DCL-85-245, Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 9 to EP M-4, Earthquake & Rev 5 to EP OR-1, Offsite Support & Assistance. W/Revised Tables of Contents

Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 9 to EP M-4, Earthquake & Rev 5 to EP OR-1, Offsite Support & Assistance. W/Revised Tables of Contents

ML20198D130
Person / Time
Site:	Diablo Canyon
Issue date:	07/18/1985
From:	PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML20198D114	List: DCL-85-245, Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 9 to EP M-4, Earthquake & Rev 5 to EP OR-1, Offsite Support & Assistance. W/Revised Tables of Contents ML20198D110
References
DCL-85-245, OL, PROC-850718-02, NUDOCS 8511120269
Download: ML20198D130 (89)

Text

.

PGandE Letter No.: DCL-85-245 o

CURRENT EMERGENCY PLAN NPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3A TITLE REY E-0 Reactor Trip or Safety Injection 0

E-0.1 Reactor Trip Response 0

E-0.2 Natural Circulation Cooldown 1

E-0. 3 Natural Circulation Cooldown with Steam Void in Vessel 1

(with RVLIS)

E-0. 4 Netural Circulation Cooldown with Steam Void in Vessel 0

(Without RVLIS)

E-1 Loss of Reactor or Secondary Coolant 0

E-1.1 SI Termination 0

E-1.2 Post LOCA Cooldown and Depressurization 0

E-1.3 Transfer to Cold Leg Recirculation 0

E-1.4 Transfer to Hot Leg Recirculation 0

E-2 Faulted Steam Generator Isolation 0

E-2.1 Alternate Auxiliary Feedwater Supplies 0

E-3 Steam Generator Tube Rupture 0

ECA-0.0 Loss of All AC Power 0

ECA-0.1 Loss of All AC Power Pecovery Without SI Required 0

ECA-0.2 Loss of All AC Power Recovery with SI Required 0

4 ECA-0.3 Restore Vital Bus 0

ECA-1.1 Loss of Emergency Coolant Recirculation 0

ECA-1.2 LOCA Outside Containment 0

ECA-2.1 Uncontrolled Depressurization of All Steam Generators 0

E CA-3.1 SGTR With loss of Reactor Coolant-Subcooled Recovery Desire 0

ECA-3.2 SGTR with Loss of Reactor Coolant - Saturated Recovery Desired 0 ECA-3. 3 SGTR Without Pressurizer Pressure Control 0

F-0 Critical Safety Function Status Trees 0

FR-S.1 Response to Nuclear Power Generation /ATWS 0

FR-5.2 Response to Loss of Core Shutdown 0

FR-C.1 Response to Inadequate Core Cooling 0

FR-C.2 Response to Degraded Core Cooling 0

FR -C. 3 Response to Saturated Core Conditions 0

FR-H.1 Response to Loss of Secondary Heat Sink 0

FR-H. 2 Response to Steam Generator Overpressure 0

FR-H.3 Response to Steam Generator High Level 0

FR-H. 4 Response to Loss of Normal Steam Release Capabilities 0

8511120269 850718 PDR ADOCK 05000275 F

PDR 0502d/0005K 07/18/85

~.n

n TABLE OF CONTENTS (Continued)

FR-H.S Response to Steam Generator Low Level 0

FR-P.1 Response to Imminent Pressurized Thermal Shock Condition 0

FR-P. 2 Response to Anticipated Pressurized Thermal Shock Condition 0

FR-Z.1 Response to High Containment Pressure 0

FR-Z. 2 Response to Containment Flooding 0

FR-Z.3 Response to High Containment Radiation Level 0

FR-I.1 Response to High Pressurizer Level 0

FR-I.2 Response to Low Pressurizer Level 0

FR-I.3 Response to Voids in Reactor Vessel 0

R-1 Personnel Injury or Illness (Radiologically Related) 15 and/or Overexposure R-2 Release of Airborne Radioactive Materials 5

R-3 Release of Radioactive Liquids 4

R-4 High Radiation (In Plant) 3 R-5 Radioactive Liquid Spill 3

R-6 Radiological Fire 8

R-7 Offsite Transportation Accidents 5

M -1 Employee Injury or Illness (Nonradiological) 13 M-2 Nonemployee Injury or Illness (Third Party) 11 M-3 Chlorine Release 5

M-4 Earthquake 9

M-5 Tsunami Warning 5

M-6 Nonradiological Fire 10 M-7 Oil Spill Isolation and Clean Up Procedure 7

M-8 Containment Emergency Personnel Hatch 0

M-9 Hazardous Waste Management Contingency Plan 2

M-10 Fire Protection of Safe Shutdown Equipment, Unit 1 3

M-10 Fire Protection of Safe Shutdown Ecuf pnent, Unit 2 3

G-1 Accident Classification and Emergency Plan Activation 5

G-2 Establishment of the On-Site Emergency Orgenization 7

G-2 51 Emergency Organization Call List Form 69-10297 2

G-3 Notification of Of f-Site Organizations 6

G-4 Personnel Accountability and Assen61y 6

G-5 Evacuation of Nonessential Site Personnel 2

0502d/0005K 07/18/85 l

NUMBER EP M-4

'T Sv43 Pacific Gas and Electric Company REVISION 9 o

DEPARTMENT OF NUCLEAR PLANT OPERATIONS DiABLO CANYON POWEA PLANT UNIT NO(S) 1 AiiD 2 g

EMERGENCY PROCEDURE EARTHQUAKE l

TITLE IMPORTANT 4 -i f N TO PLANT MANAGER c;/

DATE SAFETY APPROVEo SCOPE This procedure and changes thereto require PSRC review.

GENERAL Earthquakes affect the plant by producing ground motion causing plant This buildings and equiprent to be stressed by induced vibration.

vibration is defined by a spectrum consisting of acceleration, frecuency and duration. The values of these parameters used in the design of the Diablo Canycn Flant are given in Section 3.7 of the FSAR.

Instrumentation at the site measures and records acceleration frecuency and duration, but only the maximum acceleration along three perpendicular axes is indicated. The seismic instrumentation which meets the requirements of Technical Specification Table 3.3-7 is described in Appendix 1.

Only accelerations of greater than 0.01 g's on the ccr.tainter.t base slab are recorded on the triaxial time-history accelegraphs.

For purposes of this procedure, earthquakes are classified by the maximum acceleration indicated by the triaxial accelerometer located on the cor.tainment base slab.

DCPP NUREG-0654 NUREG-0654 Maximum Earthquake Classification Action Acceleration (c's)

Classification Criteria Level Unmeasured to 0.01 Micro Not detected None in plant.

0.01 to 0.1 Poderate Detected or felt Unusual event in plant 0.1 to 0.2 Strong Detected unusual event 0.2 tc 0.6 Large Greater than Alert OBE levels Greater than 0.6 Major Greater than Site emergency SSE levels DC0036 IIX

NUMBER EP M-4 DIABLO CANYON POWE7 PLANT UNIT NO(S) 1 AND 2 REVISION 9 DATE 6/1/85 PAGE 2 0F 50 EARTHQUAKE TITLE Unmeasured to moderate earthquakes are expected at Diablo Canyon during the life of the plant. A strong, large or major earthquake is not expected. This is based on geological explorations and on the recorded seismic history of the site.

This procedure is to be followed in the event that an earthquake occurs which triggers the recording instruments or is felt in plant.

In the event that damage occurs, follow the appropriate Emergency Operating Procedure to mitigate the consequences of the damage first, then follow this procedure for investigation of the plant for further damage and reporting.

The operator response is graduated, based on the local acceleration indicated by the Earthquake Force Monitor (EFM) up to 0.5g or on the SMP-1 playback if greater than 0.5g.

MICR0 EARTHOUAKE (Unreasured to 0.01c)

Synotems 1.

The supplerental system (SS), Terra Technology DCS-302, is triggered but the basic system (BS) Kinemetrics SPA-3, is not triggered. This near.s alarm input no,1186 is in alarm and alarm input no. 1112 is not in alarm on PK 15-24 (" Seismic Instr

}

Systen').

ff)E 1:

If ground motion is felt "in-plant" by the operations staff, discentinue this section and go to the Moderate Ear *.nqua Ae section, f0E 2:

"In-plant" is insice the double fence (Plar.t Protected A rea ).

Autcratic Actions Ncne expected.

Irrediate Ocerator Actions None.

DC0036 2IX

NUMBER EP M-4 1 AND 2 REVISION 9 Di&8LO CANYON POWER PLANT UNIT NO(S)

DATE 6/1/85 PAGE 3 0F 50 EARTHQUAKE TITLE Subsecuent Actions 1.

Subsequent Operator Action hetify the on-call Power Production Engineer (Nuclear),(EP G-2 Data Processor No. 2, on call rotation personnel), the a.

next werking day to retrieve the Supplemental System data.

Document the activation of the Supplemental System with a b.

Problem Report.

2.

Subsequent Power Prcduction Engineer Action Have the I&C departnent retrieve the data from the 6.

Supplemental Seismic Monitoring System.

1)

Perform a post-event calibratien of the SS tapes.

2)

Make strip charts of the functional free field and trigger chant (1s and others as directed by the Power Frcducticn Er.,ineer (huclear).

2 ',

Install a rev: set of tapes in the SS recorder, at discretion of cr-call Power Producticn Engineer (hacictr).

4)

Ferferi. pre-esent calibration.

5)

Forward the stric charts and rer.oved tares tc the on-call Power Production Engineer (Nuclear).

b.

Cell the U.C. Berkeley Seisnographic Station at and obtain the epicenter location and magnitude of This any earthquake which could account for the SS trigger.

recording is updated each weekday at 7:30 a.m. PST, and cosers the previcus 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period, t0TE:

If no earthquake was recorded by the Berkeley Staticn, it may be desirable to contact tt.c California Institute of Technology (Cal Tech) Seismic Center at '

for possible epicenter locatien and magnitude information.

l DC0036 3IX

1 i

DIABLO CANYON POWER PLANT UNIT NO(S)

I A 30 2 NUMBER EP M-4 1

REVISION 9 DATE 6/1/85 PAGE 4 0F 50 TITLE EARTFQUAKE forward the strip charts and any information obtained from c.

the Seismic Station to Civil Engineering, and request guidance as to the disposition of the SS tapes (i.e., erase and reuse, send to Terra Technology Corp., etc.).

Retain the SS tapes until directed by Civil Engineering as d.

to their disposition.

MODERATE EARTHCL'AKE 0.01c to 0.lg Sye'ptoms 1.

Grounc motion is felt "in-plant" (inside the double fence) by the Operaticns staff.

2.

The " Seismic Instr System" annunciator is activated (PK 15-24),

3.

The raximum acceleration on the containment base slab is indicatec to be between 0.01 ano 0.19 by the EFM.

Aat: atic Actier.s ficne expectec.

Irrediate C'perrter Actions 1.

fictif, the Sr.if t Foreran (Interic Site Emergency Coordinator).

2.

FLie ? ceneral survey of the Centrol Rcon instrumentation, with particular attention to annunciator and computer alarns, to verify that no apparent plant damage has occurred.

Subsequent Actions i

1.

Notify the shif t CARP to make preparations for entering Containment to conouct a quick fire inspection.

2.

General Establish the onsite emergency organizatien for an l'nusual a.

Event as specified in EP G-2 " Establishment of the Onsite Emergency Organization."

t l

OC0036 4!X 1

NUMBER EP M-4 1 ANO 2 REVISION 9 DIA6LO CANYON POWER PLANT UNIT NO(S)

DATE 6/1/85 PAGE 5 0F 50 EARTHQUAKE TITLE Notify offsite organizations as specified in EP G-3 b.

"hotification of Offsite Organizations."

Instruct the on-call Power Production Engineer (Nuclear) (EP G-2 Data Processor No. 2, on-call rotation personnel) to c.

come onsite and retrieve seismic data.

3.

Subsequent Operator Action If a urit trip has occurred, maintain the unit in HOT STANDSY (MODE 3) until the Plant Manager authorizes a return a.

te power.

Within two hours following an earthquake exceeding 0.024, inspect all zeres listed in Technical Specification Table b.

(If the Kinemetrics SMA-3(BS) was not 3.3-11 for fires.

triggered, assume the earthquake to be less than 0.02g.)

If a pcrtion of the Fire Protection System is damaged f6TE:

by the earthouake, as indicated by visual inspection c

'im. arrunciaticr, it should be isolated from the remainder of the system (see Appendix 3 for Fire S;.! er Isol. Vcive nutters and locations),

Comp 1rtc the " Post-Earthouake Level Indicator Check List,"

c.

(Form 69-9249) and give it to the Shift Foreman.

The Unit (s} will be placed in HOT STANDBY if investigatice reveals physical damEge which could impair the cperatier cf d.

any Seismic Class I ecuipment.

Subsecuect Pcwer producticn Engineer Action 4

Sections a, d ane f are not applicable if the Basic System POTE:

has not triggered.

Contact the I&C Department to retrieve the seismic data from the Kinemetrics SMA-3 basic seismic monitoring system (BS).

a.

(See STT I-37C.)

1)

Ferform a pcst-event calibration of the BS tapes.

2)

Replace the tape cassettes in the SMA-3 and perform a pre-event calibration.

DC0036 SIX

DIABLO CANYON POWER PLANT UNIf NO(S) 1 AND 2 NUMBER EP M-4 REVISION 9 DATE 6/1/85 PAGE 6 0F 50 riTLE EARTHQUAKE 3)

Reset the EFM.

4)

Play back the tapes removed from the SMA-3 on the SMP-1 and make strip charts.

5)

Forward tapes and strip charts to the on-call Power Production Engineer (Nuclear).

b.

Contact the I&C Department to retrieve additional seismic data from the supplemental seismic monitoring system.

1)

Perform a post-event calibration of the SS tapes.

2)

Install a new set of tapes in the SS recorder and perform a pre-event calibration.

3)

Make strip charts of the functional free field, trigger, centainment base slab and spring line channels.

4)

Fomard tapes and strip charts to the on-call Pcwer Prcduction Engineer (Nuclear).

Cali the U.C. Berkeley Seismographic station at c.

and cbtain the epicenter location and magnitude of the earthquake.

d.

Uptn receiving the Basic System tapes and strip charts:

1)

Determina if the earthquake exceeds 0.029 If so, irrrediately r.otify the Shif t Foreman and commence an engineering evaluation of the fire detection instrumentation in accordance with Technical Specification 3.3.3.8, ACTION b.

This evaluation may include the performance of applicable system functional tests, but must be completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> folicwing the earthquake.

2)

Send a copy of the record play back to the Civil Engineering Department.

3)

Retain the cassette tapes for further analysis.

DC0036 6IX

NUMBER EP M 4 1 AND 2 REVISION 9 DiAsto CANYON POWER PLANT UNt' NO(S)

DATE 6/1/8E PAGE 7 0F 50 EARTHQUAKE TITLE Upon receiving the Supplemental System tapes and strip e.

charts:

1)

Determine the maximum containment base slab acceleration of the earthquake.

If the Basic System did not trigger, and the POTE:

maximum free-field acceleration from the Supplemental System is less than.019, notify the Shif t Foreman that the event may be downgraded to a Micro Earthquake.

Secc a copy of the strip charts and the information 2) obtained from the Berkeley Seismographic station to the Civil Engineering Department and request guidance as to the disposition of the SS tapes.

Retein the SS tapes until directed by Civil Engineering 3) as to tneir disposition.

f.; ti fy IC.c centact F.inemetrics for an onsitt This must be recalibratier of SMA-3 and SMP-1 equipment.

pericmed withir. fise days following the initial event.

i Gatter local data in accordance with' Appendix 1 Post g.

Earthquake Checklist.

Close cut v.ith vertil sum ary tc offsite authorities fellowed by f.

Occument verbr.1 a wri**.c sumary tc f'PC withir 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

69-9221, " Emergency Notification Record."

surmary on Fom I' the Basic System triggered, contact a Regulatory Compliance 6.

Engineer to prepare a Special Report in accordance with the requiremer.ts of Technical Specification 4.3.3.3.2, anc document the notification in the Shift Foremans Log.

STRONG EADTH0t'tVE (0.1 TO 0.2a)

Sympicr. s The maxirum acceleration on the containment base slab is 1.

indicatec tc be between 0.1g and 0.29 by the EFM.

The " Seismic Instr System" main annunciator is activated (,PK 2.

15-24).

The ground motion is strongly noticeable to operations personnel 3.

on shift.

DC0036 71X

DIABLO CANYOh POWEF PLANT UNIT NO(S) 1 AND 2 NUMBER EP M-4 REVISION 9 DATE 6/1/85 PAGE 8 0F 50 Tir a EARTHQUAKE Automatic Actions The Unit may trip due to induced vibration or spurious relay actuation.

Imrediate Operator' Actions 1.

Notify the Shift Foreman (Interim Site Emergency Coordinator).

2.

Make a general survey of the instrumentation in the Control Room with particular attention to the main annunciator and computer alarms, to verify that no readily apparent plant damage has occurred.

Subseouent Actions 1.

Notify the shift CARP to make preparations for entering Containment to ccnduct a quick fire inspection.

2.

Gener i Establish the ensite emergency organization for an Unusual

).

a.

Event as specified in EP G-2 "Establishrent of the Onsite Emergency Organization,"

b.

Notify offsite organizations as specified in EP G-3

" Notification of Offsite Organizations."

Ir.ctruct at letst two Power Production Engineers (t;uclear) c.

(EP G-2 Data Processors No. 2 and 3, on call rotation personnel) to core to the plant to assist in the post-earthquake evaluation.

3.

Subsequent Operator Action If a Unit has tripped, maintain the Unit in the HOT STANDBY a.

condition until the Plant Manager authorizes a return to power.

l l

OC0036 81X

NUMBER EP M-4 1 AND 2 REVISION 9 OLABLO CANYON POWER PLANT UNIT NO(S)

DATE 6/1/85 PAGE 9 0F 50 EARTHQUAKE

(

TITLE b.

Follow-up Investigation The follow-up investigation involves the performance of As each check varicus tests and inspections of the plant.

is completed, the appropriate check or data sheets should be Since some forwarded to the Shif t Foreman for his review.

of the surveillance tests will take a considerable period to complete, the Shift Foreman has been provided with a post-earthquake evaluation summary sheet for this procedure (Form 69-9248) to help keep track of the progress of the investigation.

Complete the " Post-Earthquake Level Indicator Check.

1)

List" (Form 69-9249). Return it to the Shift Foreman.

Within two hours following the earthquake, inspect all 2) zones listed in Technical Specification Table 3.3-11 for fires.

If a portion of the Fire Protection System is NOTE:

caraged by the earthquake, as indicated by visual inspection or flow annunciation, it shoulc te isolated f rom the ren.ainder of the system (see Appencix 3).

Complete the following " Post-Earthquake Area Inspection 3)

Checs Lists," checking ali indicated areas for When irspecting the structural and equipment damage.

varicts areas, pe) particular attentien to chipped pairt at pipe restraints and hanger clamps indicating pipe movement; spauled grouting at equipment support anchors attached te walls or floors; concrete cracks, especially near equipment support anchors; damaged pipe snubbers as evidenced by leakage from hydraulic reservoirs and/or broken or bent hardware, a)

Containment (outside missile shield);

b)

Contaircent (inside missile shiclo, if unit is shutdown);

c)

Auxiliary Building (main area);

d)

Auxiliary Building (penetration areas);

(

DC0036 91X l

\\

01481.0 CANYON POWE] Pt. ANT UNIT NO(S) 1 AND 2 NUMBER EP M-4 REVISION 9 1

DATE 6/1/85 PAGE 10 0F 50 EARTHQbAKE 7:TLE l

e)

Fuel Handling Building (main area);

f)

Fuel Handling Building (vent equipment areas);

g)

Turbine Building; h)

Outside areas; i)

Intake Structure.

The areas referred to on the check lists are shown on the plant drawings included as Attachment I to this procedure. Return the completed checklists to the Shift Foreman.

4)

Complete the Post-Earthquake Surveillance Test Checklist (Form 69-9251). Forward all completed data sheets to the Shift Foreman, 5)

Complete the Post-Earthquake Electrical Power Checklist (Form 69-9:52). Fonvard completed data sheet to the Shift Foreman.

C The Unit (s) will be placed in HOT STAf!OBY if investigation reveals physical dar",e which could irpair the operation of any Seismic Class I equipment.

7)

Centact a Regulatory Compliance Engineer to prepare a Special Peport in acccrdance with the requirements of Technical Specification 4.3.3.3.2, and document the notification in the REMARKS section of the Pcst-Earthqt.ake Evaluation Sumary Sheet (Form 69-9248).

4 Subsequent Power Production Engineer Action Contact the I&C Cepartment to retrieve seismic data from the a.

Kinemetrics SMA-3 basic seismic monitoring system (85).

(See STF I-37C.)

1)

Perform a pcst-event calibration of the 85 tapcs.

2)

Replace the tape cessettes in tht SMA-3 and perform a pre-event calibration.

3)

Reset the EFF.

OC0036 10lX

1 AND 2 ON DiABLO CANYON POWE3 PLANT UNIT NO(S)

DATE 6/1/85 PAGE 11 0F 50 EARTH 0VAKE TITLE g

4)

Play back the tapes removed from the SHA-3 on the SMP-1, and make strip charts.

Forward the tapes and strip charts to the on-call Power 5)

ProductionEngineer(Nuclear).

Contact the I&C Department to retrieve additional seismic b.

data from thE supplemental seismic monitoring system.

1)

Perform a post-event calibration of the SS tapes.

Flay back and r:ake strip chart records of all channels.

2) 3)

Install a new set of tapes in the SS recorder and perform a pre-event calibration.

Forward the 55 tapes and strip charts to the en-call 4)

Pev.erProductionEngineer(Nuciear).

Call the L.C. Berkeley Seismographic station at ar.c cttain the et.icenter location anc magnitude cf c.

the eartnquake.

Uper. receiving the basic Syster tapes and play back records c.

the FEE cr. call sr.culd:

l ',

So.c a ce;j c' thc play back records to Civil Engineering.

Reta'r the cassette tapes fer further analysis, 2)

U;cr receiving the Supplerertti Systen. tapes and strip e.

charts the PPE on call should:

Send a copy of the strip charts and the information 1) obtained from the Berkeley Seismographic station to Civil Engineering and request guicance as to the disposition of the SS tapes.

Retain the SS tapes until directed by Civil Engineerinn 2) as to their disposition.

f.

Notify !&C to contact Kinemetrics for an ensite This must be recalibration of SMA-3 and SPP-1 equipment.

perforced within five days _ fcilowing tre initial event.

DCCC36 11IX

DIAsto CANYON POWEQ PLANT UNIT NOIS) 1 AND 2 NUMBER EP M-4 REVISION 9 DATE 6/1/85 PAGE 12 0F 50 TITLE EARTHQUAKE g.

Gather local data in accordance with Appendix 1 Post Earthquake Checklist, h.

Corrence an engineering evaluation of the fire detection instrumentation in accordance with Technical Specification 3.3.3.8, ACTION b.

This evaluation may include the performance of applicable system functional tests, but must be completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following the earthquake.

5.

Close out with verbal sucrary to offsite authorities followed by a written summary to NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Document verbal suneary on Form 69-9221.

LA9CE EARTHQUAKE (between 0.2q and 0.6q)

Symotoms 1.

The " Seismic Instr Systen" main annunciator is activated (PK 15-24).

2.

The rayirur. i.cceleratier indicated by the Earthouake Force Penitor or the SMP-1 tape playback strip chart is greater than 0.29 but less than 0.6 g's.

}

3.

Seisnic reacter trip (PK 04-15).

A tcra tic Acticr,s 1.

The Ur.it ray trip due to induced vibration.

2.

Seisnic Reacter trip at greater than er equal to 0.35g.

Immediate Ocerator Actions 1.

Notify the Shif t Foreman (Interim Site Energency Coordinator).

2.

Make a general survey of the instrumentation in the control roort, with particular attention to the main annunciator and computer alarms, to verify that ne readily apparent plant darrage has occurred.

3.

Begin appropriate action to place the unit (s) into HOT STAND 8Y on a controlled basis.

OC0036 121X

NUMBER EP M-4 1 AND 2 REVISION 9

.c otABLO CANYON POWER PLANT UNIT NO(S)

DATE 6/1/85 PAGE 13 0F 50

@DE TITus Subsecuent Actions Notify the shift CARP to make preparations for entering Contaircent to conduct a quick inspection for fires.

1.

2.

General Sound the Energency Signal.

a.

b.

Declare an ALERT.

Establish the onsite emergency organization c.

Notify offsite personnel and agencies as specified in EP G-3

" Notification of Offsite Organizations."

d.

ICCFR100 reccires the unit be placed in a shutdown condition Plant shutdown te foT10 wine earthquakes in excess of the OSE.

3.

C0wD SHUTDOWN should commence at the direction of th Ertrgency Ccurcinator.

4.

Subsecuent Operatcr Action, Ferfurt, the sare procedure as for a STRONG earthquake (0.1 c.

to 0.2g).

Production Engineer Actions 5.

Subse:; m t Pcwer Perform the ser,e procedure as for a STRONG earthcuake (0.1 a.

to 0.2g).

Close out with verbal sumary to offsite authorities followed by Document verbal 6.

a written sumary to NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

summary on Forn 69-g221.

PAJ0P EAFTHOUAKE (GREATEP THAY 0.6g's)

Syr.v toms The " Seismic Instr Systen" main annunciator is activated (PL 1.

15-24).

The maximum acceleration indicated by the earthquake force 2.

monitor is regged at 50tg.

CC0036 131X

DIAsto CANYON POWEO PLANT UNIT NO(S) 1 AND 2 NUMBER EP M-4

• REVISION 9 DATE 6/1/85 PAGE 14 0F 50 TITLE EARTHOUAXE l

3.

The maximum acceleration on the SMP-1 playback strip chart is greater than 0.6 g's.

4 Seismic reactor trip (PK 04-15).

Automatic Actions Seismic reactor trip.

Ireediate Operator Actions 1.

Check reactor (s) trippeo and unit (s) in HOT STAN0BY.

If not, trip reactor (s) manually.

2.

Notify the Shift Foreman (Interim Site Emergency Coordinator).

3.

Make a general survey of the instrumentation in the control room, with particuler attenticr to the main annunciator and computer alcres, to verify that no readily apparent plant danage has oCCutred.

Subsectent Actico,s

)

1.

Nctify shif t CASE to riake preparaticr.s for entering Containrent to concutt a cuick irspection for fires.

2.

Gerecal a.

Scun: site er.creency sigral.

b.

Declare a SITE EMERGENCY.

Establish the onsite emergency organization as specified in c.

EP G-2 " Establishment of the Onsite Emergency Organi:ation."

d.

Notify offsite personnel and agencies as specified in EP G-3

" Notification of Offsite Organizations."

3.

10CFP.100 requires the unit be placed in 'a shutcown condition following earthouaker in excess of the OBE.

Plant shutdewn to COLD SHUTOOWN should corrrence at the direction of the Site Energency Coordinator.

DC0036 141X

NUMBER EP M-4 1 AND 2 REVISION 9 OtAsco CANYON POWED PLANT UNIT NO(S)

DATE 6/1/85 PAGE 15 0F 50 EARTHQUAKE flTLE g

Subsecuent Operator Actions 4

Perforra the sarne procedure as for a STRONG earthquake (0.1 a.

to 0.2g).

Subsequent Power Production Engineer Actions 5.

Perform the sane procedure as for a STRONG earthquake (0.1 a.

to 0.29).

Close out with verbal summary to offsite authorities followed by Docunent verbal 6.

a written sumary to NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

surrary on Forr. 69-9221.

REFERENCES _

IC CFR 100, A;;endix A Section VI (a) (3).

1.

AEC Regulatcry Guide 1.12. "Instrunentation for Earthquakes."

2.

A*.11 Stat.: arc f '.L.!, " Earthquake Instrur.cntation Criteria for 3.

Nuclear Pcwer Plant."

i Ciablo CaS cr. FSAF., Settien 3.7.

4 Nc. 443296, " Seismic Instrumentation."

5.

PGandE Orawin9 FCandE Orawir.; f.0. 452417. "Diagrar. of Connectiers, Seisric 6.

Ir.str.r srtat ier Systen."

" Seismic Instrue.entation System," PGanoE Record Owg. File Nc.

7.

653697.

NUREG-0610, 'traf t Erergency Acticn Level Guidelines for f4uclear 6.

Power Plants," September 1979.

A*Tatur'ENTS Fcrr.. ts-sin, "Erergencj l.ctificatien Record", 3/61.

1.

Form 69-9248, " Post-Earthouake Evaluation Surrary", 9/84 2.

Term 69-9249, " Post-Earthcuake Level Indicater Check Lists", 9/

3.

(10 pages),

o DC0036 ISD i

OIA8LO CANYON POWE] PLANT UNIT NO(S)

I AND 2 NUMBER EP M-4 REVISION 9 DATE 6/1/85 PAGE 16 0F 50 rir a EARTHQUAKE 4

Form 69-9250, " Post-Earthquake Area Inspection Check Lists", 4/84 (10pages).

5.

Fom 69-9251, " Post-Earthquake Surveillance Check List", 4/84 6.

Form 69-9252, " Post-Earthquake Electrical Power Check List",

9/04 7.

Fom 69-10291, " Data Sheets for Peak Shock Recorders S/N 701, 710, 728", 9/84 E.

Fom 69-9283, " Data Sheet for Engcahl Peak Acceleration Recorder", 9/84.

'}

t DC0036 16!X

NUMBER EP M-4 1 AND 2 OiAaLO CANYON POWE] PLANT UNIT NO(S)

REVISION 9 DATE 6/1/85 PAGE 17 0F 50 EARTHQUAKE TITLE APPENDIX 1 SE!SMIC INSTRWENTATION DESCRIPTION AND POST EARTHQUAKE CHECKLIST DESCRIPTION 1.

Ger.eral There are three types of seismic sensors:

1) Engdahl peak shock records; 2) Engeahl peak acceleration recorders, and 3)

Kinemetrics triaxial accelerometers. The different sensors are provided at plant locations as shown on PGandE drawing 443296, 443043, and 443044 MEAS.

NO. OF DWG.

INSTRUMENT! AND SENSOD LOCATIONS RANGE INSTR. DESIG.

1.

Tria>fal Resocnse-Spectrun Reccrders (EngtaM)

a. Cce.tair.: tr.; Ease Slat, El. 69,160' 1.0-90g 1

6 2-25.4 Hz 2.

Triamie' Feak Acceicg aphs (Engcahl)

a. Containmcet Base Slab, E1. 89, 180'

29 1

3b

b. Ter (nit 1 Containrent, E1. 303.5,

59 1

3a 22i'

c. Intake near ASW Pur; i-2 Bay, E1. 2

2g 1

3f

d. Turbine Building, E1. 85, Machine

29 1

3e Shop

e. Auxiliary Building, E1. 140, Hot 229 1

3k Sher

f. Au>iliary Evilcing, E1. 14C, near

29 1

3r Control Rcom Door 3.

Triaxial Time-History Accelographs (Kineratrics)

a. Unit 1 Containrcet Base Slab. El.

21g 1

lb 89, 180' s

CC0036 171X

4 NUMBER EP M-4 1 AND 2 DiAsLO CANYON POWEn PLANT UNIT NO(S)

REVISION 9 DATE 6/1/85 PAGE 18 0F 50 EARTHQUAKE TITLE MEAS.

NO. OF OWG.

INSTRUMENTS AN9 SENSOR LOCATIONS RANGE INSTR. DESIG.

m

b. Top Unit 1 Containnent, El. 203.5, 2g 1

la 225'

' Ig 1

1p

c. Auxiliary Building, El. 64 2.

Triaxial Response, Spect' rum Recorders (Engdahl)

Each of.these units contains twelve sprin.3 steel reeds of differeni lengths and weights. A diamond-tipped stylus is attached to the free end of each reed. A flat plate is mounted adjscent to each stylus such that in the event of an earthquake, the vibrating stylus inscribes a permanent record of its deflection on the plate. Since each reed has a different resonart frequency, this arrangement provides the earthquake acceleration (as ressured by reed displacerrent) at twelve cifferent frequencies.

There are act.ually three individual shock recordar units on the conteinment base slab with cne Unit oriented along the three

}

perpendicular (x, y, 2) axes.

3.

Triaxial Peak Acceleregraphs or Peak Acceleration Recorder (Enydahl PAR's)

The accelerograph records by scribing a line on the surface of a rEccrd plate. Three reccrd plates are included in each unit, oriented along the three perpendicular axes. The lines are inscribed by a contact diamond stylus, one for each axis. The peak acceleration is treasured as the r;axiraun ceflection from the.

zero baseline.

4 Triaxial Tire - History Accelerographs (Kinemetrics)

Each triasial accelerometer unit contains three accelercreters oriented along the tnree perpendicular axes.

Each accelerometer is a damped spring mass device which is fed to a rechanica'-electrical transducer. The signals from the accelerorreters are fed to one or both of two units (see Figure 1). The first is a SMA-3 magnetic tape cassette recording system. This system h'e.s a starter unit which automatically when the acceleration drops below this level (g) and shuts it off starts the cassettes at a present level (0.01 the unit is then ready fcr a succeedir.g earthquake). The tapes can be played back on a SMP-1 playback which is rack mounted with the SMA-3 unit.

This provides a strip chart record of the acceleration.

DC0036 18!X

NUMBER EP M-4 1 Agg g REVISION 9 DIABLO CANYON POWER PLANT UNIT NO(S)

DATE 6/1/85 PAGE 19 0F 50 EARTHQUAKE 7,7tg

\\

The base slab accelerometer output also goes to an earthquake force monitor unit (EFM-1), which simply contains three The indicators (one each axis) which read out in percent of g.

indicator pointer is held at its rnaximum reading until reset, so peak acceleration can be determined, i

l l

l 0C0036 19IX 1

OLABLO CANYON POWER PLANT UNIT NO(S) I #NU 2 NUMBER EP M-4 REVIS10N 9 DATE 6/1/85 PAGE 20 0F 50 TITLE.

EARTHOUAKE APPENDIX 1 (Continued)

_ POST-EARTHOUAXE CHECK I

f0T

~E: Spare cassettes and plates are stored in the chart room adjacent to the centrol room.

1.

Replace the cassettes in the SMA-3 recording system following the retrieval instructions on page 9 of Record No. 683697-15.

Insure that a post-earthquake calibration is put on tape before removal.

Play back the cassettes and record the peak acceleratien.

Since the SMA-3 is a higher class instrument than EFM-1, base subsequent action on the peak " base-slab" acceleration recorded by the SMA-3 f f this reading is greater than the EFM-1.

strip charts with the other records of the quake.

Keep the Send the cassettes to the Supervising Nuclear Generation Engineer in the Department of Nuclear Plant Operations with instructions to pass on to the Civil Engineering Departrent.

If the indicate acceleration on the EFH is 0.5 g's, determine 4

tre actual peak acceleration from unit containment base slab as follows:

h Play back the tapes on position *1 of the play back recorder a.

gain selector switch, t.

Find the highest peak (either posittbe or negative) for the highest acceleration.

Convert tc t's.

The scaling on this range is :1.0g full c.

scale when the playback recorder gain selector switch is on pcsition el.

full scale; for switch position #4, 20.25 g's full scale for switch position 710, :0.1 g's full scale.

d.

To convert to g's for recordings made from the accelograph atop Uni I containment, scaling wculd be as follows:

playback recorder gain selector switch position #1 - 22.0 g full scale; selector switch position #2 - :1.0g full scale; switch position *4 -

- :0.2 g full scale.

0.5 g full scale; switch pcsitien #10 2.

If the maximum acceleration indicated by the earthquake force monitor is greater than 0.19, replace the recording plates in the t

Engdahl peak shock recorders (PSP's) and peak acceleration recorders (FAR's).

1 DC0036 20lX

~

NUMBER EP M-4 1 AND 2 REVISION 9 DIABLO CANYON POWER PLANT UNIT NO(S)

DATE 6/1/85 PAGE 21 0F 50 b0 TITLE g

APPENDIX 1 (Continued)

Measure to the nearest hundredth of an inch the length of the scribe marks (naximum distance of the scratched record from th 3.

zero line) on each plate from the peak shock recorder using the Record the length of the scribe on magnifying scale provided.the appropriate attached data sheet r,ating Convert the scribe length in inches number and the reed number.

to the equivalent static acceleration by multiplying by the Record this value on the data sheet.

acceleration sensitivity. Forward one copy of the data sheet, as well as t Department of Nuclear Plant Operations for transmittal to theRetain Civil Engineering Department.

plant records.

When removing or installing PAR record plates, use the following 4

procedure.

Rerove the recoro access plugs fron the PAR housing, a.

Re.c,6 cr irstall tre FAR record plates.

t.

It is inportant not to move the scribe arms of the CAUTION:

PAR in the measurement axis direction whileThis removing or installing PAR record plates.

will avoid false indications on the record plates.

Re:c"t the serici numbers of all PAR record plates and corresperding PAR location following removal on the data c.

sneet.

Reccrd the time and date of removal on the PAR record plates d.

and data sheet.

Measure, to the nearest thousandth of an inch, the length of the scribe rark (maximum distance of the scratched record from the 5.

zero line) on each record plate from the PAR"s using the Record the length of the scribe on magnifying scale provided.the appropriate attached data sheet notin Convert the scribe length, in record plate serial numbers.

inches, to the equivalent static acceleration by multiplying by Record this value on the acceleration sensitivity of the PAR. Forward one copy of the data s l

the data sheet.

l the PAR record plates, to the Department of Nuclear Plar.t Operctions, Supervising huclear Generation Engineer, for Retain the transmittal to the Civil Engineering Department.

criginal copy for the plart records.

0C0036 2J3s i

DIABLO CANYON POWEQ PLANT uni? NO(S) 1 AND 2 S ON^ 9 DATE 6/1/85 PAGE 22 0F 50 ygg.

EARTHQUAKE The nominal acceleration sensitivitie:

?A;'N wdel e-number PAR 400-1 (2 ) and PAR 400-2 (5 ).n 10 gj tecA.5 9

9 g/ inch, respectively.*

• Based on a nominal full scale defl w pf G A 1 incts; i

l DC0036 22IX

NUMBER EP M-4 DiAsto CANYON POWER DLANT UNIT NO(S) 1 AND 2 REVISION 9

/

DATE 6/1/85 PAGE 23 0F 50

/

TITLE EARTHOUAKE

\\

APPENDIX 1 (Continued) amicircIA2tm SIArzta

/

FK-1524 uirIT 1/m rurse mr wm wenugng Ac::E:,ztm.

(?eTivv EUILDINC)

( N A M DCME)

(BASE. 6 )

1 IAz:Am FCECE MONITCR V

\\/

\\/

\\/

SMA-3 ECORDDC MTEM (ComCI. 3000 l

l l

I FIGURE 1 S'.0 :: DIAGRA!'. CF KINEMETRICS ACCELEROMETER Uh1TS i

l DC0036 22 Vill

D'Asto CANYON POWEF PLANT UNIT NO(S) 1 AND 2 NUMBER EP M-4 l

.\\

REVISION 9 DATE 6/1/85 PAGE 24 0F 50 7gLE EARTHQUAKE APPENDIX 2 SUFFLEMEf;TAL SEISMIC SYSTEM (Terra Technology 0C5-302) locations of Detectors Table A2-1 Recorder Max.

Elev. CHANNEL ORIENTATION No.

g Unit Location (Ft.)

1 2

3 1-1 1

1 Containment NW.

89 Vert.

120 30 1-2 1

1 Containment NE.

89 Vert.

240 150 1-3 2

1 Containment NNW.

140 Vert.

180 90 1-4 2

1 Centainment SSE.

140 Vert.

0 270 2-1 1

1 Containment Base,S.

89 Vert.

0 270 2-2 3

1 Containrent NE.

231 Vert.

60 330 (springline) 2-3 3

i Cer tainment S.

231 Vert.

180 90

)

(s.princline) 2-4 1

1 Centainment Cntr.

91 Vert.

2 i

Ccrtainment S.

140 90 16G 3-1 2

1 Centainment W.

140 180 90 3-2 3

1 Centainrent hW.

231 Vert.

300 210 (springline) 3-3 1

1 Auxiliary Bldg. 9.7-U 100 Vert.

0 270 3-4 1

1 Auxiliary Bldg.18-H 100 Vert.

270 180 4-1 1

1 Auxiliary Bldg.18-U 100 Vert.

90 0

4-2 1

2 Turbine Bldg. 35-0*

85 vert.

180 90 1

2 Containcent N.

89 Vert.

90 1

1 Turbine Bldg. 1-0 140 0

4-4 1

2 Containment SE.

89 Vert.

210 1

1 Turbine Bldg. 1-0 140 270 l

DC0036 24IX l

l

NUMBER EP M-4 I AND 2 REVISION 9 OthBLO CANYON POWER PLANT UNIT NO(S)

DATE 6/1/85 PAGE 25 0F 50 EARTHQUAKE

(

TITLE APPENDIX 2 (continued)

SUPPLEMENTAL SEISMIC SYSTEM (Terra Technology 0C5-302) locations of Detectors Table A2-1 Elev. CHANNEL ORIENTATION Recorder Max ho.

c Unit Location (Ft.)

1 2

3 E-1 1

2 Containment SW.

89 Vert.

330 E-2 1

1 Turrirc Bldg. 1-0 EE Vert.

0 270 5-3 1

FF Pn Water Reservoir G rnd. Vert.

0 270 54 1

FF Meteorciccical Tower Grnd. Vert.

90 0

C-1 1

FF G.C. !!arehouse Grnd. Vert.

180 90

'fGE: Channel Orientation is azimutns from plant north (which is 23' ccunter-cicckwise frce the north).

l l

0C0036 25IX

.=

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP M-4 REVISION 9 DATE 6/1/85 PAGE 26 0F 50 EARTHQUAKE 7,7tg APPENDIX 3 POST EARTHQUAKE FIRE SYSTEM ISOLATION VALVES (Reference P&ID's 102018 and 108018 & OVID 106718)

Operating Valve P&ID OVID OVID ID No.

SHT No SHT No Coord System / Area FP-0-20 3

3 32-8 Pkg. Bir. 0-18 0-2 Rm. Fire Sys.

Isolation (Isol.)

FP-0-19A 3

3 32-8 Pkg. Bir. 0-1 Samp. Cooler Isol.

FP-0-304 3

3 36-8 Fire Pp. 0-1 Mini Recirc ist Off FP-0-305 3

3 35-8 Fire Pp. 0-1 Mini Recirc 2nd Off FP-0-302 3

3 36-C Fire Pp. 0-2 Mini Recire let Off FF-C-302 3

3 35-C Fire Pp. 0-2 t11ni Recirc 2nd Off FP-1-42 4

4 40-8 Unit 1 Turbine Building (T/B) N.

Sprinkler Heater Isol.

FP-1-50 4

4 44-B Unit 1 T/B So. Spr. Header Isol.

FP-2-!?

4 4

46-8 Unit 2 T/B N. Spr. Header Isol.

FP-2-66 4

4 49-8 Unit 2 T/B So. Spr. Header Isol.

FF-1-44 4

4 40-B Unit 1 T/B Loop Dividing Valve FP-1-49 4

4 44-8 Unit 1 T/B Loop Cividing Valve FP-1-332 5

6 61-E Aux. Bldg. Units 1 and 2 - 100' Elev/

Unit 1 FH Bldg - 100' Elev/ Aux. FW Pp.

1-1 Spr. Sys. Isol.

FP-1-335 5

6 61-D Unit 1 Area GE/GW Elev.115' Spr. Sys. Isol.

FP-1-338 5

6 62-D Unit 1 Area GE/GW Elev. 100' Spr. Sys. Isol.

DC0036 26IX

NUMBER EP M-4 l

1 AND 2 REVISION 9 DIABLO CANYON POWER PLANT UNIT NO(S)

DATE 6/1/85 PAGE 27 0F 50 EARTHQUAKE g

7,7 g POST EARTHOUAKE FIRE SYSTEM ISOLATION VALVES 102018 and 108018 & OVID 106718)

(Re'erence P&ID's (Page 2)

Operating Valve P&ID OVID 0"ID SHT No SHT No Coord System / Area 10 Nc.

Unit 1 Aux. Bldg. Fan Rm &

FF-1-341 5

6 63-C Cont. Rn. HVAC Equip. Rm. Spr.

Sys. Isol.

Unit 1 Aux. Bldg. Serv. Wtr. Isol.

FP-1-30 5

6 61-C (from Hose Reel Header)

Unit 1 Aux. Bldg. Serv. Wtr.1501.

FP-1-32 5

6 60-C (from Aux. Bldg. Fire Loop)

Chemical Lab. Rm. Spr. Sys. Isol.

FF-1-37 5

6 62-E Unit 1 Charging, CCW Pps. Spr.

FP-1-34C E

6 61-B 5

Sys. Isol.

Unit 2 FH Bldg. 100' Elev. Spr.

FP-2-352 5

6 67-E Sys. Isol.

Aux. FW Pp. 2-1 Spr. Sys. Isol.

FF-2-ECC r/5' 6

67-E Unit 2 Area GE/GW Elev. 100' Spr. Sys.

FP-2-861 N/S*

6 65-C Isol.

Unit 2 Area GE/GW Elev. 115' Spr. Sys FP-2-30 5

6 66-D Isol.

FP-2-359 5

6 68-D Security Ciesel Spr. Sys. Isol.

Unit 2 Serv. Wtr. Isol. from Fire Lin e

FP-2-857 5

6 66-C Elev.140' (1st Off)

Unit 2 Aux. Bldg. Serv. Wtr. Isol.

FP-2-32 5

6 66-C (frcn Unit 2 Aux. Bldg. Fire Loop)

Unit 2 Charging, CCW Pps. Spr. Sys.

FP-2-349 5

6 67-B Isol.

• Not Shown.

DC0036 271X

m.

ciAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP M-4 REVISION 9 DATE 6/1/85 PAGE 28 0F 50 TITLE _

EARTHQUAKE POST EARTHQUAKE FIRE SYSTEM ISOLATION VALVES (Reference P&ID's 102018 and 108018 & OVID 106718)

(Page 3)

Operating Valve P&ID OVID OVID ID No.

SHT No SHT No Coord System / Area FF-1-177 7

8 88-A Unit 1 Containment (Cont.) Fire Water Sys. Manual Isol.

FF-1-193 7

8 85-D Unit 1 RCP 1-1 Spr. Sys. Isol.

FP-1-203 7

8 83-D Unit 1 RCP I-2 Spr. Sys. Isol.

FP-1-189 7

8 82-C Unit 1 RCP 1-3 Spr. Sys. Isol.

FP-1-184 7

8 84-B Unit 1 RCP 1-4 Spr. Sys. Isol.

FF-1-181-A 7

8 85-B Vent Line #1 Isol. off Unit 1 Cont.

Fire Water Header

'},

FP-1-197 7

8 84-D Vent Line *3 Isol. cff Unit 1 Cent.

Fire Water Header FP-1-188-A 7

8 83-B Vent Line #2 Isol. off Unit 1 Cont.

Fire Water Header FP-2-864 7

SA 81A-B Unit 2 Cont. Fire Water Sys. Manual Isci.

FP-2-891 7

8A 84A-D Unit 2 RCP 2-1 Spr. Sys. Isol.

FP-2-883 7

8A 86A-D Unit 2 RCP 2-2 Spr. Sys. Isol.

FP-2-880 7

8A 87A-C Unit 2 RCP 2-3 Spr. Sys. Isol.

FP-2-874 7

8A 85A-B Unit 2 RCP 2-4 Spr. Sys. Isc1, FP-2-870 7

8A 84A-B Vent Line 71 Isol. off Unit 2 Cont.

Fire Wuter Header FP-2-877 7

8A 86A-B Vent Line #2 Isol. off Unit 2 Cont.

Fire Water Header l

FP-2-887 7

8A 85A-D l

Vent Line r3 Isol off Unit 2 Cont.

i Fire Water Header l

CC0036 28IX l

l

NUMBER EP M-4 1 AND 2 REVISION 9 DIABLO CANYON POWER Pt. ANT UNIT NO(S)

DATE 6/1/85 PAGE 29 0F 50 EARTHQUAKE I

7,7 g

\\

POST EARTHQUAKE FIRE SYSTEM ISOLATION VALVES 102018 and 108018 & OVID 106718)

(Reference P&ID's (Page4)

Operating Valve P&ID OVID DVIL SHT No SHT No_

Coord System / Area 10 ho.

FP-1-24 5

6 60-E Temp Unit 2 Isol.

FF-2-27 5

6 66-E Temp Unit 2 Isol.

FP-2-26 5

6 63-C Temp Unit 2 Isol.

FP-2-345 7

6 67-E Temp Unit 2 Isol.

Tc te removec frorr list when Unit 2 goes cr.-line.

o DC0036 291X

OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP M-4 REVISION 9

(

DATE 6/1/85 PAGE 30 0F 50 TITLE EARTHQUAKE I

ATTACHMENT 1 i

POST-EARTHQUAKE INSPECTION AREA IDENTIFICATION n-

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DCCC36 221V

NUMBER EP M-4 1 AND 2 REVISION 9 DlABLO CANYON POWER PLANT UNIT NO(S)

DATE 6/1/85 PAGE 310F 50 EARTHQUAKE TITLE ATTACHMENT I (Cont'd) m*

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l DC0036 2 3 :'.'

OtABLO CANYON POWEQ Pt. ANT UN'T NO(S) 1 AND 2 N

R EP M-4 DATE 6/1/85 PAGE 32 0F 50 TITLE EARTHQUAKE ATTACHMENT 1 (Cont'd) i is y?

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i UMT 2 - TURBINE BUILDING, ELEV. 85' l

DC003f, 41IV

EP M-4 1 AND 2 m

DiASLO CANYON POWER PLANT UNIT P4)(S)

REVISION 9 OATE 6/1/85 PAGE 50 0F 50 EARTHQUAKE TITLE.

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69-9249 9/84 (10)

Page 1 of 3 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNITS 1 AND 2 DATA SHEET: POST-EARTHQUAKE LEVEL INDICATOR CHECK LIST. EP M-4 UNIT DATE INSTRUCTIONS: Check the indicators twice, at about 15 minutes to one hour apart.

Inform the Shift Foreman ~of any reading outside of its normal range, or which changes by more than expected in the interval.

UNIT 1 LEVEL / TIME Vertical Board 1 Reading 1 Reading 2 l

LI-139 CCW Surge Tank 1-IA

/

/

1 LI-140 CCW Surge Tank 1-1E

/

/

)

LI-931 Spray Additive Tank

/

/

LI-9fC Containc.ert Recirc Sump

/

/

LI-941 Containment Recirc Surp

/

/

l Vertical Board 2 LI-920 Refueling kater Storage Tank (S.T.;

/

/

LI-921 Fefueling Water S.T.

/

/

L!-922 Refueling Water S.T.

/

/

L1-112 Volure Control Tank

/

/

L*-149 Prirary Water Storage Tank

/

/

'e-t':21 oer-d ?

LI-14E Cor.dersate Stcrage Tar.k 1-1

/

/

LI-147 Transfer Tank 0-1

/

/

LI-144 Raw Water Res. 01A (West)

/

/

LI-145 Raw Water Res. 01B (East)

/

/

LI-146 Fire Water S.T.

/

/

Common Aux. Bldg. Control Panel LI-180 Mor.itor Tank 1-1

/

/

LI-181 Monitor Tank 1-2

/

/

i LI-188 RCDT 1-1

/

/

LI-60 Containeer,t Structure Sump 1-1

/

/

LI-61 Containment Structre Sump 1-2

/

/

LI-62 Reactor Cavity Sump, Unit 1

/

/

i LI-229 Waste Conc. Holding Tank 0-1

/

/

DC0036 51II

~

69-9249 9/84 (10)

Pagg 2 of 3 DATA SHEET: POST-EARTHQUAKE LEVEL INDICATOR CHECK LIST, EP M-4 i

LEVEL / TIME UNIT 1 Aux. Bldg. Control Panel (Cont'd)

Reading 1 Reading 2 LI-170 Liquid Holdup Tank 1-1

/

/

LI-168 Liquid Holdup Tank 1-2

/

/

LI-167 Liquid Holdup Tank 0-1

/

/

LI-168 Liquid Holdup Tank 2-1

/

/

LI-170 Liquid Holdup Tank 2-2

/

/

LI-165 Concentrate Holding Tank

/

/

LI-158 Equip. Drain Receiver (Rec.) 0-1

/

/

/

/

LI-160 Equip. Drain Rec. 0-2 LI-162 Flecr Drair. Rec. 0-1

/

/

LI-164 Floor Drain Rec. 0-2

/

/

LI-1E0 Monitor Tank 2-1

/

/

LI-181 Monitor Tank 2-2

/

/

LI-1EE RCDT 2-1

/

/

L1-60 Cor.tainmer. Structure Sump 2-1

/

/

LI-61 Contair er: Structure Sump 2-2

/

/

]

LI-62 Feacter Cavity Sump, Unit 2

/

/

Ur.:T 2 Vertical Soard 1 LI-139 CCW Surge Tank 2-1A

/

/

L:-140 CCW Surge Tank 2-1E

/

/

LI-931 Spray Additive Tack

/

/

LI-940 Containmer.t Recirc Sump

/

/

LI-941 Containment Recirc Sump

/

/

Vertical Beard 2 LI-920 Refueling Water Storage Tank

/

/

LI-921 Refueling Water Storage Tank

/

/

LI-922 Refueling Water Storage Tank

/

/

LI-112 Volume Control Tank

/

/

LI-149 Primary Water Storage Tank

/

/

l l

l DC0036 52!I l

l l

Page 3 of 3

,69-9249 9/84 (10)

DATA SHEET: POST-EARTHOUAKE LEVEL INDICATOR CHECK LIST, EP N-4 LEVEL / TIME UNIT 2 g

Vertical Board 3 Reading 1 Reading 2 LI-148 Condensate Storage Tank 2-1

/

/

LI-144 Raw Water Res. 01A (West)

/

/

LI-145 Raw Water Res. 016 (East)

/

/

i Data Taken By:

REMARKS:

4 Reviewed Ey:

Sr.11-Fore::.:' -

Date/ Time

/

J t

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DC0036 5311

69-9250 4/64 (10)

Page 1 of 10 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANY0h POWER PLANT UNITS 1 AND 2 g

DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST CONTAINMENT (OUTSIDE MISSILE SHIELD) EP M-4 UNIT 1 CHECKED BY TIME /DATE AREA - 6* (ELEV. 140' & ABOVE) INCLUDING DOME

& LINER, SPkAY HDRS. & PIPING, ETC.

/

AREA - 17 (ELEV. 117')

/

AREA - 30 (ELEV. 91')

/

L7.*T 2 CHECKED BY TIME /DATE AREA - 9 (ELEY. 240' & A50VE) INCLUDIhG D0yr

& LIhEh, SFsA) H3R5. 6 FIPING, ETC.

/

AREA - 25 (ELEY. 117')

/

A.Er - 4.- (E.E'.. !!')

/

c.E FA: *.i :

i Reviewed Ey:

Stift Fcreca-Time /Date

/

' Area cesignations refer to Attachrent I to Emergency Procedure M-4 DCCCSE 54:1

Page 2 of 10 t

69-9250 4/64 (10)

DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST CONTAINMENT (I J

MISSILE SHIELD), EP h-4 hOTE: TO BE COMPLETED ONLY IF Uhli IS SHUT 00WN.

4 UNIT 1 CHECKED BY TIME /DATE i

/

AREA - 16* (ELEV. 117')

/

AREA - 29 (ELEV. 91')

i

/

AREA - 44 (BELOW ELEV. 91')

UNIT 2 CHECKED BY TIME /DATE

/

AREA - 24 (ELEV. 117')

/

AREA - 29 (ELEV. 91')

/

AREA - 51 (ELEV. 91')

1 i.

4 REMAR.d:

i Re.tene: E, :

Sniit Fcreman Tite /Date

/

1 l

' Area designations refer to Attachment 1 to Emergency Procedure M-4 i

a i

i i

OC0036-55II I

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-<,.,___-__-,____..%-m, x..,_,

Page 3 of 10 59-9250.4/84 (10)

DATA SHEET: POST-EARTHOUAKE' AREA INSPECTION CHECK LIST AUXILIARY BUILDING (MAIN AREA), EP M-4 s

UNITS 1 & 2 CHECKED BY TIME /DATE

/

AREA - IU* (ELEV. 140')

/

AREA - 10A (ROUF AREA & EQUIP. ABOVE ELEV 140')

/

AREA - 13 (ELEY. 115' & 126')

/

AREA - 19 (ELEY. 115')

/

AREA - 20 (ELEV. 127')

/

AREA - 21 (ELEY. 115')

/

AREA - 22 (ELEV. 115')

/

i

' AREA - 32 (ELEt. 100')

/

f AREA - 33 (ELEV. 10C')

/

AREA - 34 (ELEV. 100')

/

AREA - 35 (ELEV. 100')

/

AREi. - 45 (ELEY. 55')

/

AREA - 4f. (ELB. EE'i

/

ARE; 47 (ELEY. E5')

/

AREA 4E (ELEV. EE')

/

AREA - 62 (ELEV. 73')

/

AREA - 53 (E.EY. D')

/

ADEA - 5 (ELE \\. 60' & 64')

/

APEA - SE (ELEY. 6L' & (I')

/

AREA - 56 (ELEt. 62 6 64')

/

AREA - SI (ELEV. 64')

REMARKS:

Reviewed By:

Shift Foreran Time /Date

/

' Area desigr.ations refer to Attachmer.t 1 to Emergency Procedure M-4.

DC0036 56II

i 69-9250 4/64 (10)

Page 4 of 10 DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST AUXILIARY BUILDING i

(PENETRATION AREAS). EP M-4 UNIT 1 CHECKED BY TIME /DATE

/

AREA - 7 (ELEY. 140')

/

AREA - 16 (ELEY. 115')

/

l AREA - 28 (ELEV. 100')

/

AREA - 43 (ELEV. 85')

d UNIT 2 CHECKED BY TIME /DATE

/

AREA - 8 (ELEY. 140')

/

AREA - 25 (ELEV. 115')

/

j AREA - 3E (ELEV. 100')

/

AREA - 49 (ELE'!. bb')

'e i

REF. art.5 :

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.... - -. - - -. - _. - - _. - -..., = -

69-9250 4/84 (10)

Page 5 of 10 DATA SHEET: POST-EARTHQUAKE AREA INSPECTIOh CHECK LIST FUEL HANDLING BUILDING (MAIN AREA), EP M-4 UNIT 1 CHECKED BY TIME /DATE AREA -2 (ELEY. 140')

/

AREA - 3 (ELEV. 140') HOT SHOP AREA

/

4 AREA - 12 (ELEV. 115' & 126')

/

f AREA - 27 (ELEY. 100')

/

i UNIT 2 CHECKED BY TIME /DATE AREA 4 (ELEV. 140')

/

AREA - 14 (ELEt. III' 6 116')

/

l AEEA - 36 (E.Ei. 100')

/

REMARid:

I l

I i

i

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?

DC0036 58!!

i

Page 6 of 10 69-9250 6/64 (10)

POST-EARTHOUAKE AREA INSPECTION CHECK LIST FUEL HANDLING BUILDjNG DATA SHEET:

(VENT EQUIPMENT AREAS), EP M-4 CHECKE0 BY TIME /DATE UNIT 1

/

AREA - 1 (ELEV. 140')

/

AREA - 11 (ELEV. 115')

/

AREA - 26 (ELEV. 100')

/

AREA - 42 (ELEY. 85')

CHECKED BY TIME /DATE UNIT 2

/

AEEA-5(ELEV.140')

/

/ PEA - 15 (ELEV.'115')

/

AREA (ELEY. 100')

/

AREA - it (E.E.. Li')

T E' *.e.t.i :

4 f

I DC0036 5911

69-9250 4/84 (10)

Page 7 of 10 DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST UNIT 1 TURBINE

~

BUILDING, EP M-4

)

UhlT 1 CHECKED BY TIME /DATE

/

AREA - 58 (ELEV. 140')

/

AREA - 60 (ELEV. 107' & 119')

/

AREA - 61 (ELEV. 119' & 125')

/

AREA - 62 (ELEV. 119' & 123')

/

AREA - 65 (ELEV. 107')

/

AREA - 66 (ELEV. 104' & 108')

/

AREA - 67 (MACH. SHOP OVERHEAD)

/

AREA - 31 (ELEV.109') Mh. STM. LINE PLTFM.

/

AREA - 7C (ELEV. 65' & EELOW)

/

AREA - 71 (ELEV. 65')

/

AREA - 72 (ELE'. 85' & EELOW)

/

AREA - 73 (ELEV. EE' & EELO'<.)

/

AREA - 74 (ELEt. Et')

REMARKS:

DC0036 6011

.2 69-9250 4/82 (10)

Page 8 of 10 DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST UNIT 2 TURBINE BUILDING, EP h-4 UNIT 2 CHECKED BY TIME /DATE i

/

ARLA - 59 (ELEV. 140')

/

AREA - 63 (ELEV. 119' & 125')

/

AREA - 64 (ELEY. 107' & 119')

/

AREA - 68 (ELEY. 104' & 108')

/

AREA - 41 (ELEV.109') Mk. STM. LINE PLATFM.

/

AREA - 69 (ELEY. 107')

/

AREA - 75 (ELEV. 85' & BELOW)

/

AREA - 76 (ELEi. 85' & BELOW)

/

AREA - 77 (ELEV. 85' & EELOW)

/

AREA - 76 (ELE'. 85')

REMARL5:

i i

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i OC0036 6111

69-9250 4/84 (10)

Page 9 of 10 DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CdECK LIST OUTSIDE AREAS, EP M-4 CHECKED BY TIME /DATE AREA - 79 (UNIT 1 F.H. BLOG. EXTERIOR, STOR.

TKS, STOR. AREAS, ETC.)

/

AREA - 80 (UNIT 2 F.H. BLOG. EXTERIOR, STOR.

TKS, STOR. AREAS, ETC.)

/

AREA - El (UNIT 1 BLDG. EXTERIORS, MN, AUX. &

STUP. XFMR. BKS. & STRUCTURES, ETC.)

/

AREA - 82 (UNIT 2 BLDG. EXTERIORS, MN, 8 AUX.

XFMR. BKS. & STRUCTURES, ETC. )

/

AREA - 63 (UNITS 1 & 2 DISCP. STRUCTURE)

/

AREA - 84 (230 AV SKYD. & LINES)

/

AREA - 85 (RAi kTE. STOR. PONDS)

/

AFEA - Et (50' tv Sh'YL. & LINES)

/

P EM* h;S :

2 DC0036 6211

69-9250 4/84 (10)

Page 10 of 10 DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST INTAKE STRUCTURE, EP M-4 CHECKED BY TIME /DATE

/

AREA - 87 (ELEV. 17.5')

/

AREA - 88 (ELEV. -2')

/

AFEA - 89 (AUX. SALT WATER PUMP COMPARTMENTS

/

& VENT. SHAFTS)

AREA - 90 (PIPE & DISCHARGE VALVE GALLERIES)

/

/

4 i

REMARK 5:

4 i

.),

i

]

I

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DC0C36 63!I

69-9261 4/84 (10)

Pag) 1 of 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNITS 1 AND 2 DATA SHEET: POST-EARTHQUAgg SURVEILLANCE TEST CHECX LIST, EP M-4 UNIT DATE INSTRUCTIONS: Check the data sheet when the time test is completed and the initials of the person performing the test.

TIME

/

INITIALS A.

Instrument Surveillance Tests 1.

1-1, Channel Check (shift and daily

/

portions only) a.

Shift Data Sheet

/

b.

Dai?) Data Sheet

/

2.

1-29, Emergency Signals and Communications

/

Syster Functional Test E.

Reactor and Au>iliaries 1.

R-1A, Excccising Full Length Control Rods

/

2.

F-10, Reat:ce Cociant Syster Leakage

/

1 Evaluatict..

i C.

Misteilaneous ar.d Integrated Tests 1.

M-16E 0 eratier cf Slave Relays K6U4A

/

ar.d K604E (Safety Injection).

2.

M-16C Operation of Slave Relay K605A

/

(Safety Ir.jection).

S.

M-163 Operation cf Slave Relay K6086

/

(Safety Injection).

4 M-16E Operation of Slave Relay K633A

/

and K609A (Safety Injection and Auxiliary FW Pump Start).

5.

h-16F Operation of Slave Relay K6338

/

ana K6095 (Safety Injection and Auxiliary FW Pump Start).

6.

M-161 Operatior, of Slave Relays K606A

/

and K606B (Phase A Containment Isolation).

REMARKS:

Reviewed By:

Shift Foreman Time /Date

/

DC0036 6411

+

69-9252 9/84 (10)

Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY 1

DEPARTMENT OF hUCLEAR PLANT OPERATI0h5 DIABLO CAhYON POWER PLANT UNIT NOS 1 AND 2 i

l DATA SHEET: POST-EARTHQUAKE ELECTRICAL POWER CHECK LIST, EP M-4 g

i DATE:

l INSTRUCTIONS:

Insure that the lines indicated are functioning properly.

Insure that the batteries are unoamaged and that the chargers continue to supply the load.

j Start all diesels and bring them to rated voltage.

A.

500 rv System TIME

/

INITIALS f

1.

Midway #2 line

/

2.

Midway #3 line

/

i l

j-3.

Gates line

/

l 4

Tie line tc Unit 1

/

i S.

Tie line te Unit 2

/

i

)

6.

500 KV Switch arc

/

/

E.

230 KV Syster 1.

Morre Bay-Diatic line

/

i 2.

Merre Bay-Mese line

/

l 3.

Tie lire to startu bank 1-1

/

4.

Tie line to startup bank 2-1

/

8 23C KV Sv.itchyrre

/

C.

Statier Ett eries & Chargers 1.

Eattery 1-1

/

~t i

1.

Esttery 1-2

/

l 3.

Battery 1-3

/

4 Battery 2-1

/

l S.

Battery 2-2

/

6.

Battery 2-3

/

i L.

Diesel Generators i

1.

Generater 1-1

/

c 3

i 2.-

Generator-1-2

/

i l

3.

Generator 1-3

/

l 4

Generator 2-1

/

1 5.

Generator 2-2

/

4 i

REMARKS:

[

e Reviewed By:

l Shift Foreman Time /Date

/

(

J

[

DC0036 65!!

1

69-10298 9/84 (10)

Page 1 of 3 PAC 3FIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: CALIBRATION AND TEST DATA SHEET. EP M-4 TM PEAK SHOCK RECORDER PSR1200 -

H (NORTH / SOUTH)

RECORDER S/N 701 CALIBRATION DATE 5/3/84 INITIALS SURFACE REC 0A0 PLATES S/N EQUIVALENT ACCELERATICN STATIC REED FREQUENCY SENSITIVITY DISPLACEMENT ACCELERATION NLVEER (Hertz)

(c/ inch)

(inches)

(c) 1 1.96 0.351 2

2.56 0.550 3

3.23 0.8LO 4

3.97 1.19 5

5.18 2.23 6

6.3-3.24 7

8.10 5.06 E

.0. 2 7.63 9

,2. 7

. l.6 10

,6.1

..9.2 11 20.2 27.8 12 25.6 45.5 Ca ;irg:

2' viscous carrir; (C of 26)

TESTER TEST DATE TEST LOCATION PREPARED BY TEST N'vMBER DATE

' Values based on Kinemetrics Calibration Test Report and Certification for DCPP Seise.1: Ins trumenta ticr..

f I

DC003E 6811

-_--_____.________..m..

Page 2 of 3 69-10291 9/84 (10)

TITLE: CALIBRATION AND TEST DATA SHEET. EP M-4 i

D PEAK SHOCK RECORDER 4,

i i

PSR1200 - H (East / West) 1 RECORDER S/N 710 CALIBRAT10h DATE 5/3/84 INITIALS f

SURFACE i,

RECORD PLATES S/N t'

EQUIVALEMI I

STATIC ACCELERATION i

REED FREQUENCY SENSITIVITY DISPLACEMENT ACCELERATION NUMBER (Hertz)

(a/ inch)

(inches)

(c) l 1

1.92 0.343 f

j 2

2.50 0.537 3

3.13 0.523 f

4 3.97 1.17 5

5.20 2.20 l

6 6.40 3.22 i

7.9c 4.94 i

.I e

,0.1 11.7 9

,2. 7 12.2

• I j

j 10

. 6.1 19.'

I 11 20.3 3C.E l

12 25.4 45.5

.) ;

i i

Darbing: 1.i viscous darping (0 of 25) i j

TEST DATE i t.STEk c

TEST LOCATION PREFARED BY TEST NUPSER DATE 1

t i

I l

i i

)

i 1

1 i

I l

i DC0036 6911 i

i e

1 69-10291 9/64 (10)

Page 3 of 3

'TITL E: CALIBRATf0N AND TEST DATA SHEET, EP M-4 TM PEAK SHOCK RECORDER I

PSR1200 -

V (VERT.)

RECORDER S/t<

728 CALIBRATION DATE 5/3/84 INITIALS i

RECORD PLATES S/N SURFACE EQUIVALEhT ACCELERATION STATIC REED FREQUENCY SENSITIVITY DISPLACEMENT ACCELERATION hUMBER (Hertz)

(g/ inch)

(inches)

(c) 1 1.92 0.315 2

2.49 0.493 3

3.23 0.516 4

3.53 1.10 5

5.15 2,06 6

6.43 3.13 7

8.06 4.9E 8

10.2 7.55 9

12.7 12.5 10 16.1 15.2 11 2u.2 25.6 12 25

• 44 l

l Dan;;;r.;: L siscous darping (( of 25)

TESTER TEST DATE TEST LOCA!!O'.

PREPARED BY TEST t.LMEER DATE h

s DC0036 70!!

l i

Page 1 of 2 69-9283 9/84 (10)

PACIFfC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: CALIBRATI0t. AND TEST DATA SHEET - PEAK ACCELERATION RECORDER. EP i

s DATE TIME PAR 400-1 RECORDER S/N 669 I

RECORD PLATE S/N CAL. DATE 10/1/81 l

l LOCATION: CONTAIhMENT BASE SLAB UNIT 1. EL. 89', 180*

ACCELERATION DI5 PLACEMENT ACCELERATIOh PERFORMED BY i

i SENSOR SENSITIVITY l

n/in g / r..

Inches mm (g)

L L6.3 0.640 T

16.1 0.635 V

15.4 0.6DC 4

DATE TIME PAR 400-2 RECORDER S/N 654 RECORC FLATE S/t.

CAL. DATE 10/1/81 j

LOCAT:Gr.: TOP OF Ur.:1 1 C0fiTAlfrEt.~, EL. 3C3.5', 225' ACCELEFATIOf.

015PLACEMEhi ACCELERAT10h PERFORMED BV SETTC SENSITfYlTY c ' i r.

c r rn-Incres er (g)

L 32.5 1.25 T

30.1 1.18 j

\\

32.3

.27 i

DATE TIME PAR 400-1 RECORDER S/N 673 t'

RECORD PLATE S/N CAL. DATE 10/1/61 LOCATION: INTAKE NEAR ASW PUMP 1-2 BAY, EL. 2' I

ACCEL EP.ATIOf.

D15PLACEMEf.T ACCELERAT10!4 PERFORMED BY SENSOC SENSITIVITY c/in g/ me.

I r.che s r:n (c)

L 13.1 0.515

\\

l 7

15.4 0.606 1

V 13.8 0.543 i

DC0036 66:1 1

l 69-9283 9/54 (10)

Page 2 of 2 TITLE: CALIBRATION AND TEST DATA SHEET - PEAK ACCELERATION RECORDER. EP M-4 I

DATE TIME PAR 400-1 RECORDER S/N 672 l

RECORD PLATE S/f4 CAL. DATE 10/1/81 i

LOCATION: TURBINE BUILDING, MACHINE SHOP EL. 85' ACCELERATIOh DI5PLACEMEr.T ACCELERATION PERFOKMLD BY

[

i SENSOR SEASITIVITY g/in g/nsn Inches mm (Q) f L

16.2 0.635 4

,i T

15.6 0.615 t

]

V 14.2 0.556 DATE TIME PAR 400-1 RECORDER S/N 682 1

RECORD PLATE S/h CAL. DATE 10/1/81 i

LOCATIC'.: AUXILIAki BUILDING, HOT SHOP EL. 140' I

ACCELERATION D15rLACEMENT ACCELERATIOh PERFORMED BY t

SEUSLR SFhSITIVITY j

g/ir.

g/rr Irches er (g)

L 15.3 0.601 i

T 15.4 0.606 1

i V

12.7 0.500 i

t i

I CATE TIME PAR 400-1 RECORDER S/N 683 RECORD PLATE S/t6 CAL. DATE 10/1/81 i

f LOCATION: AU).!LIARY BUILDING NEAR CONTROL ROOM 000R, EL.140' l

ACCELERATION DI5PLACEMEhT ACCELERATION PERFORMED BY SENSOR SENSITIVITY g/in g/rxr Inches rr (g)

I L

16.2 0.635

~

i l

T 16.0 0.630 i

V 14.3 0.562 l

i 1

l DC0036 6711 l

69-9248 9/84 (10)

Page 1 of 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNITS 1 AND 2 DATA SHEET: POST-EARTHQUAKE EVALUATION

SUMMARY

EP M-4 4

1.

DATE/ TIME OF QUAKE

/

2.

POWER LEVELS: UNIT 1

MWE, UNIT 2 MWE 3.

PEAKACCELERATION(FROMEFM-1orSMA-3)

NORTH-SOUTH G: EAST-WEST G: VERTICAL G

TIME

/

INITIALS 4

CHECK LISTS a.

Seisric Instrum.ent Procedure

/

b.

Level Indicator Check List

/

c.

Surveillance Test Check List

/

d.

Electrical Power Check List

/

E.

Area Inspectic' Cnece. L1st

/

REMA:r.5:

5.

Epicer.ter:

Magnitude 0:tain cay after tne earthquake fron U.C. Berkeley Seismographic Statior. -

Reviewed by:

Pcwer Productier. Engineer Date/ Tire

/

DC0036 50!!

+

PGandE Letter Ns.: DCL-85-245 i

i CURRENT B4ERGENCY PLAN NPLEMENTING PROCEDURES

^

TMILE OF CONTENTS Yolune 38 l

TITLE REV l

OR-1 Offsite Support & Assistance 5

l OR-2 Release of Information to the Public 3

i EF-1 Activation and Operation of the Technical Support Center

• 5 EF-2 ktivatton and Operatton of the Operattonal Support Conter 5

EF-3 Activation and Operation of the Emergency Operations Facility 5

EF-4 Activation of the Mobile Environmental Monitoring Laboratory 6

i EF-5 Emergency Equipment, Instruments & Supplies 6

EF-6 Operating Procedures For EARS 9845C Controlling Stations 4

1 EF-651 Transfer of EARAUT Control 1

EF-8 EARS Operating Procedures for TSC-CC HP-1000 Station 0

i R8-1 Personnel Dosimetry 1

R8-2 Emerpncy Exposure Guides 1

R8-3 Stabte Iodine Thyroid Blocking 1

RS-4 kcess to a Establishment of Controlled Areas i

Under Emergency Conditions 2

R8-5 Personnel Decontamination 2

{

R8-6 Area a Equipment Decontamination 2

RB-7 Emergency On-Site Radiological Environmental Monitoring 4

RB-8 Emergency Off-Site Radiological Envfronmental Monitoring 4

RB-9 Calculation of Release Rate & Integrated Release 3

RB-10 Protective Action Guidelines 1

R8-11 Emerpncy Of f-Site Dose Calculations 4

RB-12 Mid and High Range Plant Vent Radiation Monitors 1

i R8-13 Improved In-Plant Air Sampling for Radiof odines 1

R8-14 Core Damage Assessment Procedure 2

1 R8-15 Sentry Post kcident Sampiing System (SPASS) l Initial Sampling Exercise After An Accident 1

i R8-15A SPASS Inf tial ktions During An Emergency 3

RB-158 SPASS Reactor Coolant Sampling (Stripped-Gas and Diluted RCS) 2 i

i f

0502d/0005K 07/18/85 i

i TITLE REY 1

(

RB-15C SPASS Containment Air Sampling 2

RB-150 SPASS Gas Chromatographic Hydrogen Analysis 2

l RB-15E SPASS RCS Liquid and Gas Sample Handling 2

i RB-ISF SPASS Data Analysis 1

RB-15G SPASS Ion Chromatographic Chloride Analysis 1

l RB-15H SPASS pH/ Conductivity / Dissolved Oggen 1

j RB-15I SPASS Sample Storage and Disposal 0

0 RB-16 SPASS Subsequent Sampling

^:

RB-16A SPASS Initial Actions During An Emergency (Not Intended to Meet The 3-Hour Time Limit) 2 i

RB-1681 SPATS Diluted Liquid Sampling From Reactor Coolant j

(Not Intended to Meet The 3-Hour Time Limit) 1 R8-16B 2 SM'a Undiluted' Liquid Samp1ing From Reactor Coolant 1

(Not Intended to Meet The 3-Hour Time Limit) 4 SMS Reactor Coolant Stripped Gas Sampling) l RB-16B 3 (Not Intended to Meet The 3-Hour Time Limit 1

i R8-1684 SMS Diluted Liquid Sampling From Ra&aste (Not Intended to Meet The 3-Hour Time Limit) 2 l

R8-1685 SMS Undiluted Liquid' Sampiing From Rahaste (Not Intended to Meet The 3-Hour Time Limit) 2 R8-16C SMS Containment Alr Samp1ing

+

(Not Intended to Meet the 3-Hour Time Limit) 1 i

RB-160 SM Gas Chromatographic Hydrogen Analysis 4 4

(Not Intended to Meet the 3-Hour Time Limit) 1 RB-16E SM Liquid and Gas Sample Handling

)

(Not Intended to Meet The G-Hour Time Limit) 1 j

RB-16F SMS Data Analysis (Not Intended to Meat The 3-Hour Time Limit) 0 RB-16G SM Ion Chromatographic Chloride Analysis (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16H; SE Ph/ Conductivity Dissolved Oxygen (Not Intended to Meet The 3-Hour Time Limit) 1 i

RB-16I SM Undiluted Containment Air Sampling l

(Not Intended to Meet The 3-Hour Time Limit) 0 RB-16J SMS Sample Storage and' Disposal l

(Not Intended tof Meet The 3-Hour Time Limit) 0 d

y i

+

i s

y [.

r l

s

'?

h 2-07/18/85 l

0502d/0005K

.,+-s

~

r-.y..

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,m, m

v.-,,ww m,n

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a.,,.,,,

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NUMBER EP OR-1 9GsG Pacific Gas and Electric Company REVISION 5 DATE 5/15/85 OEPARTMENT OF NUCLEAR Pt. ANT OPERATIONS PAGE 1 0F 2

]

ciAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE TITLE:

OFFSITE SUPPORT AND ASSISTANCE IMFORTAN Y

TO APPROVED:

PLANT MANAGER,)

DATE SAFETY SCOPE This procedure provides a functional list of non-PGandE organizations which are available for emergency response support and assistance.

Telephone numbers are provided which are to be used for initial notification of the need for emergency support. Organizations required to be notified of an emergency are addressed in the procedures referenced below or in the procedure dealing with the type of event. This procedure and changes thereto requires PSRC review, s

GENERAL 1.

Requests for support or assistance from non-company organizatico should be specific concerning the nature of the support or assistance requested, the location where needed, when it is needed, and the phone number to use to return a call. Requests may be made to mobilize support on a standby basis.

2.

All initial request for support shall be approved by the Site Emergency Coordinator or the Recovery Manager at the EOF.

Subsequent requests shall receive the same approval if they require additional resources. Requests for assistance from organizations supporting San Luis Obispo County also require County Emergency Services Director approval prior to making the request.

3.

Emergency response organizations are listed in Appendix 1 under the following functional titles:

Radiological Emergency Protective Actions Medical Emergency Fire Emergency Health Physics / Assessment Support Plant Operation / Repair Support Offsite Emergency Response Support Law enforcement emergency contact means are addressed in the appropriate security procedures, DC0043 1XI j

l

O l[lSf0N otA8LO CANYON POWER PLANT UNIT NC S) 1 AND 2 5

OATE 5/15/85 PAGE 2 0F 2 TITLE.

OFFSITE SUPPORT AND ASSISTANCE SUPPORTING PROCEDURES NPAP Cll, and its supplements, "Non-routine Notification and Reporting to the NRC and Other Governmental Agencies" EP G-3

" Notification of Offsite Organizations" ATTACHMENTS

1. - Offsite Support and Assistance Functional Description 2.

Table 1 - Offsite Emergency Support Organization Phone List.

4 DC0043 2XI

PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 ATTACHMENT 1 TITLE: OFFSITE SUPPORT AND ASSISTANCE CONTACT LIST - EP OR-1 I.

Radiological Emergency Protection Actions The organizations If sted in Table 1 under this heading provide support to the San Luis Obispo County Emergency Organization in implementing protective actions for the general public.

All support requests from these organizations should be coordinated with San Luis Obispo County. Direct requests for support would not ordinarily be required, but exceptions to this may be necessary in the event of an initial notification to San Luis Obispo County requiring imediate protective actions in the low population zone (6 mile radius) or beyond in the affected sectors.

II. Medical Emergency The organizations Ifsted in Table 1 under this heading provide assistance in the transportation or treatment of persons injured and contaminated with radioactive material, and/or overexposed to radiation or radioactive materials. Persons so i

injured will nonnally be treated at French Hospital in San Luis Obispo, however, Saint Francis Memorial Hospital is also available should the need for additional hospital services arise.

III. Fire Emergency The organizations listed in Table 1 under this heading provide backup fire fighting support to the California Departcent of Forestry (CDF), in the site area. Assistance is coordinated through CDF in all cases.

IV. Health Physics / Assessment Support The organizations listed in Table 1 under this heading provide assistance in on or offsite monitoring, radiation protection or radiological accident assessment.

Requests for assistance are coordinated through the Emergency Radiological Advisor for onsite or near site activities and with San Luis Obispo County for offsite activity.

V.

Plant Operation / Repair Support The organizations Ifsted in Table 1 under this heading provide assistance in technical assessment of plant conditions, and in maintenance / repair projects. Only those organizations with defined emergency response roles are included. Assistance from these organizations and from the resources of PGandE, other utilities and vendors are available through the Corporate Emergency Response Organization.

~

I DC0043 3VIII

Page 2 of 2 TITLE: OFFSITE SUPPORT AND ASSISTANCE CONTACT LIST - EP OR-1 VI. Offsite Emergency Response Support The organizations listed in Table 1 under this heading provide offsite response support to the San Luis Obispo County Emergency Organization, or are available for support of PGandE offsite operations. These support organizations are categorized as:

1)

Transportation 2)

Law Enforcement 3)

Traffic Control 4)

Public Alerting and Care O

=

i l

)

DC0043 4VIII

PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS, 1 AND 2

\\

TABLE 1 TITLE: 0FFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 Organization Function (s) location (s)

Phone Number (s)

I.

Radiological Emergency Protective Actions US Coast Guard

1) Clear craft from Marine water near DCPP Safety Office

2) Shipboard San Francisco radiological or i

monitoring Monterey Operation decontamination State Protective actions in San Luis Obispo Department of State Parks & Beaches:

Headquarters Parks &

Montana De Oro Recreation Avila State Beach Hearst Castle Pismo State Beach

~

Morro Bay State Park Pismo Ranger Atascadero State Beach Station Pismo Dunes Station State Ingestion pathway 744 "P" St.

Department of monitoring coordination Sacramento, CA Public and food stuff Health-Radiolog-interdiction as required.

feal Health Section II.

Medical Emergency (See procedures M-1 and R-1 also)

San Luis Onsite ambulance service. 358 Santa Rosa Ambulance San Luis Obispo i

Service, Inc.

Air Ambulance, Air Transportation 701 Skyway Inc.-

(fixed wing or San Carlos CA helicopter) from site or airport (under PGandE contract).

l California Air Medivac Hunter Ligget j

National Guard

~

l l

DC0013 SX

=

d Page 2 of 9

\\

TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued) i Organization Function (s)

Location (s)

Phone Number (s)

San Francisco Ambulance Service in 2829 California Ambulance the San Francisco Area.

Street Service San Francisco French Hospital Emergency Medical 1911 Johnson Ave.

Treatment San Luis Obispo Dr. Fred Mettler Consultant on VA Hospital (REMS Corp.)

Radiological Injuries Albuquerque, New Mexico

- or -

3004 La Mancha St.'

N.W.

Albuquerque, NM i

Saint Francis Emergency Medical 900 Hyde Street Memorial Treatment San Francisco Hospital i

III.

Fire Emergency California

' Primary Site Fire Highway 1 T

Department of Fighting Response San Luis Obispo I

Forestry Air Attack Base 3

Paso Robles Airport Arroyo Grande Backup fire fighting 140 Traffic Way Fire Departwent support.

Arroyo Grande Pismo Beach Backup fire fighting 1000 Bello Ave.

Fire Department support.

Pismo Beach San Luis Obispo Backup fire fighting Garden & Pismo Fire Department support.

Streets San Luis Obispo South Bay Fire Backup fire fighting 2315 Bayview Department support.

Heights Drive Los Osos Morro Bay Fire Backup fire fighting 715 Harbor Department support.

Morro Bay l

l p

1 OC0043 6X

Page 3 of g TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued)

\\

Organization Function ('s)

Location (s)

Phone Number (s)

IV. Health Physics / Assessment Support Onsite Nuclear

1) Onsite assessment 1450 Maria Lane Regulatory

2) Coordinate federal Suite 260 Commission technical response Walnut Creek, CA Region V

3) Develop protective action Incident Response recommendations.

Center

4) Radiological monitoring Sacramento Chemical-Radiation Rancho Seco Municipal assistants and equipment. Heald, CA Utility District Control Room Southern Health Physics San Onofre California technicians and San Clemente, CA Edison equipment.

Portland

. Chemistry and/or Portland, Oregon General Electric Radiation Protection V.P. Nuclear Gen.

Technicians and Mgr., Tech.

Equipment.

Funct.

Trojan Plant General Manager Washington Health Physicist and WNP-2, Hanford, Public Power Health Physics / Chemistry Wash. Emerg.

Supply System Technicians and equipment Coordinator or Security Control Arizona Public Radiological Engineer or Shift Supv.

Service Supervising Radiation or Physicist, Chemist or Supervising Chemist, Rad. Prot. Office Radiation Protection Tech, Chemistry Techs.

0C0043 7X L.

~

Page 4 of 9 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued)

Organization Function (s) location (s)

Phone Number (s)

Department of

1) Federal offsite San Francisco Energy monitoring and Operations assessment Office-Region 7 coordination.

7333 Broadway

2) Coordination of Oakland, CA Federal response (IREPCoordination).

Nevada Operations not in service Office Las Vegas, Nevada Environmental Complete radiological Dave Duncan, Protection mcnitoring and Regional Agency assessment assistance.

Radiation Representative, Region IX, San Francisco Wayne Bliss, Director of Office of Radiation Programs, Las

)-

Vegas Facility Department of Assist in monitoring and HQ-6th Army l

Defense medical assistance if Presidio of San (Army) requested by the IRAP Francisco coordinator or local authorities (Nuclear Accident Incident Control Teams),

i l

Department of Assist in monitoring and Comander - Naval Defense medical assistance if Base (Navy) requested by the IRAP San Diego, CA Coordinator (Nuclear Accident Teams).

National Weather reports, -

WSFO-Redwood Weather forecasts and special Service -

advice from Weather City-(NOAA)

Service Forecasting Offices (WSFO)-normally WSFO-Los coordinated through Angeles l-Meterology personnel in l

CIRC.

l I

DC0043 8X

-~.

Page 5 of 9

. TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (cont I

Organization Function (s)

Location (s)

Phone Number (s)

State Office Assessment support to Emergency of Emergency local agencies.

Response Center Services Sacramento, CA State Department Ingestion pathway 744 "P" Street of Pubite monitoring coordination Sacramento, CA Health-Radiolog-and food stuff ical Health interdiction as required.

Bureau San Luis Obispo Coordinate county County Gov't.

County of emergency response Center Emergency activities and emergency San Luis Obispo Services planning.

San Luis Obispo Direct offsite moni-2191 Johnson Ave County toring and _ssessment San Luis Obispo Environmental activities of San Luis Health

'Obispo County.

5574 Capistrano Ave. Atascadero V.

Plant Operation / Repair Support Westinghouse Technical, onsite or Monroeville (Notify as Electric Company materials assistance or Nuclear Center Indicated Below) reactor systems or components.

NOTIFY ONLY IF TECHNICAL, ONSITE OR HATERIALS ASSISTANCE ON REACTOR SYSTEMS IS NEEDED PROVIDE PLANT EMERGENCY NUMBER FOR REPLY. NOTIFY ONE WESTINGHOUSE CONTACT ONLY USING THE BELOW LIST IN THE ORDER SHOWN.

TITLE NAME OFFICE /HOME/HOME HOT LINE NOTE: Ur.less indicated otherwise, all phone numbers are area code Where an area code other than is shown, it applies to the office, nome, and HHL numbers.

~

1.

SITE SERVICES RON BUCilHOLZ MANAGER 2.

OPERATING PLANT GIL KUBANSEK RESIDUAL MANAGER IST ALTERNATE JOH1 GALLIK 2ND ALTERNATE JOHN MISK0 DC0043 9X

~

Page 6 of g TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued)

TITLE NAME OFFICE /HOME/HOME HOT LINE 3.

SERVICE RESPONSE TOM MITLO MANAGER IST ALTERNATE 808 STOKES 2ND ALTERNATE J0E LEBLENG 4

EMERGENCY RESPONSE TOM ANDERSON l

DIRECTOR i

5.

EMERGENCY RESPONSE RON LEHR l

OEPUTY DIRECTOR 6.

EMERGENCY NEWS MIKE MANGAN COMMUNICATIONS Organization Function (s)

Location (s)

Institute of

1) Locating emergency Emergency Nuclear Power manpower and Response Center Operations equipment Atlanta, Georgia

2) Operational analysis s

3) Information J

dissemination

4) Organization of experts for advice Rogers Helicopter on standby Rogers Helicopter Helicopter under PGanaE contract Clovis, CA sound system and lighting.

Rory Rogers (home)

- or -

Robin Rogers Rotor-Aids, Inc. Helicopter (s), as Rotor-Aids, Inc.

available, under PGandE 0xnard, CA contract.

Aris Helicopter Helicopter (s),as San Jose available under PGandE contract. Medivac capability.

DC0043 10X J

4 Page 7 of 9 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued) 4 Organization Function (s) location (s)

Phone Number (s)

Condor Helicopter (s),as Condor Helicopters available, under PGandE Helicopters and contract. At least 1 Aviation Inc.

Ifght duty helicopter Oxnard Airport available at all times.

Ventura, CA or Mr. Gary O' Conner Chief Pilot l

Air Ambulance, Fixed wing or helicopter Mr. Steve Smith International air ambulance service 795 Skyway San under PGandE contract.

Carlos, CA California Fixed wing and helf-Air Attack Base Department of copter for county /

Paso Robles Forestry state support, as Airport available.

VI. Offsite Emergency Response Support Transportation California

1) Fixed wing or San Francisco Area Highway Patrol helicopter for 455 8th Street transportation of San Francisco essential personnel.

2) Escort of priority vehicles.

State San Luis Obispo Area S.L.O. H.Q.

l' Parks and Recreation Hearst Castle Department Ken Huddlescon Emergency Coordinator l-24 Hour Dispatcher Pismo Beach (Ranger' Station)

DC0043 11X.

Page 8 of 9 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (contin Organization Function (s)

Location (s)

Phone Number (s)

Law Enforcement San Luis Obispo 1) Law enforcement in Ofspatch office l

I County Sheriff county areas not County under city PD's.

Operational

2) Primary response Facility agency under SLO Highway 1 County emergency San Luis Obispo plan.

Arroyo Grande Law enforcement in 200 N. Halcyon Police Arroyo Grande.

Rd.

Department Arroyo Grande Atascadero law enforcement in Administration Police Atascadero.

Building Department Lewis Ave.

Atascadero Morro Bay Law enforcement in 850 Morro Bay

}

I Police Morro Bay.

Boulevard Department Morro Bay Pismo Beach Law enforcement in Pismo 1000 Bello Ave.

Police Beach.

Pismo Beach Department San Luis Obispo Law enforcement in San 575 Santa Rosa l

i l

Police Luis Obispo.

San Luis Obispo Department Monterey County Law enforcement in Salinas l

Sheriff Monterey County.

Santa Barbara Law enforcement in Santa Santa Barbara County Sheriff Barbara County.

Traffic Control (City police, fire and public work also support)

California

1) Primary traffic 675 Calif. Blvd.

Highway Patrol control support to San Luis Obispo SLO County.

(

2) Fixed wing or Coastal Div. H.Q.

~

helicopter traffic 1122 Laurel Lane surveillance.

San Luis Obispo DC0043 12X

i Page 9 of 9 i

TITLE:

OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - E Organization Function (s)

Location (s)

Phone Number (s)

Public Alerting and Care American Nuclear Emergency assistance 270 Farmington Insurers (ANI) funding of the public for Ave.

emergency response Farmington, Conn.

expenses from an extraordinary nuclear occurance. Assistance is coordinated through CIRC, C.orporate Liaison Coordinator.

American Red Primary operator of care 1216 Morro Cross and feeding facilities San Luis Obispo in support of SLO County.

Emergency Primary stations for XVEC Broadcast providing emergency 820 Walnut Stations public information in San Luis Obispo support of SLO County.

KSLY 2895 S. Higuera San Luis Obispo KATY 1146 Monterey San Luis Obispo 6

J DC0043 13X

- __