ML20092K833

Public Version of Emergency Plan Implementing Procedures, Including EP OP-0, Reactor Trip W/Safety Injection, Rev 4 to EP G-2, Establishment of Onsite Emergency Organization & Rev 0 to EP RB-14, Core Damage Assessment Procedure

ML20092K833
Person / Time
Site:	Diablo Canyon
Issue date:	05/21/1984
From:	PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML16341C179	List: DCL-84-189, Forwards Public Version of Emergency Implementing Procedures,Including Rev 6 to EP OP-0, Reactor Trip W/ Safety Injection & Rev 4 to EP G-2, Establishment of Onsite Emergency Organization. W/Jm Felton 850625 Memo ML20092K833
References
PROC-840521, NUDOCS 8406290132
Download: ML20092K833 (94)

Text

_

1 PGandE Letter No. : DCL-84-189 I

,O l

a CURRENT EMERGENCY PLAN i.

H IMPLEMENTING PROCEDURES TABLE OF CONTENTS f

Volume 3A TITLE REV l

i

)

6

\\

OP-0 Reactor Trip With Safety Injection OP-1 Loss of Ccolant Accident 7

[

2 l-OP-2 Loss of Secondary Coolant OP-3A Steam Gen Tube Failure 5

l' OP-38 Minor Steam Gen Tube Failure 1

OP-4A Loss of Electrical Power 1

0 i

OP-4B Loss of All AC Power OP-5 Reactor Trip Without Safety Injection 5

6~

.OP-6

. Emergency Boration r

l-OP-7 Loss of Condenser Vacuum 2

i l

OP-8 Control Room Inaccessibility 8

~

OP-9 Loss of Reactor Coolant Pump 4

OP-10 Loss of Auxiliary Salt Water 2

t OP-11 Loss of Component Cooling Water 3

l j

OP-12 Malfunction of Auto Reactor Control System 1

OP-12A Failure of a Control Bk to Move in Auto 2

OP-128 Cont Withdrawl of a Control Rod Bank 3

l OP-12C Cont Insertion of a Control Rod Bank 2

OP-120 Control Rod Pos Indication Sys Malfune 3

i E

OP-12E Control Rod Misalignment 2

2

'0P-12F Dropped Control Rod OP-13 Malfunction of Reactor Press Control System 3

2 OP-14 High Activity in Reactor Coolant OP-15 Loss of Feedwater 4

l' OP-16 Nuclear Instrumentation Malfunctions 3

OP-17 Malfunction of RHR System 2

1 OP-18A Loss of Charging 0P-188 Loss of Nomal Letdown 1

OP-19 Malfunction of Reactor Makeup Control 2

l 0P-20 Excessive Reactor Coolant System Leakage 2

1 f

l

+

l s

i 1

B406290132 840625 l

PDR ADOCK 05000275 F

PDR-05/21/84 l

i 0502d/0005K

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i

., -,. -... -. - - ~,..... ~..,. - - _., - - - - - - -. - -. - -. -. -.. - - - - -. _. ~ -..

n G' f REY TITLE 2

OP-21 Loss of A Coolant Loop RTD 1

OP-22 Emergency Shutdown OP-23 Natural Circulation of Reactor Coolant 3

1 OP-24 Loss of Containment Integrity 2

OP-25 Tank Ruptures 1

OP-26 Excessive Feedwater Flow 1

OP-27 Irradiated Fuel Damage 1

CP-28 Startup of an Inactive Reactive Coolant Loop 1

OP-29 Excessive Load Increase 1

OP-30 Inadvertent load Fuel Assiv Improper Pos 1

OP-31 System Under Frequency 1

OP-32 Rod Ejection 1

OP-33 Loss of Instrument Air 1

OP-34 Generator Trip - Full Load Rejection OP-35 Loss of Vital or Non-Vital Instr AC Sys 1

1 OP-36 Turbine Trip OP-37 Loss of Protection System Channel 1.

5' OP-38 Anticipated Transient Without Trip (ATWT) 1 OP-39 RCP Locked Rotor Accident 1

OP-40 Accidental Depressurization of MS System 1

OP-41 Hydrogen ". Explosion" Inside Containment

(~_

OP-44 Gaseous Voids in the RCS 2

11 R-1 Per Injury (Rad Related) And/0r Overexp 4

R-2 Re1 of Airborne Radioactive Materials 3

R-3 Re1 of Radioactive Liquids 3

R-4 High Radiation (In Plant) 3 R-5 Radioactive Liquid Spill 6

R-6 Radiological Fire 4

R-7 Offsite Transportation Accidents 11 M-1 Employee Injury of Illness (Nonradiological) 10 M-2 Nonemployee Injury or Illness (Third Party) 5 M-3 Chlorine Release 7

M-4 Earthquake 5

e M-5 Tsunami Warning 8

M-6 Nonradiological Fire 6

M-7 011 Spill ISO and Clean Up Procedure 0

M-8 Containment Emergency Personnel Hatch 1

i M-9 Hazardous Waste Management Contingency Plan G-1 Emergency Classification and Emergency Plan i

3 Activation G-2 Establishment of the On-Site Emergency 4

Organization G-2 S1 Emergency Organization Call List Fonn 69-10297 0

2 G-3 Notification of Off-Site Organizations 3

i G-4 Personnel Accountability and Assembly 1

G-5 Evacuation of Nonessential Site Personnel 05/21/84 0502d/0005K

i NUMBER EP OP-0 3Gy43 Pacific Gas and Electric Company REVISION 6 DATE 4/12/84 A

DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 20 I q' l

CIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 IMPORTANT f

EMERGENCY OPERATING PROCEDURE TO l

T TLE.

REACTOR TRIP WITH SAFETY INJECTION

.., n e

SAFETY g

O APPROVED:

FLlJiT MANAGERM OATE l

SCOPE This procedure covers the initial operating steps to be taken in the eventThe safety i of a reactor trip with safety injection signal.

If this is may occur at some time after the reactor trip has taken place.the Injection) procedure and will use this procedure to control and analyze the This procedure and changes thereto require PSRC review.

plant condition.

I SYMPTOMS l

The following symptoms are typical, of those which may arise in a plant which' is undergoing a loss of reactor coolant, loss of secondary coolant or steam generator +ube rupture (one or more symptoms in each category may appear in any order)2:

LOSS OR REACTOR COOLANT 6

l to Pressurizer Pressure Lo Pressurizer Water Level Hi Pressurizer Water Level

. Letdown Isolation / Pres 5urizer Heater Cutout Increased Charging Flow l

Hi Containment Pressure Hi Containment Temperature Hi Containment Humidity Hi Containment Radiation Hi Containment Recire. Sump Water Level l

The process variables referred to in this Instruction are typically monitored 1

~

The redundant channels should be by more than one instrumentation channel. checked for consistency The pressurizer water level indication should always be used in conjunction with other specified reactor coolant system indications to evaluate i

system response and to initiate manual operator actions.

2

__._.-m

N ER EP OP-0 OtASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2

.p o9 DATE A/12184

-l PAGE 2

-CF 20-t REACTOR TRIP WITH SAFETY INJECTION TITLE:

LOSS OF SECONDARY COOLANT

~

Lo Pressurizer Pressure Lo Pressurizer Water Level Letdown Isolation / Pressurizer Heater Cutout Lo-Lo Reactor Coolant Tavg Hi Contair. ment Pressure Hi Containment Temperature Hi Containment Recire. Sump Level l

Steam Flow /Feedwater Flow Mismatch Lo Steam Line Pressure (one or, all Steam Lines)

Lo Steam Generator Water Level Hi Steam Flow (one or all Steam Lines)

Lo Feedwater Pump Discharge Pressure STEAM GENERATOR TUBE RUPTURE Hi Air Ejector Radiation Lo Pressurizer Pressure to Pressurizer Water Level Increasing Charging Flow Letdown Isolation / Pressurizer Heater Cutout Steam Flow / Feed Flow Mismatch Hi Steam Generator B10wdown Radiation Increasing Stem Generator Water Level AUTOMATIC ACTIONS _

1.

Reactor Vip and turbine trip.

2.

Safety injection initiated.

1 OBJECTIVES g

To verify the reactor trip and safety injection.

1.

-,~

r NUMBER EP 0P-0 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 DATE 4/12/84

• [

PAGE 3 OF 20 3

TITLE REACTOR TRIP WITH SAFETY INJECTION

[f the Alant is in a condition which warrants a reactor trip NOTE.-

and safety injection and an automatic reactor trip and safety

~P yet occurred, it is the reactor operators inject r-h==

i aa+

responsibility to manually initiate the reactor trip and j

safety intee. tion.

To verify all SI equipment is operating and performing the intended I

2.

function.

To monitor plant parameters and diagnose the initiating SI signal.

3.

l To mitigate the consequences of a valid SI signal by providing direction 4.

once the initiating signal is identified.

IEEDIATE OPERATOR ACTIONS

_ COMMENTS l

ACTION i

1.

Verify the following automatic actions.

If required, use manual control to satisfy the action.

i l

Reactor trip (all rods on bottom, DRPI -

l a.

Nuclear Instruments Decreasing.)

I

~

b.

Turbine trip (all four SV closed on EH panel.)

Vital 4160 busses F, G and H transferred c.

to startup ' power (breaker positions on i

VB 4.)

l Vital 4160 busses F, G and H voltage normal l

d.

(120 volts indicated on 480 volt vital busses l

F, G and H, VB-4.)

l Diesel generators running and voltage normal f

e.

(diesg3 RPM and generator voltmeter on V8-4.)

l Auxiliary building ventilation system in build-l ing and safeguards mode (mode light on venti-l f.

1ation section of VB-4).

Control room ventilation system in mode 4 l

g, (mode light on VB-4).

1 Both motor driven auxiliary feedwater pumps

(

j' h.

and all 4 auxiliary feedwater LCV i

running (Motor breaker position lights and open.

1 LCV position indicators on VP-3).

e l

NuusER EP OP-0

[

1 AND 2 REVISION 6 AsLO CANYON POWER PLANT UNIT NO(S)

DATE 4/12/84 ot PAGE 4

CF' 20' l

REACTOR TRIP WITH SAFETY INJECTION TITLE:

l' l

C09?ENT!

ACTION Check the safeguards postage stamp

~

l 1.

monitor lights on V8-1.

2 steam loops have Hi steam finw in

.I.f.

alam with any 2 loop Lo pressure in alam 2 steam loops have Hi steam flow in l

OR alam with any 2 loop Lo-Lo Tavg in l

i alam Verify all 4 main steam isolation THEN:

valves, bypass valves and all 4 steam generator blowdown stop valves IC closed (valve oosition indication l

lights on VB-3).

l J. Verify minimum of one ALL ECCS pumps have started and ECCS train operating automatic valve operations have (SI, charging and RHR l

j.

occurred (all SI/FW ISOL/STM GEN pump)

LEVEL postage stamp monitor lights on VB-1 not in alam).

i Contaiment Phase A and contaiment k.

ventilation isolation (all contain-ment Phase A postage stamp monitor

[

lights on VB-1 not in alam).

l p

SUBSEQUENT OPERATOR ACTIONS (PART A) 5 Verify the following pump flows.

1.

i l

If the flows are not occurring, attenpt l

to operate equipment manually or locally I

I to establish the flows.

l I

I t

I l

9 i

ER EP OP-0 1 AND 2 IABLO CANYON POWER PLANT UNIT NO(S)

I D

DATE 4/12/84 PAGE 5 OF 20

<]

REACTOR TRIP WITH SAFETY INJECTION TITLE:

COM9ENTS ACTION a.

NOTE: If W.R. rcd Pressure i

R1nimum ui une safety injection is greater than the shut-l

+

a.

pump running with flow indicated off head of the SI pump, when *..;. RCS pressure is less continue on with this pro-than the SI pump shutoff head cedure to monitor W.R. RCS l

(1465 psig).

(VB-1) pressure and verify SI pump flow if pressure drops be-i low the shutoff head of the SI pump.

b.

Minimum of one charging pump running with flow via BIT indi-cated on FI 917.

(VB-2) f Verify both motor driven AFP c.

running and flow indicated, to all 4 steam generators (VB-3),

l OR Start the steam driven AFP by opening FCV 95 and establish j

flow to all 4 steam generators (VB-3).

c.

Automatic Steam Generator Maintain maximum AFW flow until the steam generator water levels level control only applies are in the narrow range. When the to motor driven AFP's.

SG water levels approach 33% NR, verify automatic steam generator level control.

d.

Atmospheric steam dump will d.

Verify RCS heat removal by be blocked by an existing i

" Turbine Tripped" condition.

1) Observing automatic If condenser steam dump has dump to condenser or atmos-been blocked due to a pheric steam dump via the 10%

control malfunction or loss steam dump valves (VB-3).

of the " Condenser Available" l

condition, decay heat re-A,,,ND, 2) RCS Tavg decreasing to no-load moval will be effected by temperature 547'F (VB-2) automatic actuation of the i

steam generator 10% atmos-l pheric steam dump valves, or if i

l

-iy y

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I NUMBER EP OP-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6

{

DATE 4/12/84 PAGE 6

.OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION i

I ACTION C0tWENTS these prove ineffective, tle r

steam generator cde safety valves. In this event, i

steam pressure will be main-i tained at the set pressure of the controlling valve (s) l and reactor coolant average temperature will stabilize at approximately the saturation temperature for the steam pressure being maintained.

2.

Monitor containment pressure (VB-1),

if containment pressure reaches or exceeds 22 psig, verify the following actions. If required, use manual control to satisfy the action.

a.

Main Steam Isolation Valves and Bypass Valves closed. Phase B isolation postage stamp monitor lights not in alarm (V8-1).

d b.

Steam Generator Blowdown Valves IC closed. Phase 8 isolation postage stamp monitor lights not in alann (VB-1).

Containment spray initiated (phase c.

B isolation postage stamp monitor l

lights not in alarm V8-1).

i d.

Phase B isolation (phase 8 isolation postage stamp monitor lights not in alara VB-1).

CCW to the lube oil coolers e.

e.

Manually trip all 4 RCP's.

will be lost on the phase B isolation.

3.

Monitor the core exit thermocouple' temperatures for indications of inadequate core cooling.

If indications

, 't of inacequate core cooling exist, perform 1

Appendix 3 cf this procedure.

'O

---

w,*

i NUMBER EP 0P-0 1 AND 2 REVISION 6 IABLO C ANYON POWER PLANT UNIT NO(S)

DATE 4/12/84

,l

~

D PAGE 7 OF 20 4

s REACTOR TRIP WITH SAFETY INJECTION Tn1E:

i SUBSEQUENT OPERATOR, ACTIONS (pART B)_

kCCIDENT,0! AGNOSTICS 1.

Evaluate RCS pressure:

Verify closed by observing a.

If W.R. RCS pressure falls below or position indication lights a.

is below 1950 psig, close or verify and discharge pipe temp-closed the following valves, erature indicators.

Pressurizer Spray Valve PCV 455A Pressurizer Spray Valve PCY 455B Auxiliary Spray Valves 8145 and 8148 i

Pressurizer Power Relief Valve PCV 474 Pressurizer Power Relief Valve PCY 456 l

Pressurizer Power Relief Valve PCV 455C t

If W.R. RCS pressure remains above 1950 b.

psig and is stable or increasing, go to Step 1 of Part C Subsequent Operator r

(

Actions.

l

.2.

NOTE: The conditions for If W.R.RCS pressure continues to decay stopping RCP must be con-l 2.

below 1220 psig or is below 1220 psig tinuosly monitored through-l and stable.

out the transient.

SI flow rate will increase a.

Again verify a minimum of one with decreasing RCS press-a.

l charging pump delivering flow ure.

l and one SI pump delivering flow to the RCS Then, STOP all four reactor coolant 1

b.

pumps. Maintain seal water flow to i

the RCP seals.

c.

NOTE: When the W.R. RCS Close the centrifugal charging pressure is restored above c.

pump recirculation valves, 8105 2000 psig,106 to prevent reopen valves and 8106.

8105 and 8 pump damage.

1 d.

If component cooling water to the RCP's is isolated due to a containment phase B isolation,

'k stop all RCP's within 5 minutes and maintain seal flow as above.

I I

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NUMBER EP OP-0 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S)

REVISION 6 i3 DATE 4/12/84 PAGE 9 0F 20 TITLE:

SUBSEQUENT OPERATOR ACTIONS (pART C)_

COMMENTS ACTION 1.

This step is entered from 1.

Assume the event is NON SPURIOUS Accident Diagnostics step safety injection until all of the 1 b.

following items are verified NORMAL.

i a.

Containment pressure.

b.

Containment temperature Containment recirc. sump level.

c.

d.

Containment area radiation monitor, t

Condenser air ejector radiation.

i e.

f.

Auxiliary Bldg. control board area radiation.

i g.

Reciprocal charging pump room area radiation.

h.

Plant ventilation particulate monitor.

l f

1.

Plant ventilation radio gas monitor.

f

. If the above items a. through 1. cannot be verified NORMAL, return to step 1 of Accident Diagnostics.

If the above symptoms a. through i. are normal, and when W.R. RCS pressure is greater 2000 psig.

j.

NOTE On spurious SI recovery, if RCS pressure decreased below the shutoff hea (1520 PSIG) during the transient perform leak test (STP V-5) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the ECCS actuation on those valves listed in Table 3.4-3 the SI pumps Tech Spec 4.4.6.2.2 which actuated or if there was flow through the valve.

J AND k.

Pressurizer water level is greater than 227..

1.

If the RCS subcooling meter AND 1.

RCS indicated subcooling is greater is inoperable or is than 35'F.

suspected to be incorrect.

use wide range That in cnnjunction with the attached RCS saturation curve (graph) to detennine RCS subcooling.

k

i NL#18 P OP-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 4/.12/84 PAGE 8 OF 20 intE REACTOR TRIP WITH SAFETY INJECTION l

s l

ACTION COMMENTS f

3.

If condenser air ejector radiation monitor is reading abnorwelly hjjj! radiation AND containment pressure, containment area radiation monitor, and containment recirc.

l sump level exhibit NORMAL readings, dis-continue this procedure and begin pro-(

cedure OP-3A, Steam Generator Tube l

Rupture.

\\

4.

If steam generator pressure is 4.

This is indicative of a ABNORMALLY LOW in one steam gener-secondary break upstream of ator as compared to the other MSIV.

steam generators, discontinue this procedure and begin procedure OP-2, Loss of Secondary Coolant.

5.

If containment. pressure, containment area 5.

NOTE:

For very small coolant radiation monitor, or containment recirc.

breaks inside the containment, sump level exhibit ABNORMALLY HIGH or the containment pressure and INCREASING levels, discontinue this containment recirc. sump level may increase very procedure and begin procedure OP-1 Loss slowly and possibly not of Reactor Coolant.

recognizable by the operator immediately. Therefore, the operator should monitor these parameters throughout the transient.

6.

If containment pressure, containment 6.

This is indicative of a area radiation monitor and containment secondary break downstream recire. sump level remains stable in of MSIV.

the pre-event rance, discontinue this procedure and begin procedure OP-2 Loss of Secondary Coolant.

i I

NUMBER pp op-0 1 AND 2 REVISION 6 DIABLO CANYON POWER PLANT UNIT NO(S)

OATE 4/12/84 I

PAGE 12 OF 20 REACTOR TRIP WITH SAFETY INJECTION TITLE:

C0P99ENTS ACTION i

3.

Verify the following:

With normal RCS charging, the pressur-a.

izer water level remains above 10%.

W.R. RCS pressure remains above b.

1850 psig.

c.

CAUTION: Stopping and start-RCS indicated subcooling greater than ing of the ECCS pumps can c.

35' F.

cause pump motor overheating or reduced motor life, If item a., b., or c. above cannot be verified MANUALLY. REINITIATE SAFETY _

INJECTION and return to diagnostic Step 1, subsequent action Part "B", of this procedure, fftheECCSpumpsare restarted, add 15 F to item c. above.

(

Verify auxiliary feedwater flow and steam g'enerator wter levels approaching NO LOAD 4.

i evel (33% narrow range).

5.

Establish nonnal letdown.

Check open or open letdown valves a.

LCV-459 and 460.

Open letdown isolation valve 8152.

I b.

Open one 75 gpm letdown orifice valve.

c.

Verify PCV-135 opening by observing d.

letdown flow.

Establish VCT makeup and transfer 6.

charging pumps suction to VCT.

existing Adjust VCT makeup blend to the a.

boron concentration.

Open VCT outlet velves LCV-1128 and C.

,b.

i Close RWST to charging pump suction l -

c.

l5 valves 8805A and 8.

Verify divert valve LCV-112A in AUTO.

d.

l Verify charging flow nonnel.

e.

O

l l

NUMBER EP 0P-0 1 AND 2 REVISION 6 1

IASt.O CANYON POWER PL. ANT UNIT NCKS)

DATE 4/12/84 D

PAGE 10 of 20 '

f REACTOR TRIP WITH SAFETY INJECTION I

TITI.E:

COP 9 TENTS r

ACTION AND m.

Auxiliary feedwater flow to each i

steam generator is greater than 205 gpm o.t l

l One steam generator wide range water level instranent indicates a level greater than 75%.

THEN_

2.

CAUTION.: 1) Automatic rein-2.

Reset safety injection.

itiation of safety injection will not occur after this step since the reactor trip breakers are open. If the operator has indication that an SI is required after this step, he must initiate it ma6ually.

CAUTION: 2) If loss of off-site power occurs after re-setting safety injection, it will be necessary to load the safeguards equipment onto the vital busses manually.

If safety injection is reinitiated manually after the loss of off-site power the vital busses will auto-matically sequentially load the safeguard equipment.

If manual loading or a'uto-matic loading is performed, verify the equipment given

~

in Appendix A is loaded onto the vital busses.

Reset containment isolation phase a.

A, train A and train 8.

1 b.

Stop one charging pump at a time Maintain and evaluate RCS pressure.

sufficient charging flow to supply adequate seal injection flow and to prevent RCS pressure fmm decaying.

If RCS pressure drops below 1850 psig, o

,---n--

a ------

- ~.

- - - ~ - - - -

-~m e,ee--

---m--om--m--n--

~m

-m-+-.

I NU P 0P-0 l

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

DATE 4/12/84 PAGE 13 OF 20 m,

REACTOR TRIP WITH SAFETY INJECTION TITLE:

COPMENT ACTION 7.

Start RCP 1 or 2 if 7.

If RCP's are not running, establish possible to provide j

conditions for starting RCP's and start Pressurizer Spray at least one RCP.

capability.

8. With pressurizer level controlleo in l

manual, verify pressurizer pressure control in AUTO and pressurizer sprays and heaters centro 111ng pressure.

I

9. Stop all 3 diesel generators, place diesel generator control switches in l

AUTO.

10. Insure the main and feedpump turbines on turning gear once O RPM speed is reached.

11. E after securing safety injection and 11.

Calf 7 ION: Do not reset the reactor trip breakers until transferring the plant to normal pressur-authorized by the Plant izer pressure and level control, the reactor coolant pressure does not drop below the Superintendent.

low pressurizer pressure setpoint for safety injection actuation AND the pressur-izer water level remains above 10%, AND I

the reactor coolant indicated subcooTEg is greater than 35'F, then consider the event a spurious safety injection. Continue to monitor these parameters closely; if any parameter fails to remain above the limit, l

manually reinitiate Safety Injection and return to Step 1 of the Diagnostic section.

SPURIOUS SI SIGNAL RECOVERY 1.

Proceed to a normal Hot Standby condition as follows:

If steam line isolation has occurred:

a.

1) Close or check closed all 35 and 40% steam dump valves.

l

2) Prepare or verify main condenser avaHable for service.

3) Equalize or attempt to equalize

3) A steam line brerk down-1 stream of PtSIV's will and o' pen all 4 MSIV's. Monitor steam generator pressure closely prevent equalizing.

,y during this operation.

Innediately close all MSIV's if steam pressure 5

l rapidly drops during this operation.

Establish steam dump to condenser 4) using steam pressure mode set at 1005 psig.

NUMBER EP OP-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6.

OATE 4/12/84 PAGE 11 OF 20 Tm.E REACTOR TRIP WITH SAFETY INJECTION l

L

)

ACTION C0feENTS reinitiate SI and return to Step 1 I

of the diagnostics.

i l

c.

Stop both RHR and SI pumps.

t I

i d.

Verify AC turbine bearing oil pump i

and Hi pressure seal oil backup pump running after oil pressure decays to 11 psig and turbine l

bearing lift pump starts at 600 l

RPM turbine speed.

j f

e. Establish nonnal charging.

j

1) Open instrument air valves FCV-584 and 682.

2) Check open or open nonnal j

charging valve 8146.

i

3) Check close or close charging to auxiliary spray valves 8145 l

and 8148 and alternate charging l

valve 8147.

i i

4) Open charging line isolation valves MO 8107 and 8108.

l

5) Adjust HCV-142 and FCV-128 or j

^

reciprocal charging punp speed to achieve RCP seal flow and charging i'

flow as required to maintain pressurizer level greater than 22%.

h

6) Open RCP seal return valves MO 8100

.i and 8112. Check RCP seal return flow nonnal.

7) Close the BIT inlet and outlet valves 8803A and 8, 8801A and 8.

I t

NUMBER EP OP-0 j

DIAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION o i

DATE 4/12/84 l

PAGE 15 OF ZU in t.E.

REACTOR TRIP WITH SAFETY INJECTION l

t COPMENTS ACTION l

l

4) Open containment rad. Gas monitor valves FCV-681, 678 and G79.

(

2) Verify nonnal readings on containment l

air particulate and radio gas monitors on RMS board.

f h.

Reset radweste isolation valves reset switches.

1 1.

Open fire water valve FCV-633 and primary water to c6ntainment valve 8029.

I

~

to PRT.

f

j. Open valve 8045 N2

~

l

k.

• If the incore chiller has been in service prior to the SI open incore chiller valves

~

FCV 655, 657, 654 and 656.

1.

If the gross failed fuel detector has

(

been in service prior to the SI, open l

Hot Leg sample valves 9356A and B.

1) Verify flow returns on the GFFD

'i flommeter.

2) Verify'the GFFD countrate returns on scale and stabilizes s't a value below the post SI countrate on the recorder.

Open the pressurizer steam space sample m.

valves 9354A and B Open pressurizer relief tank gas j

n.

analyzer v,alve 8034A.

t 2.

Maintain Hot Standby conditions until i

authorized to pmceed with a nomal startup or infom the plant superinten-dont that the unit is proceeding to Cold Shutdown, i.

l r

I t

(

r

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

l N

P OP-0 l

1 AND 2 ous.O CANYON POWER PLANT UNIT NO(S)

ME DATE 4/12/84 I

PAGE 14 OF 20 I

i REACTOR TRIP WITH SAFETY INJECTION Tms:

i i

COMENTS l

ACTION

5) If steam dump to the condenser is established, verify all atmospheric steam dump valves closed, b.

Open the main generator motor operated disconn a t-switch and reenergize the unit auxiliary tr6nsformers by back-i feeding from the 500 KV yard. Transfer l

all station auxiliary busses (12 and 4 KV busses) to the unit auxiliary trans-I i

formers.

l Return the auxiliary buildirg ventilation j

c.

system to nonnal by resetting the "S" i

signal on both POV cabinets and selectin 2 building only mode on V8 3.

d '. Reset both Units 1 and 2 control room ventilation systems on Unit 2 radiacion control board and verify both Units 1 i

and 2 ventilation systems return to the nonnal mode of operation.

l When directed by the SFM, shutdown the e.

following-I

1) One auxiliary saltwater pump.

2) Steam driven auxiliary feedwater pump after steam generator levels are greater than 331 and motor l

driven pumps are controlling level.

I

3) Close CFCU maxi flow valves then l

l shutdown 1 CCW pump.

l

4) Remove 2 CFCU's from service and place the running CFCU's on fast speed.

i I

Flush BIT outlet to cold leg injection lines for f.

Drain approximately 20 minutes by opening SI-1-A969.

i and refill the BIT using OP 8-1C IV Restoring Boron I

i Injection Tank After Safety Injection.

Reset containment ventilation isolation trains A and g

g.

train 8.

i I

a l

l t

Q EP OP-0 1 AND 2 tAALO CANYON PCMER PLANT UNIT NO(S)

O DATE 4/12/g4 PAGE 17 OF 20 i

l REACTOR TRIP WITH SAFETY INJECTION I

TITLE l

APPENDIX A BLACKOUT WITH SAFETY INJECTION EMERGENCY L If the vital busses lose voltage orfor to resetting the safety injection l signal, the vital busses will automatically load the vital equipment 1.

Verify the equipment has been loaded by observing breaker given below.

lights on the control board.

l If the vital busses lose voltage after the safety injection itgnal has been reset, load or verify loadedWequipment given below onto the 2.

Allow approximately 4 seconds between loading of vital busses manually.

nto a given vital bus. Load or verify that the nt g piece of equgow gpee VITAL BUS are running VITAL BUS f

VITAL BUS H

G l

F D/G 1-1 0/G 1-2 f

0/G 1-3 MCC 1-H MCC 1-G I

MCC 1-F St Pp 1-2 l

CC Pp 1-2 CC Pp 1-1 r

St Pp 1-1 RHR Pp 1-2 l

RHR Pp 1-1 I

CFCU 1-2 CFCU 1-4 CFCU 1-3 CFCU 1-1 CCW Pp 1-3 CFCU 1-5 CCW Pp 1-1 AFW Pp 1-2 ASW Pp 1-1 CCW Pp 1-2 2

ASW Pp 1-2 l

AFW Pp 1 3 Lead the containment spray Pu:nps only if they were running prio 3.

blackout.

VITAL BUS VITAL BUS H

G f

Cont Spray Pp 1-1 Cont Spray Pp 1-2 f

I l

I I

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t

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- - + -.. - - - - - - - - - -,, -

I l

i NUMSER EP OP.0 1 AND 2 OIABL.O CANYON POWER PL. ANT UNIT NO(S)

REVISION 6 I

DATE 4/12/84.

i I

PAGE 16 OF 20 l

REACTOR TRIP WITH SAFETY INJECTION Tm.E.

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RCS Temeerature (J00 600 200 0

100 200 300 400 500 F)

i N

R EP OP-0 l

DIABLO CANYON POWER PLANT UNIT NCMS) 1 AND 2 OATE 4/12/84 PAGE 19 OF 20 l

m REACTOR TRIP WITH SAFETY INJECTION TITLE l

APPENDIX 5 (Cont.)

C0leENTS ACTION _

l t

Declare a General Emergency a.

Implement The Instructions given in Emergency Procedure G-1 regarding on and off-site protective actions.

b.

Attempt to establish SI flow to the RCS and AFW flow to the steam i

Generators.

I Continue menitoring core outlet I

c.

temperature to detemine the effectiveness of the remaining actions.

d.

DEPRESSURIZE THE RCS by method 1 or 2 below.

1) Dump steam to the condenser

1) THIS IS THE PREFERRED METH00_.

i or at.mosphere if the steam generator levels are in the narrow range and AFW flow is evident.

i

2) Verify the SIS or charging

2) Opening the PORV's will pro-vide a drop in RCS pressure pumps are running and available sufficient to allow the 51 to deliver water to the RCS.

flow required to cool the

core, THEN i

This method is to be used p

Open the pressurizer PORV's.

only if 1) (above) is inef-i i

factive, If no means of depressurization are e.

available, or if the depressurization Attespt to establish CCW and seal l

e.

did not result in decreasing core water flow to the pump; however, J

exit thermocouple tenveratures, if CCW and/or seat water flow

[

cannot be established, proceed to r

i THEN start a RCP. The pump must be started to move coolant thru the l

START one RCP if possible.

core.

If the RCP fails after starting, replace l

i the lost RCP with any remaining RCP.

e

1 AND 2 NUMBER EP OP-0 o:AsLO CANYON POWER Pt. ANT UNtf NOISI REVISION 6 DATE 4/12/84 REACTOR TRIP WITH SAFETY INJECTION PAGE 18 0F 20 TITLE.

APPENDIX B DETERMINATION OF ADEQUATE CORE COOLING This appendix provides the guidance to determine adequate core cooling if inadequate core cooling is suspected. Further, the instructions for regaining adequate core cooling are presented.

COMMENTS ACTION 1.

Monitor the core exit thermocouple temperatures.

If the P-250 is available go s.

to step 2.

b.

If the P-250 is not available go to step 3.

2.

If 5 or more P-250 thermocouple readings exceed 1200*F. notify the Shift Foreman that inadequate core cooling exists and go to step 5.

If there are not 5 or more that ex-ceed 1200*F. discontinue this appen-dix but continue to monitor the thermocouple readings.

3.

Monitor the thermocouple readout on PAMS 3 and 4.

If 5 or more thermo-couple readings exceed 1200'F notify the Shift Foreman that inadequate core cooling exists and go to Step 5.

If there are An t 5 or more readings that exceed Iz w'F, discontinue this appendix but continue to monitor the thermocouple readings.

t The Shif t Foreman will verify if inadequate 4.

core cooling exists using the appropriate steps above.

If inadequate core cooling exists the Shift Foreman will direct l

operations as follows:

.4 1

~1 se

NUMBER EP G-2 7Ost3 Pacific Gas and Electric Company pgy;3;gg 4 DATE 3/15/84 DEPAnfMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 20 OIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERG"NCY PROCEDURE ESTABLISHidENT OF THE ON-SITE EMERGENCY IMPORTANT TITLE ORGANIZATION TO g

" O

'N APPROVED PLANTMANAM OATE SCOPE This procedure describes the responsibilities of the positions in the On-site Emergency Organization and the actions required by plant personnel for establishing the On-site Emergency Organization.

This procedure and changes thereto require PSRC review.

l GENERAL 1.

The transition from a normal operating organization to an On-site Emergency Organization involves the following three basic steps:

7 Filling appropriate On-site Emergency Organization positions e.

cr an interim basis with personnel who are imediately available on-site at the time of the emergency. See Figure 1 fur the description "" the " Suggested Interim Emergency Organization."

b.

Notifying plant personnel off-site and on-site that their assistance is required (refer to EP G-2 Supplement 1 for j

I instructions on this).

Filling positions in the long-term emergency organization, c.

as described in Figure 2, "Long-Term Emergency Organization," with apprcpriate plart personnel as they arrive at the Control Room. Operations Support Center, Technical Support Center, or the Emergency Operations Facility.

2.

Plant personnel shall be assigned to emergency organization positions on an interim or long-term basis and are ranked in l

order of preference according to Supplement 1. " Emergency Organization Call List."

Interim position-holders shall be responsible for performing the duties of the position as described in Table 1. "On-site Emergency Organizations' Responsibilities," until relieved by the 'ong-term l4 I

OC0075 1:V

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i i

,-m-NUMBER EP OP-0 1 AND 2 REVISION 6,

IASLO CANYON POWER PLANT UNIT NO(S)

D DATE 4/12/84 PAGE 20 OF 20 REACTOR TRIP WITH SAFETY INJECTION TITLE APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS 4

When this emergency procedure has been implemented, and upon direction 1.

from the Shift Foreman, proceed as follows:

Designate this event a Nofification of Unusual Event a.

for this classification by implementing Emergency is 1.ndicated.

ification of Off-Site Organizations" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activ Reclassify this event according to the Appendix I instructions in 0?-3A " Steam Generator Tube Rupture" or OP-1 b.

either these procedures.

In the event inadequate core cooling is verified per Appendix 8 Not reclassify this event as a General Emeroency.and respen c,

with EP G-1.

1 9

1 4

- ~ - -, - - - -. _. _. _ _ _ _.,, _ _

h ON otA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 3/15/84 PAGE 3 0F 20 ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TITLE.

INITIATING CONDITIONS Notification and establishment of the On-site Emergency Organization j

shall be initiated by the Shift Foreman when he declares an Unusual 1

Event Alert, Site Area or General Emergency in accordance with Emergency Procedure G-1, " Accident Classification and Emergency Plan Activation."

IMMEDIATE ACTIONS The Shift Foreman shall assume the position of the interim Site 1.

Emergency Coordinator, assess the situation, and appoint members of the on-site operating staff to assume the positions shown in Figure 1, " Interim Site Emergency Organization," as he deems necessary to terminate or mitigate the emergency.

NOTIFICATION OF AN UNUSUAL EVENT s

1.

The interim Site Emergency Coordinator shall contact, as a minimum, position holders for the long-term emergency 7

organization positions indicated by the Unusual Event Stop Callout Point on the " Emergency Organization Call List" in Supplerent 1.

Personnel contacted will inform the caller as to whether they will proceed to their emergency response location or remain on standby status.

Additicnal plant personnel may be called out as deemed necessary 2.

by any of the above personnel.

NOTIFICATION OF AN ALERT, SITE AREA EMERGE *'CY, OR GENERAL EMERGENCY l

The interim Site Emergency Coordinator shall contact 1.

position-holders to fill positions in the long-term emergency i

69-10297 " Emergency Organization Call l

organization per Form During normal working hours, sounding of the Site List."

Emergency Signal may be used as a means of establishing the i

emergency organization.

l b

1 DC0075 3V i

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otAsto CANYON POWER PLANT UNIT NCNS)1 AND 2

$0N DATE 3/15/84 PAGE 2 0F 20 ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TITLE Long Tenn position holders are responsible f, position-holder.

performing the duties of the position, as described in Table 1, until duly relieved, and penrission for relief is received ' rom the Site Emergency Coordinator, or the Site Emergency Coordinator

. determines that the emergency organization position is no longer required. Form 69-9370, " Site Emergency Organization Assignments" may be used to record emergency assignments and shift rotations.

The Shift Foreman shall remain in the Control room, where ha isHe 3.

responsible for overall connand and control of the emergency.

shall assume 3 e position of the interim Site EmergencyHe shall not

. Coordinator.

operation but'shall maintain a broad perspective of operational conditions affecting the safety of the plant, in compliance with Nuclear Plant Administrative Procedure, NPAP A-102.

4. ' When an emergency is declared and notification of plant staff and offsite response organizations is in process, incoming phone calls or the plant emergency number shall be answered and the plant emergency. number shall be provided to offsite personnel needing to contact the plant. Calls on the normal plant number will be answered to the extent possible without interfering wit' the emergency response.

All notifications shall be recorded, Form 69-10297 " Emergency Organizstion Call List " should'oe used for initial callou 5.

used to record incoming calls or calls to persons not on Form 69-10297.

All records genersted by the utilization of this procedure for an exercise or emergency shall be forwarded the next working day to 6.

for review and the Assictant Plant Manager, Support Services, retention.

Records genersted from exercises will be categorized as non permanent and retained for a minimum of five years, a.

Records gen'. rated from actual emergency events will be categorized as lifecime and placed into lifetime storage in b.

accordance with procedure " Requirements for Retention and Extended Storage of Operation Phase Activity Records (AP E-151)."

a OC0075 2V

I 0iAoLO CAWON POWER Pt. ANT UNIT NO(S)1 AND 2 ON DATE 3/15/84 PAGE 5 0F 20 t

ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TITLE EP G-3, " Notification of Off-site Organizations" EP G-4, " Personnel Assembly and Accountability" AP E-151, " Requirements for Retention And Extended Storage Of Operation Phase Activity Records" AP A3, Supplement 1. "On Call System and Personnel Availability" NPAP A-102, " General Authorities And Responsibilities Of The Shift Foreman" TABLES On-site Emergency Operating Organization - Responsibilities 1.

FIGURES 1.

Typical On-Shift Emergency Organization And Assignments l

2.

Long-term Emergency Organization 3.

Interim EOF Organization ATTACHMENTS Form 69-9370," Site Emergency Organization Assignments."

1.

2.

Form 69-9221. " Emergency Notification Record."

i l

l l

l OC0075 SV

s s

i 1

r NUMBER EP G-2 I

otASLO CANYON POWER PLANT Nif NO(S) 1 AND 2 REVISION 4 DATE 3/15/84 t

PAGE 4 0F 20 l

TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION 1

t l

i During off-normal hours or if sounding the Site Emergency Signal 2.

l is not desirable, the interim Site Emergency coordinator shall l

appoint a Liaison Assistant who shall notify necessary olant The Liaison personnel per Supplement 1 to this' procedure.

l l

Assistant may perform.the callout from the control rocm area or l

may be dispatched to the.ichnical Sooport Center (TSC) to activate the TSC telephone switchboard to receive incoming emergency calls and complete plant staff notification.

l If long-term emergency position holders and support staff are 3.

l already on station. notify them of the escalation or reduction of the emergency classification. 'Particular care should be given to notifying personnel at the following locations:

l l

TSC or Control' Room (depending or, locatien of the Site a.

Emergency Coordinator) b.

EOF, and monitoring teams under the control of EOF.

f OSC and Security Shift Supervisor' c.

Personnel who may be performing emergency actions in varien d.

areas of the plant site (other than at emergency facilities).

j Additional Liaison Assistants ady be assigned to assist in l

4.

notifications or coordinate message dissemination between the Site Emergency Coordinator and,the Emergency Liaison Coordinator.

3 l

r SupportstaffcalledYn-sit 0(wh'oarenotgivenapredesignated 5.-

response location) should be directed to report to the Security Building lunchroom. Upon arrfval,..they will call the TSC or Control Room to receive further direction.

SUPPORTINGPROCkURES l

EP G-1, " Accident Classificat' ion and Emergency. Plant Activation" E c-2, Supplement 1

=

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l DC0075 4V ~

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l otAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R

ON OATE 3/15/84 i

I

_/

PAGE 7 0F 20 I:

ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TITLE r

• j Authorized any extraordinary emergency measures, such as the use of company emergency personnel exposure i

limits.

The Site Emergency Coordinator will establish the emergency 2.

response organization in the TSC and then relieve the individual l

who initially assumed the interim Site Emergency Coordinator duties (normally the Shift Foreman) and assume the following duties.

Prior to the time that the corporate Recovery Manager l

a.

assumes his position at tha Emergency Operation Facility, j

)

the Site Emergency Coordinator is responsible to:

i i

• 1) Provide direction for all emergency response operations 3

performed by Company personnel in the San Luis Obispo County Area.

• 2) Authorize any reconsnendations of the Company regarding j

evacuation, confiscation of food, or other emergency measures, to noncompany emergency support groups.

• 3) Authorize changes in the Emergency Action Level l

classification to off-site authorities.

Authorize any extraordinary emergency measures, such as

• 4) the use of company emergency personnel exposure limits.

j i

Request assistance as necessary for on-site or off-site 5) f radiation monitoring from federal agencies, either i

through the county / state emergency response

[

organization once established, or directly.

Coordinate and direct all on-site activities.

b.

Maintain liaison with off-site emergency support groups c.

providing on-site assistance and support the corporate f

Recovery Manager in the development of a coordinated recovery action plan for on-site.

Reconnend changes in Emergency Action Level Classification d;

l' to the Recovery Manager.

i

• Responsibility that may not be delacated.

DC0075 7V l

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04ASLO CANYON POWER PLANT UNIT N0(S) 1 AND 2 ON DATE 3/15/84 PAGE 6 0F 20 ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TITLE TABLE 1 ON-SITE EMERGENCY ORGANIZATION RESP 0NSIBILITIES A.

Site Emergency Coordinator Prior to being relieved by the Site Emergency Coordinator, 1.

the Interim Site Emergency Coordinator is responsible for the following in addition to the duties and responsibilities of the Shift Foreman:

Make the initial evaluation and classification of the

• a.

situstion.

Assign plant staff personnel to positions in the Site

• b.

Emergency Organization, Notify, or direct the notification of:

c.

1)

Plant staff personnel 2)

Company off-site emergency organizations Local noncompany emergency suoport groups 3)

San Luis Obispo County, California Office of 4)

Emergency Services and the Nuclear Regulatory Commission Authorize the sounding of the site emergency signal.

• c.

Authorize the evacuation of the plant site and specif,

• e.

the appropriate evacuation route.

Authorize overtime and other expenses associated with

• f.

establishing and maintaining an appropriate site emergency organization.

Provide direction for all emergency response operations

• g.

performed by Company personnel in the San Luis Obispo County Area.

Maintain liaison with off-site emergency support

• h.

groups.

Make protective action recensnendations regarding

• i.

evacuation, sheltering, confiscation of food, or other emergency measures to local government agencies.

• Responsibility that may not be delegated.

i DC0075 6V w

oiAsto canyon POWER PLANT UNIT N0(S) 1 AND 2 ON

~

OATE 3/15/84 PAGE 9 0F 20 ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TIT 12 Maintain contact with on-site and off-site emergency support 3.

groups, regulatory agencies, and monitoring teams and transmit instructions and information to and from the Site Emergency Coordinator.

Maintain records of incoming and outgoing messages. Operate 4.

communications equipment and develop message content as required to support the above.

5.

Provide general assistance to the Site Emergency Coordinator.

C.

Liaison Assistant Assist the Emergency Liaison Coordinator in communications 1.

and recording messages and carrying out his assigned duties.

D.

Emergency Maintenance Coordinator This position provides coordination of maintenance, repair and

(.

material deployment in response to the emergency situation with the following duties and respcnsibilities:

At the direction of the Site Emergency Coordinator fabricate 1.

and set up any special equipment necessary for recovery operations.

Provide managenant direction to the Operational Support 2.

Center Supervisor and maintenance organizations.

Coordinate the movement and accountability of support 3.

personnel brought to the site.

Provide general advice and assistance in these matters to 4.

the Site Emergency Coordinator and other evaluations personnel.

E.

Maintenance Organizations Electrical, mechanical and instrument coordinators are assigned to provide technical advice in these areas and supervise maintenance, repair or installation of special equipment required to respond or recover from the emergency at the direction of the Emergency Maintenance Coordinator.

. i..

DC0075 9V

9 tAst.o CANYON POWER PLANT UNIT NO(S)1 AND 2 h

ON o

DATE 3/15/84 PAGE 8 0F 20 ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TITLE Manager TSC Operations through the three TSC Emergency This includes collecting and analyzing the e.

Coordinators.

technical information necessary for assessment of plant operational aspects, providing technical counsel in sucport of the Control Room (CR), assessment of radiological release potential, and determination of actual or potential release rates,on-site exposure monitoring and contamination control, repair of plant components or systems as required by the emergency and/or consequences, and on-site personnel accountability.

Provide management direction to the Control Room (CR) f.

through the Emergency Operations Coordinator.

Provide management direction to the Operational Support Center (OSC) through the Emergency Maintenance Coordinator.

g.

Assign plant staff pe-sonnel to positions in the On-site h.

Emergency Organization as appropriate.

Authorize overtime and other expenses associated with

• i.

maintaining an appropriate On-site Emergency Organization throughout the recovery period.

Establish and maintain on-site personnel accountability.

J.

Authorize the evacuation of the plant site and specify the

• k.

a;propriate evacuation route.

Obtain the Recovery Managers approval prior to authorizing

• l.

any extraordinary emergency measures such as the use of Company emergency personnel exposure limits.

B.

Emergency Liaison Coordinator This position provides control of verbal and writtencommunication responsibilities:

Handle communications to and from the site and between site 1.

emergency response groups.

As directed by the Site Emergency Coordinator, notify plant staff and other affected individuals and organizations of 2.

the emergency and their assignments.

i.

• Responsibility that may not be delegated.

j OC0075 8V

oiasi.O CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 ON

~

m DATE 3/15/84 PAGE 11 0F 20

(_

ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TITLE.

7.

Provide operation and control of emergency data transmission systems, and review and evaluate plant data.

H.

Emergency Radiological Advisor _

This position provides overall cuordination of radiological aspects of the emergency with the following duties and

_ responsibilities:

3 1.

Advise the Site Emergency Coordinator and/or Emergency EvEluations and Recovery Coordinator on matters relating to radiological safety.

Ha shall. be responsible for coordinating and supervising 2.

radiological surveys and investigations, both in plant and near site. He will work with the Radiological Emergency Recovery Manager in making an overall assessment of radiological conditions.

Cnordinate and supervise all on-site radiological surveys 3.

ar.d investigations, and provide management of the on-site radiation protection program.

Assist the Emergency Evaluation and Recovery Coordinator in 4.

operation and control of radiological emergency data transmission systems, review and evaluation of data from these systems, and development of data and status updates for transmission off-site I.

Site Chemistry and Radiation Protection Coordinator This position assists the Emergency Radiological Advisor in coordinating on-site radiological protection and chemical and These duties include radiological surveys and investigations.

the following:

1.

Personnel exposure monitoring and record keeping.

2.

Radiological and chemical analysis of in-plant samples.

3.

In-plant surveys and establishment of radiation and/or contamination control area boundaries.

Determine radiation protecticn access requirements for entry 4.

to controlled areas.

k DC0075 11V i

l

{

t

{

oiAsLO CANYON POWER PLANT UNW NCXS) 1 AND 2 ON DATE 3/15/84 PAGE 10 0F 20 inLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION l

l F.

Operations Support Center Supervisors These positions are initially filled by the designated assembly area supervisors assigned to the access control and adjacent cold machine shop in-plant assembly areas.

(See EP G-4 " Personnel Assembly and Accountability.") These persons are responsible for personnel accountability in these areas and immediate dispatch of fire fighting, maintenance, search and rescue and/or radiological monitoring personnel to assist the shift staff in response to the l

L emergency.

Following the initial response, personnel called from off-site or out of plant assembly areas will initially assemble at the plant security building lunchroom where a maintenance foreman will be designated Operational Support Center (OSC) supervisor to i

coordinate assignment of personnel to tasks designated by the control room or technical support center and maintain i

accountability of personnel dispatched from the OSC.

G.

Emergen ;y Evaluations and Recovery Coordinator l

This position provides overall technical coordination of the i

plant response activities with the following duties and l

responsibilities:

1.

Evaluate the safety consequences of the occurrence and aavise the Site Emergency Coordinator accordingly of appropriate response actions and on-site ano off-site recomended protective measures.

[

i t

2.

Advise the Site Emergency Coordinator on technical matters relating to nuclear and radiological safety.

i 3.

Provide coordination and supervision of all company support teams operating at or in the vicinity of the site.

4.

Provide coordination and supervision of all company technical support work as part of the overall recovery program developed by the Site Emergency Coordinator and Recovery Manager.

S.

Advise the Site Emergency Coordinator of actions and findings of company support groups.

l f

6.

Assist the Site Emergency Coordinator in determining personnel deployment to emergency support assignments.

[

f i

I DC0075 10V I

l i

i

NUMBER EP G-2 DIA8LO CANYON POWER Pt. ANT UNIT N0(S) 1 AND 2 REVISION 4 p

DATE 3/15/84 PAGE 13 0F 20 i

TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION 2.

Maintain communications with the Emergency Operations Facility and Mobile Environmental Monitoring Laboratory for reporting results and maintaining cognizance of the emergency situation.

3.

Coordinate monitoring activities and reporting of results with the county personnel assigned to the monitoring team.

4.

Provide recommendations regarding establishing controlled access areas and determining the boundaries of such areas in j

cooperation with county personnel assigned to the monitoring team.

5.

Assist in monitoring personnel and evaluating their exposure as required.

6.

Maintain proper logs and records.

l 7.

Keep the Radiological Emergency Recovery Manager informed cf l

their actions and findings.

i L.

Emergency Operations Coordinator This position provides senior plant management representation in the control room.

1 l

1.

Manage Operational Activities.

I 2.

Supervise the Shift Foreman in the operational control of the plant.

I 3.

Advise the Site Emergency Coordinator on operational matters.

M.

Emergency Operations Advisor This is a position filled by an individual knowledgeable in l

operational matters to provide general operational advice and i

assistance to the Site Emergency Coordinator and other evaluations personnel in the TSC. This position may be assigned other operational duties such as radwaste management as required by the situation.

P DC0075 13V

=O s.

I NUMBER EP G-2 otAato CANYON POWER PLANT UNIT NO<s) 1 AND 2 REVISION 4 DATE 3/15/84 PAGE 12 0F 20 TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION i

t i

5.

Maintain proper records and logs.

6.

Keep the Emergency Radiological Advisor and/or the Emergency Evaluation and Recovery Coordinator informed of actions and findings.

J.

EARS Operator - TSC This position assists the Emergency Radiological Advisor in radiological data processing.

K.

Emergency Radiological Monitoring Teams Emergency radiological teams will be 2-man teams established for near site and off-site monitoring in the event of a radiological i

release emergency. They have the following duties and i

responsibilities:

Near Site Team (s):

1.

Perform radiation surveys in and around the plant site and obtain appropriate samples for analysis.

2.

Ma ntain connunications with the Control Room or Technical Support Center for reporting monitoring results and maintaining cognizance of the emergency situation.

3.

Es+ablish controlled access areas to contain or limit the spread of radioactive contamination, as appropriate.

i 4.

Issue personnel protective equipment and clothing, 5.

Establish and post radiation and/or contamination area i

boundaries.

6.

Monitor personnel and evaluate their exposure, if required.

l 7.

Maintain proper records and logs.

I 8.

Keep the Emergency Radiological Advisor and/or the Emergency Evaluation and Recovery Coordinator informed of their j

actions and findings.

Off-Site Team (s):

1.

Perform radiation surveys at off-site locations as l

designated by the Radiological Emergency Recovery Manager and obtain appropriate samples for analysis.

i DC0075 12V

+ - - - " + -

-m.-m

otAaLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 ON l

DATE 3/15/84 PAGE 15 0F 20 i

TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION l

l l

and are authorized to take action to the extent justified.

Personnel in the inanediate area of the injured personnel, or as dispatched by the Site Emergency Coordinator, will provide care until off-site assistance arrives.

R.

Data Processing These positions provide engineering assistance to the Emergency l

Evaluation and Recovery Coordinator in performing those duties relating to evaluation of plant core / thermal hydraulics, l

i electrical and mechanical data, coordination of technical support i

work, operation of computer systems and other on-site emergency I

response activities.

S.

Advisor to the County Emergency Organization The function of this position is to activate and provide interim management of the Emergency Operations Facility and t:e available to advise the County Emergency Organization on the meaning and

~

significance of information being transmitted from the site.

Basic duties and responsibilities include:

i Prior to the arrival of the Recovery Manager and until 1.

relieved, act as the EOF Director to activate the utility portion of the Emergency Operation Facility (EOF and UDAC trailers).

In this capacity, specific functions include:

+

a)

Direct the activation of the utility portion of the Emergency Operation Facility (trailer) by appropriately energizing equipment and activating comunications, b)

Provide administrative and management direction of the EOF interim staff in carrying out the duties of the Radiological Emergency Recovery Manager, the Public Information Recovery Manager, the Operations and Analytical Recovery Manager, and the EOF-EARS operator, c)

Keep the Site Emergency Coordinator informed and serve as his single point contact at the EOF.

2.

Keep the senior county response staff member advised of plant conditions and reconinended protective actions.

3.

Coordinate security of the EOF, UDAC and EOC with the Sheriff's office.

I OC0075 15V e-

,,7,

h oiAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON 4 DATE 3/15/84 PAGE 14 0F 20 Tmz ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION N.

shift Engineer This is a position in the nonnal operating organization which shall remain filled througnout the emergency recovery period.

The initial function of this individual is to assist the Shift Foreman in the evaluation of the occurrence, possible consequences, and possible courses of action.

In the long term, this position may assist in the Control Room or TSC on plant evaluation or radiological evaluation, as required by the l

Occurrence.

r N.

Fire Brigades These teams are responsible for on-site fire suppression activities.

0.

Evacuation Coordinator This is a temporary position to coordinate evacuation of non-essential personnel from the site if warranted by the situatten.

It would nonnally be assigned to the security force staff but may be assigned to a member of the emergency planning staff.

P.

Evacuation Team These are temporary positions consisting of a group leader and a i

monito' who will accompany the evacuees in the event a site evacuation is necessary. The basic functions of this team are to:

1.

Assure that the evacuees stay together and take the correct route.

2.

Assist in personnel accountability at the evacuation off-site assembly area.

i 3.

Secure radiation survey equipment and survey personnel and vehicles at the collection area and arrange for cecontamination as required.

Q.

First-Aid and Medical e

Although the importance of providing prompt first-afd is well l

recognized, no provisions are incluoe for establishing a first-aid team. All plant staff shall receive first-aid training DC0075 14V

1 AND 2 S ON iAsLO CANYON POWER PLANT UNIT NO(S)

D DATE 3/15/84 PAGE 17 0F 20 ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION mLE f

(

Coordination and direction of off-site response activities 3.

involving local support, including activation and operation of radio and telephone systems and maintaining proper

{'

records of communications.

W.

Interim Public Information Recovery Manager This position assists the Advisor to the County Emergency Organization in formulating news releases concerning the emergency condition, obtaining approval of the release, and i

coordinating the news release with county and corporate public It is staffed by a local public information personnel.

infonnation representative until relieved by the Corporate Public Information Recovery Manager.

Technical Advisor to the Public Information Recovery Manager j

X.

This position assists the Public Information Recovery Manager by providing technical assistance in the preparation of news l

releases and participation in news media briefings.

y.

Monitoring Team Liaison Ccordinator_

i This position assists the Radiological Emergency Recovery Manager in communications with monitoring teams, the mobile van, UDAC and other emergency response locations until relieved by the Corporate Monitoring Of rector.

Z.

County Liaison This position assists the Ad'isor to the County Emergency Organization by facilitating the flow of information between the EOF and EOC.

i i

e li lh l

DC0075 17V

-,-,n

_n

sasLO CANYON POWER PLM4T UNIT NCHS)1 AND 2 ON o

DATE 3/15/84 PAGE 16 0F 20 ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TITLE Interim Radiological Emergency Recovery Manager T.

This position assists the Advisor to the County Emergency Organization in coordination and direction of all off-site radiological assessment activities and development of radiological status information, until relieved by the corporate Basic duties and i

Radiological Emergency Recovery Manager.

responsibilities include:

Develop radiological data and status information for j

approval and distribution to EOF, UDAC and EOC personnel, 1.

Direct the activities of off-site monitoring teams and the i

2.

mobile environmental monitoring laboratory, maintain records, and provide findings in status reports.

(

l Perform dose projections and provide radiological assessment 3.

information for the determination of protective action j

recommendations, i

U.

EARS Operator--EOF _

This position assists the Radiological Emergency Recovery Manas" in the performance of his duties, including activation and operation of the EARS computer system, activation and operatior.

of the health physics radio system and communication with off-site monitoring teams and maintenance of logs and record are preparation of status reports as directed, until relieved by tne corporate EOF EARS operator.

Interim Operations and Analytical Recovery Manager V.

This position assists the Advisor to the County Emergency Organization in providing plant status information anocoor directed, until relieved by the Corporate Operations and Basic duties anc responsibilities Analytical Recovery Manager.

include:

Activation and operation of plant data computer systems for 1.

obtaining plant data.

Preparation of plant status updates for approval and 2.

distribution to EOF, UDAC and EOC personnel, l

I t,

DC0075 16V

1 AND 2 NUMBER EP G-2 otAsLO CANYON POWER PLA..I UNIT NO(S' REVISION 4 DATE 3/15/84 PAGE 19 0F 2C

(-

ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TITI.E.

FIGURE 2 I

LONG-TERM EMERGENCY ORGANIZATION strE EP'ERGENCY CCORQ!NATOR (TSC) j I

u I

VEaaENCf' EMERGENCY EMERGENCY EPER3ENCY T

LIAISON MAINTENANCE OPERATIONS EVALUATIONS &

g COORDINATCR C00RDINATOR C00R0!NATOR RECOVERY I

(TSC) i (T5C)

(CR)

C00R0!NATOR T5C i

I ADVISCR TO LIh150.N MECHAhiCAL 5MIFT A5515tANTS MAINTENANCE FCREMAN COUNTY EMERGENCY (TSC)

OP.GANIZAI!CN (CR)

ORGAN!!ATION (05C) i SEE FIGURE 3 EMER5ENCY '

l Ei.E TRICAL 5elFT FCR INTERIM ENGINEER OPERATIONS,J PA!!4TE?CJiCE ADVISOR CRGANIZATION (CRorTSC)

EOF OP.GANIZATIO4 (75Ci I

(CSC) 0FERAicR5 I:.5:FEENT (CR)

FAINTE!!A*4CE OR3ANIZATICN (OSC) y --

8EIGA0E5 GF Es ailc.AL 5'J7 PORT CE*4TER 5'JPER*!!50R (CSC) i r

i i

DATA Evac.ATICN EPiiLE.08 FI'5T A13 &

PROCESSORS COC:0"::?"R RA"I";0GICAL PE0! CAL AO'i!SOR SI:50?aEL (750)

(TSC)

I l E. A;.A;;c..

E vi; 5E*.c r SITE CPE!!

TE:'t 2:0!O' 03* C:;

. A:;0 RAD PROTECTION CC01014ATOR

'.*.E'iO :

)

Ure Aut":rit/

.....Lir.e Aw:=:etty wetil Ree:ve*y ttanager Assges EOF Panage ent E te;eac/ 0:e sticas Fac'Ittf E*r Te:*nical 56::ce: Ceate*

?!:

C:ecatio*al Sw:::e: Ceate*

i CIC OC0075 191V

\\

1 AND 2 NUMBER EP G-2 0iAsLO CANYON POWER Pt. ANT UNIT NO(S)

REVISION,4 DATE 3/15/84 PAGE 18 0F 20' TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION FIGURE 1

{

TYPICAL ON-SHIFT EMERGENCY ORGANIZATION AND ASSIGNMENTS

\\

l 5tte !

Emergency Coordinator l

I i

Emergency i

Emergency Emergency Evaluations and I

Liaison 1 Operations 1 Recovery Coordinator Coordinator Coordinator i

l i

l I

r First Aid &

Fire EJnergency Liaison on Bricade _

Radiological Medical ass 9s'ent Team

. Personnel i

Tvoical Assianmeat position Shift Foreman (Shift Engineer if not 1

Interim Lite Emergency Coordinator available)

(See Taale 1 for responsibilities)

Auxiliary Operator, or Shift Control Interim Emergency Liaison Co'rdinator t

e Technician (Develocs notification messages and perforas off-site notification)

Sr. Control coerator or Control Coeratcr Intech Emergency Coerations Coordinator (Provides operational 5

control of the plant)

Shift Engineer (STA) (Assisted by Shift Interim Emergency Evaluations &

CARP Tecnnician and/or Control Coerators Recovery coordinator if necessary)

(plant and Radiological Assessment)

Shift Clerk. Auxultery Operator or Liaison Assistants Shift Control Technician (Notifies olent staff, coordinates message dissemination among Itaf son personnel)

Assignments per the Interim Site Operators Emergency Coordinator See Emergency Procedure M-6 or R-6 fire 8rigade Shif t C&RP Technician and Auxiliary Emergency Radiological Team Operator (if required)

Employees at the scene First Aid and Medical i

• Required Assigments 4

DC0075 181V e

.e

-,-,a

i NUMBER EP G-251

} S v4 3 Pacifi:; Gas and Electric Company REVISION 0 m

DATE 3/22/84 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 1 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 It4PORTANT EMERGENCY PROCEDURE 69-10297 i

EMERGENCY ORGANIZATION CALL LIST FORM TITLE YS

[

APPROVED.

PLANTMANAM DATE SCOPE This procedure supplement provides the call sequence and listed numbers for the notification of the on-site emergency organization, and indicates the preferred candidates to fill each position as required by Administrative Procedure NPAP A-5.

This procedure and changes thereto requires PSRC review.

i o

PROCEDURE Notification of required personnel in an emergency is made using the 69-10297, listed numbers and call sequence of this supplement, Form

" Emergency Oruanzation Call List."

An The preferred position holders should be contacted when possible.

"On-Call" rotation for essential positions in the emergency

[

organization is maintained in accordance with NPAP A-3, Supplement 1.

i The on-call person may be called if the preferred position holder is not imediately available or whenever judged necessary by the Shift The primary means of notification during "off hours" or wht, the site emergency signal is not sounded during normal working hours Foreman.

The secondary means of notification is the pager is the telephone.

for those individuals designated "0N CALL". Key plant managers have UHF radio equipped. cars which can be used fer initial contact and two l

Because these persons way comfruncations while enroute to the plant.are essentially on-warranted in off hours to ensure rapid comunication and response.

I SUPPORTING PROCEDURES NPAP A-5, "0granizational Control Of Emergencies" NPAP A-3, Supplement 1. "On Call System & Personnel Availability" l

ATTACHMENTS Form 69-10297, " Emergency Organization Call List" i

l I

i i

DC0234 III l

r -

i NUMBER EP G-2 1 AND 2 REVISION 4 Asto CANYON POWER PLANT UNIT NO(S)

DATE 3/15/84 ot PAGE 20 0F 20 ESTA8LISHMENT OF THE ON-SITE EMERGENCY ORGANIZ l

787LE-f r

i i

FIGURE 3 k

!_NTERIM EOF ORGANIZATION l

i ADV150R T0 COUNTY l

EMERGENCY ORGANIZATION l

I l

l l RADIOLJGICAL

[

l OPERATIM5 AND EERGENCY l

FMQhlTORING TEAM PuBLIG ANALYTICAL RECOVERY

~

LIA150N MANAGER INFORMATION RECOVERY RECOVERY MANAGER

_C0CR0!NAYOR i

L MANAGER 3

.z OR. l OP s

CLERICAL L EAMS EOF 3

ADVI R TO l

THE 8U8LIC l

MOBILE i j

INFORvTION f

RECOVERY CCWTY VAN.I

.t.! AISON FANAGER y l

l 1

i

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l l

I

................. Indicates Coseunication Channel f

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DC0075 20!V i

f

1 NUMBER EP G-251 N3W3 Pacific Gas and Electric Company REVISION O m

DATE 3/22/84 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 1 OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE It4PORTANT TITLE EMERGENCY ORGANIZATION CALL LIST FORM 69-10297 YS f'

APPROVED PLANTMANAM DATE SCOPE f

This procedure supplement provides the call sequence and and indicates the preferred candidates to fill each position as required by Administrative Procedure NPAP A-5.

This procedure and changes thereto requires PSRC review.

PROCEDURE

__ Notification of required personnel in an emergency is made using the 69-10297, listed numbers and call sequence of this supplement, Form

" Emergency Oruanzation Call List."

An The preferred position holders should be contacted when possible.

"On-Call" rotation for essential positions in the emergency organization is maintained in accordance with NPAP A-3, Supplement 1.

The on-call person may be called if the preferred position holder is not irrnediately available or whenever judged necessary by the Shift i

The primary means of notification during "off hours" or whea the site emergency signal is not sounded during normal working hours Foreman.

The secondary means of notification is the pager is the telephone.

for those individuals designated "0N CALL". Key plant managers have UHF radio equipped. cars which can be used for initial contact and two Because these persons way contruncations while enroute to the plant.are essentially on-c warranted in off hours to ensure rapid consnunication and response.

SUFPORTING PROCEDURES NPAP A-5, "0granizational Control Of Emergencies" NPAP A-3, Supplement 1. "On Call System & Personnel Availability" ATTACHMENTS Form 69-10297, " Emergency Organization Call List" i

i DC0234 III

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Destnoe emergem.y u m rc,-v-Personnel ta report to cssigned location f:r A1 rt Classification er higher; optional for unusual event.

60 E :

H/P FREQ.

MERG.

NOT ON-CALL HOME PHONE /

PAGER CALL # CONTACTED WILL BE IN

,kGANil.

AVAlly P05 2

'0511 ION ABLE HOLDER NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL #

YES NO TIME YES NO alled for. Describe eve.

1. J. V. Boots

'neergency Chem & Rad Prot. Mgr.

M r; opt ediologiul utvis.r (Assigswd

• 2. W. A. 0'llara

(" ISCI

$r. Chem A Rad Prot. Eng.ng.

H/P FRL HOME PHONE /

PAGER CA

• 3.

II. W. C. Iong PLANT Pil0NE GROUP CA.

i Chem & Rad Prot. Eng.

tng.

Page 4 0F 29 Insert date person is not available.

D00/34 1.

Insert date person assunw?s "on-call" responsibility.

'l 2.

(Person on call will posst*ss the page ir this position) w/

. I twent. uca.iv....-

Page 1 0F 29 Insert date person is not available.

Insert date person assumes "on-call" responsibility.

0C0234 1.

(Person on call will possess the pager for this position) 211 2.

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NOT FOR PUBLIC DISCLOSURE IM(RGENCY ORGANIZATION CALL LIST i9-10297 4/84 (100)

Call Out Instructions:

ilable person.

Contact one person for each position. Contact first listed available person (preferred position holde 1.

Persons with a

• are designated for on-call rotation.

2.

Describe event if requested.

Dest. ribe emergency classification and position person is called for.

3.

4.

l event.

Personnel to report to assigned location for Alert Classification or higher; optional for unusua NOTE:

H/P FREQ.

EMERG.

NOT ON-CALL HOME PHONE /

PAGER CALL # CONTACTED WILL BE IN YES NO 9NGANIZ.

AVAIL 7 POS. 2 NAME/NON-EMERGENCY IIT1E PLANT PHONE GROUP CALL #

YES P0 TIME POSIT 10N ABLE HOLDER I

• ). W. B. Kaefer Advisor to the Support Services Mgr.

County Emerg.

Organization (Assigned

• 2. W. J. Keyworth to EOF)

Leergency Planning Supervisor

• 3. T. E. Brake Pow. Prod. Eng. (PIMS)

• 4. W. J. Kelly Regulatory Compliance Engineer i

l Page 6 0F 29

(

Insert date person is not available.

DC0234 1.

Insert date person assumes "on-call" responsibility.'or this position)

'll 7.

(Person on tall will possess the pag 1

n.

NOT FOR PUBLIC DIS JSURE EMERGENCY ORGANilATION CALL LIST 9-10297 4/84 (100) all Out Instructions:

Contact one person for each position. Contact first Itsted available person (preferred position holder); if unavai Persons with a

• are designated for on-call rotation.

Describe event if requested.

Describe emergency classification and position person is called for.

Personnel to report to assigned location t'or Alert Classification or higher; optional for unusual event.

10TE:

H/P FREQ.

HOME PHONE /

PAGER CALL # CONTACTED WILL BE IN IMERG.

NOT ON-CALL

'OSI T ION ABLE HOLDER NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL #

YES NO TIME YES NO

)RGANil.

AVAlly P05 2

~

^

(No On-

1. J. A. Sexton mergency Call Operations Manager lperations idvisor Person for Assigned

. TSC) this

2. S. R. Fridley position)

General Operating Foremar

3. T. J. Martin Training Manager 9

4. W. G. Crockett Sr. Power Prod. Eng.

(Operations)

Page 7 0F 29 Insert date person is not available.

0C0234 1.

Insert date persosi assisines "on-call" responsibility.

HII 2.

(Person on c.ill will possess the payer for this position)

4

. +.

NOT FOR PUBLIC Olb..JSURE ENERGENCY ORGANIZATION CALL LIST-9-10297 4/84 (100) c11 Out instructions:

w.,

ilable person Contact one person for each position. Contact first listed available person (preferred position holder);

Persons with a

• are designated for on-call rotation.

Describe event if requested.

l Describe emergency classification and position person is called for.

i Personnel ts.'eport to assigned location for Alert Classification or higher; optional for unusual event 10TE:

H/P FREQ.

iMERG.

NOT ON-CALL HOME PHONE /

PAGER CALL # CONTACTED WILL 8E IN

)RGANIZ.

AVAILy HOLDER _2NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL #

YES NO TIME YES NO POS.

'OSITION A8LL (No On-

1. J. A. Sexton i

l

'mergency Call Operations Manager iperat< f ons Person

$dvisor for Assigned this

2. S. R. Fridley

. TSC) position)

General Operating Foreman

3. T. J. Martin Training Manager

4. W. G. Crockett Sr. Power Prod. Eng.

(Operations)

Page 7 0F 29 Insert date person is not available.

Insert date person assumes "on-call" responsibility.

DC0234 1.

(Person on call will possess the pager for this position) 811 2.

l NOT FOR PUBLIC DISCLOSURE' EMERGENCY ORGANIZATION CALL LIST

! -10297 4/84 (100) 11 Out Instructions:

I Contcct one person for each position. Contact first listed 'available person (preferred position holder); if unavailab P:rsens with a

• ave designated for on-call rotation.

Describe event if requested.

Describe emergency classification and position person is called for.

4 Personnel to report to assigned location for Alert Classification or higher; optional for unusual event.

i

~

H/P FREQ.

HOME PHONE /

PAGER CALL # CONTACTED WILL BE IN RG.

NOT ON-CALL i

.ANIZ.

AVAlly POS. 2 NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL #

YES NO TIME YES NO i! TION ABLE HOLDER I

-t

• l. D. B. Miklush ergency Main-Maintenance Manager n:nce Coor-nistor

.ssigned

• 2. R. Manninga

.TSC)

Sr Pow Prod Eng (Maint)

• 3. D. L. Bauer Sr. Pow. Prod. Eng.

• 4. W. R. Ryan Gen. Maint. Foreman

• 5. G. M. Zocher l

Gen. Elec. Foreman L

Determine if the Stop call out at this point for the Unusual Event Classification, continue for high classification.

1)

ITE: Site Emergency Coordinator requires additional personnel.

Request the Emergency Maintenance Coordinator wrations to assign a maintenance foreman as OSC support ipport Center Jpervisor center supervisor.

Page 8 0F 29 '

Insert date person is not available.

DC0234 1.

H*

2.

Insert date person assumes "on-call" rese-isibility.

this position)

(Person on call will possess the pagt,

~

NOT FOR PUBLIC DISuCSURE EMERGENCY ORGANIZATION CALL LIST 9-10297 4/84 (100) all Out Instructions:

if unavailable, contact the next available person Contact one person for each position. Contact first listed available person (preferred position ho Describe event if requested.

)

P2rsons with a

• are designated for on-call rotation. Describe emergency classifica for.

higher.

Personnel to report to assigned location for Alert Classification or 10TE:

H/P FREQ.

WILL BE IN NOT OH-CALL HOME PHONE /

PAGER CALL # CONTACTED MERG.

PLANT Pil0NE GROUP CALL #

YES NO TIME YES NO IRGANIZ.

AVAlly POS. 2 NAME/NON-EMERGENCY TITLE ABLE HOLDER

'OSITION

• l. H. A. Ferguson site Chemistry Rad. Prot. Mon. Foreman i R:diation

)rstection

• 2. L. T. Moretti

oordinator Chem & Rad Prot. Forema Access Control)

• 3. R. 5. Snyder Chem & Rad Prot. Forem.

• 4. P. W. Baxter Rad. Prot. Mon. Foreman

• S. L. Vulchev Chem & Rad Prot. Foreman' l

l i',

k Page 9 0F 29 Insert date person is not available.

Insert date person assumes "on-call" responsibility.GPerson on ca

~_

i DCO234 1.

1011 2.

o NOT FOR PUBLIC DISCLOSURE EMERGENCY ORGANIZAll0N CALL LIST 1-10297 4/84 (100) 311 Out Instructions:

Contact one person for each position. Contact first Itsted available person (preferred position: holder); if unava t

e P;rsons with a

• are designated for on-call: rotation.

Describe eve'nt if requested.

. Describe emergency classification and position person-is called for.

Personnel to report to assigned location for_ Alebt Classification or higher.

s DIE:

N/PFREd.

g MERG.

NOT ON-CALL HOME PHONE /

PAGER CAtt #' CONTACTED WILL BE IN g

h YES NO

_%E HOLDER NAME/NON-EMERGENCY TITLE' PLANT Pil0NE GROUP CALL #

YES NO JIME g

P05..j RGANIZ.

AVAll A

051 TION t

ut-Of-Plant (No on-

1. E A. Ferguson tonitering 8.'

cr.11 Rad. Prot. Mon. Foreman x

person n.Plcnt' hemistry'&

for this

2. L. T. Moretti cdt:Lior

• position)

Chem & Rad; Prot. Forema.

4 rctcction

3. R. S. Snyder trsonnel Rad. Prot. Mon. Foreman

~~

.Six cssigned

.o mobli van

4. P. W..Baxter prcge; six Chem & Rad Prot. Eng.

3

' ~

issigned to

• >1cnt)

S. W. A. O'Hara Chem & Rad. Prot. Eng.

t s

Request a minimum of six personnel for initial Off-Site Monitoring Teams.

Request a minimum of six CARP Personnel for in-plant monitoring and chemistry.A m NOTE:

A.

B.

D.

or site Chemistry and Radiation Protection Coordinator.

Page 10 0F 29 11C0234 1.

Insert date person is not availal>le.

Insert date person assumes "on-call" re<nonsibility.

5l 2.

(Person on call will possess the pag

- this position)

.,-7

NOT FOR PUBLIC DI w.05URE EMERGENCY ORGANIZATION CALL LIST 9-10297 4/84 (100) cil Out Instructions:

Contact one person for each position. Contact first listed available person (preferred position holder); if una PIrsons with a

• are designated for on-call rotation.

Describe event if requested.

Describe emergency classification and position person is called for.

I.

I.

Personnel to report to assigned location for Alert Classification or higher.

40TE:

H/P FREQ.

.NERG.

NOT ON-CALL HOME PHONE /

PAGER CALL # CONTACTED WILL BE IN

)HGAMil.

AVAILy POS. 2 NAME/NON-EMERGENCY TITLE PLANT PHONE _

GROUP CALL f YES NO TIME YES N0

>0SITION ABLE HOLDER ISC/ EOF (No on-

1. C. D. Lampert

1:rical call Office Supervisor Assistance person for this

2. K. C. Long position)

Asst. Office Supervisor

3. M. A. Hoff Senior Plant Clerk t

Request supervisor to dispatch three (3) clerks to the TSC and two (2) clerks to the EOF.

NOTE:

Page 11 0F 29 0C0234 1.

Insert date person is siot available.

Insert date person assumes "on-call" responsibility.

1211 2.

(Person on call will possess the pager for this position) j

~

NOT FOR PUBLIC DISCLOSURE _

EMERGENCY ORGANIZATION CALL LIST 29-10297 4/84 (100)

Coll Out instructions:

=,

Contact one person for each position. Contact first ilsted available person (preferred position holder); if ~ unavailable 1.

.2.

Persons with a

• are designated for on-call rotation.

~

Describe event if requested.

3.

Describe emergency classification and position person is called for.

4.

,j r-

'Personriel to report to assignedalocation for Alert Classificatiorp o' higher.

r

~

NOTE:

a s

j i P'FREQ. e t/

HOME PHONE /.

PAGER CALL F CONTACTED WILL BE IN

.)

[MERG.

800T ON-CALL a

^

POSJT10N ABLE HOLDER NAME/ MON-EMERGENCY Ti1LE 'yPLANT PHONE GROUP CALL s',YES NO TIME YES NO 7

P05 2 DHGANIZ.

AVAIL t

4 Rediological call Sr. Chem & Rad Prot.'Eng.

Interi:a

' JHo on-

1. W! A. O'Hara

~

~

4 s j '<f a

Emf 9ency person Recov::ry Manager, for this 2.-5; J. Fahey-Benson (Assigned to position)

Chem & Rad Prot. Eng.

LOF) y 4

3. B. D. Guilbeauft Chem. & Rad. Engl"neer.

?

-i I

e

,'O s,

I

/

r

)

l i.

./

i i

I

'I

[

/

i Page 12 0F 29 DC0234 1.

Insert date person is not available.

ill 2.

Insert date person assumes "on-call" ponsibility.

(Persori ori call will possess the pa..

or this position)

A 4

1-10297 4/84 -(100)

EMERGENCY ORGANIZATlun CALL LIST NOT FOR PUBLIC 01-.

JSURE' sil'Out Instructions:

Contact one person for each position.

Contcct first listed available person (preferred position holder); if unavailable, contact the nex't available person-P2rsons with a

• are designated for on-call rotation.

Describe emergency classification and position person is called for. Describe event if requested.-

.0TE: P2rsonnel to report to assigned location for Alert Classification or higher.

H/P FREQ.

MERG.

NOT ON-CALL HOME PHONE /

PAGER CALL # CONTACTED WILL BE IN y

POS. 2 IRGANIZ.

AVAll

'0SITION ABLE HOLDER N#4E/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL #

YES NO TIME YES N0 interim (No on-

1. W. B. Scott OF-EARS call Pwr. Prod. Eng. (Staff)

- iperator person l Assigned to for this

2. D. R. Unger Of )

position)

Chem and Rad Prot. Engr.

3. E. R. Psoter Chem and Rad Protection Analyst f

Page 13 0F 29 DC0234 1.

Insert date person is not available.

Insert date person assumes "on-call" responsibility.

1411 2.

(Person on call will possess the pager for this position)

N E

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R N

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i o rrs pl t a s

2 bac s

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nhi eer hani a

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r NOT FOR PUBLIC DI_ 050RE EMERGENCY ORGANIZATION CALL LIST l

.i9-10297 4/84 '(100)

' o11 Out instructions:

ilable, contact the next available person Contact one person for each position.

Contact first listed available person (preferred position holder); if unavaDescribe event if requested.

1.

Describe emergency classification and position person is called for.

' 2.

3.

Personnel to report to assigned location for Alert Classification or higher.

3

' MOTE:

WILL BE IN NOT ON-CALL HOME PHONE /

PAGER CALL f CONTACTED EMERG.

PLANT PHONE GROUP CALL i YES NO TIME _

VES NO

ORGANIZ.

AVAlly P05 2 NAME/NON-EMLRGENCY TITLE _

A8LE HOLDER

! POSITION (Both

1. Sue Brown personel

'Public information Interia Public infonnation carry )

2. Missie P. Hobsom pagers Racevrry Public Information Man *ger (Assigned

3. Pam Zweifel i

to EOF)

~

Manager, Information Center

.L Page 15 0F 29 Insert date person is not available.

Insert date person assumes "on-call" responsibility.(Person on call w DCO234 1.

1611 7.

N E

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NOT FOR PUBLIC Olsd OSURE EMERGENCY ORGANIZATION CALL LIST 1-10297 4/84 (100) all Out instructions:

w, ilable person Contact one person for each position. Contact first Ilsted available person (preferred position holder); if un Describe event if requested.

Describe emergency classification and position person is called for.

Personnel to report to assigned location for Alert Classification or higher.

01E:

MERG.

NOT ON-CALL HOME PHONE /

PAGER CALL i CONTACTED WILL BE IN

• GANIZ.

AVAlly POS. 2 NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL #

YES NO TIME YES ~ NO 4)Slil0N A8LE HOLDER (Personnel 1. Roland Richardson Schil Dept. of Engr. Research rotate invironmental tonitoring pager as

.t.boratcry required) 2. Mike Kunde

)perater Dept. of Engr. Research l

Page 17 Of 29 Insert date person is not available.

DC0234 1.

Insert date person assumes "on-call" responsibility.

1811 2.

(Person on call will possess the pager for this position)

r_

NOT FOR PUBLIC DISCLOSURE

[MERGENCY ORGANIZATION CALL LIST i9-19297 4/84 (100)

!all Out Instructions:

w, tact the next available person l

Contact one person for each position. Contact first If sted available person (preferred position hold 1.

Describe event if requested.

Persons with a

• are designated for on-call rotation. Describe emergency classificatio f.

3.

1.

Personnel to report to assigned location f or Alert Classification or higher.

]TE:

H/P FREQ.

WILL BE IN NOT ON-CALL HOME PHONE /

PAGER CALL # CONTACTED PLANT PHONE _

GROUP CALL #

YES NO TIME YES NO EMERG.

ORGANIZ.

AVAlly POS. 2 NAME/NON-EMERGENCY TITLE.

POSITION ABLE IlOLDER

• l. R. H. Garacci EARS Operator Sr. Chem & Rad Prot.

TSC Analyst (Assigned to TSC)

• 2. J. N. Johnson

~

Chem L Rad Prot. Analyst

• 3. E. R. Psoter

~

~

Chem & Rad Prot. Analyst

~

i l

l l

t Page 18 0F 29 Insert date person is not available. Insert date person assumes "on-call" re-%ns DC0234 1.

I 2.

% DI will possess the page

NOT FOR PUBLIC 01. JSURE EMERGENCY ORGANIZATION CALL LIST

>-10297 4/84 (100) all Out Instructions:

lder);ifunavailable, cont.;ttheneItavailableperson.

Contact one person for each position. Contact first listed available person (preferred position Describe event if requested, P;rsons with a

• are designated for on-call rotation. Describe emergency classi lled for.

i tion or higher.

l P;rsonnel to report to assigned location for Alert Classif ca t

bl[E:

H/P FREQ.

WILL BE IN NOT ON-CALL HOME PHONE /

PAGER CALL # CONTACTED PLANT Pil0NE GROUP CALL #

YES NO TIME YES NO EMERG.

ORGAMil.

AVAlly POS. 2 NAME/NON-EMERGENCY TITLE ABLE HOLDER POSITION

l. J. E. Molden Emergency Trng. Coord.

Licison Assister.t #1

• 2. L. R. Sawyer (Assigned Asst. Trng. Coord.

~ - - -

to TSC)

• 3. R. F. Sargent Asst. Trng. Coord.

+4. R. L. Graham Asst. Trng. Coord.

• S. J. P. Northness Asst. Trng. Coord.

~

~ ~

Page 19 0F 79 Insert date person is not available.

Insert date person assumes "on-call" responsibility.(Person on ca DC0234 1.

2011 2.

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!I

~ t available person Contact one person for each position. Contact first listed available person (preferred position holder); if Persons with a

• are designated for on-call rotation.

Describe event if requested.

Describe emergency classification and position person is called for.

Personnel to report to assigned location for Alert Classification or higher; optional for unusual even OTE:

H/P FREQ.

-NERG.

NOT ON-CALL HOME PHONE /

PAGER CALL # CONTACTED WILL BE IN

?OSITION ABLE HOLDER NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL i YES NO TIME YES NO

)RGANIZ.

AVAlly P05 2

1. L. F. Womack Data Processor Sr. Pwr. Prod. Eng.

No. I (Congmter)

(Assigned to 150)

• 2. T. Black Pwr. Prod. Eng. (Computer)

• 3. D. A. Remington Pwr. Prod. Eng. (Computer)

• 4. J. D. Brady Pow. Prod. Eng. (Planning)

~

G. V. Johnson EngineeringTrainee(Compub'

• S I

• 6. J. D. Lodge

~

Power Prod. Eng.

Page 21 Of 29 Insert date person is not available.

Insert date person assumes "on-call" responsibility.

D00234 1.

(Per nn on call will possess the pager for this position) 2211 2.

DIABLO CANYON POWER PLANT PGeE PROCEDURE ON-THE SPOT CHANGE w, '-a'. :r.re-*

n 3

unnso i y zu ia 2e i

-- - a u.: - -

aev.

a..,... s.

=.sonnel acewer=M14 r, au Se e=-1v Unit 2 Fuel i. cad f TEMPOany(p % g,:3rg:::n4 :,

t,:. -: cw;e C pawAxENT (green) 5teve Joiner, evt. 3S*

E eenancv P1anniac envator

., :,,,c,n.n, (ooes rnis aster tne.ntent of ongmai proceeure> O vs. 6 ~oi Pmonese Change:

(Oces' tt :enstitute an unnviewec safety /snvircreental :uestion? C vg3 g 30)

This temporary change describes actions to be taken concerning Unit 2 if the site emergency signal is sounded.

i 1.

Unit 2 Containment

,e If the normal evacuation alarm is not in service for Unit 2 containment, then the compensatory measures are a manually operated alarm located on the 140' elevation and ccmcressed air horns carried by "firewaten" patrol persons at each elevation. Should the site emergency signal i

}

be scunded, the Shift Foreman will dispatch an oce-ator to immediately S

sounc the alarm.

In the event a fire or other e ergen:y ccnditicn isU: n detected by a "firewatch," that individual will sounc nis air horn.

hearing an air horn, "firewatch" ce-sonnel at all statier.; ull scunc l

air horns ano the manual alarm will be activated.

l r

1 meenan for Change:

E :gre all areas of Unit 2 are notified prom:tly o# olan: evacuation and/or fire the event normal means are not available during construction.

7 4'- Z 6 - 8 0 h

/,4

_ /A8v 4 O af e '

iP'as4Narager ent Staff e'SEC L C0Ft 1 is; ant ManageW;a'11 I

aitial :ss:rt:wt.:n

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5 -10709-1 3/22 (!C)

PtCIFIC GAS AND ELECTRIC CCMPANY PAGE 2 Op 2 C:AELO *ANYCN POWE:. 7tAh..

eqaa-rg:e sq.-.r. :r-au;nGr

-'-t N..:.L....~,

.... :r :

PROCEC'.RE NO.

E-3 4 REV.

3

10PCSED CFA:iGI'EEAS N FOR C4ANGE:

2.

Other areas of Unit 2 All "firewaten" personnel are provided air horns to alert workers in high,oise, welcing.end confined areas of a fire or other Tne Security Shift Supervisor will contact emergency concitioc.. Construction Security to dispatch security personnel to if tne site emergency signci is sounded. They will make a Unit 2 These security walkthrough to ensure all areas know to evacuate.

officers are ecui; ped with compressed' air horns.

e I

l l

e

PGandE Letter No.: DCL-84-189 C

v CURRENT EMERGENCY PLAN DFLEMENTING PROCEDURES TABLE OF CONTENTS Yolume 38 TITLE REY 3

OR-1 Offsite Support & Assistance 2

OR-2 Release of Information to the Public EF-1 Activation and Operation of the Technical Support Center 2

2 EF-2 Activation of the Operational Support Center EF-3 Activation and Operation of the Emergency Operations Facility 3

4 EF-4 Activation of the MEML 4

EF-5 Emergency Equipment Instruments & Supplies 2

EF-6 Operating Procedures For EARS 9845C Controlling Stations 1

EF-651 Transfer of EARAUT Control EF-7 Activation of the Nuclear Data Comunications Systems 1

0

(

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

R8-1 Personnel Dosimetry 1

RB-2 Emergency Exposure Guides 0

RB-3 Stable Iodine Thyroid Blocking RB-4 Access to a Establishment of Controlled Areas 0

Under Emergency 0

RB-5 Personnel Decontamination 1

R8-6 Area & Equipment Decontamination 3

RB-7 Emergency On-Site Radiological Environmental Monitoring 2

RB-8 Emergency Off-Site Radiological Environmental Monitoring 2

RB-9 Calculation of Release Rate & Integrated Release 0

i RB-10 Protective Action Guidelines 3

RB-11 Emergency Off-Site Dose Calculations 1

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

R8-13 Improv$d In-Plant Air Sampling for Radiof odines 0

R8-14 Com Damage Assessment Procedure 1

l 05/21/84 0502d/0005K

.-_,--.-..--------,.-,,-,.m,-...r.-w..,.

NUMBER EP RB-2 T GV43 Pacific Gas and Electric Company REVISION 1 DATE 4/6/84 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 5 DIA8LO CANYON POWER PLANT UNIT Nots) 1 AND 2 IMPORTANT EMERGENCY PROCEDURE TITLE EMERGENCY EXPOSURE GUIDES TO APPROVED PLANTMANAE$R DATE l

i SCOPE This procedure addresses required authorization, guidance, and maximum l~

exposure criteria in the event of a radiological emergency where it may be necessary for emergency workers to exceed established quarterly or annual exposure limits. This procedure and changes thereto l

requires PSRC review.

PROCEDURE 1.

Authorization The approval of the Site Emergency Coordinator shall be a.

obtained prior to undertaking any attempted rescue or corrective 4ctions which could potentially or actually result in an individual exposure in excess of established quarterly or annual exposure limits. After the Recovery Manager arrives at the EOF, he shall also approve such actions.

The Emergency Evaluations and Recovery Coordinator with the b.

assistance of the Emergency Radiological Advisor will provide the Site Emergency Coordinator with an evaluation of conditions requiring the exposure, If time permits, prior to exposure, the Emergency c.

18-10554 Emergency Radiological Advisor shall complete Form Exposure Permit. The Site Emergency Coordinator and the volunteer (s) shall sign the Emergency Exposure Permit.

i If the situation requires immediate action, Form Note:

18-10554 may be completed following the exposure, l

although verbal authorization is required.

2.

Volunteer Criteria l\\

l I

OC0011 111

hhf0N osasto CANYON POWER PLANT UNIT WS) 1 AND 2 DATE 4/6/84

,l PAGE 2 0F 5 TITLE EMERGENCY EXPOSURE GUIDES i

a.

Personnel shall be volunteers or professional rescue t

personnel (e.g., firemen who " volunteer" by choice of employment).

b.

Rescue personnel shall be broadly familiar with the consequences of any exposure received under emergency conditions.

j c.

Volunteers should be above age 45.

i d.

Women with a suspected or known pregnancy shall not take part in these actions.

l 3.

Exposure Control a.

Individuals shall not enter any area where dose rates are unknown or beyond the range of instruments being used.

e l

b.

Personnel shall wear dosimeters appropriate for measurement i

of anticipated exposure levels. This shall include:

1)

Two (2) direct-reading pencil dosimeters for whole body exposure:

1-100 or SOR range range. 1-5R range.

2)

Film badge or thermoluminescent dosimeters to permanently record whole body exposures.

3)

If anticipated extremity exposure exceeds 25% of 4

quarterly extremity limit, whole body exposure rings shall be worn.

c.

Protective clothing and/or respirators should be used as appropriate.

In all cases where airborne contamination is anticipated, personnel shall be fitted with pressure / demand Self Contained Breathing Apparatus (SCBA) as a minimum, d.

Potassium Iodide (KI) tablets should be administered where high levels of radio-iodine are suspected. Refer to EP RB-3, " Stable Iodine Thyroid Blocking."

Administrative methods used during normal operations to e.

minimize personnel exposure (such as Special Work Permits (SWPs) and ALARA measures) should remain in force to the extent consistent with timely. rescue, corrective, and protective actions.

I DC0011 211

otAato CANYON POWER PLANT UNIT NO(S)1 AND 2 ON DATE 4/6/84 PAGE 3 0F 5 TITLE EMERGENCY EXPOSURE GUIDES Exposures under these conditions should be limited to once f.

in a lifetime.

4.

Emergency Expostfre Limits Emergency Exposure Limits contained in Table 1 are defined a.

for three categories: 1) Lifetaving actions; 2) Corrective or protective actions; and 3) Sampling under emergency conditions. Example emergency conditions in these categories may be defined as follows:

1)

Lifesaving actions a)

Removal and/or rescue of injured personnel.

2)

Corrective or protective actions l

[

I a)

Providing first aid.

[

b)

Providing ambulance service.

1 I

c)

Providing medical treatment service.

l d)

Performing personnel decontamination.

l l

e)

Undertaking corrective action on plant equipment and systems.

l 3)

Sampling under emergency conditions Collection of in-plant airborne and liquid a) samples.

b)

Use of the post-accident sampling system.

REFERENCES i

NUREG-0737, November 1980.

1.

2.

NCRP Report No. 39, 1971.

" Manual of Protective Action Guides and Protective Actions for 3.

Nuclear Incidents," U.S.E.P.A., September 1975 (Revised June i

1980).

i

(

i i

DC0011 311

---e-

l l[fff0N otAsLO CANYON POWER PL. ANT UNIT NO(Si 1 AND 2 i

DATE 4/6/84 PAGE 4 0F 5 TITLE EMERGENCY EXPOSURE GUIDES l

j SUPPORTING PROCEDURES 1.

RB-3, Stable Iodine Thyroid Blocking TABLES 1.

Emergency Exposure Limits.

ATTACHMENTS f

1.

Form 18-10554 " Emergency Exposure Pennit."

e F

DC0011 411

F

[f[0N iAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 o

~

DATE 4/6/84

(

PAGE 5 0F 5 TITLE.

EMERGENCY EXPOSURE GUIDES TABLE 1 EMERGENCY EXPOSURE GUIDES Sampling Under Corrective or Lifesaving Accident Conditions (a) Protective Actions (c) Actions (c)

Whole Body 5

25 75 Thyroid 15 125 No Limit (d)

Extremities 75 100(b) 200(b)

(a) NUREG-0737, November 1980.

(b) NCRP Repor', No. 39, 1971.

(c) EPA Protective Action Guides, June 1980.

Thyroid exposure should be minimized to the extent feasible by (d) the use of respiratory protection and/or thyroto prophylaxis.

However, no upper limit is specified for lifesaving action since complete loss of thyroid function may be considered an acceptable risk for saving life.

(

'z DC0011 511

r I

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'" "8~l4

}3W3 Pacific Gas and Electric Company REVISION O

~

DATE 4/7/84 DEPARTMENT OF NUCLEAR PLANT O,ERATIONS PAGE 1 0F 11 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE IMPORT. ANT i

TITLE CORE DAMAGE ASSESSMENT PROCEDURE To y a Th 4Wk?+ SAFETY r

A,,movfo PLANT MANAGER 0/

OATE l

l SCOPE This procedure describes the evaluation of the extent of core damage This following an accident that can lead to inadequate core cooling.

l l

procedure and revision thereto requires PSRC review.

DISCUSSION I

ruel damage resulting in the release of radioactive material can occur I

following a loss of coolant accident (LOCA) or following the loss of l

These events, if uncorrected, can lead to l

available heat sinks.

localized or widespread overheating of reactor fuel and eventually to The description of plant fuel rod cladding failure, and/or fuel melt, parameters indicative of conditions that can lead to fuel failure or melt are provided in the Emergency Equipment Operation Procedures (OP Series).

l This procedure supplements other emergency procedures by providing a methodology to determine the extent of core damage that may have This procedure does not replace procedures resulted frem an accident.

that are used to provide instructions regarding accident identification and/or mitigation or dose assessmer,t although similar data and assessment is utilized in this precedure to determine the type and extent of fuel damage.

I The objective of this procedure is the classification of fuel damage inte ene of four broad categories:

(1) no fuel damage, (2) fuel Within the cladding damage. (3) fuel overheat, and (4) fuel melt.latter th damage as a proportion of core radionuclide inventories that have been released to the reactor coolant and/or containment atmosphere.

It provides a preliminary and a long term methodology for ass core damage.

plant parameters such as reactor vessel level and reactor coolant l

temperatures to confirm that conditions exist which can lead to core damage, and quantifies the damage through the use of containment The long-term hydrogen levels and containment radiation levels.

methodology requires that reactor coolant and containment air samples 4,

.l DC0279 1111

• ~

l ri J~

nato CANYON POWER PLANT UNIT NtXS)1 AND 2 ON t>

DATE 4/7/84 PAGE 2 0F 11 CORE DAMAGE ASSESSMENT PROCEDURE TmL be obtained and analyzed for radiochemical and chemical parameters.

f. These results are then used, along with other plant param determine the extent of core damage. The preliminary assessment can yield quick initial results (within approximately)10 minutes).

The hours to obtain long-term assessment could require up to three (3 sample anal results, but yields additional information necessary to distinguish between cladding failures, fuel overheat, and fuel melt, PROCEDURE 1.

Preliminary Assessment _

Corroboratino Evidence for Core Damage a.

If evaluation personnel in the TSC have indicated that conditions exist that could lead to inadequate core cooling (per EP OP-0 Appendix B), or ineffective ESF functioning under LOCA conditions (per EP OP-1, Appendix H), skip this Otherwise, determine tne section and proceed to Section b.

potential for fuel damage as described below:

Check the Aopropriate Answer _

YES g

Are five or more core exit thermocouples 1) temperatures greater than 1,200*F7

[]

2)

Can 51 and/or charging flow to the RCS

[]

be verified?

3)

Can AFW flow to the steam generators and

[]

CCW and ASW flow be verified?

Are RCS pressure and temperature within 4) the " Acceptable Area" of subcooling

[]

as determined using Figure 17 Are containment rad, monitors (RE-30 5) and 31) reading greater than 1R/hr.?

[]

6) is containment pressure greater than

[]

1.3 psig?

4 f

DC0279 2111

l NUMBER EP R8-14 WGLO CANYON POWER MT W %S) 1 AND 2 REVISION O O

DATE 4/7/84 PAGE 3 0F 11

(

CORE DAMAGE ASSESSMENT PROCEDURE TITLE t

l YES

_NO 7)

Is containment temperature greater than

[]

r I

120*F7 i

I Is containment hydrogen level as f

8) indicated by monitors CEL-82 and

[]

CEL-83 up scale?

l If any of the boxes (as opposed to line spaces) for the previous l

questions were checked, then those conditions are poten l

l l

If none of the boxes were checked, continue with this procedure.

caonitoring the situation in accordance with applicable procedures, I

t i

l I

l l

\\

r In general, the more boxes that are checked, the greater theHowe 1

I

• NOTE:

potential for inadequate core cooling.

necessary to determine the significance of this information.

e For conservatism, continue with this procedure if a full evaluation cannot be performed.

t t,

l l

DC0279 3!11 l

t

i NUMBER EP RB-14 Dum.O CANYCN POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION O DATE 4/7/84 PAGE 4 0F 11 TrnL CORE DAMAGE ASSESSMENT PROCEDURE FIGURE 1

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I DC0279 4111 i

i k

i I

l NUMBER EP RB-14 usto CANYON POWER PLANT UNIT QS)1 AND 2 REVISION O o

DATE 4/7/84 PAGE 5 0F 11 i

(

CORE DAMAGE ASSESSMENT PROCEDURE l

T'T*

h Preliminary Assessment of LOCA resultino in Core Damage b.

If loss of reactor coolant to the centainment is not l

occurring, skip this section and proceed to Section 2.

hrs @

f 1)

Record time since reactor trip.

Record reading)of containment area R/hr@

f 2) monitor (RE-30.

R'ecord reading)of containment area R/hr@

3) monitor (RE-31 4)

Determine rag rea monitor R/hr@

l

)/2].

reading [(

+

l t

5)

If the value of Item is < 1 R/hr, I

ndicated, I

then no core dama to calculated I

otherwise compare t

l curves of area mon r response Estimate provided in Figures 2 and 3.

the level of clad or core damage by curves provided interpolating between Record the for the time interval i

results as indicated.

l Interpolation can be a plished Check One _

?

gg by taking the reading nd No damage monitor GAP I

dividing by the expect i,

reading for 100 percent core Melt

~

meltorGAPreleaseattimeh, multiplied by 100.

I t

l l

l l

l I

i i

l 4 l 4 l 4 l

i O.C.O.279 5111

• O

'a E

omo CANYON POWER P1. ANT UNIT NCHS)1 AND 2 ON 5

OATE 4/7/84 PAGE 6 0F 11

?

CORE DAMAGE ASSESSMENT PROCEDURE TITLE

.e

[

FIGURE 2 EXPOSURE RATE VS POST ACCIDENT DECAY TIME I

RE 30 AND 31 WITH GAP RELEASES e.......

E CAP ELIASES 3

-p S

2 100% CAF 10 WORLE CASES 7

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NUMBER EP RB-14 dmo CANYON POWER PLANT UNIT NCNS) 1 AND 2 REVISION O DATE 4/7/84

(

PAGE 7 CF 11 TffLE:

CORE DAMAGE ASSESSMENT PROCEDURE I

I FIGURE 3 F

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1 NUMBER EP RB-14 DesaLO CANYCN POwn Nen' UNff NO(S) 1 AhD 2 REVISION 0 DATE 4/7/84 PAGE 8 0F 11 N

CORE DAMAGE ASSESSMENT PROCEDURE 6)

If no damage, or a G/.P release is indicated, then corroborative results y

can be attempted using containment r

hydrogen levels. If care melt is indicated, proceed to Section 2 of this

~ precedure.

7) -Determine the average containment hydrogen concentration from containwnt l

hydrogen monitors CEL-82 and CEL-83.

r 8)- Compars item OE determined in Chect One Step 7 with thT curve of expected H2 No damage concentration versus percent clad l

t failurr'found in Figure 4 Clad faTTIire Estimate the perce9t clad damage and """~

[

i record the result.

2.

Lone-TermAssessmeg a.

Request Sample i

1)

Request that the Emergency Radiological Advisor (ERA; l

assign a sampling team to collect a RCS and centainment air sample from tne post-accident sampling system (PASS). The following analyses pall be performed:

a)

Ganna spectrometry on:

(1) RCS liquid and off-gas (2) Containment air j

{

• NOTE: Hydrogen levels in containment are a valid indicator of damage only within the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the accident, assuming that the hydrogen recombiners are not operating. Since complex l

mechanisms dictate the amount of H2 and radioactive materials released to containawnt it is not possible to predict which l

ast,essment of cisd damage is more accurate.

If results of l

monitors l

damage assessment using the rad, monitors and the Na dif fer, try to utilize corroborating data from RVLIS, etc., to i

I l

select the most representative assessment of damage. If l

resolution cannot be obtained, use the highest estimated level t

of clad failure.

P DC0279 8111

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t i

l NUMBER EP RS-14 pueLO CANYON POWER PLANT UNIT %$1 1 AND 2 REVISION 0 l

DATE 4/7/84 PAGE 9 0F 11 i

! I l

T' M -

CORE DAMAGE ASSESSMENT PROCEDURE I

I Ha) levels on:Containa nt air b)

(1 y

Request that the sample analysis be decay corrected l

r

(

back to the time of sampling.

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PAGE 10 0F 11 N

CORE DAMAGE ASSESSMENT PROCEDURE FIGURE 4 7.-

RESPONSE Or CONTA!IpqENT NTDR0 GEN NOMITORS (CEL-82 and CEL-83) TO PRODUCED BY THE Zr-REACTION to P

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t PAGE 11 0F 11 i

I l

I.

l TITLE CORE DAMAGE ASSESSMENT PROCEDURE f

o l

i Await sample analyses. This may take up to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

2)

In the interim, continue to assess core damage via the l

l When l

,e technioues provided in Part 1 of this procedure.

sample analyses are available, proceed to Section 2.2.

r b.

Analysis of Sample Results 1)

Complete Attachment 1, " Water Entrained Inventory Worksheet."

(

2)

Complete Attachment 2, " Airborne Inventory Worksheet."

i l

If reactor power for the 30 days prior to shutdown 3) remained relatively constant (within the range of 220 percent) and the average power level is at least l

l 80 percent, proceed to Attachment 3 and determine the Otherwise, power corrected source inventories.

(

complete Attachment 4 to correct source inventories for e

a variable power history.

i Complete Attachment 5 to determine percentage of core l

4) or GAP activity released.

i Refer to Attachment 6 to determine what type of faih.re t

5)

(no damage, clad, overtemp, melt) is occurring (if any).

Report results determined by this procedure to the l

6) individual making the recuest for a core damage i

assessment.

Continue to monitor the situation by utilizing this 7) procedure as necessary.

ATTACHMENTS 1.

Water Entrained Inventory Worksheet i

2.

Airborne Inventory Worksheet l

Calculation of Power-Corrected Source Inventories for Constant 3.

Power Levels i

Source Inventory Power Correction for Variable Power History 4.

l l

Comparison of Expected and Actual Source Inventories lk 5.

6.

Qualitative Assessment t

DC0279 11III e

e y

L i

i PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 3 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIK u CANYON POWER PLANT UNIT N05. 1 AND 2

'~

~

I.

TITLE: WATER ENTRAINED INVENTORY WORKSHEET f

ATTACHMENT 1 t

1.

Check the appropriate sample type:

ReactorCavitySump@

l

['

_ RCS RHR Convert the elapsed time since reactor trip and the collection of the

[

2.

RCS sample to hours:

hr @

If the sample is a RCS sample, record the following information:

l 3.

f

'F RCS Temperature (Tave) l psia RCS Pressure RCS Density Correction Factor (Figure 5) gal @

4 Last RWST volume prior to accident gal @

5.

Current RWST volume gal @

VolumeofRWSTinjected(h-@)=

6.

Determine which ECCS volumes have been released into the RCS or containment, ano determine the total volume in the Containment Sump:

l 7.

Actual Used ir. DCS Total Volume f

(1) RWSTVelume=@x3.785h=

c@

7 l

(2) Each Accumulator = 4.28 X 10 cc (there are cch 7

four accumulators) 8 3.56 x 10 cc @

f f

f (3) RCS = 3.56 X 10 cc (4) Total Volume (@ + @ + @)

cc @

8.

Enter the values of E and on the next page and calculate the total water entraine invent as indicated.

t 9.

' Proceed to Step 2.2.1 of this procedure.

\\

l a

i

Page 2 or 3 TITLE: WATER ENTRAINED INVENTORY WORKSHEET ATTACHMENT 1 (Continued) l lDJ B '3 C

A' Measured Liquid Activity at Total i

Sample Activity RCS Conditions Water Entrained r

. Isotope (uC1/cc)

(uCi/cc)

Inventory (Ci}

r Kr-87 Xe-133 1-131 1-132 Te-132 Cs-134 Ba-140 La-140 (a) B = A < h (b)C=Bx@

x 10~

Liquid is defined as the total activity from the RCS sample, including any off gases.

0

PACIFIC GAS AND ELECTRIC COMPANY Page 3 of 3 DEPARTMENT OF NUCLEAR PLANT OPERATIONS l

f OIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 FinURE 5 I

TITLE: WATER ENTRAINED INVENTORY WORKSHEET l

i l

PASS LIQUID SAMPLE DEM51TY CDRAECTION I

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PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATION DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 m

I TITLE: AIRBORNE INVENTORY WORKSHEET i

ATTACHMENT 2 t

Record the elapsed decay time since reactor trip and the collections of l

l 1.

the containment air sample in hours:

he {

+

2.

Record the following information:

Containment Temperature

'F ntainment Pressure psig l

C + 14.7 =

psia Calculate the Containment atmosphere Pressure and Temperature (P-T) correction factor using the following formula:

l 3.

530 P-T Correction Factor =

I Where530isroomtemperatureonRankineScale.

h I

P-T Correction Factor

?

Record the containment airborne sample activities in Column A on page 2 I

of this attachment.

(NOTE: The containment activities reported by the 4.

j sampling teams are at room temperature and pressure, Adjust the reported activities to the conditions of temperature andby!

l 5.

pressure fcund in the contain and recording the result in Colwn B.

by the P-T correction factor, Calculate the total airborne inventory of the nuclides of interest ey (This is the 6.

multiplying all the values in Column B by 7.36E+04.

Congainment volume of 7.36E+10cc and the conversion factor of l

10~ Ci/uti.) The results should be recorded in Column C.

i l

s l

9 i

0C0279 14111 i

_ _. _ ~..... _,.. _. _. _

Page 2 of 2 i

AIRBORNE INVENTORY WORKSHEET -

TITt.E:

f ATTACHMENT 2 (Continued)

I glaj clbj g

l Activity at Total Airborne Measured Sample Containment Conditions Inventory (Ci)

Activity (vCi/cc)

(vCi/cc)

Nuclide Kr-87 i

Xe-133 I-131 l

I-132 la] 8 = A x h (b)C=Bx7.36E+04 Proceed to Step 2.b.3) 7.

'\\

• I:!

t I

PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS I

DIABLO CANYON POWER PLANT UNIT N05.1 AND 2

(

TITLE: CALCULATION OF POWER-CORRECTED SOURCE INVENTORIES FOR CONSTANT POWER LEVELS l

ATTACHMENT 3 (This form l

[. Estiraate and record the average power for the last 30 days.!

1.

and has remained relatively constant [within the range of 220 percent in the last 30 days). If the power level has not been relatively constant, i

use Attachment 4.

2.

Multiply the source inventory values listed in Column 1 by the value on l

Line 1, and recerd the result in Column 2.

3.

Enter the corrected values.

I 1

2 EQUll'BRIUM CORRECTED i

SOURCE SOURCE NUCLIDE (Cil (Ci) l I

GAP INVENTORY

~

Kr-87 3.9E+4 Xe-133 1.3E+6 1-131 8.0E+5 1-132 1.3E+5

[

i FUEL PELLET I

INVENTORY' t

Kr-87 5.9E+6 Xe-133 1.9E+8 Te-132 1.4E+8

{

Cs-134 3.1E+6 f

1.6E+8 Ba-140 e

La-140 1.8E+9

q 1-131 9.7E+7

[

+

I-132 1.4E+8 F***7Q

'Ai77

i

~

PACIFIC GA5 AND ELECTRIC COMPANY Page 1 of 3

,i DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 m

SOURCE INVENTORY POWER CORRECTION FOR VARIABLE POWER HISTORY I-TITLE:

ATTACHMENT 4 When the power level has not been relatively constant at 80 percent for the last 30 days, nuclides of interest have not had enough time to build up to e epilibrium levels.

In this case, the effects of each significant power change must be taken into account. The formula to be used is:

t t

t 13 9-Ag 2j PF4=IFj j (1-e-A Where:

4 = 30-day power factor for Nuclide i PF F = fractional power level for time Period j 3

i 1i = nuclear decay constant for Nuclide i tij = length of time Period j l

2j = time from end of time Period j to end of 30-day period.

t The calculatier of power factor must be repeated for every nuclide.

The power factor determined in this way should be recorded in Column B c' this This power factor should then be multiplied by the value in Colur-C with from.

the result rect.rded in Column D.

Sample power factor calculation:

The Plant has operated for the 30 days prior to the accident with Se i

following cower history:

i 100-percent pcwer for 10 days 70-percent power for 5 days 0-percent power for 7 days 70-percent power for 8 days t

I i

t-CS77Q

• 77?'

l Page R of 3 l

TITLE: SOURCE INVENTORY POWER CORRECTION FOR VARIABLE POWER HISTORY

\\

ATTACHMENT 4 (Continued) 100 70%

7#

30 Day Power History Prior to Accident 05 0

10 15 22 30 For time Period 1, F3 = 1.0, t33 = 10 days, t21 = 20 days For time Period 2, F2 " 0*7' *12 = 5 days, t22 = 15 days For time Period 3,

= 8 days F3 = 0.0, t33 = 7 days, t23 For time Period 4,

= 8 days, t24 = 0 days F = 0.7, t34 4

The equation for Nuclide i would be:

PF = [1.0 (1-e-Ai (10 days)),-19(20 days))

i (5 days)),-A, (15 days))

4

~A

+[0.7(1-e i

days)),-Ag (8 days))

+[0.0(1-e-A

+[0.7(1-e~Ai (8 days)),-14(0 days))

e 4

DCO279 1811I

P t

i i

Page 3 of 3 i

f

/

TITLE: SOURCE INVENTORY POWER CORRECTION FOR VARIABLE POWER HISTORY i

i ATTACHMENT 4 (Continued) l CORRECTION FOR VARIABLE POWER LEVEL l

p r

(

A B

C 0

l l

l Power Equilibrium Corrected Decay Correction Source Scurce Constant Factor inventory Inventory NUCLIDE (day ~1)

(PF )

(Ci)

(C1)

{

4 f

l t

[

I Gap Inventory l

t Kr-87 13.10 3.9E+4 Xe-133 0.13 1.3E+6 I-131 8.62X10"#

8.0E+5 I-132 6.94 1.3E+5 Fyg,ggypt l

Kr-87 13.10 5.9E+7 Xe-133 0.13 1.9E+8 Te-132 2.13X10~l 1.4E+8 r

f Cs-134 9.21X10~'

3.1E+6 Ba-140 5.42X10~2 1.6E+8 La-140 4.15X10~l 1.8E+E f

I-131 8.62X10" 9.7E+7 I-132 6.94 1.4E+8 l

[

I i

l t

i l

OCC279 19111 I

r

i PAC 1FIC EAS AND ELECTRIC COMPANY Page 1 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS

.i DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 p-~

~

I. _/

TITLE: COMPARISON 0F EXPECTED AND ACTUAL SOURCE INVENTORIES

(

ATTACHMENT 5

[

Copy both the total waterborne and airborne nuclide inventories into 1.

l Columns 1 and 2 of the attached Form.

' 2i' Add Columns 1 and 2 to get the total release inventory of each nuclide i

lof interest, and record the result in Column 3.

~

i Copy the expected source inventory into Column 4 from Attachment 3 or 4 3.

For each nuclide, divide the value in Column 3 by the corresponding 4.

value in Column 4, and record the result in Column 5.

l t

5.

Go to Section 2.2 Step 5.

L i

I i

l F

l L

<T l

DC0279 20!!!

I

i i

Page 2 of 2 TITLE: COMPARISON 0F EXPECTED AND ACTUAL SOURCE INVENTORIES j

(

ATTACHMENT 5 I

1 2

3 4

5

(

f Expected i

t Total Source l'

Total Total Released Inventory (Ci)

Waterborne Airborne Inventory (Attachment 3 Percent Isotope (Attachment 1) (Attachment 2)

(C1) or 4)

Released v

i Gas Gap Inventory i

Kr-87 Xe-133

[

t I-131 i

1-132 Average t Fuel Pellet i

inventory Kr-87 Xe-133 I

I-131 l

1-132 Cs-134 Te-132 Ba-140 La-140 Average %

Check One:

(

'Do not use fer calculating " average No damage j

percent". Use only for qualitative GAP release i

assessment on Attachment 6.

Core melt l

i e-PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2

(-

iA TITLE: QUALITATIVE ASSESSMENT ATTACHMENT 6 1.

For each nuclide listed on the attached worksheet, check the box which corresponds to the inventory percentage found on attachment 5.

Circle

[' the applicable iodine ratio.

2.

To best determine the category of damage, concentrate on the presence or absence of key nuclides (e.g., Te, Cs, Ba, La).

3.

The general location of the marks should give an indication of the type of core damage.

l 4.

Enter the type of damage that has been determined on Attachment 5, and proceed to step 2.2.6.

NOTE:

If Ag-110m was found in any of the samples, it is a good indicator of fuel melt ( Ag is from the control rods).

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