Load if

~

Necessary the Following Vital Equipment On the Available 4KV Vital Busses:

a. Verify valve alignment as a. If VCT sLction NOT applicable and load a avaTTable THEN establish centrifugal charging pump RWST suction. 4.

in accordance with OP B-1A i;'

CVCS - Prepare For Service.

1) Set VCT for Automatic

~

Makeup.

2) Set Baron Concentration for GREATER than RCP Baron concentration.

b. Verify valve alignment and load CCW pump as applicable in accordance with OP F-2 ~'

CCW - Make Available.

c. Load available containment fan cooler units as necessa ry.

d. Lead available vital -

ventilation equipment as necessa ry.

6. Verify Leaded or Manually Lead if Necessary Motor-Driven AFW - -

Pumas on Available 4XV Busses:

t CC0137 30II .

_,v--,- , , . - -

W N R DIAaLO CANYON POWER PLANT UNIT NCXS) ' l'AND 2 fPOP-48 DATE 2/25/83

(.7 TITLE- LOSS OF ALL AC POWER PAGE 310F 61

. APPENDIX D ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l

a. Check steam generator a. If narrow range is less Narrow Range levels greater ifian 33% THEN:

than 33%. -

1) Load a motor-driven AFW pump on the available 4KV vital bus.

2) Control AFW flow to maintain narrow range level at 33%.

3) Go to 4 tep 7.

b. Return each motor-driven .

AFW pump to service, if

,. necessary.

U 7. Return The Following Safeguards Pumps To Service, if necessary.

a. '.SI Pumps.

b. RHR Pumps.

c. Containment Spray Pumps.

CAUTION: ESTABLISH RCP SEAL COOLING WITH CAUTION, IN ORDER TO PREVENT POTENTIAL INTRODUCTION OF STEAM INTO THE CCW SYSTEM AND THERMAL SHOCK TO THE RCP,

~~

8. Establish RCP Seal Cooling, if necessary:

~

a. Establish CCW flow to RCP thermal barriers:

1) Establish ccmmunications between the control room and at FCV-357. - -

( '-

DC0137 311I

. n DIABLO CANYON POWER PLANT UNIT NO(S) 1.AND 2' g ghPOP-48 DATE 2/25/83 !

PAGE 320F 61 +-

TITLE: LOSS OF ALL AC POWER 1

APPENDIX 0 ACTION / EXPECTS PESPONSE RESFONSE NOT OBTAINED

2) Monitor RCP lower bearing temperature (TE 152, 153, 154, 155). ,

3) .

Manually FCV-357 (crackopen locally). . i

4) Monitor flow on FI-91 (PNL 185 locally at FCV-357)

5) Increase ficw to the thermal barrier slowly -

reducing lower bearing

- temperature (TE 152,

. 153,154,155)ata c maximum rate of 1*F per 9 minute until full thennal barrier flow is

~

returned to normal.

~

b. Establish Seal Injection Flow to RCP's:

1) Wait until seal leak off water temperature .

(TE-148, 146, 132, 125 )

has decreased to 235*F.

i 2) Verify that Chemical and Volume Control

System is available as oer OP 8-1A CVCS -

Prepare For Service with the exception of.

l CVCS-8382 A&B CLOSED. .

3) Crack open CVCS-8382 A&B as applicable.

l .

1 DC0137 32II ,

i .

NUMBER EP OP-48 DIABLO CANYCN POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 2/25/83 DATE

( PAGE 33 0F 61

(

TRLE: LOSS OF ALL AC POWER APPENDIX D ACTION /EXHCTED ESPONSE- ESPONSE NOT CBTAINED

4) Carefully reestablish injection flow, -

reducing the lower bearing water -

temperature at a maximum rate of 1*F per minute until the lower

bearing water temperature is below

- 225'F.

5) Verify adequate seal leak off.

-x CAUTION: DO NOT START ANY RCP PRIOR TO A COMPLETE STATUS EVALUATION,

UNLT5T RCP START IS REQUIRED TO COMBAT AN INADEQUATE CORE C00LlhG SITUATION.

9. Verify That Containment 9. If Actuated, THEN Reset Isolation Phase A Signal Has fontainment Isolation Phase A Not Been Activated. Signal.

10. Verify or Establish Charging:

a. Throttle charging line flow control valve to establish desired flow.

11. Verify or Establisn Stable Steam Generator Pressures:

O M

( .

DC0137 33II

)

NU E '

DIABLO CANYON POWER PLANT UNIT NO(S) 1 %ND 2

p ON -

DATE 2/25/83 PAGE 34 OF 61 s Tnts: LOSS OF ALL AC POWER APPENDIX 0 .

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

a. Set each steam generator i 10% dump controller to maintain existing steam generator pressure. ,

b. Return steam dump system to b. Maintain desired steam automatic steam pressure genera. tor pressure in

. control when support manual steam dump control.

Systems are available.

12. Check RCS Conditions.

a. RCS pressure - stable or a. If decreasing, THEN check increasing. NCS subcooling. I?

subcooling is less than 35'F on subcooling monitor (VB2),

THEN increase dumping steam "

to achieve 35'F subccoling.

b. RCS hot leg temperature - b. If increasing, THEN check stable or decreasing. ACS subcooling.- TT

- subcooling less tnan 35'F on subcooling monitor (VB2), THEN increase dumping steam to achieve 35'F subcooling.

13. Check Pressurizer Level:

a. Level - greater than 10% a. If less than 10%, THEN go To Appencix C~ Itep c.

~~

b. Level - greater than 17" b. Verify letdown isolation, Ij:_

NOT manually '

isolate

.- .~.

Tetdown.

c. Level - trending to 22% .

c. . Manually control charging to restore pressurizer level.

1 CC0137 34II ,

I l

l N E l DIABLO CANYON POWER r:. ANT UNIT NO(S)' 1.AND 2 O

OATE 2/25/83

( pau 35 op 61

! Ting. LOSS OF ALL AC POWER l

l

. APPENDIX D ACTION / EXPECTED RESPCNSE RESFONSE NOT OBTAINED

14. Check Steam Generator Levels:

a. Level - IN NARROW RANGE a. Continue filling steam generators until level is in narrow range.

b. Throttle AFW flow to i maintain narrow range level -

at 33%.

. 1) Shutdown the turbine driven Auxiliary Feedwater pump at 33%

Narrow Range Steam Generator Level.

15. Check CST level: .

, )

a. CST level - greater than a. When CST level decreases to 55% less than 10% switch to alternate AFW water supply as follows:

1) Verify a level in the raw water storage reservoir; then open FCV-436 and FCV-437 (Reservoir supply to AFW pumps). Allow the AFW pumps to run during

% -. the transfer. Monitor the AFW flow closely.

If AFW flow is lost, trip all 3 AFW pumos until the transfer is

~

complete, then restart the pumps.

2) If the raw water storage reservoir is not available, go to Appendix B (AFW Pump Suctiert Supply from

(

DC0137 351I '- -

e - - < , ,. - - - - . - ,n., n .

. 2 l

I NUMBER P OP-48 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2'

, REVISION .'

og73 2/25/83 --

PAGE 30 CF 61 ints: LOSS OF ALL AC POWER APPENDIX 0 ACTICfUEXPECTED RESPCNSE RESPONSE NOT CBTAINED Fire Water Tank Procedure). Allow the AFW pumps to run during the transfer. Monitor the AFW flow closely.

If AFW flow is lost, trip all 3 AFW pumps unit the transfer is complete, then restart the pumps.

NOTE: When the CST Lo Lo level alarm occurs, the operator has approximately 20 minutes to perform q Steps l'or 2 above. ; gj

16. Establish Pressurizer Level in Normal Operating Range.

a. Establish letdown.

b. Open letdown orifice isolation valves, as necessa ry,

c. Place charging flow control valve controller in automatic.

17. Establish Stable RCP Pressure:

a. Manually load pressurizer heaters on the available 4KV vital bus as necessary. , ,.

btJTICN: ON NATURAL CIRCULATION RTO BYPASS TE4PERATURES AND ASSOCIATED INTERLOCKS WILL BE INACCURATE.

l l

DC0137 36II .

s .

l' AND 2 NUMBER P 0P-48 OtA8LO CANYON POWER PLANT UNIT NO(S) ,

REVISION DATE 2/25/83 37 OF 01

('

PAGE ints. LOSS OF ALL AC POWER APPENDIX D ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

18. Verify Natural Circulation F' rom 18. If na'tural circulation NOT Trended Values verified, THEN increase cumping

. steam.

a. RCS subcooling - Greater ,

than 35'F

b. Steam Pressure'- STABLE -

c. RCS hot leg temperature -

STABLE or SLOWLY DECREASING

d. Core exit TC's - STABLE or SLOWLY DECREASING

e. RCS cold leg temo - NEAR SATURATION TEMPERATURE FOR STEAM PRESSURE.

Q' i

19. Check RCS subcooling - greater 19. Establish 50*F Subcooling THAN 50*F

a. Increase RCS pressure

b. Dump steam

1) Limit RCS cooldown rate to less than 25'F/HR

2) Dump steam with steam generator 10% dumps l 20. Check Nuclear Instrumentation

a. Flux-Below 10 10 amps a. Proceed to step 21. When (P-6) flux decreases below

- 10 10 amps (P-6), THEN do l steps 20 b and c.

l b. Verify source range b. Manually re-energize source l detectors re-energized. range detectors.

l

(

OC0137 3711 -

a N

DIABLO CANYON POWEfl PLANT UNIT NO(S) 1 AN'O 2 - '

RE s 0

. DATE 2/25/83 -

PAGE 380F 61

' m LE: LOSS OF ALL AC POWER

~

APPENDIX 0 ACTION / EXPECTED RESPONSE- ESPONSE-NOT OBTAINED

c. Transfer nuclear recorders to source range scale.

21. Try to Restore Normal AC Power: .

a. From the 230KV Startup Power in accordance with -

OP J-3. ,

~

b. From the 500KV System in accordance with OP J-2.

c. If it appears that all sources of offsite power will be unavailable for a .

considerable length of time use Appendix I to energize . (],5 the 'non-vital 480 Volt U; busses with an operable - - - - - - -

diesel generator. This i step should not be taken f

'~

without the approval of the l Plant Superintendent. I

22. When normal offsite power is 22. If normal offsite power is not )

restored from either the 230 or restored and the plant must be !

500 KV system, start the cooled down. Refer to Appendix ;

following equipment in A of EP OP 4A.

accordance with the applicable l operating procedure.

a. Ai r. compressors.

b. Control rod drive shroud coolers.

c. Service cooling water -

pumps.

l

d. Reactor coolant pumps.

\ l l

CC0137 38II .

l l

e

N BER OtABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND.2 p N QATE 2/25/83

(, PAGE 39 OF 61

' m LE. LCSS OF ALL AC POWER APPENDIX D ACTION / EXPECTED ESPCNSE ESPONSE NOT OBTAIED

e. Place the main turbine on the turning gear.

f. If plant is to be cooled down: .

1) And a RCP is started, go to OP L-5 Plant Cooldown From Minimum Load to Cold Shutdbwn.

2) IF RCP's cannot be ,

started go to EP OP-23 Natural Circulating.

=

r

(

CCCl37 3911

. , , . , _ , , _ y-..- --,y.

-,7 .. - , , , - . . . _ , _ . _ . . _ . _ .

1.AND 2, NUMBER EP OP-48 DIABLO CANYON POWER PLANT UNIT NO(S) m REVISION O DATE 2/25/83 -'

PAGE 4(DF 61 Tnis: LOSS OF ALL AC POWER I

APPENDIX E

~

LOCAL INJECTION / RECIRCULATION CHANGE 0VER PROCEDURE ACTION / EXPECTED RESPCNSE RESFONSE NOT OBTAINED

1. All steps listed below'must be 1. If a valve fails to respond or carried out expeditiously in a to complete ,its demanded precise orderly sequence. Do operation, postpone any not interrupt the operation corrective action until the i until all actions are subsequent operational steps completed, are performed.

2. If all 3 diesel generator are 2. If any diesel generator is not running and supplying the 4KV operating such that its vital Vital Busses continue with bus is dead go to Appendix F.

these instructions as written.

3. At the vital 480 volt load centers F and H, close the breakers for the following .

valves if not already f performeE. ~

a. 8980 RHR pumps supply from

. RWST 52-1F-31.

b. 8976 SI pump supply from RWST 52-1H-20.

4 Reset SI, Phase E isolation and containment spray signals if, not, al ready reset.

5. If offsite power is available, shutdown all 3 diesel generators and leave them in Auto if this has not been perforEec.

6. Close (cut in) the series . -

contactors for the following valves from the toggle switches in the control room if not

~~~

already CUT IN.

s CC0137 401I ,

i ,

DIABLO CANYCN POWER PtANT UNIT NO(S) l'AND 2 hPCP-4B oAls 2/25/83

( PAGE 410F 61

( Tirtz LOSS OF ALL AC POWER l

l l

APPENDIX E ACTION / EXPECTED RESPONSE RESPONSE F0T OBTAINED l

a. 8809 A & B RHR pumps injection to cold legs.

b. 8974 A & B SI pumps recirculation. -

c. 8982 A & B RHR pumps ,

. suction from sump.

7. Close the two RHR heat exchanger outlet crosstie valves (8716A & B).

8. Close the No. 2 RHR pump nomal suc% ion valve (87008).

9. Open the No. 2 RHR pump suction valve from the containment recirculation p' ump (89828).

10. Open the component cooling water outlet valve from No. 2 RHR heat excharger (FCV-364).

11. Close the safety injection pump recirculation valves ,

(8974A & B).

l 12. Open the safety injection pump l suction from RHR pump No. 2 i

(88048).

13. Close the safety injection pumps nomal suction valve (8976) from the RWST.

14 Open the alternate suction valves for the centrifugal charging pumps 8807A & B).

15. Close the No. 1 RNR pump normal suction valve (8700A),

i . _

DC0137 41II

~

, CY ---

r e

i NUMBER EP OP-4B ,

OIABl.O CANYON POWER PLANT UNIT NO(S) 1Ar[02 REVISION 0 DATE 2/25/83 -' i PAGE 42 OF 61 {

rats. LOSS OF ALL AC POWER i APPENDIX E ACTION / EXPECTED RESPONSE' ESPONSE'NOT OBTAINED

16. Open the No. 1 RHR pump suction valve from the containment recirculation sump (8982A). .

17. Check the level in the recirculation sump again for ,

. adequate NPSH. !

. 18. Open the component cooling !

. water outlet valve from No. 1 RHR heat exchanger (FCV-365). ,

19. Open the centrifugal charging-pumps alternate suction valve ~

from RHR pump No. 1 (8804A).

20. Close the charging pumps normal 'l'-

suction valves from the RWST (8805A & B).

. 21. Close the RHR pumps normal suction supply valve from the RWST (8980).

22. If either containment sump to RHR suction valve failed to open (valves 8982A or 3) or either RHR train to centrifugal charging pumps or SI pumps s . . ,

suction valves 8804A or B failed to open, go to Appendix G (RHR Train Failure).

23. Return to Appendix C "Resps,se Not Obtained" column, step 5.a.3). . .

d s

OC0137 42I1 '-

Y a e e N R otAsto CANYON POWER PLANT UNIT NC(S) 1 AND 2 fPOP-48

/ cATE 2/25/83 RAGE 430F 61 Tnts: LOSS OF ALL AC POWER APPENDIX F LOCA INJECTION / RECIRCULATION CHANGE 0VER WITH ONE VITAL 4KV EMERGENCY BUS DEENERGIZED A. 4KV Bus H Deenergized .

1. At the vital 480 volt .

load centers F close the breakers for the following valves if not already -

pe rformed.

a. 8980 RHR pumps supply from RWST 52-1F-31.

2. Reset SI, Phase B isolation and containment spray signals jf,notalreadyreset.

3. Close (cut in) the series contactors for the following valves from the toggle switches in the control room if ---

- not already CUT Ifl. ,

a. 8809 A & B RHR pumps injection to cold legs. ,

b. 8974 A & B SI pumps recirculation.

c. 8982 A & B RHR pumps suction from sump.

4. Close the two RHR heat exchanger outlet crosstie valves (8716A & B). , __ ..__

5. Close the safety injection pump -

recirculation valves (8974A & B).

6 "e

DC0137 43II

a '

s a N R P otAato CANYON POWER Pt. ANT UNIT NO(S) 1*AND 2 p N OATE 2/25/83 440F 61 Q'

PAGE _/

TITLE: LOSS OF ALL AC POWER ,

., APPENDIX F

6. Open the alternate suction valves for the centrifugal .

charging pumps (8807A & B).

7. Close the No.1 RHR pump suction valve from the containc.ent recirculation sump .

, (8982A).

8. Open the No. 1 RHR pump suction -

valve from the containment i recirculation sump (8982A).

~

9. Check the level in the recirculation sump again for adequate NPSH.

10. Open the component cooling water outlet valve from No.1

RHR heat exenanger (FCV-365). th y.

11. Open the centrifugal charging pumps alternate suction valve from RHR pump No. 1 (8804A).

12. Close the charging pumps normal suction valves from the RWST (8805A & B).

i

13. 'Close the RHR pumps normal suction supply valve from the RWST (8980).

14 Manually close the safety injection pumps normal suction valve (8976) from the RWST.

i

15. Verify the cold leg recirculation flow path as follows: -

I

.DC0137 a111 l

,e mr - -- -

r ,

CIABLO CANYCN POWER PLANT UNIT NO(S)

i AND 2 jPOP-48 DATE

(, p,g 2/ /8 TITLE: LOSS OF ALL AC POWER APPENDIX F

a. RHR pump 1 from containment -

sump to cold legs 1 and 2, SI pump 1 from RHR pump I to all cold legs, charging pumps 1 and 2 from RHR pump 1 to all cold legs via the .

BIT.

NOTE: Throttle HCV-638 to -

provide adequate suction for the SI and charging

. pumps (approximately 20 psig above containment pressure while maintaining RHR pump motor current less than 57.5 amps).

16. Return to Appendix C " Response Not Obtained" column step u 5.a.3). .

B. 4KV Bus G Deenergized

1. At the vital 480 volt load centers F and H, close the breakers for the following valves jf, not already performeo,

a. 8980 RHR pumos supply from RWST 52-1F-31.

b. 8976 SI pump supply from RWST 52-lH-20.

2. Reset SI, Phase B isolation and containment spray signals if,f - -

. not already reset.

3. Close (cut in) the series

! contactors for the following t valves from the toggle switches I

in the control room if not

~

already CUT IN.

OC0137 45II l

. .- n l

l otAs!.O CANYON POWER Pt. ANT UNIT NO(S) 14ND 2 RE CN DATE 2/25/83 PAGE 4pF g1 ./

TITLE: LOSS OF ALL AC POWER

4. l l

APPENDIX F l l

a. 8809 A & B RHR pamps injection to c61d legs. ~ )

l

b. 8974 A & B SI pumps recirculation.

l 1

c. 8982 A & B RHR pumps

suction from sump. ]

4. Check that the containment '

recirculation sump level l

ll indicators read at least 40% to

, provide adequate NP5H to the

,. RHR pumps.

l

5. Close the two RHR heat l exchanger outlet crosstie

valves (8716A & B). ..

l

! 6. Close the No. 2 RHR pump normal ,

suction valve (87008).

i l 7. Open the No. 2 RHR pump suction I l

. valve from the containment i

( recirculation sump (89828).

8. Open the component cooling

! water outlet valve from No. 2 !

l RHR heat exchanger (FCV-364).

l

9. Close the safety injection pumo recirculation valves (8974A & 8).

10. Open the safety injection pump suction from RHR pump No. 2 l (88048).

11. Close the safety injection , ,

pumps normal suction valve (8976) from the RWST.

-0C0137 46II l

a ,

a s R P OP-4B

. DIABLO CANYON POWER PLANT UNIT NO(S)

1*AND 2 DATE 2/25/83 ANF 61

((

PAGE TITLE. LOSS OF ALL AC POWER APPENDIX F

12. Open the alternate suction valves for the centrifugal ~

charging pumps (8807A & B).

13. Close. the chargin'g pumps normal suction valves from the RWST '

(8805A & B).

14. Close the RHR pumps normal .

suction supply valve from the RWST (8980).

15. Verify the cold leg recirculation flow path as follows:

a. RHR pump 2 from containment sump to cold legs 3 and 4,

SI pumps 1 and 2 from RHR s," pump 2 to all cold legs, charging pump 1 from RHR pump 2 to all cold legs via the BIT.

NOTE: Throttle HCV-637 to prcvide adequate suction for the SI and charging pumps (approximately 20 psig above containment pressure while maintaining RHR pump motor current less than 57.5 smps).

16. Return to Appendix C " Response Not Obtained" column step 5.a.3).

C. 4KV Bus F Deenergized . .

1. At the vital 480 volt load centers F and H, close the breakers for the following valves if, not already l cerfonned.

( .

(,

.~

DC0137 471I l

. G

~

DIABLO CANYCN POWER PLANT UNIT NC(S) 1 AND 2* NE CN DATE '~'

PAGE 2/2p/83 4f 61 ,,,

TITLE: LOSS OF ALL AC POWER

, APPENDIX F

a. 8976 SI pump supply from RWST 52-1H-20.. .. .

2. Reset SI, Phase B isolation and containment spray signals E g already reset.

3. Close (cut in) the series contactors for the following valves from the toggle switches .

in the control room if not

~

already CUT IN.

~

a. 8809 A & B RHR pumps injection to cold legs.

b. 8974 A & B SI pumps reirculation,

c. 8982 A & B RHR pumps .:D

. suction from sump, n

4. Close the two RHR heat exchangar outlet crosstie l

valves (8716A & B).

5. Close the No. 2 RHR pump normal

suction valve (87008).

( 6. Open the No. 2 RHR puces I suction valve from the I containment recirculation sump i (89828).

t .

7. Open the component cooling I water outlet valve from No. 2 l RHR heat exchanger (FCV-364). ,

8. Close the safety injection pump recirculation valves - -

(8974A & B).

i i

CC0137 a811

o .

N OtA8LO CANYON POWER PW(T UNIT WS) 1 AND 2 fPOP-4B

( DATE 2/25/83

-( PAGE 490F 61 ,

TITts: LOSS OF ALL AC POWER APPENDIX F

9. Open the safety injection pump -

suction from RHR pump to No. 2 (88048).

10. Close the safety injection pumps normal suction valve -

(8976) from the RWST.

~

. 11. Open the alternate suction valves for the centrifugal charging pumps (8807A & B).

12. Close the No. 1 RHR pump normal suction valve (8700A).

13. Open the No. 1 RHR pumps suction valve from the containment recirculation sump (8982A).

14 Check the level in the recirculation sump again for adequate NPSH.

15. Open the component cooling water outlet valve from No.1 RHR heat exchanger (FCV-365).

16. Open the centrifugal charging pumps alternate suction valve from RHR pump No. 1 (8804A).

17. Manually close the RHR pumos normal suction suppl valve from the RWST (8980)y .

i

18. Verify cold leg recirculation .

flow path as follows:

a. RHR pump No. 2 from containment sump to cold legs 3 and 4 and to SI pump No. 2.

(

DC0137 4911

. 9 DIABLO CANYON POWER PLANT UNIT NC(S) 1*AND 2* R S ON ' h DATE 2/25/83 >

PAGE 500F 61 TITLE: LOSS OF ALL AC POWER

. APPENDIX F

b. SI pump No. 2 from RHR No. .

2 to all cold legs.

c. RHR pump No.1.from containment sump to cold leg 1 and 2 and to No. 2 .

centrifugal charging pump.

d. Centrifugal charging pump -

No. 2 from RHR Pump No. 2 to all cold legs via the

BIT.

NOTE: Throttle HCV-638 %nd F to provide adequate suction for the SI and i charging pump (approximately 20 psig above containment pressure .

I while maintaining RHR pump s motor current less than 57.5 amps).

19. Return to Appendix C " Response Not Obtained" column, step 5.a.3).

e e O O DC0137 50!I .

-g- - , - , - --+ n , ,

o .

e e I

OtA8LO CANYON POWER PLANT UNIT NO(S) . 1.AND 2 NhfPOP-4B DATE PAGE 2/g5/83

( 51 61 i Tnts: LOSS OF ALL AC POWER

. APPENDIX G RHR TRAIN / COMPONENT FAILURE A. FAILURE IN RHR TRAIN NO. 2

1. If RHR pump No. 2 failed containment sump to RHR valve 8982B or RHR pump -

No. 2 to SI suction valve 88048 failed to open proceed with steps a.

to d. to provided charging and SI ~

pump suction from RHR pump No. 1.

. a. Verify RHR pump No. I crosstie valves to SI pump suction valve 88043.

b. Close or verify closed Train No.

2 to SI pump suction valve 8804B.

c. Throttle HCV 638 to ensure adequate suction for the SI and centrifugal charging pumps

- (approximately 20 psi containment pressure)gwhile above maintaining RHR pump motor current less than 57.5 amps.

d. Return to Appendix C, " Response Not Obtainec" column, step 5.a.3) te the step that was next to perform.

(

OC0137 51II '- I

. . m

. NU R P Op 4B DiAsto CANYON FCWER Pt. ANT UNIT NC(S) 1'AND 2 DATE 2/25/83 PAGE ggCF gi .,-

ints: LOSS OF ALL AC p0WER APPENDIX G

. B. FAILURE IN RHR TRAIN NO. 1 ACTION

1. If RHR pump No. 1 failed, containment sump to RHR valve 8982A -

or RHR pump No. 1 to charging pumps suction valve 8804A failed to open, ~

proceed with steps a. to d. to provide charging and SI pump suction from RHR pump No. 2.

a. Verify RHR pump No. 2 crosstie valves to SI pump suction 8807A or B open.

b. Close or verify closed Train No.

I to SI pump suction valve 8804A. .

(.

c., Throttle HCV 637 to ensure adequate suction for the SI and centrifugal charging pumps (approximately 20 psi containment pressure)g above while maintaining RHR pump motor current less than 57.5 amps.

d. Return to Appendix C " Response Not Obtained" column, step 5.a.3) to tne step that was next to perform.

)

1 1

OC0137 52II

6 . ,

NUMBER EP OP-4B DIABLO CANYCN POWER PLANT UNIT NO{S) 1 A50 2 REVISON O DATE 2/25/83

( ,

PAGE 530F 61 ints. LOSS OF ALL AC POWER APPENDIX H ENERGIZING VITAL 4KV BUSSES WITH DIESEL GENERATOR SCOPE The purpose of this aspendix* procedure is to make available a selected vital 4KV bus in the event its diesel generator is inoperable. This is accomplished by energizing the bus from an operable diesel generator. Since this is an extremely unusual situation and since we are cross connecting safety related trains, this procedure will only be used when no other alternative means of power is available and ONLY with the Plant Superintendent's permission.

DISCUSSION This procedure deals with the situation of the 4KV F vital bus being inoperable due to the 13 swing diesel generator being committed to the other Unit and either 11 or 12 diesel generator is inoperable. The procedure shall address energizing the 4KV F vital bus or another de-energized vital bus, G or H depending on the second inoperable diesel generator. This procedure is written in the Unit 1 perspective i.e., all bus and breaker number use Unit 1 designators.

The following is a list of the minimum number of essential components required for plant cooldown with NC safety injection.

a. ' 1 Centrifugal Charging Pump - 580KW

b. 1 Component Cooling Water Pump - 323KW

c. 1 Auxiliary Saltwater Pump. - 340KW

d. 3 Containment Fan Coolers - 660KW

e. 1 Auxiliary Feedwater Pump - 429KW

f. 1 Pressurizer Heater Group - 485KW

g. 2 480V Motor Control Centers .

- 1033KW (MAX)

DC0137 53II

, o e .

otAsto cANYCN PCWER PLANT UNIT NO(S) 1 AND 2 N CN DATE 2/25/83 d PAGE 54 CF 61 Tnis: LOSS OF ALL AC POWER APPENDIX H As a general guideline, in this situ'ation of trying to cooldown a unit on i diesel generator the Shift Foreman should attempt to.only operate a centrifugal charging pump, component cooling water pump and the 480V motor control centers on a continuous basis. He should attempt to cross connect with the other unit auxiliary salt water system when possible if there is more power available. He should use the turbine driven auxiliary feedwater pump as much as possible and only operate ,

the motor driven auxiliary feedwater pump, the containment fan coolers

. and the pressurizer neaters intermittently to maintain the plants critical parameters within the desired operating band.

. PROCEDURE

1. Cutout the AUTO Transfer FCO's for 4KV busses and 12KV busses.

2. Depress all AUTO Transfer Reset Push Buttons, g: The Auto Transfer Reset will NOT reset and tne BLUE light will NOT ce-energize for the F bus iT the 13 diesel generators is 7:[

operatiiig on the other Unit.

3. This step is only used to energtze the 4KV F vital bus when the

. 13 diesel generator is operating on the othe,r unit.

a. Dispatch an Operator to the 4KV Bus F Switchgear Cubicle 7, to overvoltage relay 59HFG1/59HFG2

1) Remove the cover

2) Pull down on the 2 " RED" handled switches (Terminal 5 and 10).

b. THEN at the Main Control Board, depress the Auto Transfer Reset Push Button for the 4KV F vital bus. Notice the

" BLUE" light goes "OUT".

c. The Operator at the 4KV Bus F Switengear may now return the 2 " RED" handled switches to .their norma.1 position and replace the cover.

4 OPEN or verify OPEN all vital bus 4KV auxiliary feeder breakers, 52-HH-13, 52-HG-13 and 52-HF-13.

1 DC0137 541I O

o .

N n P OP-4B OtASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2

( DATE 2/25/83 j' .

PAGE 55CF 61 TITLE: LOSS OF ALL AC POWER APPENDIX H

5. OPEN or verify OPEN all vital' bus' 4KV startup feeder breakers, 52-HH-14, 52-HG-14 and 52-HF-14.

6. OPEN or verify OPEN startup feeder breaker to the vital busses F, G and H, 52-HG-15. ,

7. Cut in the FC0 to place all Diesel Generator Protection in service for the operating Diesel Generator. .

S. OPEN or verify OPEN the 4KV to 480V bus feeder breaker.

a. If bus F is to be re-energized OPEN 52-HF-10.

b. If bus G is to be re-energized OPEN 52-HG-10. *

c. If bus H is to be re-energized OPEN 52-HH-10. .

9. CLOSE the 4KV startup feeder breaker for the bus that will be supplying power to the inoperable bus.-

a. If diesel generator 11 is operating CLOSE 52-HH-7.

~

b. If diesel generator 12 is operating CLOSE 52-HG-5.

EAlfTION: IF THE DIESEL GENERATOR APPEARS UNSTABLE DURING THE ERFORMANCE OF STEP 10 OR AT ANY TIME BEYOND THIS POINT IN THE ROCEDURE IMMEDIATELY OPEN STARTUP FEEDER BREAKER FOR THE INOPERABLE US TO SEPARATE THE DIESEL FROM THE INOPERABLE BUS.

10. CLOSE the 4KV startup. feeder breaker for the inoperable bus.

a. If bus F is to be re-energized CLOSE 52-HF-14.

b. If bus G is to be re-energized CLOSE 52-HG-14 l . .

c. If bus H is to be re-energized CLOSE 52-HH-14.

CAllTION: STATION AN OPERATOR AT THE VB4 TO MONITOR THE DIESEL GENERATOR. IF AN SI SHOULD OCCUR IMMEDIATELY OPEN THE 4KV STARTUP FEEPER BREAKER FOR THE BUS WITH THE OPERABLE DIESEL GENERATOR TO PREVENT OVERLOADING THE OPERABLE DIESEL GENERATOR WHEN THE SI LtADS SEQUENCE ON THE BUS.

I DC0137 55II

OP-4B DiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 OATE 2/25/83 #..

PAGE 56 oF 61 rnts: LOSS OF ALL AC POWER APPENDIX H

11. CLOSE the 480V motor control center feeder breaker.

NOTE: Evaluate the load on the diesel generator prior to energizing each additional load to ensure its reserve capacity is not exceeded. As each additional load is added if the diesel overloads it may only be necessary to trip the last lead adced rather than tripping the entire bus.

a. If bus F was re-energized CLOSE 52-HF-10. .

b. If bus G was re-energized CLOSE 52-HG-10, 4

c. If bus H was re-energized CLOSE 52-HH-10.

12. START additional equipment necessa y to restore the minimum systems needed for plant cooldown.

O m..~

\

DC0137 56II .

v ,

OP-4B DIABLO CANYON POWER PLANT UNIT NO(S) 1Ar[02

( '

DATE 2/25/83 PAGE 57 cF 61

-(

Tins; LOSS OF ALL AC POWER

~

. s APPENDIX I ENERGIZING NON-VITAL 480V BUSSES WITH OIESEL GENERATOR SCOPE The purpose of this procedure is to make available selected non-vital systems to lessen the restrictions on recovery until normal 0FF-SITE power is restored. This procedure deals with the situation when both Units are down and the some total of all power sources are the !

combined 5 emergency diesel generators. In this case ~one unit will be deprived of the swing diesel generator. The selected non-vital systems which are desired to be returned to service are plant

- instrument air, service cooling water, CRDM shroud cooler fans, Turbine Generator lift pump and turning gear drive, 230KV and 500KV switchyard.

DISCUSSION This procedure deals with. both units since the plant air compressors are powered from either unit and are normally cross connected such

~

that it is coninon to both units. Therefore, the unit which the swing diesel 13 is conunitted will be responsible .for re-energizing the compressed air system. Unit 1 is responsible to re-energize the 230 and 500KV switchyard. Any additional loading will be done by Shift Foreman evaluation of remaining diesel generators capacity. This procedure is written in the Unit 1 perspective, i.e., all bus and breaker numbers use Unit I designators.

The following is a list of the minimum number of loads required for plant cooldown.

a. 1 Centrifugal Charging - 580KW x b. 1 Component Cooling Water - 323KW

c. 1 Auxiliary Salt Water - 340KW

d. 3 Containment Fan Coolers - 660KW.

e. 1 Auxiliary Feedwater - 429KW

f. 1 Pressurizer Heater Group - 485KW

g. 2 480V Motor Control Centers - 1033KW (MAX)

/ 0C0137 57II

, N NUM8 P OP-48 otAsto CANYON PCWER Pt. ANT UNIT NO(S) 1 AND 2 DATE 2/25/83 J PAGE 58 CF 61 ,

riTte LOSS OF ALL AC POWER APPENDIX I

~

PROCEDURE

1. . Determine which diesel ge,nerator will be used as source for the .

non-vital busses.

a. On the Unit which has the 13 swing diesel generator available, transfer the maximum number of essential leads to the 4KV bus F and remove all non-essential leads from bus G.

b. On the Unit which does not have the 13 swing diesel generator available, transfer the maximum number essential loads to bus G and remove all non-essential loads from bus H.

2. Cut out the Auto Transfer FCO's for all 4KV busses and 12KV busses. .

3. Depress all Auto Transfer Reset Push Buttons. ,

'~

NOTE: The Auto Transfer Reset will NOT reset and the BLUE light will NOT de. energize for the F bus iT the 13 diesel generator is operating on the other unit.

4 OPEN or verify OPEN all vital bus 4KV auxiliary feeder breakers, 52-HH-13, 52-HG-13 and 52-HF-13.

5. OPEN or verify CPEN all vital bus 4KV startup feeder breakers, 52-HH-14, 52-HG-14 and 52-HF-14. .

6. OPEN or verify OPEN startup power to vital busses F, G, H, 52-HG-15.

7. OPEN or verify OPEN auxiliary feeder to 4KV busses 0 and E, 52-HE-2 and 52-HD-2.

8. OPEN or verify OPEN startup feeder to 4KV busses D and E, 52-HE-3 and 52-HC-14,

9. OPEN or verify OPEN startup transformer 12 feeder breaker 52-HD-14.

10. OPEN ALL 4KV feeder breakers to 480 volt busses on 4KV busses D and E. . _

DC0137 58II

NUMBER EP 0P-48 ciAsto CANYON POWER PLANT UNIT NO(S)

1 AND 2 REVIS3CN 0 DATE 2/25/83

( PAGE 59 CF 61

[ LG5" 0F ALL AC POWER Tn12.

APPENDIX I

11. Cut in the FC0 to place all Diesel Generator Protection in service for the Diesel Generator selected to power the non-vital busses.

12. Verify all Condensate / Booster pump stand-by switches are set in MANUAL.

13. Verify the Nash Vacuum pump is OFF and the No. 2 Heater Drip Pump is 0FF. .

14. CLOSE the startup feeder breaker to the vital bus.

a. If Diesel Generator 11 is the non-vital bus power source CLOSE 52-HH-14.

b. If Diesel Generator 12 is the non-vital bus pcwer source CLOSE 52-HG-14

c. If Diesel Generator 13 is the non-vital but power source CLOSE 52-HF-14.

~

CAUTION: IF THE DIESEL GENERATOR APPEARS UNSTABLE DURING THE PERFORMANCE OF STEP 15 OR AT ANY TIME BEYOND THIS POINT IN THE PROCEDURE, IMMEDIATELY OPEN 52-HG-15 TO SEPARATE THE DIESEL FROM THE NON-VITAL SYSTEM.

15. CLOSE startup power to vital busses F, G, H, 52-HG-15.

NOTE: There will be a short load syrge on the Diesel Generator as the startup transformer 12 is energized.

16. CLOSE startup feeder to 4KV bus 0, 52-HE-3.

17. CLOSE startup feeder to 4KV bus E, 52-HD-14

18. On the Unit which has the 13 swing diesel generator carrying the F vital bus energize the following 480V busses.

NOTE: Evaluate the load on the diesel generator prior to energizing each additional load to ensure its reserve cacacity is not exceeded. As each additional load is added if the diesel gener.ator overloads it may only be necessary to trip the last load added rather than tripping the entire bus. - -

t

~.

DC0137 5911

e '

Y i NUMBER EP OP-4B DIABLO CANYON POWER PLANT Uri!T NO(S) 1A002 REVISONO

-)

DATE 2/25/83 J

' PAGE 60 CF 61 ints. LOSS OF ALL AC. POWER

- APPENDIX I .

a. Energize non-vital bus 157 CLOSE 52-HD-6. -

b. Energize non-vital bus 110 CLOSE 52-HD-10.

19. Return the instrut.ent air system to service as per GP K-1.

20. Energize the 500KV switchyard CLOSE 5,2-HE-7.

t

a. Dispatch an Operator to the 500KV switchyard to verify i

, CLOSED or CLOSE the local 4KV bus feeder breaker in the 500KV switchyard.

~

b. Operator should also verify 480V bus is energized and 500KV switgpgear compressed air system is available.

c. Operator should verify 230KV yard 4KV bus is energized via the emergency tie cable and its compressed air system is available. , .

21. Additional 'oads such as CRDM shroud coolers, turbine generator lift pump and turning gear drive may be made available and their 480V busses energized at the discretion of the Shift Foreman, l .

dependent on diesel generator reserve capacity.

om see **

l l

DC0137 60!I -

e ,

O NLNBER P OP-4B DiAsLO CANYON POWER PLANT UNIT NO(S)

l' AND 2 DATE 2/25/83

(

PAGE 610F 61 F ints: 105S OF ALL AC POWER

, APPENDIX Z

.' EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS

1. When the emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:

a. Designate this event a Notification of Unusual Event.

Notify plant staff and response organizations. required for this classification by implementirig Emergency Procedure G-1 .

" Establishment of the On-Site Emergency Organizations" and l

,' Emergency Procedure G-3 " Notification of Off-Site Organization" in accordance with Emergency Procedure G-1

" Accident Classification and Emergency Plant Implementation.

~

b. Designate this event an Alert if all of the vital busses (F.

G and H) fail to be powered oy the applicable diesel generator (step 4). Notify plant staff and response organizations required *by EP G-2 and EP G-3 in accordance with EP G-1.

c. Designate this event a Site Area Emergency if AC power cannot be restored to any vital bus (F, G or H) by either Diesel Generators or off-site power within 15 minutes of the total loss. Notify plant staff and response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.

- m 6 m

(

DC0137 61II '-

e w , --- ,4- -- + - - ~ , , , -

e PGwE DIABLO CANYON POWER PLANT PROCEDURE ON-THE-SPOT CHANGE ZA%/((3" Rev, b*' *

(Jntt No. t 0 2O ia O Procedure No.8 R-b RA biOLO61 C.AL MEE

(-t Titg _

TEMPORARY (yellowli Expiration Date Type of Change: h PERMANENT (green)

_ Originator M _ Wl%WW Ngueshng 0epartment WMhdL %PPORT Proposed Change:

(Does this atter the intent of onge.at procedure? O ve E noi

@ NO)

(Does' l's constitute an unreviewed safety / environmental question? O ,TES a

PAGE % 3 PARr 1.l_ d

$cesse.Queatr m W A M Ca 6 WRt"TV DGPAR MEkfT 'EMTEu!Aokas As h,;

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g (.

% 'm, q L s t.)

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o 8 - .

NI Noon for Change: g m y cept imettwe L._ ,

E W "" I As of 4-1-93 .

8

- A Date

Authorizations: ( 'lant Management Staff w/SRO Ucanse)

(Ptant Madgemenpfarf) Initial Cistribution By:

O YES S NO Isr:ediate distribution to the Control Recrs and af fected work areas required?

Ofstributed To: O Control Rop, O otaers h

F Date Received by Cocun:ent Control _ / n~

i Date stove *ptus 14 days oc t PSRC Peview and P! ant Mana#s approval no Istsr than 3

UN Review Cats _

2E PSRC recornmends a;;provalO vesO no Ptant Manager's Approval 0 NIA o u'

$$ Meedng Nutr.ber O O - 0 0 0

"!o Md!ticnal informaron O j

Follow-up To Reim:ted On-the-Spct Chans+

,i A: tion Taken/NmaAs:

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'55 hcc c Pfense see actional sree:s[

htCTDir's ITim ,. n Same as Ongmal . .. O Otners_

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P GerE DIABLO CANYON POWER PLAMT Ufey4 ff[)"* PROCEDURE ON-THE-SPOT CHANGE Procedurs No. f:P M-l Rev. 9.. Unit No. t 0 2O t a 28 FM Ptev F' F-- IW313Rv CR ltLME55 / M ck! P_At>12tf2_6.LQt3

, ~ 7,n.

Type of Change: h PERMANENT (green) O TeueOR>Rv <re>iow); c ir. tion care Reovesting Department _ WGMLR SUPPORY Originetor 59. DA13FrRW Propo d Change: (Does this alter the intent of criginal procedure? O vos G "o)

(Does 1't constituta an unreviewed safety /envircreental question? O,YES E NO) p g.tr 5 , PART 5 o " TRAMLPORTATIOM of, (M3UE.Cb PERS'HNEL" C.HAN(aE ro RCAD AS FoLLDWS *

3 [F" AMSULAucE. cR MEDICAL PERsoWNEL ARE TO EMTER THE SITE. ,

CCbMTAct' THE SEcuRiy DEFARTNENT'hMI,r,jk$khMD MVE 5

h THEM NOTIFY WE ".:EIuRtTy F:DRCE AT THE ECR.T SAM LDIS o -

if .

EMTRAWcE. IT 15 WECE55ARy TD H/44 AM ES(.ogt NCOMFMNy WE AHe0LAucE. PER5CMMEL FRoM tvE ORtTy eutt_otMc= To THE. NATLENT".* .

1

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R.e.on er Change: REauttE.S WESWT TcEEMAN T (mwTACT ~$E AVILA CMTE, . ThE

. EP tH PUcc.EbCCE. *.AAoOLD E.E EEVtSED *tt> HAVE TVE. We"Rlly D(:_FARTI^ENT* MATE, WE MonG1CAnDu. Wit Albo IUCLUDE:5. REVLSED SI400tYy EYT1:Uttcus.

ai - A

"' b Authoniarons: Date *

(Plant VinagegerfStaff) (Plaitt Management Statt w/SRO Ucense)

Initial Distribution By:

Ierediate distribution to the Control Rocra and affected work areas required? O YE5 % NO Distributed To: O Control itocra O Others l

fu Date Received by Document Control 4 ./'s-Q!b j PSRC Review and Ptant Managers approval no later than . Mf r3 ate above 'plus 14 days t

N Review Date 2E PSRC recommends approvalO vos O~ No og Ptant Manager's Approval O N/A 6

j Meeting Numbe, O- 00 Foibw-up To Rejected On-the-Spot Change Additional Informatioa O Action Taken/Remarts:

NN W ::

6t E8

-.em.~..,..... rm Same as Ongeal p n,n,,, , ,

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3GsE OIABLO CANYON POWER PLANT '

PF.OCEDURE ON-THE-SPOT CHANGE wece C:"2 )

(4/8 o recedure No._EP 2 ~7 Rev. "2- Und No.1 2 1&2@

3 r,.,, c FT: ".stits TCAusco 27ATtc a Na htNM Type of Change: h PERMANENT (green) TEMPCRARY (yen o w); Empiratten Oate

-T1Ef.905LAL a popergi" g gg,, _ epp p, y Aequest 's DecartJMnf Proposed Change: (Does this alter the infant of cogrial procedure? O vs. O Rai (Coes' it ceristitute an unrtvie-ed safety /envirornental question? a YES S NC) cp a 7 pa Aprenoix z accacucy r.wcroe2s notic cMcu ru-x:ocncm *

7. tem 2.a. suPERYtuW4 M,U cifATl O CMATIOM EOCalWCER [IE/E"cualEl- f CMv e.ca w_MTA4. MFCTy) ,

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g A-.- eor caense: m :cecRvisia. wucu c cucumou eaaum n m. rei-o no~ , uor n w_ w . w ue c = c:, e asie.uf.

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. Aunor&mes:/ ,e .

(Piant Managemoni Staff wr$RO Lcensel Cara" (P'antManageMnt Staff) l Initial Distrieut1cn fy:

[ I nediate cistritution to the Centrol Room and affected wort aress recuired? TES gNO

cistributed To: O Controi neem a otners Cate Received by Cocument Centrol c2 /$

b rsRC nov.~ and P:ani Manage ~~Lo Gic_AQ Tg, of Crese; h FEAMANENT (gr en) ] TEMPCRARY (yertow)* Eapiration Oate Onsinator 4AboJ N DAD 6WC:V f necuesting cesartenant~~

~~W1JNIN AMSTAw" Propo d change: (Coos this aner the intent of ensnal procedure? C Yes h No)~~
(Dees' it constitute an unreviewed safety /envircrrnental questien! C TES S NO)
EP M-t_ Arrn W tN f l " GenP A9 paw' A. ce: PHyStC.1ARS, AMButAuIs, AMD HotPirAts te viuca we IMMcciArt nra Azocuo nAew cAwycw" -
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- cuame exaAes c. vtestan. mout wea e: '
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O ATTAcuMEuT 8 " PAWE1 os: PHfstctAus, AMaptA4Ces, Mb RosPtrAts (msT VALLEYS Divi sicsJ LoMPoc. - C4AucaE. LoHPot. Mcc.PrTAu bsstT1T W34~. WTER TO s..
n.a.on for change: tVE WcWE NOMP_E25 AS USTE:> 14 *tVE A2cv6 NTTACOMCuT5 ARE.tuc w ,
7E LW WuMcEns N cwww3 As hb ts twt _ W m E
Authornatchs:A !
(Piant danagem/ Staff)
(Ptant Management Staff w!S30 beansd 4 ~ 2 7~ P3 Dat e
~~l Initial Distrttu..cn Sy: [~~
Imediate distributien to the Control Roan and affected wort areas required? O YES g NO '
01stributed io: O Centnal Rocin C Others
!$ Oate Received by Docrent Control J/[' f 3 3 Date above
~~pus b*, cays PSFIC Powew and Plant Manager's accrevat later than - M s~~
E5 Review Date 2E PSAC recommends ap;revalO vee O no o* e m uana ,< s Aa n an a wa n
'g ueew uu,-~ O O - O O O
/cIlow-uc To Petected Orwthe-Soot Change M,crbonal infonnaren O
' A non TamervAemarts:
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3 GerE DIABLO CANYON POWER PLANT
~~"' PROCEDURE ON-THE-SPOT CHANGE~~
**(a'[g[N
> + 07C'9 C*"f EP M ~2- Pev. _ f*> Unit No.1 2O is 28 .
(
Prceecure No.
7,,
veu cAwar tuJunv rso y wGss f rutRS PA1:=vi f
TEMPORARY (yeitow); uciration Cate _
Typ of Change; h PERMANENT (green) i sw.w v. t9 user:v n,ove ung cecanrnoni e nuemver Ong,n, tor Froposed Change:
(Does tnts alter the intent of onginal procedure? O v = 8 uai (Coes' It constitute an unreviewed safety /envircrrrental cuestion? O ft$ Q NO)
AFFE4DJy Z " EME12fd."WC\/ F20Cebu2E. NoTIF"Ic.ATtoW lusmcTtcwas" (TEM 3. b uvistou Ficto U AtMs tuvestieront .
Act:) -nes pgous d so -UwT IT APNO AS "M t'Eto*' ; l
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Reason for change:
I *THE. ADDITIOMAL., PttodE WOMDCR MS JDED g NE.SCHtEN M "! MAT ^ CouTACTtWCw PAFTtCS N CaHT HAVE E.Abt Ett. Nr E.55
~ 31" ?3
Autnonzatons: _~ (Ptant Management Staff w3AO LJcansel Cate (P'antAfanagyrdnt Staff) Initial cistrieutten Sy:
Ime'diate distribution to the Control Roan and affected -ort aress required? O YE5 K NQ j
Distributed To: O Control Roan C Otners a$
Oate Received by Document Control M,[3 5[/M
. ate amo,e t 4us 14 eay, PSRC Aewew and P! ant Manager's approvat no later than
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nov.ew case g;
a PsnC rec-eno. aco,ov= O ve O na Plant Manager's Approval C N/A
$3
'g uset.ng Nunter O O - 0 0 O ^
Fellow-up To A*1ceted On-me. Spot ChangeO acemonat intormarea O ,
f kton Tamen/ Aereans:
(
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~ . . . _ . _ . . .
3GsE DIABL'O CANYON POWER PLANT 0;'"y[j'[j"' PROCEDURE ON-THE-SPOT CHANGE
, Procedure No. 35P M-b Pev. ~7 Unit No.10 . 2 O ia 22 '
\
7,3, __ McsJ WR t OttMIC.AL. FIEE Typs of Change: h PERMANENT (green) O TEueCarav <>eitowi: uniration : ate
~
W/DUfL4L R";1STAWM Onstrator MWW P- NQ/atLCETY _
peouesting Ceoartment Propen.d Change: (Does ets after the intert of cr9tul procedure? O vs. 8 "oi (Does' it ccnstitute an unreviewed safety /envircreental questienf C YES S NO)
~~p. ~6 $USSEQUENT* ACTlg4$~~
Ircr4 2. bJcTf 3.
- CHAWaf $f*/ r* 1 DEPAjZTMEuT EVTEd S TO 7:
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b**NF WE TMy CCPAlt.TME5JT I".VTEM::no4 W CHMC EFFE(.T1M *$-l-83 Authorizatons- A .h
= 4 - 2 7" EI8 (P'. ant Management Staff MAO t. cense) D ate *
(PlarganagegStaff)
Initial Distribution By:
1..rwdiate distributi(n to the Centrol Recrn and affected wort areas required? O TES A0 Distributed To: O control Room C Others d 04te Received by Docunent Centrol - d f3 / '
PSAC Feview and P' ant Manager's accreval ne later than -
//, 3 Nato acove ' sus 14 days
~ 3: . .
35 Reven Cete 2E PSAC recommends approvalO veeO no (t g Plant Manager's Accroval O air to Z
-g useong Nunee,o o - o o o Festow-up Ts Repcted Cn.the-Spot ChangeO Ace.+ona informaton O .
~~Acten Tamen/Pemams:~~
si -
EE
- *** ~ * * ~ * *
~~M -- - Ptease see acconas seestal S~~
. .e 3G:rE DIABLO CANYON POWER PLANT Wyfy[f'"' PROCEDURE OPj-THE-SPOT CHANGE Procedure No. F' P M*7 -
Aev- 4 Und No.10 20 2a23
(.' ' ' -0LIAalDP MOCDZ _
Title ___ Of L Mll L ITUD TEMPORARY (yenew); Zagiration Oate Type cf Change; h PERMANENT (green)
W 'I.(A L M S M A4?'" Originater _ 91AW*3 P. h Aecasteg Ceoartment -
Propo 4 Change: (Does this alter the intent of crv;inal precedure? O ve. O "oi (Oces it constitute an unreviewed safety / environmental questienf C YES M NQ) p.Z 3*TEt4 2. C. EwiwEuTAL Pgotvht3ou A6tucy .
- CHAMAE PHouE,u eC2 To
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2 -
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M S N Q TO
~D4t'. KRA F%NE tb WO L.Du6ER.
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Authortzatons: / Cate (Ptant /anagef taff) (Ptant Management Staff JISRO Ucensel Initial 01strttutien 3y:
Imediate distribution to the Control Eccre and affected wort areas required? O YES [0 l
Distributed To: O Control Rocra C Others Oate Received by Doc:; ment Control M
/
b S: .
/
Nato acove
~~sus la cays PSRC Aeview and P' ant Manager's amrovat no tator than 3 //~~
3 E5 Review Date 22 PSAC rwommencs approvalO vesO no-gm Ptant Manager's Approval C N/A 43
-g voeung Nm,neerOO - 0 0 0 re new.uo To Petected On-the-Spot ChangeO Aae.
~~on f mformat=a O~~
/' on Ta.oruRem .: ,
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. , e 2GoI DIABLO CANYON POWER PLANT '
- PROCEDURE ON-THE-SPOT CHANGE 1*Je"Q'[)"
Procedure No.M"3 An s. 1 Unit No.10 2O ia2 nw e cu_Am c54 rs c A :6tTE C4diAWl74TlCMS _
TEMPC A ARY (yellowli Exciration
~~ate Type of Change h PERMANENT (green)~~
~I"- fAMt(AL M5M- Cr;inator GM**1 ? MMHMTV -_
Requesting Decartenent Proposed Change: (Odes trus alter the ntant of ong.nal precedure? h Yes h No)
(Oces' it censtitute sn unreviewed safety /envircrwental question? O, YES @ NO)
FecM (A-10296 EMcc4r.xcv casive esA*W11AtiN cAta.1hT-
~8 .
2 b
a -
O M 1MSTtTVTE es- MuttrA2 hCR C)PEM71c5JS
- so c m s w e w ect y 6
N* " D' N9" ro w A 69-lcC98 UP-To - DtT21 Authoritatorts: /M
~~7 / " ) 7~~ '~~
(Plant M,aisageme[ta'f) (Pla"nt Management SIAff wlSTj0 Ucansel Cate * '
j Initial Cistributton By:
Irrnediate distribution to the Centrol Roon and affected wort areas required? O YES [NO l
, Ofstributed To: O centrol accra O ctners
' ate Received by Document Control Na:e ateve *;Ns la days PSAC Feview and Pian: Manager's a:crt;N no later *han 3
N Review Cate 2E no oW PSAC roccmmends a;provalO ve=
6I Plant Manager's Acproval O N/A
'g usew uunee,0 0 - 0 0 Fcuaw-up To Feiected Cn-the-Sixx ChangeO Ieruon=> *irormaronO
[ Ac:en Taken/Pemams:
.. :t .,
et =
52 E3
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- ~ ~ . . . . _ _ , _ _ _ _ , . _ . _ m% _
c_ . ..,
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. I PGeE* DIABLO CANYON POWER PLANT T mp ,.gg {dl
)*"*
~~m. its (4/82 PROCEDURE ON-THE-SPOT CHANGE ~~~
i a 20 m.
Py,e.a,e su EP G-4 ,p. .
2 'unano.iO 2O 4 Personnel Assembly and Acccuntability _
l Tg. os chanse: C FEFMANENT (green) O rtuece.^av <>e<>c->; a:f r.cica :at. _
Technical Assistant _e ny,n ,,, W. J. Keyworth l pecu,snng cdartnen, '
Proposed change: (Coes :rus aner the antent of ong nal procedure 7 0 ve. G "oi (Ooes' it constitute an unreviewed safety /envircreental question? C,TES 8 NO)
Pg. 3, item 4 - Add " Access Training Trailer" and " Unit i Visitors Parking Lot" as assembly areas.
Pg. 3, items 7 and 8 - Change " Security Training Trailer" to " Visitors Parking Lot" Pg. 7, item 2 - Add to TSC assignments" .
~~r. Divisiori of Engineering Research Dosimetry staf e will report to DAAS by phone from the TSC lab.~~
o i s. Chemistry and Radiation Protection Syst' ems Analysts 3 (TSC EARS Operators).
~ Pg. 7, item 5 - Change security building phone to ext Pg. 8, item 7 - Change Security Training Trailer phone to e t (Cont. on next page)
L_/. . ..
Reason for Change:
Add new assembly areas; update phone numbers.
/ -
Authorcatons s/
7 * /
~' (P' ant Management Staff hSRO Lceesel care *
(Piar%anagerg5tarf)
Init:al Districutien sy:
!. mediate distributien to the Control Rocra ano affec*ed wort areas required? O TEs $ NO Distributed To: C Control Rcom C Otr.ers .
N Date teceived by Occ:nnt Control 9 s!/f ;M _3 .
. l 3-
/ Nats above
~~pus 14 days l PSAC Pev Tw and Pfant Managers aws.af no trier than ,~~
3 .
~5 Review cate 9E li-ra 3 esac ree nes ap-as O vee O aa P' ant Manager's Acproval O si^
'g ueenna surneer 0-000 Fonow-up To Pelected On-the-Spot ChangeO ecc:t>oa ' <*=r=^ tea O .
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.' .o i 69-10709-1 8/82(50)
PACIFIC GAS AND ELECTRIC COMPANY PAGE 2 0F 2 l DIABLO CANYON POWER PLANT l PROCEDURE ON-THE-SPOT CHANGE ,
CONTINUATION SHEET l':
'J PROCEDURE NO. EP G-4 REV. 2 l l
l PROPOSED CHANGE,E%'MYI)32XGNi3RX
+
l
. Pg. 8 - Add new assembly areas:
~~8. Access Training Trailer'~~
~~a. Personnel Supervisor and staff~~
~~b. Budget Analyst -~~
s c. All clerical personnel and janitors
~ ~
_. ? -
itors Parking Lot (phene [3835.}or[3836]for CASS)
~~a. Non-essentiaT General Office personnel onsite~~
~~b. Non-essential Coast Valley personnel cnsite - - - - - - - - - - - - -~~
~~c; Unit i vi i tors~~
~~d. We s' . cechtel ano other consultants not otherwise assigned.~~
,, Replace fo'rm with the attached version dated 4/83. _
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P 69-10050 4/83 (50) -
Pace 1 of 3 DEPARTt:ENT OF SUCLEA'R PLAtif OPERATICriS
.d \ DIAELO CAT:YCN PCWER PLANT UNIT NOS.1 At:0 2 J
SUt'FARY OF PERS0titiEL ACCCUNTASILITY AtiD ASSIGNMEt;TS SY . DATE INITIAL PERSOfit:El ACCOUNTASILITY CONTROL In Charge. . Report In At Hours y00M _ g No. Of People Accounted for L J Yes [ ] No g , g' Mtssing .
}
Injured y . Remarks i
TECHNICAL In Charge Report In At Hours
. SUPPORT No. Of People Accounted For L J Yes [ ] No JFmR, Missing g Injured Remarks [
.. i ,
i COLD In Charge Report In At Hours MACHINE No. Of People Accounted For [ J Yes [ ] No SHOP Missing
..."j~ ]
Injured i
\ Remarks I
ACCESS In Charge Report In At Heurs
, CONTROL., No. Of Peopic Accour.ted For L j Yes t ] i;o L.~._ J X Missing Infured Remarks SECURITY In Charge Rep'o r In At Hours TRAINING No. Of People Agcounted For L j Yes [ ] No' r TRAILE.h Missing L, ' - -
y injured Remarks OC0005 16II ,
g .
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F_. _ . . .
___ . . . P I ' ' '
~~69-IC060 4/83 (50) Face 2 cf 3 .~~
OE?ARTMEi:T O' F NUCI:EAP. PLA!;i OPERATIONS -
DIABLO CANYCN POWER PLAN 7 L";IT i:05.1 At:0 2
. SUIF.ARY OF PER50HiEL ACCOUI(TASILITY,AND A55IG:.;4ENTS SY DATE
, INITIAt. PER50NiiEL ACCOUNTABILITY r
ACCESS In Charge Report In At Hours TRAIN!flG No. Of Peo' pie Acccunted For L j Yes [ ] No ,
TRAILER Missing Injured -
.. . Remarks
'. ~ SECURITY-in Charge ~ ~ Report In At Hours JUILDING No. Of Peopie Acccunted For L j Yes [ ] fio g j_ -
Missing Injured }
Remarks TEMPORARY. In Charoe Report In At Hours 0?.:
TRAINING No. Of People . Accounted For L j Yes [- ] No ' l'
._ .SUILDING , Missing
'. b- f GENERAL In Charge Report In At~
Hours CONSTRUCTION No. Of Peopie Acccunted For L j Yes [ ]'No pREAC) Missing gN u ' f injured l Remarks VISITORS In Charge Report In At Hours
. A No. Of People Accounted For L j Yes [ ] No CONTRACTORS Missing injured
,N J AREA 5_A f Dy Rer. arks . .
w.._
. S n i CC0005 17II '
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3
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'I 69-10060 4/83 (50) Page 3 cf 3
('
DEFARTMENT OF huCLEAR Pt.AtiT OPERATIONS
~~k. '~~
~~DIABLO CaliYON F0WER PLAJT d !IT NOS.1 A:40 2 l~~
~~SUMMARY~~
OF FER50!;NEL ACCCUitiABILITY AriO ASSIG?iMENTS BY . DATE li!ITIAL PER50!iMEL ACC00tlTABILITY GENERAL In Charge Report In At Heurs CONSTRUCTION No. Of People ~
Accounted For L j Yes [ ] No AREA - , Missing
. F Injured
. Remarks -
. UNIT 1 In Charge Report In At Hours VISITORS No. Of People Accounted For L j Yes [ ] No PARKING LOT Missing Injured Remarks ,
SIOLOGY In Charge -
' Report In At ' Hours
'A No. Of People -
_ Accounted for L j Yes t ] No Missing
-] Injured Remarks -
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OCC005 181I l
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_ _ _ _ - . . - - -

ML20077B491

Text

SUMMARY

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