Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP OP-15 Re Loss of Feedwater Flow,Ep OP-20 Re Excessive RCS Leakage & EP OP-32 Re Rod Ejection.Revised Table of Contents Encl
	ML20049J002
Person / Time
Site:	Diablo Canyon
Issue date:	02/11/1982
From:	; PACIFIC GAS & ELECTRIC CO.
To:	;
Shared Package
ML16340C377	List: ML16340C378; ML20049J002;
References
	PROC-820211-01, NUDOCS 8203110156
	Download: ML20049J002 (100)
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NUMBER EP OP -15 FGEJE Paci!!c Gas and Electric Company REVISION . 4 b) q, ,

A DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE PAGE 1 12/31/81 OF 4 EMERGENCY OPERATING PROCEDURE h TITLE LOSS OF FEEDWATER FLOW IL APPROVED:

PLANT MANAGER /j DATE SCOPE This procedure provides instructions to prevent a reactor trip if Main Feed-water is lost during start-up or if both Main Feedwater Pumps (MFP's) are running and one MFP trips. If a reactor trip occurs, the operator is direct-ed to EP OP-3-~-

SYMPTOMS

1. Indicated S/G feedwhier flow and level decreasing.

2. Main Feedwater pump discharge pressure decreasing (PI-49, PI-50).

3. Main Feedwater header pressure decreasing (PI-508).

(f 4. Feedline/Steamline differential pressure decreasing (PI-509).

5. 'Possible annunciators:

a. STEAM GENERATOR NO. (PK-09-1, 2, 3, or 4).

1) S/G level low from reference.

b. PROTECTION CHANNEL ACTIVATED (PK-04-7).

1) S/G low level and S/G flow mismatch bistables.

2) S/G low-low level bistable.

c. FEEDWATER PUMP TRIP (PK-09-12).

d. FEEDWATER PUMP NO. (PK-09-13, 14) .

1) Feedwater trouble alanns.

AUTOMATIC ACTIONS

1. Possible auto start of auxiliary feedwater pumps.

S/G blowdown isolation due to auto start of AFW pumps.

2.

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1 NUMBER EP OP-15 1 AND 2 REVISION 4 QJA,fjp, CANYON POWER PLANT UNIT NO(S) ,

LMtKbtNCY OPERATING PROCEDURE DATE 12/31/81 PAGE 2 OF 4 TITLE: LOSS OF FEE 0 WATER FLOW

3. Possible reactor trip on S/G low level coincident with S/G flow mismatch, or S/G low-low level.

4. Possible turbine trip due to reactor trip.

OBJECTIVES

1. Prevent a reactor trip if possible.

2. Ensure sufficient feedwater to all S/G's.

3. Stabilize the primary and secondary coolant systems.

COMMENTS IMMEDIATE OPERATOR ACTIONS

1. If a reactor _ trip occurs, discontinue this procedure and go to EP OP-5, Reactor Trip without SI. s

2. MAIN FEEDWATER LOST DURING START-UP:

a. Design capacity

a. Attempt to avoid a reactor of the AFW sys-trip by reducing power to match the capacity of tem is % 6%

the Auxiliary Feedwater (AFW) power.

system.

b. Ensure motor driven AFW pumps are running and supplying flow to S/G's. .

BOTH MFP's 0PERATING AND ONE MFP TRIPS:

3. ,

a. Attempt to avoid a reactor trip by quickly reducing turbine load to < 50%.

b. Drive rods in

b. Check or place control rods in AUTO and manually if l

verify rods are stepping in. necessary.

SUBSEQUENT OPERATOR ACTIONS

' l. MAIN FEEDWATER LOST DURING START-UP:

a. Verify AFW level control valves are maintaining program level. Take manual action if necessary.

b. If feedwater flow is not sufficient:

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I NUMBER EP OP-15 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND'2 REVISION 4 EMERGENCY OPERATING PROCEDURE DATE -12/31/81 PAGE 3 OF 4 TITLE LOSS OF FEEDWATER FLOW

1) Start turbine driven AFW pump and/or,

2) Further reduce power as necessary, to match feedwater capacity.

2. BOTH MFP's OPERATING AND ONE MFP TRIPS:

a. If manual oper-

a. Check that Main Feedwater regulating ation was requir-valves are automatically controlling ed, match S/G S/G levels. Take manual control if levels to program necessary to maintain proper level.

level. When con-

b. Check proper operation of steam dump trol has stabili-control system if actuated, and verify zed, maintain TAVG is being reduced to match TREF. program level for approximately 3

c. Monitor PZR and ver.ify level and pressure minutes (for con-are at or returning to progranned values. trol system stab-ilization) then If Load Transient Bypass action has place in AUTO.

i d.

( occurred because of the rapid load rejection, verify the following and d. Load Transient take manual action if necessary: Bypass relay action will FCV-55 opens occur if turbinc

1) load is > 70%

and

2) FCV-31 opens. Turbine load i rejection is

3) TCV-23 opens > 10% in a 2 FCV-230 opens minute period.

4) NOTE: When all FCV-30 closes valves are in

5) the proper posi-tion, red light

6) LCV-12 closed on condensate

7) Standby condensate and condensate LTB control booster pump set starts automatically. switch will ill-uminate.

3. If blowdown isolation occurred, re-establish blowdown when plant conditions have stabilized.

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NUMBER EP OP-15 1 AND 2 REVISION 4 DIABLO CANYON POWER PLANT UNIT NO(S)

DATE 12/31/81 EMERGENCY OPERATING PROCEDURE PAGE 4 OF 4 TrrLE: LOSS OF FEEDWATER Fl.0W APPENDIX Z ,

EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS

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

a. Notify the Plant Superintendent. Supervisor of Operations, and Plant Manager or their designated alternates, As a minimum, within one

b. Designate this event a Sionificant Event.

hour, notify the NRC Bethesda Operations Center using the red phone in the Control Room. Gather sufficient information from all Refer sources prior to calling so that the phone call is meaningful.

to Operating Procedure 0-4 " Operating Order (One Hour Reporting Notify Requirements to NRC)" for a suggested format for reporti of Significant Events). .

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FGW3 NUMBER EP OP-19 Pacific Gas and Electric Company

. REVISION -2 m

DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 2/11/82 (O*; I i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 FAGE 1 OF 4 EMERGENCY OPERATING PROCEDURE m

w MALFUNCTION OF REACTOR MAKEUP CONTROL SYSTEM APPROVED: J 6 -

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' PLANT MANAGEP[j DATE SCOPE This procedure outlines the steps to be taken in the event the automatic reactor makeup control system fails to maintain or adjust the boron concentra-tion or fails to maintain level in the volume control tank.

SYMPTOMS

1. Volume control tank high or low-low level alarm (PK04-24).

2. Unusual or Unwarranted auto control rod movement.

3. Control rod insertion low limit or low-low limit alarm (PK03-13 or 14).

( 4. Primary water and/or boric acid flow deviation alarm (PK-05-11).

5. Unexpected change in countrate when the reactor is shutdown.

6. Possible Source Range High Flux at shutdown alarm (PK03-07).

7. Possible TAVG-Tref deviation alarm (PK04-01).

8. Gross deviation between calculated and actual boron concentrations.

9. Charging pump suction swap from VCT to RWST.

AUTOMATIC ACTIONS

1. If the volume control tank low-low level (5".) is reached the charging pump suction is switched to the refueling water storace tank (valves 8805A & B open and the volume control tank outlet valves,LCV-112B&C,close).

2. Possible control rod movement if rods are in automatic.

3. Possible letdown diversion to liouid hold uo tanks.

OBJECTIVES

1. Restore VCT level.

2. Maintain or restore desired VCT boric acid concentration.

O, . Teminate any uncontrolled boron dilution or adcition due to malfunction of makeuo system.

NUMBER EP OP-19 OtABLO CANYON POWER PLANT UNIT NO(S) I'AND 2 REVISION 2 DATE 2/11/82 PAGE 2 OF 4 TITLE: MALFUNCTION OF REACTOR MAKEUP CONTROL SYSTEM IMMEDIATE OPERATOR ACTIONS COMMENTS ACTIONS ,

1. If.a malfunction resulted in an inadvertent boron dilution or addition.

a. Take action to terminate the event.

b. If necessary emergency borate as per EP OP-6.

c. Restore RCS boron concentration.

2. If VCT level is not being maintained in auto:

a. Check VCT makeup system is properly lined up for automatic 3 control.

b. Check divert valve and controller for proper operation.

c. Check VCT for possible failed level channel .

d. Restore automatic control of VCT makeup system if possible.

3. If automatic control will not function, use manual control as necessary to ter-minate the energency and restore the VCT to an adequate level and/or boron concen-tration.

SUBSEQUENT OPERATOR ACTION CCMMENTS ACTIONS

1. If charging pump suction has swapped to the RWST:

a. Use control rods and/or turbine load to maten Tavg and TREF.

b. When the VCT level has been restored to 1i0% and the VCT makeuo rate exceecs tr.: Onarging rate.

8 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP OP-19

% DATE 2/11/82 PAGE 3 OF 4 TITLE: MALFUNCTION OF REACTOR MAKEUP CONTROL SYSTEM

1) Open LCV-112 B and C. -

2) Close valves 8805 A and B. 2) Verify proper charging flow.

3) Check for stable or increasing VCT l evel .

c. Have Rad and Chem department take a c. RWST is saturated RCS sample. with 0 2

2. If normal makeup flows cannot be established proceed as follows:

a. Start a primary water, pump and transfer a boric acid pump to high speed.

b. Open or check open FCV 110A

,. c. Open the manual emergency borate c. Establish comunica-

'( valve (8471). Adjust its position tion with the to give desired blend with 70gpm control room to set primary water. -

desired boric acid fl ow.

d. Open the manual emergency primary water valve (8441) and adjust its position to achieve 70gpm flow.

e. When VCT level has been restored to

>10% and level is increasing, open EVC-112 B and C. Then close 8805 A & B and verify nomal charging flow and stable or increasing VCT level

f. Observe the control rods and adjust the manual borate valve (8471) to avoid any rod position limits.

3. If necessary continue to operate manually to control VCT level until repairs are made to the system.

4. Verify the RCS boron concentration, dissolved 02 and H2 concentrations are within limits for existing plant status, d

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l'NND2 NUMBER EP OP-19 DIABLO CANYON POWER PLANT UNIT NO'(S) REVISION 2 DATE 2/11/82 PAGE 4 OF 4 TITLE: MALFUNCTION OF REACTOR MAKEUP CONTROL SYSTEM APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS l'. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:

a. Notify the Plant Superintendent, Supervisor of Operations and Plant Manager or their designated alternates.

b. Designate this event a Sionificant Event. As a minimum, within one hour notify the NRC Betnesda Operations Center using the red phpne in the Control Room. Gather sufficient infomation from all sources prior to calling so that the phone call is meaningful. Refer to

. Operating Procedure 0-4 " Operating Order (One Hour Reporting Require-I ments to NRC)" for a suggested famat for reporting. Notify the l NRC that your call is pursuant to 10 CFR Part 50.72, (Notification t

of Significant Events). ,

c. Review subsequent plant conditions against the classification criteria in Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."

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NUMBER EP OP-20

,FGs#E Pacific Gas an'd Electric C~ompany !

REVISION - 2 A ~

DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 12/15/81 Y DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY OPERATING PROCEDURE PAGE 1 OF 5 TITLE: EXCESSIVE REACTOR COOLANT SYSTEM LEAKAGE g

APPROVED: L PLANT MANAGER [ ~ DATE SCOPE This procedure outlines the steps to be taken in the event of reactor coolant system leakage in excess of the Technical Specifications limits, yet within the capacity of the charging system. If leakage is detected, the primary goal should be to identify and isolate or reduce the magnitude of the leak.

SYliPTOMS Any one or more of the following symptoms may indicate excessive reactor coolant leakage:

1. Unexpected auto make-up to Volume Control Tank (VCT).

2. Unexpected charging pump speed or flow increase during steady-state

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operation.

3. Increased level, temperature and/or pressure in the Pressurizer Relief Tank (PRT).

4. Possible annunciators:

a. HIGH RADIATION (PKil-21)

1) Containment Area Rad Monitor alarm.

2) Incore seal table Area Rad Monitor alarm.

3) Sampling room Area Rad Monitor alarm.

4) Charging pump room Area Rad Monitor alarm.

5) Auxiliary building control board Area Rad Monitor alarm.

6) Process monitor Hi-Rad alarm.

b. CONTAINMENT ENVIRONMENT (PK01-16)

c. PRESSURIZER SAFETY OR RELIEF LINE TEMPERATURE (PX05-23).

d. PRESSURIZER RELIEF / SAFETY VALVES OPEN (PX05-20).

e. BUILDING SUMPS (PK15-01).

1 AND 2 NUMBER EP OP-20 DIABLO CAtttfCN "DWC A PLANT UNIT NO(E) REVISION 2 EMERGENCY C=ERATIING PROCEDURE

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DATE 12/15/81 TITLE: EXrWVE : REACTOR COOLANT SYSTEM LEAKAGE

1) Lontainment sump high level alarm.

2) Reactor cavity sump high level alarm.

f. PRESSURH2ER LEVEL HI/LO ( '05-21) 9 PRE 55UR22ER LEVEL HI/LO CONTROL (PK05-22).

h. REACTOR FLANGE LEAX0FF TEMP HI (PX11-02).

i. RCS VALYE STEM LEAKAGE . ,

(PK05-8).

AUTOMATIC AC IONS _

l. Possible charging pump flow increase.

2. Possible process monitor isolation actions:

a. Component cooling water surge tank vent valve closure,

b. Steam generator blowdown and sample line isolation.

c. Containment ventilation isolation.

3. Possible PRT vent header isolation at 10 PSIG in PRT.

4. Possible pressurizer letdown isolation.

OBJECTIVE

1. Identify the source and rate of leakage.

2. Isolate the leak, if possible.

3. Take actions as necessary to comply with Technical Specifications requirements.

COMMENTS IMMEDIATE OPERATOR ACTIONS

l. Monitor pressurizer level and start another charging pump as necessary.

2. If pressurizer level continues to drop, isolate letdown.

3. If pressurizer level cannot be maintained, manually initiate SI and go to EP OP-0, Reactor Trip with Safety Injection.

DIABLO CANYON POWER PLANT UNIT NO(S) ' 1 AND 2 NUMBER EP OP-20

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EMERGENCY OPERATING PROCEDURE R '"

D A-- 2/15/81 PAGE 3 OF 5 M LE: EXCESSIVE REACTOR COOLANT SYSTEM LEAXAGE SUBSEQUENT OPERATOR ACTION

1. Monitor the VCT level and take manual control as necessary to maintain VCf level. If charging pump suction is swapped to the RWST, commence a rapid load reduction and proceed to shut-down the reactor.

2. Attempt to determine the magnitude of 2. Refer to STP R-10.

the leak while continuing with this procedure.

3. If S/G tube leakage is indicated, go to EP OP-3B, Minor S/G Tube Leak.

4. Check for indication of leakage from 4. Refer to Technical Specifi-PZR Safety valves and PORV's by obser- cations 3.4.4 if block ving discharge temperatures and sonic valve is closed.

flow detector. If leakage is indicated from PORV, close the associated block valve.

5. If the leak appears to be inside containment:

a. Check the containment tempera- a. Monitoring system is ture and dewpoint monitoring located in Mech. Panel system and attempt to determine 199 next to the HSD

- the location of the leak. Panel. Refer to P&ID drawing No.

b. Consider making containment entry 102023 sheet 8 for for inspection. detector location table and map.

6. Check other possible sources of leakage:

a. Primary sampling system.

b. Component cooling water surge tank. b. If leakage is indicated in CCW system, go to

c. If reactor vessel flange leakage EP OP-ll.

is indicated:

1) Close 8032 on VB2.

2) Close 8069B, then open 8069A.

3) Open 8032 and check for indications of leakage past the outer 0-ring.

O 4) If leakage occurs past the outer 0-ring, proceed with reactor shutdown.

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP OP-20 EMERGENCY OPERATING PROCEDURE REVISION 2 DATE 12/15/81 PAGE 4 OF 5 TITLE: EXCESSIVE REACTOR C0OLANT SYSTEM LEAKAGE

d. Cneck unusual inflow to liquid radwaste system.

e. Check for possible discharge e. Refer to OP A-4B:IV, into the PRT from relief valves Table 1 & 2 for list of or valve stem leakoff. valves that discharge into the PRT.

7. If leakage is indicated in the 7. If leakage is due to a let-auxiliary building, conduct a down or charging failure, radiation survey to assist in refer to EP OP-18.

locating the leak.

8. If leak is located, atter.pt to isolate it.

9. When the leak rate is determined 9. Technical Specifications j and classified, take actions as 3.4.6.2.

required by the Plant Technical Specifications.

10. Continue to monitor leakrate as ,

nece sary.

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I DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND* 2 NUMBER EP OP-20 EMERGENCY OPERATING PROCEDURE REVISION 2 DATE- 12/15/81 PAGE 5 OF 5 -

, TITLE: EXCESSIVE REACTOR COOLANT SYSTEM LEAKAGE

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APPENDIX Z I EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS

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

a. Designate this event a Notification of Unusual Event. Notify plant staff and response organizations required for this classification by implementing Procedures G-2 " Establishment of the On-Site Emergency Organization" and G-3 " Notification cf Off-Site Organizations" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation".

b. If the RCS leak rate is calculated to be > 50 gpm or one centrifugal charging pump is unable to maintain pressurizer level with normal

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. lecdown flow, designate this event an Alert. Notify plant staff ano response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.

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PG943 Pacific Gas and Electric Company NUMBER REVISION EP OP-30 1

DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 2/11/82 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 OF 3 EMERGENCY OPERATING PROCEDURE w INADVERTENT LOADING OF A FUEL ASSEMBLY INTO AN IMPROPER POSIT N APPROVED: N b- - NL PLANT MANAGE @ -

DATE SCOPE This. procedure addresses the event in which either manufacturing errors or core loading errors result in placing fuel in a core position calling for fuel of lesser enrichment. This can result in power shapes which peak in excess of design values.

SYMPTOMS

1. The resultant high peaking factors would readily be detectable by evaluation of flux maps taken during the performance of STP R-3D.

2. Incore thennoccuple maps might indicate an abnormally high enthalpy rise.

( 3. If the resulting peaking factors are severe enough or if the affected fuel #

assembly is at an incore flux detector location, the problem will be dis-covered during low power physics testing.

AUTOMATIC ACTIONS None OBJECTIVES

1. To place the reactor in an acceptable mode or power level as per Technical Specifications upon discovery of the problem.

I!HEDIATE OPERATOR ACTIONS COMMENTS

1. If at power and Fg (Z)' exceeds its 1. Technical Specification 3.2.2 limit: with 15 minutes, reduce thermal power at least 1% for each 1% FQ (Z) exceeds the limit.

2. If at power and R1 exceeds its limits, 2. Technical Specification 3.2.3 reduce thermal power to less than 50% within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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NUMBER EP OP-30 DIABLO CANYON POWER PLANT UNIT NO(S). 1 AtiD 2 REVISION 1 QATE 2/11/82 PAGE 2 OF 3 Tn e INADVERTENT LOADING 0F A FUEL ASSEMBLY INTO AN IMPROPER POSITION SUBSEQUENT OPERATOR ACTIONS ACTION COMMENTS

1. If power was reduced due to high Fg(Z):

a. Within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reduce a.With setpoints reduced, power operation the power range neutron flux may continue for up to a total of 72 high trip setpoint by the same hours.

percent as power was reduced.

b. Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months place the b. Refer to L-5.

reactor in at least not standby.

c. If continued power operation is desired while the problem is being investigated:

1) While in at least hot -

standby, reduce the OPAT trip setpoint by at least 1% for each 1".

FQ(Z) exceeded its limit.

2) Bring the' reactor to an -

acceptable power level.

l If power was reduced due to high 2. Comply with Technical Specification

2. 3.2.3 action requirements.

R1 condition, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months -

reduce the power range neutron flux Hi trip setpoint to 55%

rated power, t

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP OP-30 REVISION 1 DATE 2/11/82 PAGE 3 OF 3 Tm~. INADVERTENT LOADING OF A FUEL ASSEMBLY INTO AN IMPROPER POSITION APPENDIX Z -

EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS

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

a. Notify the Plant Superintendent, Supervisor of Operations and l the Plant Manager or their designated alternates.

b. Designate this event a significant event. As a minimum, within one hour notify the NRC Bethesda Operations Center using the red phc.e in the Control Room. Gather sufficient infornation from all ources prior to calling so that the phone call is meaningful.

Refer to Operating Procedure 0-4 " Operating Order (One Hour Reporting Requirements to NRC)" for a suggested femat for reporting. Notify the NRC that your call is pursuant to 10 CFR Part 50.72, (Notifi-cation of Significant Events).

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c. If the plant conditions requires entering a Technical Specification action statement requiring plant shutdown, designate this event a Notification of Unusual Event. Notify plant staff and resconse organizations in accorcance with Emergency Procedures G-2 "Estab-lishment of the On-Site Emergency Organization" and G-3 "Notifi-cation of Off-Site Organizations" in accorcance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."

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NuuaER EP OP-32 T

L GEi3 Pacific Gas and Electric Company REVISION 1 A DATE 2/11/82 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 OF 3 EMERGENCY OPERATING PROCEDURE Te w R00 EJECTION

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/ D APPROVED:

PLANT MANAGER 6 DATE SCOPE This procedure provides guidance in the event of a control or shutdown rod ejection from the reactor core. The basic assur.1ption i; that the reactor is at power with control rods on manual with bank 0 at the Lo-Lo insertion limit.

The ejection occurs as a result of a mechanical failure in the vessel head such that a breach of the reactor coolant system exists.

SYMPTOMS

1. Reactor trip on Hi Flux .

2. Turbin,e trip alarms.

i 3. PZR pressure lo press alarm.

4. SI initiated.

AUTCPATIC ACTIONS

1. Reactor trip.

2. Turbine trip.

3. Auxiliary power transfer to startup power.

4. Steam dump activated.

5. SI activated on RCS Lo pressure.

OBJECTIVES

1. To ensure a reactor shutdown.

2. To prevent core damage by maintaining ECCS systems operating.

3. To ensure the plant stabilizes at a condition where no fuel damage occurs.

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NUMBER EP OP-32 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND '2 REVISION 1 DATE 2/11/82 PAGE 2 OF 3

' TITLE: ROD EJECTION IMMEDIATE OPERATOR ACTIONS ACTIONS COMMENTS

1. Go imediately to 0P-0.

SUBSEQUENT OPERATOR ACTIONS None i

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1 AND 2 -

NUMBER EP OP-32 DIABLO CANYON POWER PLANT UNIT NO(S)

REVISION 1 O ROD EJECTION DATE PAGE 3 2/11/82 OF 3 rnts:

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APPENDIX Z -

EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS

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

a. Designate this event a Site Area Emeroency. Notify plant staff and response organizations by implementing Energency Procedures G-2 " Establishment of the On-Site Energency Organization" and G-3 " Notification of Off-Site Organizations" in accordance with Energency Procedure G-1 " Accident Classification and Emergency Plan Activiation."

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3D(BF43 EP OP-33

^

NUMeER Pacific Gas and Electric Company REVISION 1 m

DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 2/11/82

{ 4 V- DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 OF EMEF.3ENCY OPERATING PROCEDURE N

Q LOSS OF INSTRUMENT AIR APPROVED: , L 1 PIMT MANAGER /') ~ DATE i SCOPE This procedure provides guidance to the operator should the instrument air header pressure decrease to alarm levels. It is assumed herein that the Class I backup pneumatic supply system is available. Backup nitrogen system status as noted. In addition, this procedure directs operator action when all available air compressors cannot provide nonnal system pressure.

SYMPTOMS

1. Low instrument air header pressure ci n (PK13-16).

2. Low instrument air header pressure (PI-380 on VB-4).

AUTOMATIC ACTIONS

{

1. Air compressor standby start.

2. Probable reactor /turoine trip on Hi or low steam generator levels as MSIV's, cond/bstr pps, FW pps recire. valves and FW isolation valves begin to move to the failed air position.

3. Possible random air-operated valve movement.

OBJECTIVES

1. Restore proper instrument air header pressure.

2. In the event that normal system pressure cannot be maintained:

a. Prepare for a reactor trip and minimize the severity of tne loss of air.

b. Maintain the plant in a safe condition.

IMvEDIATE OPERATOR ACTIONS ACTIONS COMMENTS i

Verify all available air comoressor control 1. Will allow automatic N switenes are in AUTO. Place all comoressors start of ccmcressors.

in CN if they fail to start in AUTO. 0-3 anc 0 4

I f M BER EP OP-33' O!ABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 ,

DATE 2/11/82 PAGE 2 OF 4 TRIE: LOSS OF INSTRUMENT AIR I

ACTIONS COMMENTS SUBSEOUENT ACTIONS ACTIONS

1. Monitor air header pressure (PI 380 on VB4).

2. If pressure increases, gp to OP-K-1:IV ,

2. OP-K-1:IV, Compressed Air System-Abnormal Operation

3. If air header pressure continues to indicate 3. Operator should be antici-low or is decreasing: pating a cr,mplete loss of instrument air.

a. Initiate turbine runback at 200MWe/ min.

I to approximately a 200MWe load, s

I

b. When turbine load reaches approximately i 200PWe, manually trip the reactor.

c. Perform the Immediate Operator Actions in OP-5 (Reactor Trip Without Safety Injections).

d. Verify a heat sink for the RCS exists.

1) Auxiliary feedwater system is feeding all steam generators.

2) Steam dump valves open (VB3 indication). 2) If the MISV's have failed closed verify 10% steam dumps open on all stm. generators.

Use backup control air bottles if necessary.

e. Trip main feedwater, condensate and booster e. Feedwater iso valves and pumps. Pp recirc vivs are air-to-open/ fail-closed.

f. Verify RCS temperature and pressure are approacning hot standby values.

'g. Evaluate cnarging and letdown flow status.

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' NUMBER EP OP-33 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 DATE 2/11/82 PAGE 3 OF 4 Tale: LOSS OF INSTRUMENT AIR l

ACTIONS COMMENTS l

1) Verify charging flow is maintain- 1) On loss of air, ing pressurizer level above 22%.

a) Recip Chg Pp goes to maximum speed.

b) FCV-128 opens c) Normal charging paths should be available.

2) Verify seal water flow to all oper-ating reactor coolant pumps.

h. Maintain steady state hot standby condition until the instrument air system is restored.

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NUMBER EP OP.-33 DIABLO CANYON POWER PLANT UNIT NO(S). 1 AND 2 REVISION 1 DATE 2/11/82 PAGE 4 OF 4 TITLE: LOSS OF INSTRUMENT AIR APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS

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

a. Notify the Plant Superintendent, Supervisor of Operations and the Plant Manager.

b. Designate this event a significant event. As a minimum, within one hour notify the NRC Bethesda Operations Center using the red phone in the Control Room. Gather sufficient information from all sources prior to calling so that the phone call is meaningful.

Refer to Operating Procedure 0-4 " Operating Or 2r (One Hour Reporting Requirements to NRC)" for a suggested fannat iv. reporting. Notify the NRC that your call is pursuant to 10 CFR Part 50.72, (Notifi-cation of Significant Events).

c. Review subsequent plant conditions against the classification criteria in Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."

i 1

1 l

l

I 9GF43 Pacific Gas and Electric Company NuusER REVISICN EP OP-39 1

m

(~h "

OEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 2/11/82 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Pf.GE 1 OF 3 ll "; EMERGENCY OPERATING PRCCEDURE W REACTOR COOLANT PUMP LOCKED ROTOR ACCIDENT APPROVED: C ^

3- /* b _

PLANT MANAGER (./ DATE SCOPE This procedure provides instructions for the condition where one reactor coolant pump rotor locks and the pump comes to an abrupt stop. A reactor trip results from low loop flow or pump breaker overcurrent trip if above P-7. If below P-7 a hi reactor coolant pressure reactor trip will probably occur.

With the abrupt reduction in flow, the primary system heat removal rate is reduced significantly. Primary system pressure and temperature increase and the pressurizer relief and safety valves operate to terminate the pressure transient.

SYMPTOMS l

1. Reactor Coolant Pump Trip alarm.

2. Loop Low Flow alarm.

3. Pressurizer High Pressure alann.

4. Pressurizer High Pressure Reactor Trip alann.

AUTOMATIC ACTIONS

. Reactor trip.

2. Turbine-Generator trip.

3. Pressurizer relief valves open.

4. Pressurizer safety valves open.

OBJECTIVES

1. Restore normal primary system pressure and temoerature to avoid possible DNBR conditions.

2. Initiate a plant cooldown to a cold shutdown mode.

O

DIABLO CANYON POWER PLANT UNIT NO(S) , 1 AND 2 NUMBER EP OP-39 REVISION 1 DATE 2/11/82 PAGE 2 OF 3 ,

TITLE: REACTOR COOLANT PUMP LOCKED ROTOR ACCIDENT IMMEDIATE OPERATOR ACTIONS ACTIONS COMMENTS

1. Verify the reactor tripped; follow OP-5.

2. Verify the turbine tripped.

SUBSEQUENT OPERATOR ACTIONS ACTIONS

1. Verify steam dump operating.

2. Verify steam generator levels and auxiliary FW pumps operating and delivering flow.

3. Verify pressurizer sprays operating to regain control of pressurizer i pressure.

4 Verify PORV's closed when pressure 4 Close backup valves as required.

drops below 2260 psig.

5. Monitor pressurizer relief tank 5. If the safety valves lifted and pressure, temperature and level. one sticks open, the pressurizer pressure and pressurizer relief tank parameters should indicate this. If safety injection occurs, go to OP-0.

6. Monitor steam generator levels. 6. Additional indicators are Hi air If any level increases rapidly ejection, off gas activity, and with decreasino RCS pressure, a the radiation level in the steam I steam generator tube may have generator blowdown.

I ruptured due to hi primary system pressure. In this case, j an automatic or manual SI must be imposed at a primary system l pressure of 1850 psig.

7. Using Operating Procedure L-5 l proceed to take the plant to cold shutdown to repair the RCP.

l

DIABLO CANYCN POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP OP-39 DATE 2/11/82

\j[ PAGE 3 OF 3 TITLE: REACTOR COOLANT PUMP LOCXED ROTOR ACCIDENT APPENDIX Z -

EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS l

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

a. If a pressurizer pressure, overtemperature aT or overpower aT protection system channel is tripped or reactor power exceeds the safety limit in Technical Specification figure 2.1-1, designate this event a Notification of Unusual Event. Notify plant staff and response organizations requirec for this classification by imple-

. menting Emergency Procedures G-2 " Establishment of the On-Site l

Emergency Organization" and G-3 " Notification of Off-Site Organi-zations" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."

b. If, subsequent to the pump trip, a reacter coolant sample indicates i

activity in excess of Technical Spec _ificat Mn 3.4.3 limits (Figure 3.4-1 equivalent of I-131 or > 100/E uci/cc specific activity) designate this event as an Alert. Notify plant staff and response organizations required by EP G-2 and G-3 in accordance with EP G-1.

c. If none of the above occur, refer to the reporting requirement of Emergency Operating Procedure OP-9 " Loss of a Reactor Coolant Pump." Review subsequent plant conditions against the classifi-cation criteria in Emergency Procedure G-1 " Accident Classifica-tion and Emergency Plan Activation."

d

e 9GF43 Pacific Gas and Electric Company NUMBER REVISION EP OP-44 2

DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 2/11/82 CIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 OF 8 EMERGENCY OPERATING PROCEDURE TITLE g GASEOUS VOIDS IN THE RCS APPROVED: I h1 b PLANT MANAGER d DATE SCOPE The objective of these instructions is to specify required operator actions and precautions necessary to remove gases from the reactor vessel head by increasing RCS pressure or by operation of the Reactor Vessel Head Vent.

Gases in the reactor coolant system may result from several types of plant events. An accumulator tank discharge or a core uncovery may result in non-condensible gases (e.g. nitrogen or hydrogen) being trapped in the RCS.

A rapid RCS cooldown may result in the vessel head temperature being greater than the primary saturation temperature and result in a steam bubble being developed. The operator should suspect the presence of gases in the RCS if any of the above events occur.

( SYMPTOMS

1. Reac^w r vessel level is less than 100% on:

a. The Reactor Vessel Level (narrow range) indication with no RCP's running (natural circulation).

b. The Flow Head (wide range) indication with all the RCP's running.

c. Plenum Level indication with no RCP's running .(natural circulation).

2. Abnormal reactor coolant system conditions have occurred such as a large unexpected variation in pressurizer level during normal charging or spraying operations. -

3. Reactor vessel head temperatures equal to or greater than saturation temperature.

4. Plant events have occurred (such as accumulator tank discharge, rapid RCS cooldown, or core uncovery events) that may result in the presence of a gaseous void in the vessel head.

AUTOMATIC ACTIONS None O

G

NUMBER EP OP-44 DIABLO CANYON POWER PLANT UNIT NO(S). 1 A'ND 2 REVISION 2 OATE 2/11/82 PAGE 2 OF 8 Tm.E: GASEOUS VOIDS IN THE RCS OBJECTIVES

1. To remove any condensible gases from the RCS'by increasing RCS pressure.

2. To vent any noncondensible gases by use of the Reactor Vessel Head Vent System.

PREREOUISITES AND CAUTIONS

1. Do not trip any running or start any non-oprating reactor coolant Tripping an operating pumps during the performance of this procedure.

reactor coolant pump could result in gases in the reactor coolant loops collecting in the steam generator U-tubes and may disturb natural circulation and primary to secondary heat transfer. Starting reactor coolant pumps would disperse any gases already collected in the vessel head and make tt sir removal more difficult.

1

2. Place the containment Hydrogen Monitor System in service and perform Appendix A of this procedure prior to the venting operation.

3. The pressurizer level and pressure requirements throughout the prt,eedure I do not include error allocations due to an adverse containment environ-ment. Therefore, it is assumed that containment temperature is near nonnal operating conditions.

4. This venting procedure should not be used asThethe crimary meansistonot vent flowpath mitigate an Inadequate Core CooTTng event.

sized to provide this capability and should only be used in conjunction with the ICC procedures.

5. During a POST-LOCA cooldown and depressurization operation, if throttling safety injection flow is required, perfonn the venting operation prior to the throttling of the flow.

IMMEDIATE OPERATOR ACTIONS None SUBSEOUENT OPERATOR ACTIONS COMMENTS ACTIONS _

Tenninate any changes to the 1. Stability will help in deter-

1. mining the size and position of reactor coolant system that may the void.

be in progress and bring the RCS to as close to a steady-state condition as possible.

Do not trip any running or start any idle RCP curing

nis procecure.

NUMBER EP OP-44

/ OIABLO CANYON POWER PLANT U' NIT NO(S) 1 AND 2 REVISION 2 DATE 2/11/82 Tm.E: GASEOUS VOIDS IN THE RCS SUBSEQUENT OPERATOR ACTIONS (con't)

ACTIONS -

COMMENTS

2. If the SIS in in operation, dis- 2. This step may be slow acting and regard this step and go to step 3. if an upward trend is evident on If SIS in not in operation, attempt the vessel level indicator con-to recombine any condensible gases tinue until the head is refilled by increasing RCS pressure through or the upward trend stops.

the use of the pressurizer backup heaters and increased charging flow.

If this step is successful in con-densing the gas volume in the vessel head, then return to the ap-propriate operating procedure.

CAUTION: Increased charging flow with condensible gases in the RCS may result in a decreasing pressurizer level, due to steam bubble collapse. If pressurizer I' level decreases to less than 20%

of span, then attempt to restore level by continuing the charging flow or manually starting safety injection pumps. If level cannot be restored, then manually initi-ate safety injection and proceed to EP OP-0, Innediate Actions and -

Diagnostics.

3. In preparation for venting, iso- 3. Starting CFCU's will prevent late the containment purge and forming H2 gas pockets and help exhaust system and the pressure ensure a representative H2 conc.

vacuum relief line and start all reading.

available containment fan coolers.

4. Increase the RCS sub-cooling to 4. . Increasing RCS pressure is the 85'F by either initiating an RCS preferred methoo.

pressurization or by dumping steam from the non-faulted steam generators.

5. Complete Appendix A to determine 5. This will limit containment H2 the maximum allowable time period conc. to <3 volume ".

for venting.

i

- NUMBER EP OP-44 OtABLO CANYON POWER PLANT UNIT NO(S)' 1 AND 2 REVISION 2 DATE 2/11/82 PAGE 4 OF 8 M LE: GASEOUS V0 IDS IN THE RCS SUBSEQUENT OPERATOR ACTIONS (con't)

~

ACTION

6. If the SIS is in operation, go to step 9. If the SIS is not in opera-tion, isolate letdown and initiate an RCS makeup by the chemical volume and control system to increase pres-surizer level to greater than 50% of span.

If not already performed, manually 7. The venting operation may re-

7. sult in pressure decreasing block the low pressure SI initiation below the SI setpoint. Action if the parmissive is energized. should be taken to manually block the automatic SI signal when the permissive is energized

8. Start an additional charging

8. Increase charging flow to maximum pump if necessary.

to limit the pressurizer pressure and level decrease during the venting period.

9. Observe the pressurizer level trend during the venting (step 10) and, from the following conditions, det' ermine the probable status of the reactor coolant system.

a. Voids are expanding

a. Increasing pressurizer level-rapidly due to depres-Gaseous voids exist in the RCS surization.

other than the reactor vessel head or pressurizer.

f Constant pressurizer level- b. Steam / water flow rate out

b. the vent = makeup flow No significant gaseous voids rate.

exist in the reactor coolant system.

c. Flow rate of the gases

c. Decreasing pressurizer level- is far greater than the Gaseous void exists in the makeup flow.

reactor vessel head,

10. Open the vent isolation valves in one head vent flow path. If one or both valves fail to open, close both valves and open the isolation valves in the carallel flow path.

< " UMBER EP OP-44 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 g DATE 2/11/82

"~

PAGE 5 OF 8 TITLE: GASEOUS V0 IDS IN THE RCS. .

SUBSEQUENT OPERATOR ACTIONS (con't)

ACTION COMMENT

11. Close both vent isolation .alves 11. If during the venting period, when: a loss of reactor coolant pump operation occurs, continue the

a. Reactor vessel level indi- venting and allow natural cir-cation stabilizes, culation to establish itself.

or b. The time period determined in Step 5 is met, or c. Pressurizer pressure de-creases by 200 psi, or d. Pressurizer level decreases below 20 percent of span, or e. Reactor coolant sub-cooling decreases below 35'F, I

or f. The reactor vessel head is refilled as indicated by a decrease in the rate of a depressurization or a change in the rate of the pressurizer level trend.

12. If the SIS is in operation, go to Step 14.

If the SIS is not in operation, re-estab-lish normal charging and letdown to main-tain the pressurizer water level in the operating range.

13. Evaluate the response of the pressurizer 13. If multiple venting operations level trend to detennine if a gas bubble are required and the contain-existed, and if the venting was terminated ment hydrogen concentration is prior to the vessel head being completely equal to or greater than 3 vol.

refilled, then return to Step 4. percent, then provisions must be made to remove or reduce the volume of hydrogen from the containment prior to re-opening the reactor vessel head vent.

14. Return to the appropriate operating instruction following the successful O

\

completion of the venting of the reactor vessel head.

NWBER EP OP-44 DIABLO CANYON POWER PLANT UNIT NO(S). 1 AND 2 DATE 2 PAGE 6 OF 8 TITLE: GASEOUS VOIDS IN THE RCS APPENulX A DETERMINATION OF VENTING TIME PERIOD

1. Convert the containment free-volume to containment volume at standard temperature and pressure conditions:

a. Average Containment Temp. = 'F + 460 = 'R

b. Containment Volume 0 STP:

NOTE: For conservatism, the pressure factor for the conversion will be equal to one.

6 3 Temp.,*R) I Cont. Vol (STP) = (2.63 X 10 Ft ) X (Avg. Co

= Ft3 Date/ Initials

2. Determine the containment hydrogen concentration in volume percent units.

Place the Containment Hydrogen Monitor in service and open the sample line valves.

NOT(: The containment hydrogen conc 9ntration will be insignificant if there has been no leakage from the PCS to the containment.

= %

a) H2 Conc. Recorder No.

= %

b) H2 Conc. Recorder No.

l l Date/ Initials

3. Calculate the maximum hydrogen volume that can be vented to the containment which will result in a containment hydrogen concentration of less than or l equal to 3 volume percent. For conservatism, use the highest value recorded in Step 2.

Maximum H2 Volume = (3.0% - CONT. Ho CONC.%) X (Cont. Volume [STP])

to be Vented 100%

l = Ft3 Date/ Initials A. From Figure #1 (W.R. RCS Pressure vs. H2 Flow Rate) determine the H2 flow rate, then calculate the venting period which will limit the containment hydrogen concentration to 3 volume percent.

Venting Period = Max. H2 Vented (From Step 3)

H2 r now Rate

= Mins. Date/ Initials

.i ,

NdMBER EP OP-44 DIABLO CANYON POWER Pt. ANT UNIT NO(S) IkND2 REVISION DATE 2/11/82 PAGE 7 OF 8 Tm.E: GASEuuS VOIDS IN THE RCS -

FIGURE ONE: RCS PRESS vs. H2 FLO'i RATE

. ._._ . _ . . _... ......5....

1

. . _ .. .. ... .. ._ .. _.... ....i..

. .. . _. .....i . . . ... ...

. . .. _... .i . . . . -. ... ..

.C.

....t..._.........._... ._ . . .__.... . _. _. _.. .... ._ .-.. .

_ . ...-._ _ . _ _ _... _ . _.-.._. . ... 2._.. _ .. . ... ._ ._....

.. .._...r.__...

. _. _ ...= i._....._... .._.. . . ..... . ......._...

. .. _..._ .. . ...-............_....t.._...

2CC0 . _ - . _ . , _ . _ _ . _ .._ .... _

..s _ ..

.... .._._....._.._..r... . . . _ . _. .. ..... ........ ... .. ._. ....__ .

f

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

q

_ s_ _ _ _ . _

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_ _. _. _ . . . _ _ ._ _ _ _ _____.s_ i

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Pres- e._.

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. _ _ _... ._ _.__ _..__. _ _ . _ . - . _ _ .__ .1. _ _.. ..- .-. ._._.-........ .

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1

, . . t......

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1000 20C0 2000 4CCO 50C0 HYeRC . r G,,I ch. .~.i: . ~. ( e.Cc- u) ..

NUMBER EP OP-44 OtABLO CANYON POWER PLANT UNIT NO(S) . 1 AfiD 2 REVISION 2 DATE 2/11/82 PAGE 8 OF 8 TITLE: GASEOUS VOIDS IN THE RCS APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS 1 When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:

a. Designate this event a Notification of Unusual Event if no other emergency condition exists. Notify plant staff and response organi-zations required for this classification by implementing Emergency Procedures G-2 " Establishment of the On-Site Emergency Organization" and Emergency Procedure G-3 " Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classifica-tion and Emergency Plan Activation."

b. If a severe loss of fuel clad integrity is evident, by increased reactor coolant activity (> 300 uci/cc equivalent of I-131 or greater than 1% fuel failures within 30 minutes or 5 total fuel failures as indicated by a sample), designate this event a Site -

Area Emercency. Notify plant staff and response organizations required for this classification by implementing EP G-2 and EP G-3 in accordance with EP G-1.

c. If inadequate core cooling is verified per procedure 0P-0, or con-tainment hydrogen level increases when venting the reactor vessel head, designate this event a General Emeroency. Notify plant staff and response organizations required for tnis classification by implementing EP G-2 and EP G-3 in accordance with EP G-1.

l l

F G 5fd 3 Pacific Gas and Electric Company NUMBER REVISION EP'G-1

,, 2

(, DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 1/i8/82 y

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 OF50 EMERGENCY PROCEDURE TITLE. ACCIDENT CLASSIFICATION AND EMERGENCY W PLAN ACTIVATION E-APPROVED:

PLANT MANAGER DATE SCOPE This procedure describes the guidelines for Accident Classification and responsibilities for Activation of the Emergency Plan. Implementation of this procedure constitutes declaration of an emergency condition.

GENERAL This General Emergency Procedure provides guidance on activating the I emergency plan and classifying an accident. The steps required by this procedure are in addition to the steps required to maintain or restore the plant to a safe condition.

Prompt notification of offsite authorities should be given within about 15 minutes for the Unusual Event class and sooner (consistent with the need for other emergency actions) for other classes. The time is measured from the time which the Shift Foreman recognizes that events have occurred which make declaration of an emergency class appropriate.

This procedure is organized as follows:

ACTIVATION OF EMERGENCY PLAN The initial steps to be taken for each of the established accident classifications are listed below under:

1. Notification of an Unusual Event

2. Alert

3. Site Area Emergency

4. General Emergency Figure 1 may be used for guidance in assignment of shift personnel to activate the Emergency Organization and implement the Emergency Plan.

l b\

l G l

DC00A3 1 l

l

l' OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION 2 DATE 1/28/82 PAGE 2 OF 50 TITm ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION ACCIDENT CLASSIFICATION Table 1 provides guidance and criteria for determining if an event meets the emergency action levels requiring declaration of one of the four accident classifications. Normally the classification guidance contained in the appropriate OP, R, or M series emergency procedures will be used to determine the initial classification. In the event none of the OP, R or M series procedures is appropriate to the imediate situation, Table 1 and judgement should be used for the initial classification (and future events as necessary).

NOTE: If multiple emergency situations are occurring simultaneously such that the probability of a release of radioactive materials is increased over what it would be for the single occurrence, classify the emergency one level higher than it would otherwise have Deen, based on the most severe single occurrence.

Table 2 summarizes the emergency classification guidance in the OP, R, and M series procedures.

In addition, procedures included in the emergency procedures which meet the NRC reporting requirements for "Significant events" (10 CFR 50.72) but do not meet the criteria for implementing the emergency plan are included in Table 3 for reference. Refer to Operating Procedure, 0-4, " Operating Order l (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Reporting Requirements to the NRC)" for appropriate reporting for these events.

i PROCEDURE 1

1. NOTIFICATION OF UNUSUAL EVENT

a. Description l Unusual events, generally characterize off-normal plant conditions that are in process or have occurred which indicate a potential degradation of the level of safety of the plant if proper action is not taken or if circumstances beyond the control of the operating staff render the situation more serious from a

, safety standpoint. No releases of radioactive material requiring I

offsite response or monitoring are expected for this classification unless further degradation of the level of safety of the plant occurs.

l l DC00A3 2

OfABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION 2 DATE 1/28/82 I^l PAGE 3 OF 50 N TITm ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION

b. Objectives

1) Evaluate the situation and determine if corrective actions are required to place the plant in a stable, safe condition.

2) Organize the on-shift staff to take actions to maintain, or return to safe plant conditions.

3) Notify offsite emergency support groups, regulatory es mies and off-shift plant personnel of the situation to a .:

that the first step in any response has been carried out.

c. Actions

1) Assign on-shift personnel to perform the functions required for implementation of the Emergency Plan.

Assignments may vary at tne discretion of the interim Site Emergency Coordinator, however, a typical organization and assignments are given in Figure 1.

Duties and responsibilities are listed in EP G-2,

" Establishment of the Onsite Emergency Organization."

a) If organizational requirements are given in the appropriate OP, R, or M Procedure, they should be followed, b) The minimum functions which must be assigned are:

(1) Operational control of the plant by on-shift personnel (Emergency Operations Coordinator).

(2) Notification of offsite organizations and off-shift staff (Emergency Liaison Coordinator).

2) Notify off-shift plant staff of the emergency situation per l EP G-2 " Establishment of the Onsite Emergency Organization."

3) Promptly notify and inform the on-call recovery Manager of the nature of the Unusual Event situation per EP G-3,

" Notification of Offsite Organizations."

DCCCA3 3 t

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

REVISION 2 DATE 1/28/82 PAGE 4 OF 50 Tne ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION

4) Promptly actify county and state agencies and the NRC of the emergency situation, its classification and their anticipated response per EP G-3 " Notification of Offsite Organizations."

5) Escalate to a more severe class, if appropriate.

OR

6) Close out with a verbal sumary of corrective actions or temination of the event to offsite authorities.

7) Retain all notification records and other documentation of the event for use in preparation of a written sumary of the event within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of closecut.

2. ALERT

a. Description Events are in progress, or have occurred, which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

It is the lowest level of classification where emergency near-site or offsite response may be anticipated. For most Alert events, the plant would be brought to a safe condition, and radioactive releases, if any, would be minimal.

b. Objectives

1) Evaluate the situation and determine corrective actions required to place the plant in a stable, safe condition and minimize the potential for release of radioactive material.

2) Organize the on-shift staff to take actions to maintain, or return to safe plant conditions.

3) Notify and infom offsite emergency support groups, regulatory agenc'ies and off-shift plant personnel of the situation so appropriate emergency response may be initiated as needed.

OCCCA3 4

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

REVISION 2

/7 DATE 1/28/82 Op 50 h TITte ACCIDENT CLASSIFICATION AND PAGE 5 EMERGENCY PLAN ACTIVATION

4) Assess the potential for, or extent of, release of radioactive material to determine what protective action recommendatims, if any, should te given to offsite authorities and what protective actions, if any, should be implemented for onsite personnel.

c. Actions

1) Assign on-shift personnel to perform the functions required for implementation of the Emergency Plan. Assignments may vary at tha discretion of the interim Site Emergency Coordinator, however, a typical organization and assignments are given in Figure 1. Duties and responsibilities are listed in EP G-2, " Establishment of the Onsite Emergency Organization.'

a) If organizational requirements are given in the appropriate OP, M, or R procedure, they should be followed.

' b) The minimum functions which must be assigned are:

(1) Operational control of the plant (Emergency Operations Cocrdinator).

(2) Notification of offsite organizations and off-shift staff (Emergency Liaison Coordinator).

(3) Evaluation of plant conditions and radiological assessment (Emergency Evaluations and Recovery Coordinator).

2) Sound the site emergency signal, if appropriate, to initiate site as:embly and accountability per EP G-4, " Personnel Assembly and Accountability."

3) Notify off-shift plant staff of the emergency situation and their assignments in the long-tem emergency organization to activate the Technical Support Center (TSC), Emergency Operations Facility (E0F) and Operational Support Center (OSC) per EP G-2, " Establishment of the Onsite Emergency Organization."

i v

DCCOA3 5

1 AND 2 NUMBER EP G-1 otABLO CANYON POWER PLANT UNIT NO(S) 2 REVISION DATE 1/28/82 PAGE 6 OF 50 TrTLE.'

ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION

4) Promptly notify and inform the county of the alert status and their anticipated response per EP G-3, " Notification of Offsite Organizations." -

5) Promptly notify the Recovery Manager of the Nature of the alert status per EP G-3, " Notification of Offsite Organizations."

6) Promptly notify the state and NRC of the nature of the alert status per EP G-3, " Notification of Offsite Organizations."

7) Dispatch the Liaison Assistant to activate the Technical Support Center (TSC) telephone console to receive incoming phone calls, if required.

8) Initiate onsite monitoring and associated comunications per EP RB-7, " Emergency Onsite Radiological Monitoring Program,"

if a release is occurring or anticipated.

9) Order evacuation of nonessential site personnel per EP G-5,

" Evacuation of Nonessential Site Personnel" if appropriate.

10) Provide periodic (approximately every 15 minutes) plant status updates, meteorological assessments, and dose estimates to offsite authorities. Use Form 18-10262

" Radiological Emergency Status Form" per EP G-3,

" Notification of Offsite Organizations."

11) Escalate to a more severe class, if appropriate.

OR

12) Closecut or recomend reduction in emergency class by verbal comunication of temination of the event to offsite authorities.

13) Retain all notification records and other documentation of the event for use in preparation of a written sumary of the event within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of closecut.

O DCCOA3 6

DIABLO CANYON POWER PtWJT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION 2

(-s T DATE 1/28/82 NJ -.

7i7g.' CCIDENT CLASSIFICATION AND PAGE 7 OF 50 EM1RGENCY PLAN ACTIVATION

3. SITE AREA EMERGENCY

a. Description Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. The Site Area Emergency classification reflects conditions where there is a clear potential for significant releases of radioactive material, such releases are likely, or they are occurring, but in all cases a core meltdown situation is not indicated based on current information. Any releases are not expected to exceed EPA protective Action Guideline Exposure levels except near the site boundary.

, b. Objectives

1) Evaluate the situation and determine corrective actions required to place the plant in a stable, safe condition and minimize the potential for, or actual release of, radioactive material.

2) Augment on-shift staff to take actions to maintain, or return to safe plant conditions.

3) Assure that on and offsite emergency response centers are manned.

4). Provide consultation with appropriate local and state authorities and the NRC so that appropriate emergency response may be initiated, including protective actions for the general public.

5) Implement protective actions on-site required for personnel safety and to minimize radiation exposure.

6) Provide status updates for the public through offsite response personnel authorities.

c. Actions

1) Assign on-shift personnel to perform the functions required for implementation of the Emergency Plan. Assignments may vary at the discretion of the interim Site Emergency Coordinator; however, a typical organization and assignments are give in Figure 1. Duties and responsibilities are listed in EP G-2, " Establishment of the Onsite Emergency O Organization."

DC00A3 7

)

l u

1 ENO 2 NUMBER EP G-1 1 DIABLO CANYON POWER PLANT UNIT NO(S)

REVISION 2 !

l DATE 1/28/82 l

!7g ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION a) If organizational requirements are given in the appropriate OP, M, or R procedure, they should be followed.

b) The minimum functions which must be assigned are:

l 9 (1) Operational control of the plcnt (Emergency Operations Coordinator).

(2) Notification of offsite organizations and off-shift staff (Emergency Liaison Coordinator).

(3) Evaluation of plant conditions and radiological assessment (Emergency Evaluations and Recovery Coordinator).

(

2) Sound the Site Emergency Signal to initiate site assembly and accountability per EP G-4 "Personnal Assembly and Accountability."

3) Notify off-shift plant staff of the emergency situation and their assignments in the long-tem emergency organization g

per EP G-2, " Establishment of the Onsite Emergency

. Organization."

4) Promptly inform the county authorities of the emergency situation, its classification and their anticipated response per EP G-3 " Notification of Offsite Organizations." Include a reconinendation as to whether protective actions for the general public are reconinended at this time.

5) Promptly infonn the Recovery Manager to insure activation of the Corporate emergency organization per EP G-3,

" Notification of Offsite Organizations."

6) Promptly infonn the state and NRC of the nature of the Site Area Emergency and maintain communication per EP G-3, l " Notification of Offsite Organizations."

7) Activate the Technical Support Center (TSC) Switchboard to receive incoming phone calls.

8) Determine the need for evacuating non-essential on-site personnel per CP G-5 " Evacuation of Non-essential Site Personnel."

DCCOA3 3 i !

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 .

REVISION 2 DATE 1/28/82

!m PAGE 3 OF 50 D) Tu ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION

9) Initiate on-site and off-site monitoring per EP RB-7,

" Emergency On-site Radiological Monitoring Program," and EP RB-8, " Emergency Off-site Radiological Monitoring Program."

10) Provide periodic release and dose projections based on available plant conditions and meteorological information and foreseeable contingencies to NRC, local and state authorities. Use Form 18-10262 " Radiological Emergency Status Form" per EP G-3, " Notification of Offsite Authorities."

11) Escalate to general emercency class, if appropriate.

OR

12) Closecut or recomend reduction in emergency class by verbal comunication to offsite authorities at EOF or by pnone.

13) Retain all notification records and other documentation of the event for use in preparation of a written sumary of the event within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of closecut.

4 GENERAL EMERGENCY

a. Description The General Emergency action level reflects accident situations involving actual or iminent substantial core degradation or melting with the potential for loss of containment integrity.

Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the imediate site area.

b. Objectives

1) Evaluate the situation and detemine corrective actions required to restore the plant to a stable, safe condition and minimize the potential or actual release of radioactive material.

2) Augment the on-shift staff to take actions to restore safe plant conditions.

3) Assure that on and off-site emergency response centers are manned.

[

n U

CC00A3 9

l l

OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION 2 DATE 1/28/82 PAGE 10 OF 50 7,7g'. ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION

4) Recommend evacuation of the low population zone and provide consultation with appropriate local, state and federal authorities so that additional appropriate emergency response may be initiated.

5) Evacuate nonessential site personnel per EP G-5, " Evacuation of Nonessential Site Personnel," and implement other protective actions required on-site for personnel safety and to minimize radiation exposure.

6) Provide status updates for the public through offsite response personnel.

c. Actions

1) Assign on-shift personnel to perform the functions regiired for implementation of the Emergency Plan. Assignments may vary at the discretion of the interim Site Emergency Coordinator; however, a typical organization and assignments are given in Figure 1. Duties and responsibilities are listed in EP G-2, " Establishment of the Onsite Emergency Organization."

a) If organizational requirements are given in the appropriate OP, M, or R procedure, they should be followed.

b) The minimum functions which must be assigned are:

(1) Operational control of the plant ( Emergency Operations Coordinator).

(2) Notification of offsite organizations and off-shift staff (Emergency Liaison Coordinator).

(3) Evaluation of plant conditions and radiological assessment (Emergency Evaluations and Recovery Coordinator).

(4) Evacuation of nonessential site personnel (Site Evacuation Coordinator).

(5) Recomendation of protective actions for the general public to appropriate local and state authorities (Site Emergency Coordinator).

O DC00A3 10

OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION 2 DATE 1/28/82 PAGE 11 OF 50 Cs)

m. m ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION

2) Sound the site emergency signal to initiate site assembly and accountability per EP G-4, " Personnel Assembly and Accountability." -

3) Notify off-shift plant staff of the emergency situation and their assignments in the long-term emergency organization per EP G-2, " Activation and Notification of Onsite Emerger:y Organization."

4) Promptly notify and inform the county authorities of the emergency situation, its classification and their anticipated response per EP G-3, " Notification of Off-Site Organizations." Recomend evacuation out to the LPZ and alerting of the general oublic in tne basic emergency p_lanning zone to County Autnorities.

5) . ptly inform the Recovery Manager to insure activation of the Corporate emergency organization per EP G-3,

" Notification of Offsite Organizations."

l 6) Promptly inform the State and NRC of the nature of the General Emergency and maintain comunication per EP G-3,

" Notification of Offsite Organizations."

7) Order evacuation of nonessential site oersonnel per EP G-5,

" Evacuation of Nonessential Site Personnel."

8) Activate the Technical Support Center (TSC) Switchboard to receive incoming phones calls.

9) Dispatch onsite and offsite monitoring teams, per EP RB-7 and EP RB-8.

10) Provide release and dose projec*. ions based on available plant condition and meteorological information and foreseeable contingencies to tre NRC, local and state authorities. Use Fom 18-10262 " Radiological Emergency Status Form" per EP G-3, " Notification of Offsite Authorities."

11) Closecut or recomend reduction of emergency class by briefing of offsite authorities at EOF or by phone.

12) Retain all notification records and other documentation of the event for use in preparation of a written sumary of the p event within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of closecut.

V DCCOA3 11

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

REVISION 2 DATE 1/28/82 Tn1E: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION TABLES

" Emergency Action Levels" 1.

2. " Emergency Operating Procedures - Accident Classifications"

3. " Emergency Operating Procedures - Significant Events"

4. Technical Specifications Applicable to Unusual Event Condition No. 9.

l FIGURES

1. " Typical On-Shift Emergency Organization and Assignments" SUPPORTING PROCEDURES EP G-2

" Establishment of the Onsite. Emergency Organizati n" EP G-3 " Notification of Offsite Organizations" EP G-4 " Personnel Assembly and Accountability" EP G-5 " Evacuation of Nonessential Site Personnel"

(

1 DC00A3 12

1 AND 2 NUMBER EP G-1 .

OtABLO CANYCN POWER Pt. ANT UNIT NO(S)

REVISION 2 DATE 1/28/82

(T (s,) PAGE 13 CF50 T m E. ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION TABLE 1 EMERGENCY ACTION LEVELS NOTIFICATION OF UNUSUAL EVENT NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

1. Emergency Core Cooling 2, stem 1. a. Safety Injection (ECCS) initiated and discharge Initiate, Safety Injec-to vessel. tion Activation and Safeguard Channel g

Activated Alarms.

b. ECCS flow indicated.

2. Radiological effluent tecnnical 2. In accordance with Technical specification limits exceeded. Specifications Sections 3.11.1.1 and 3.11.2.1.

a. Radiological Effluent Process Monitor High Radiation Alarm with a valid reading in excess of the technical specification alarm setpoint on any of monitors RE 14A or B, RE 28A or B, RE 24, RE 27, RE 18, RE 23, RE 3, or RE 16.

b. Unplanned or uncontrolled release exceeding alarm setpoint.

3. Fuel damage indication. 3. Gross Failed Fuel Monitor (hot leg sample line monitor) channel alarms with:

).)

DC00A3 13

NUM.'FR EP G-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 2 OATE 1/20/82 PAGE 14 OF 50 TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION NOTIFICATION OF UNUSUAL EVENT (cont.)

l NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

a. Sample of'RCS confirms dose equivalent I-131 activity greater than Technical Specification limits for an iodine spike (Technical Specification Figure 3.4-1),or

b. Sample of RCS confirms specific activity greater than 100/E uCi/gm in accordance with Technical specification 3.4.8.

4. Abnormal coolant temperature 4. a. High T or pzr low l press $T$rm,,or and/or pressure or abnormal

! fuel temperatures outside of technical specification limits. b. Over temperature delta T or overpower delta T channel activated, or l

c. Reactor Power exceeds safety limits shown in l

Technical Specification Figure 2.1-1.

5. Exceeding either primary / 5. Indication of Reactor Coolant

' secondary leak rate technical PRESSURE BOUNDARY LEAKAGE, or specification or primary systam leak rate technical specification. a. 1 GPM UNIDENTIFIED LEAKAGE, or l

l O

DC00A3 la l

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

REVISION 2 DATE 1/28/82 Tnv~.~

ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION NOTIFICATION OF UNUSUAL EVENT (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

b. 1 GFM total prima ry-to-secondary leakage through all steam generators and 500

- gallons per day through any one steam generator, or

c. 10 GPM IDENTIFIED LEAKAGE f

from the Reactor Coolant System, or

d. 40 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2230:20 psig, or

e. 1 GPM leakage at a Reactor. Coolant System pressure of 2235:20 psig from any Reactor Coolant System pressure isolation valve specified in Technical Specification Table 3.4-1,

6. Failure of a safety or relief 6. a. Abnormal system pressure, valve in a safety-related system flow or temperature on to close following reduction of affected safety-related app"Icable pressure, system and relief valve verified to be failed open, or DC00A3 15

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

REVISION 2 DATE 1/28/82 PAGE 16 OF 50 TITLE.

ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION NOTIFICATION OF UNUSUAL EVENT (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

b. Pressurizer PORV indicates open, or pzr safety or PORV line high temperature alarm, or sonic detector indicates flow following valve activation.

7. Loss of offsite power or loss of 7. a. Vital 4 KV Bus Auxiliary onsite AC power capability, or Startup Breaker alarm, and auto transfer to startup power or auto start of applicable diesel generator, or l b. Power sources not l operable in accordance with Technical l

Specification 3.8.1.1.

8. Loss of containment integrity 8. a. Inability to close any requiring shutdown by techr.ical penetration required to specifications. be closed in an accident condition by v,alves, blind flange, deactivated automatic valves or operable containment automatic isolation valve, or 1

b. Air lock leakage exceeds Technical Specification 3.6.1.3.b.

i l

l 1 DCCOA3 15 i

e

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND'2 NUMBER EP G-1 REVISION 2 DATE 1/28/82

^

TITLE ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION NOTIFICATION OF UNUSUAL EVENT (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON P0TENTIAL CONDITIONS INDICATED CONDITIONS

9. Loss of engineered safety 9. The malfunction or disabled feature requiring shutdown by equipment results in a plant technical specifications (e.g., condition not meeting a due to malfunction, personnel Technical Specification error, or procedural limiting conditior, for opera-l inadequacy). tion listed in Table 4 and the activ.. required by the Technical Specification requires plant shutdown.

10. Fire within the plant las. ting 10. Fire alarm received or fire more than 10 minutes. -

detection instrument alarm received, fire verified by fire brigade personnal and fire not under control within 10 minutes of initiating fire-fighting efforts.

11. Indications or alanns on 11. a. Loss of seismic trip l process or effluent parameters requiring shutdown or l not functional in control room I

to an extent requiring plant b. Loss of remote shutdown shutdown or other significant or accident monitoring loss of assessment or comuni- instrumentation requiring cation capability (e.g., plant plant shutdown as per computer, Safety Parameter Technical Specification l

Display System). 3.3.3.5 or 3.3.3.6 or

c. Total loss of comunication capabilities with San Luis Obispo County, California State OES or NRC.

O V

DC00A3 17

DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 ANO 2 NUMBER EP G-1 REVISION 2 DATE 1/28/82 PAGE 18 OF 50 7gtg. ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION NOTIFICATION OF UNUSUAL EVENT (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

12. Security threat or attempted 12. a. Threat received by Plant entry or attempted sabotage. Personnel or

b. Plant Security Force '

reports attempted forceable entry or i sabotage attempt or

c. Plant personnel detect attempted sabotage.

13. Natural phenomenon being experienced or projected beyond usual levels. .

a. Any earthquake felt a. Seismic monitoring system in-plant or detected on activated (setpoint station seismic instrumentation. 0.01g).

b. 50-year flood or low water, b. 1) Flooding of any tsunami, hurricane surge. plant structure (turbine building auxiliary building, fuel storage building) that

- affects the operation of the plant, or i 2) Intake structure l sump level high

! alarc.1 with circulating water pump alarm or trip, or

(

1 DC00A3 18 i

l

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION 2 DATE 1/28/82 PAGE 19 OF 50 k-<. Tu ACCIDENT CLASSIFICAT:0N AND EMERGENCY PLAN ACTIVATION NOTIFICATION OF UNUSUAL EVENT (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

3) Observed low water level at the intake structure indicative of a tsunami, or

4) 'fqni icant tsunami

t. oc icane warning received from State of California, National Oceanic and

( Atmospheric Administration, NWS, Coast Guard or System Dispatcher, or

5) Observation of waves exceeding the intake structure main deck elevation.

c. Any tornado onsite, c. NWS warning and tornado cloud sighted within site boundary,

d. Any hurricane. d. NWS warning and winds in excess of 75 mph (34 m/sec) at any elevation on the meteorological tower.

14. Other hazards being experienced or projected.

l

a. Aircraft crash onsite or a. Report of crash onsite or I unusual aircraft activity unusual activity over the over facility. plant by plant personnel.

}

OCCCA3 19

1 AND 2 NUMBER EP G-1 DIABLO CANVON POWER PLANT UNIT NO(S)

REVISION 2 !

DATE 1/2 8/82 T Tts; ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION I

l NOTIFICATION OF UNUSUAL EVENT (cont.) l l

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL i CONDITIONS INDICATED CONDITIONS I

b. Near or onsite explosion, b. Report of explosicn by plant personnel.

c. Near or onsite toxic or c. Report of toxic or flanurable gas release, flamable gas release by plant personnel.

l d. Turbine rotating component d. Turbine trip and turbine l failure causing rapid plant supervisory alarm, "High shutdown. Vibration."

l l

DCCOA3 20

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION 2 p) i h ACCIDENT CLASSIFICATION AND DATE PAGE 21 OF 50 1/28/82 Tam EMERGENCY PLAN ACTIVATION NOTIFICATION OF UNUSUAL EVENT (cont.)

NUkEG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

15. Other plant conditions exist 15. a. Plant conditions require that warrant increased awareness entry into a Technical on the part of a plant operating Specification action staff or state and/or local offsite statemer.t requiring ,lant authorities or require plant shutdown shutdown, or under technical specification require-ments or involve other than nonnal b. Equipment failure, controlled shutdown (e.g., cooldown personnel error or rate exceeding technical specification procedural error causes limits, pipe cracking found during plant conditions during operation). shutdown which, in the opinion of the Shift Foreman, indicate a potential degradation in the level of safety of the plant, or

'c . Personnel error or procedural inadequacy which, during normal operations, anticipated operational occurrences, or accident conditions, prevents or could l prevent, by itself the l fulfillment of the safety function of those structures, systems, and components important to safety that are needed to: (1) shutdown the reactor safely and maintain it in a safe O

OC00A3 21 l

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION 2 DATE 1/28/82 PAGE 22 OF 50 Tn'm ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION NOTIFICATION OF UNUSUAL EVENT (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS condition; or (2) remove residual heat following reactor shutdown; or (3) limit the release of radioactive material to acceptable levels or reduce the potential for such a release.

16. Transportation of contaminated 16. Report of injury or over-injured individual from site to exposure involving radio-offsite hospital. acti;e material onsite and recuiting offsite medical assistance or hospitalization.

17. Rapid depressurization of PWR 17. a. High steam flow and low secondary side. steam pressure and/or low Tave' U"

b. Reduced primary pressure, Safety Injection Initiated and Main Steam l Isolation.

l DC00A3 22

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION 2 1/28/82 O) k/

DATE PAGE 23 OF 50

\-

TRLE. ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION ALERT NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

1. Severe loss of fuel cladding:

a. Very high coolant activity a. Reactor Coolant Sample is sample (e.g., 300 uCi/cc greater than or equal to equivalent of I-131). 300 uCi/cc equivalent of I-131.

b. Failed fuel monitor b. Gross failed fuel monitor

, indicates increase greater channel alarms. Sample than 1% fuel failures within of Reactor Coolant 30 minutes or 5% total fuel confirms conditions as failures, stated.

2. Rapid gross failure of one 2. High Radiation Alarm on Air steam generator tube with Ejector Vent, or High loss of offsite power. Radiation on Steam Generator Blowdown, and Increased charging pump flow rate, or volume control tank low level alarm, and

. Offsite power loss is indicated by meters and under

)ltage alarms from 12 KV Bus U&E and 4 KV Bus D&E.

3. Rapid failure of steam generator 3. Reactor Trip and Safety tubes (e.g., several hundred gpm Injection initiates, and primary to secondary leak rate).

High Radiation alarm on Air Ejector Vent or High Radiation Alarm on Steam Generator Blowdown, and O

U CC00A3 23

I.AND 2 NUMBER EP G-I DIABLO CANYON POWER PLANT UNIT NO(S)

REVISION 2 DATE 1/28/82 PAGE 24 OF 50 7gts; . ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION ALERT - (cont. ) -

NUREG-0654, APPENDIX 1 DIABLO CANYON P0TENTIAL CONDITIONS INDICATED CONDITIONS Increasing water level on affected steam generator.

4. Steam line break with signi- 4. Known significant primary to ficant (e.g., greater than. secondary leakage indicated 10 gpm) primary to secondary by high radiation alarms on i leak rate. the air ejector or steam generator blowdown, or by sample, and Steam Line Isolation and Safety Injection initiated on High Steam Line Flow with either Low-Low T or SteamPressureaiXfms. Low

5. Primary coolant leak rate 5. a. One or more of the following greater than 50 gpm. indications or alarms: ,

1) Containment High Activity Alarm;

2) Containment Sump High Level Alann or increased containment sump discharge;

3) Pressurizer Relief Tank has increased temperature / level or pressure;

4) Pressurizer PORV indicates open per safety or PORY Line High Temperature Algrm, or O

DCCOA3 24

1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) NUMBER EP G-1 REVISION 2 DATE 1/28/82 PAGE 25 OF 50 kjf

+

ACCIDENT CLASSIFICATION AND TITLE.

EMERGENCY PLAN ACTIVATION i ALERT - (cont. ) -

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS sonic detector indicates flow;

5) Air Ejector High Activity Alam;

6) Steam Generator Blowdown High Activity Alarm;

7) Volume Control Tank icw'

! level alarm, and One Centrifugal charging pump is unable to maintain pressuri:er level with normal letdown flow.

6. Radiation levels or 6. a. An unplanned or unanticipated airborne contamination rise in radiation levels from wnich indicate a severe a contained source so that degradation in the control one of the following of radioactive materials situations result:

(e.g., increase of a factor of 1,000 in direct 1) Radiation levels above radiation readings within 1 R/hr outside the the facility). boundaries of the controlled areas, or

2) Radiation levels above 1 R/hr in portions of the controlled area which are passageways, are normally occupied or accessible areas and are nomally less than 15 mR/hr, or C

CC30A3 25

OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION 2 DATE 1/28/82 PAGE 26 OF 50 UTLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION ALERT - (cont.) -

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL -

CONDITIONS INDICATED CONDITIONS

3) Radiation level increases of 1 R/hr or more in accessible areas normally between 15 and 100 mR/hr.

b. The level for airborne radioactivity levels within plant structures is set at an unexplained increase of 100 times MPC.

7. Loss of offsite power and 7. 4 KV Bus F,G, and H Undervoltage loss of all onsite AC power Alarm or Auxiliary and Startup (See Site Area Emergency Breaker Alarm, and for extended loss).

Applicable Diesel Generator inoperable alarm, and Vital 4 KV load center voltmeters indicate zero volts.

8. Loss of all onsite DC power 8. DC Bus 11,12, and 13 undervoltage.

(see Site Area Emergency for extended loss).

9. Coolant pump seizure leading 9. One or more of the following to fuel failure. indications or alarms:

a. Reactor Coolant Pump Trip Al a m.

b. Reactor Protection Signal Alarm on Loop Low Flow, DC00A3 26 l

i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER gp g_1 REVISION 2 ,

DATE

( 1/28/82 l PAGE

( 27 OF 50

'. TULE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION i ALERT - (cont.) ~

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

c. Pressurizer High Pressure Alarm, and

d. Subsequent Reactor Coolant system activity is in excess of Unusual Event Condition number 3 levels.

I 10. Complete loss of any function 10. Loss of both residual heat needed for plant cold shutdown. removal trains.

11. Failure of the reactor 11. Plant conditions indicate the protection system to initiate required coincidence for and complete a scram which Reactor Trip has occurred or brings the reactor subcritical. the required coincidence of bistables have tripped, or trip is manually activated, and Nuclear Instrumentation indicates reactor not suberitical (non-negative start-up rate).

F 12. Fuel damage accident with 12. a. High Containment release of radioactivity to Radiogas and/or containment or fuel handling particulate alarms or building. Containment Ventilation Isolation caused by e high containment activity while in the refueling mode or O

\~ > ,

DCCOA3 27

EP G-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 [8S ON AGE OF 28 .

TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION ALERT - (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

b. High Fuel Handling Building Area Radiation Alarm or Fuel Handling Building Ventilation automatic change to the Iodine i Removal Mode, while irradiated p fuel is in the building.

13. Fire potentially affecting 13. Unusual Event Condition No.10, and safety systems. the fire is located in one of the following areas:

1) Containment

2) Control Room

3) Cable Spreading Room

4) Diesel Generator Room

5) Auxiliary Building

6) Intake Structure Pump Room

14. Most or all alarms 14. All or most of the main control panel annunciators and indicators (annunciators) are lost. do not respond.

l l

1 GC00A3 28

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

DATE 1/28/82 PAGE 29 OF50 TITLE: ACCIDEld CLASSIFICATION AND EMERGENCY PLAN ACTIVATION

~

ALERT - (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

15. Radiological effluents 15. Radiological effluent process greater than 10 times monitor alarm (Unusual Event technical specification Condition No. 2) with effluent instantaneous limits (an analysis or evaluation confiming instantaneous rate which, 10x Technical Specification limits if continued over 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months exceeded.

would results in about 1 mR at the site boundary under average meteorological I conditions).

16. Ongoing security ccmpromise. 16. Ongoing security threat involving physical attack on the facility, Security Response Procedure initiated.

17. Severe natural phenomena being experienced or projected:

a. Earthquake greater than a. Earthquake greater than 0.29 OBE levels. verified by Seismic Monitors.

b. Flood, low water, tsunami, b. High water exceeding Intake hurricane surge near Structure main deck elevation design levels. or low water causing temporary shutdown of both ASW pumps.

c. Any tornado striking c. Unusual Event condition No.

facility. 13.c. and tornado cloud strikes the plant.

d. Hurricane winds near d. Sustained wind of 85 mph design basis level. (38 m/sec) at any elevation p) q on the Meteorological Tower.

DCCOA3 29

NUMBER EP G-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 2 UAE 1/29/82 PAGE 30 OF 50 TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION ;

ALERT - (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

18. Other hazards experienced or projected:

a. Aircraft crash on facility. a. Unusual Event condition No. 14.a. and crash occurs involving a plant structu re.

b. Missile impacts from b. Confirmed missile impact whatever source on on a plant structure.

facility.

c. Known explosion damage to c. Unusual Event condition No. 14.b. and the facility affecting plant operation. explosion affects piant operation.

d. Entry into facility environs d. Unusual Event condition of uncontrolled toxic or No. 14.c. and the gas is flar. unable gases. detected within plant structures other than the intake structure.

e. Turbine failure causing e. Confirm report of casing penetration. conditiens as stated.

19. Other plant conditions exist 19. Conditions as stated in the that warrant precautionary judgement of the Shift Foreman activation of Technical Support Center and placing near-site Emergency Operations Facility and other key emergency personnel on standby.

20. Evacuation of control room 20. As stated.

anticipatea or required with control of snutdown systems l

established from local stations.

i l

DCCOA3 30

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

REVISION 2 DATE 1/28/82 (p)s PAGE 31 OF50 TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION SITE AREA EMERGENCY NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

1. Known loss of coolant 1. Alert condition number 5, and accident greater than '

makeup pump capacity. Safety Injection with abnormally high or increasing levels of containment pressure, containment area radiation or containment recirc sump level.

2. Degraded core with possible loss 2. Refer to General Emergency of coolable geometry (indicators Section, Condition 8, to should include instrumentation classify this condition.

to detect inadequate core cooling, coolant activity and/or contain-ment radioactivity levels.

- 3. Rapid failure of steam generator 3. ALERT Condition number 3 and tubes (several hundred gpm Offsite power loss is leakage) with loss of offsite indicated by meters and power. undervoltage alams from 12 KV Bus D and E and 4 KV Bus D and E.

4 Steam line break with greater 4 ALERT Condition number 4 and than 50 gpm primary to secondary ALERT Condition number 1 leakage and indication of fuel concurrently.

damage.

5. Loss of offsite power and loss 5. ALERT Condition number 7 of onsite AC power for more than exists for longer than 15 15 minutes. minutes.

DCCOA3 31

NU BE EP G-1 DIABLO CANYON POWER PLAN 1 UNIT NO(S) 1 AND 2 E g ON DATE 1/28/82 PAGE 32 OF 50 TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION SITE AREA EMERGENCY (cont.)

l NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL l CONDITIONS INDICATED CONDITIONS

6. Loss of all vital onsite DC 6. ALERT Condition number 8 power for more than 15 minutes. exists for longer than 15 minutes.

7. Complete loss of any function 7. a. Complete loss of emer- '

needed for plant hot shutdown. gency.feedwater capa-bility, or

b. Complete loss of Steam Dump System and steam generator safety valves, or I

c. Complete loss of Chemical l and Volume Control System capability to maintain i

the RCS inve.ntory or to l

increase the concentration of the boric acid in the RCS, or

d. Complete loss of Chemical and Volume Control System Capability to increase l the concentration of Boric Acid in the RCS sufficient to maintain a K less than or equal t8 99 in Mode 4 (hot shutdown) with a loss of capability to trip control rods.

DCCOA3 32

DlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER gp g.1 REVISION g DATE

'N 1/28/82

) PAGE 33 OF 50 TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION SITE AREA EMERGENCY (c6nt.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

e. Complete loss of Auxiliary Saltwater System or Component Cooling Water System, or

f. Complete loss of Vital 4160 Volt buses, or

g. Complete loss of 4

Instrumentation or Controls required for any of the systems capabilities in items i 7.a-f. above.

8. Transient requiring operation 8. ALERT Condition number 11 of shutdown systems with and power generation indicated failure to scram (continued on power range channels, and power generation but no core damage immediately evident). No gross fuel failure evident, (absence of Alert Condition No. 1).

9. Major damage to spent fuel in 9. Alert Condition number 12, and containment or fuel handling building (e.g. , large object Confirmed gross fuel damage or damages fuel or water loss loss of water level to below below fuel level). fuel lavel.

10. Fire compromising the functions 10. ALERT Condition number 13, and of safety systems.

Confirmed loss of safety systems functions that causes entry into a Technical Specification action I)

V statement.

DC00A3 33

NUMBER EP G-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 2 DATE 1/d8/82 PAGE 34 OF50 TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION SITE ' AREA EMERGENCY (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL INDICATED CONDITIONS CONDITIONS

11. ALERT Condition number 14

11. Most or all alarms and lasting for more than 15 indicators lost for more than minutes, and 15 minutes and plant transient is initiated or in progress or not in cold shutdown. Plant is not in cold shutdown or plant transient occurs.

12. a. An actual or projected

12. a. Effluent monitors release which is calculated on detect levels EARS, or in accordance with corresponding to EP R-2, to exceed the follow-greater than 50 mR/hr ing criteria at the site for 1/2 hour or greater boundary (800 m.):

than 500 mR/hr k.B. for two minutes (or five 50 mR/hr for 1/2 hr., whole times these levels to body.

the thyroid) at the j

site boundary for 17 mR total dose, whole body.

adverse meteorology.

250 mR/hr for 1/2 hr. , thyroid.

85 mR total dose, thyroid.

or, a peak release rate exceeding two minutes duration which exceeds the following criteria at the site boundary l when calculated in accordance with EP R-2:

500 mR/hr for 2 minutes, whole body.

2500 mR/hr for 2 minutes, thyroid.

DC00A3 34 l

I DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-1 REVISION g DATE 1/28/82 A) PAGE 35 OF 50 (Y TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION SITE AREA EMERGENCY (c6nt.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS "l9ICATED CONDITIONS

b. The dose rates are b. As stated.

projected based on other plant parameters (e.g.,

radiation level in contain:ent with leak rate aor opriate for existing containment pressure) or are measured in the environs.

( c. EPA Protective Guidelines c. As stated.

are projected to be exceeded outside the site boundary.

13. Imminent loss of physical control 13. On-going security threat of the plant. involving physical attack on the facility which may resul t.

. in the loss of physical control of the station.

Security response procedure initiated.

14. Severe natural phenomenon being experienced or projected with the plant not in cold shutdown:

a. Earthquake greater than a. Earthquake greater than SSE levels. 0.6g verified by Seismic Monitors.

b. Flood, low water, tsunami, b. High water causing hurricane surge, greater flooding of ASW pump than design levels or compartments or low water failure of protection of causiag the shutdown of vital equipment at icwer both ASW pumps for more levels. than 15 minutes, d

DC00A3 35

NUMBER EP G-1 DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION g UAE 1/28/82 PAGE 36 OF 50 TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION SITE AREA EMERGENCY (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

c. Sustained winds or tornados c. Meteorological in excess of design levels. Instrumentation indicates susti.ined wind speed gr ater than 100 rep. ( ~ ; m/sec).

15. Other hazards being experienced or projected with plant not in cold shutdown:

a. Aircraft crash affecting a. Alert condition No.18.a vital structures by impact and crash occurs or fire. involving the main olant structures or the intake l structure.

l b. Severe damage to safe b. Alert condition No. 18.b i shutdown equipment from or 18.c and damage to missiles or explosion. plant equipment requires entry into a technical I

specification action i

statement.

c. Entry of uncontrolled c. Alert condition No. 18.d.

flannable gases into vital and the gas is detected areas. Entry of uncon- in the Control Room, hot trolled toxic gases into shutdown panel or other vital areas where lack of area where a plant access to the area manipulation required for constitutes a safety safe shutdown must be problem. performed.

O DCCOA3 36 _

I

DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 NWBER EP G-1 REVISION p DAE O'..

TITLE: ACCIDENT CLASSIFICATION AND PAGE 37 OF 1/28/82 SO EMERGENCY PLAN ACTIVATION SITE AREA EMERGENCY (c6nt.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

16. Other plant conditions exist 16. Condition as stated in the that warrant activation of judgment of the Shift Foreman emergency centers and tronitor-ing teams or a precauti lary notification to the put,. .c near the site.

17. Evacuation of control room and 17. As stated.

! control of shutdown systems not established from local stations in 15 minutes.

C CCCOA3 37

1 AND 2 tauMaER EP G-1 DIABLO CAf4YCP4 POWER Pt/J4T UtilT P40(S) REVIS!Ctd 2 DATE 1/28/82 PAGE 38 CF 50 TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION GENERAL EMERGENCY NUREG-0554, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

1. a. Effluent monitors detect 1. a. As calculated in levels corresponding to Erergency Procedures, 1 rem /hr W.B. cr 5 rem /hr R-2 " Release of Airborne thyroid at the site Radioactive Material" or bcundary under actual RB-11 " Emergency Offsite meteorolacical conoitions. Dose Calculations" or projected on EARS.

b. These dose rates are pro- b. As calculated in jected based on other plant Emergency Procedure '

parameters (e.g. , radiation RB-11 Emergency Offsite levels in containment with Dose Calculations or leak rate appropriate for projected on EARS, and existing containment pressure confir ed by near-site with scme confir .ation f rcm monitors. vent monitors or in-plant radiation effluent monitors) or are samples.

measured in the environs.

~

2. Loss of 2 of 3 fission 2. a. SITE AREA EMERGENCY Condit cn product barriers with a number 2 and ALERT potential loss of 3rd Condition numcer 5 with barrier, (e.g. , loss of high potential for loss of primary coolant boundary, contairment isolation or clad failure, and high pressure suppression potential for loss of capability (e.g., icss of all Containment Spray containment). capability or icss of two fan coolers anc one Cen-tainment Spray Train), or

b. SITE AREA EMERGENCY Condit icn numcer 2 and 3, concurrent ly or CCCCA3 38

I 1 AND 2 NUMBER EP G-1 OlABLO CANYON POWER PLANT UNIT NO(S) )

REVISION 2 O DATE 1/28/82 k.I PAGE 39 OF50 Tn1E: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION GENERAL EMERGENCY - (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

c. SITE AREA EMERGENCY Condition number 4 in Containment with high potential for loss of containment isolation or pressure suppression capability (e.g., loss of all Containment Spray capability or loss of two I fan coolers and one containment spray train),

or,

d. SITE AREA EMERGENCY condition numcer 4 outside containment with inability to isolate the break.

e. SITE AREA EMERGENCY condition number 2 and

' UNUSUAL EVENT condition number 8, concurrently.

f. SITE AREA EMERGENCY condition number 1 and UNUSUAL EVENT condition number 8, concurrently.

3. Loss of physical control of 3. On-going Security threat which the facility. results in the entry of unautnorized persons to the facility (Turbine Building, auxiliary or fuel handling building or intake structure).

DCCCA3 39

1 AND 2 NUMBER EP G-1 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 1/23/82 PAGE 40 OF50 TnLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION GENERAL EMERGENCY - (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS 4 Other plant conditions exist, 4 Condition as stateo in the from whatever source, that judgment of the Shift Foreman make release of large amounts of radioactivity in a short time period possible, e.g.,

any core melt situation.

a. Small and large LOCA's a. Site Area Emergency Condition with failure of ECCS Number 1, with verified to perform leading to inacequate core cooling per severe core Appendix F of EP OP-1 or degradation or melt in failure of the ESF per from minutes to hours. Appendix H of EP OP-1.

Ultiriate failure of containment likely for

.11t sequences.

(Several hours likely to be available to complete protective actions unless containment is not isolated).

b. Transient initiated by b. Loss of feedwater followed loss of feedwater and by ccmplete loss of condensate systems auxiliary feedwater (Site (principal Area Emergency Condition heat removal system) No. 7a) and loss of level followed by failure of indication in all operat-emergency feedwater system ing steam generators.

for extended period. Core melting possible in several hours. Ultinate failure likely if core melts.

DCCOA3 40

1 AND 2 NUMBER EP G-1 D!ABLO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 1/28/82 TITLE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION GENERAL EMERGENCY - (corit.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS Transient requiring opera- c. Site Area Emergency Con-c.

tion of shutdown systems dition No. 7 and Alert with failure to scram which Condition No.1, results in core damage or concurrently or additional failure of core 5.te Area Emergency cooling and makeup systems Condition No. 8 requiring (which could lead to core safety injection and melt). subsequent failure of ESF I per Appendix H of EP OP-1.

d. Failure of offsite and d. Site Area Emergency Con-onsite power along with dition No. 5 and numoer total loss of emergency 7.a concurrently with feedwater makeup capability loss of level indication for several hours. Would in all operating steam lead to eventual core melt generators.

and likely failure of containment.

e. Small LOCA and initially e. Loss of coolant accident successful ECCS. Subsequent with failure of Contain- ,

failure of containment heat ment spray and cooling removal systems over several per Appendix H of EP hours could lead to core OP-1.

melt and likely failure of containment.

7. Any major internal or external 7. Condition as stated in the events (e.g., fires, earth- judgement of the Shift Foreman quakes, substantially beyond design basis) which could cause massive comon damage to plant i systems resulting in any of the

[N)

C above.

OCCOA3 41

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NuveER EP G-1 REVISION 2 DATE 1/28/82 PAGE 42 OF 50 7ge ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION GENERAL EMERGENCY - (cont.)

NUREG-0654, APPENDIX 1 DIABLO CANYON POTENTIAL CONDITIONS INDICATED CONDITIONS

8. Degraded core with possible loss 8. a. One or more of the of coolaole geccetry (indicators fullcwing indications snculd include instrumentation of inadecuate core to detect inedecuate core cooling:

cooling, coolanc act'vity and/or containment radioac../ity levels). 1) One or more RCS (Note: This condition is a hot leg wide range reclassification of Site Area RTD's are at their Emergency Condition No. 2). upper scale limit. ,

or

2) Five (5) or more plant comcuter incare tneraccoucle readings are greater than 17]0*F, or

3) Three (3) of the ten (10) core center thermoccuple readings en the Incore Boarc exceed 700*F, or

4) Safety Injection System ficw to RCS and feeewater ficw to the Steam Gent ators cannot be veririsc, and

b. Reactor Coolant activity exceecs ALERT Concition No. 1 or cannot :e cete rmi ned.

O CC00A3 a2

1AD2 OIABLO CANYON POWER Pt. ANT UNIT NO(S) NUMBER EP G-1

' DATE 1/28/82 PAGE 43 Op 50 Tm ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION TABLE 2 EMERGENCY OPERATING PROCEDURES - ACCIDENT CLASSIFICATIONS PROCEDURE EMERGENCY CLASSIFICATION EP OP-0 Rx Trip with SI Unusual Event EP OP-1 Loss of Coolant Accident Site Area Emergency EP OP-2 Loss of Secondary Coolant Unusual Event EP OP-3A Stm. Gen. Tube Rupture Alert EP OP-38 Minor Stm. Gen. Tube Unusual Event if lea ige exceeds Failure Tech Spec Limits EP OP-4 Loss of Electrical Power Unusual Event

~

( EP OP-8 Control Room Inaccessibility Alert ,

EP OP-10 Loss of Aux. Salt Water Unusual Event EP OP-11 Loss of Component Cooling Unusual Event for loss of Water one vital loop EP OP-14 High Activity in RCS Unusual Event EP OP-18 Failure of Charging or Unusual Event Letdown Line EP OP-20 Excessive RCS leakage Unusual Event 1

EP OP-22 Emerger.cy Shutdown Alert EP OP-23 Natural Circulation of Unusual Event Reactor Coolant EP OP-24 Loss of Containment Unusual Event Integrity l EP OP-25 Tank Ruptures Unusual Event i

EP OP-27 irradiated Fuel Damage Alert O

DCCOA3 43 l

l

1 AtiD 2 NUMBE9 EP G-1 DIABLO CANYON POWER PUWT UNIT NO(S) REVISION 2 DATE 1/28/82 PAGE 44 OF 50 7,7g' ACCIDENT CLASSIFICATION AfiD EMERGENCY PLAN ACTIVATION TABLE 2 (cont.)

PROCEDU'IE EMERGENCY CLASSIFICATION EP OP-32 Rod Ejection Site Area Emergency EP OP-35 Loss of Vital or Unusual Event Non-Vital Instrument AC System EP OP-38 Anticipated Transient Alert Without Trip EP OP-39 RCP Locked Rotor Accident Unusual Event EP OP-40 Acci antal Depressuri- Unusual Event zation of Main Steam System EP OP-41 Hydrogen " Explosion" General Emergency Inside Containment EP OP-44 Gaseous Voids in the RCS Unusual Event EP M-3 Chlorine Release Unusual Event EP M-4 Earthquake Unusual Event if greater than 0.01g EP M-5 Tsunami Warning Unusual Event EP M-6 Nonradiological fire Unusual Event /if greater than 10 minutes to control.

EP R-1 Personnel Injury Unusual Event if offsite (Radiologically Related) assistance is required.

and/or Overexposure CCCCA3 24

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

REVISION 2

/' DATE 1/28/82 i PAGE 45 OF 50 TIT E '.

ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION TABLE 2 (cont.)

PROCEDURE EMERGENCY CLASSIFICATION EP R-2 Release of Airborne Unusual Event if greater than Radioactive Materials Technical Specification Limits.

EP R-3 Release of Radioactive Unusual Event if greater than Liquids Technical Specification Limits EP R-4 High External Radiation unusual Event (In-plant)

EP R-6 Radiological Fire Unusual Event RP R-7 Offsite Transportation Unusual Event if shipment Accidents: originates or is destined for the plant.

( MOTE: The emergency classification listed is the least significant classification for that procedure. The event covered by each procedure may progress into a more severe classification.

6 CC00A3 45

1 AND 2 NUMBER EP G-1 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 1/28/82 PAGE 46 OF 50 7gtg. ACCIDENT CLASSIFICATION Afl0 EMERGENCY PLAN ACTIVATION TABLE 3 EMERGENCY OPERATING PROCEDURES - SIGrilFICANT EVENTS Activation of the emergency plan requires notification to the County offsite authorities within 15 minutes. Emergency procedures that are not initially classified in the Emergency Plan but may be reportable (within one hour) to the NRC only as a "Significant Event' (10 CFR 50.72) are listed below:

EP-OP-5 Reactor Trip Without Safety / Injection EP-OP-6 Emergency Boration EP-OP-7 Loss of Condenser Vacuum EP *.J-9 Loss of Reactor Coolant Pump EP-0P-12 Malfunctions of Automatic Reactor Control System EP-0P-13 Malfunction of Reactor Pressure Control System EP-0P-15 Loss of Feedwater Flow EP-0P-16 Nuclear Instrumentation Malfunction EP-0P-17 Malfunction of RHR System i EP-0P-19 Malfunction of Reactor Makeup Control System EP-0P-21 Loss of a Coolant Loop RTD EP-0P-26 Excessive Feedwater Flow EP-0P-28 Start-up of an Inactive Reactor Coolant Loop EP-0P-29 Excessive Load Increase EP-0P-30 Inadvertent Loading of a Fuel Assembly Into an 1 Improper Position EP-0P-31 System Underfrequency EP-0P-33 Loss of Instrument Air DCCOA3 46

l

~

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

REVISION 2 DATE 1/28/82 PAGE 47 OF 50 TITE'. ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION TABLE 3 - (cont.)

EMERGENCYOPERATINGPROCEDURES-SkGNIFICANTEVENTS EP-0P-34 Generator Trip - Full Load Rejection EP-0P-36 Turbine Trip EP-0P-37 Loss of Protection System Channel EP-M-1 Employee Injury (Nonradiological)

EP-M-2 Injury to Nonemployee (Third Party)

EP-R-5 Radioactive Liquid Spill NOTE: Refer to Operating Procedure 0-4, " Operating Order (One Hour I Reporting Requirements to NRC)", for appropriate reporting for these events.

l l

)

V DC00A3 47 -

1 AND 2 NUMBER EP G-1 ;

DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 1/ 28/82 PAGE 48 OF50 URE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION lAELE4 TECHNICAL SPECIFICATIONS APPLICABLE TO UNUSUAL EVENT CONDITION N0. 9 NUMBER TITLE 3.1.2.2 Reactivity Control System--Operable Flow Paths 3.1.2.4 Reactivity Control System--Operable Changing Pumps 3.1.2.6 Reactivity Control System--Borated Water Sources--Operating 3.1.3.1 Reactivity Control System--Movable Control Ass'y--Group Height 3.1.3.6 Reactivity Control Sydi.m--Control Rod Insertion Limits 3.3.1 Instr--Reactor Trip System Instr 3.3.2 Instr--Engineered Safety Feature Actuation System 3.3.3.5 Instr--Remote Shutdown Instrumentation 3.3.3.6 Instr--Accident Monitoring Instrumentation 3.3.4.1 Instr--Turbine Overspeed Protection 3.4.1 RCS--RC Loops and Coolant Circulation 3.4.2.2 RC--Safety Valves 3.4.3 RCS--Pressurizer 3.4.4 RCS--Relief Valves 3.4.6.1 RCS Leakage Detection System 3.4.6.2 RCS--Operational Leakacs 3.4.7 RCS--Chemistry 3.4.8 RCS--Specific Activity 3.4.9.1 RCS--Pressure / Temperature Limits 3.4.9.2 RCS--Pressurizer 3.5.1 ECCS--Accumulators 3.5.2 ECCS--ECCS Subsystems 3.5.4.2 ECCS--Heat tracing 3.6.1.1 Containment Systems--Primary Integrity 3.6.1.3 Containment Systems--Containment Air Locks 3.6.1.4 Containment Systems--Internal Pressure 3.6.1.5 Containment Systems--Air Temperature 3.6.1.6 Containment Systems--Containment Structural Integrity 3.6.1.7 Containment Systems--Containment Ventilation 3.6.2.1 Containment Systems--Containment Spray System 3.6.2.2 Containment Systems--Spray Additive System 3.6.2.3 Containment Systems--Containment Cooling System 3.6.3 Containment Systems--Containment Isolation Valves 3.6.4.1 Containment Systems--Hydrogen Analyzers / Monitors 3.6.4.2 Containment Systems--Electric Hydrogen Reconbiners 3.7.1.1 Plant Systems--Turbine Cycle--Safety Valves 3.7.1.2 Plant Systems--Auxiliary Feedwater System CCCCA3 48

1 AND 2 NUMBER EP G-1 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 1/28/82

(~)

\ PAGE 49 OF50 TULE: ACCIDENT CLASSIFICATION AND EMERGENCY PLAN ACTIVATION TABLE 4 (Cont'd)

~

TECHNICAL SPECIFICATIONS APPLICABLE TO UNUSUAL EVENT CONDITION N0. 9 NUMBER TITLE 3.7.1.3 Plant Systems--Condensate Storage Tank 3.7.1.4 Plant Systems--Activity 3.7 1.5 Plant Systems--Main Steam Line Isolation Valves 3.7.3.1 Plant Systems--Vital Component Cooling Water System 3.7.4.1 Plant Systems--Auxiliary Saltwater System 3.7.5.1 Plant Systems--Control Room Ventilation Systems 3.7.6.1 Plant Systems--Auxiliary Building Safeguards Air Filtration System 3.8.1.1 Electrical Power Systems--AC Sources 3.8.2.1 Electrical Power Systems--Onsite Power Distribution 3.8.3.1 Electrical Power Systems--DC Sources Operating l

l

i O

O DC00A3 49 l

l

A NUMBER EP G-1 1 AtiD 2 REVISION 2 DIABLO CANYON POWER PLANT UNIT NO(S)

DATE 1/28/82 PAGE 50 OF 50 TITLE: ACCIDENT CLASS 9 CATION A.fl0 EMERGENCY PLAN ACTIVATION FIGURE 1 TYPICAL Off-SHIFT EMERGENCY ORGANIZATION AND ASSIGMM Site 1 Emergency

, Coordinator Emergency Emergency Emergency Operations 1 Evaluations &

Liaison 1 Recovery Coordinator Coordinator) Coordinator Operators Fire Emergenc FirstAidI Lia son Brigade Radiological , Medical Assistant . Team ! Personnel TYPICAL ASSIG!iMEtlT_

POSITION Interim Site Emergency Coordinator 1

ShiftForeman(STAifnotavailable)

Shift Control Technician, l- Interim Eme Ccordinator{gencyLiaison or Auxiliary Operator l

Sr. Control Operator or Control Interim Eme Operator Coordinator [gencyOperations Shift Engineer (Assisted by Shift Interim Emergency Evaluations & C&RP technician if necessary)

Recovery Coordinator Shift Control Technician or Shift Liaison Assistant Clerk Assignments per the Interim Site Operators Emergency Coordinator Sr. Control Operator Fire Brigade Captain See Procedure M-6 or R-6.

Fire Brigade Shift C&RP Technician or Auxiliary Emergency Radiological Team Operator (if required)

Employees at the Scene First Aid and Medical 1Reouired Assignment CCCOA3 50

_ ;: ~ ~ _ _..

PGvE DIABLO CANYON POWER PLANT M,". YIN 2)"* PROCEDURE ON-THE-SPOT CHANGE Procedu No..R B - 6 Rev. o Und No.10 2O ia2g ndaund-[qaipant Deeantamindion Type of Change PERMANENT (green) TEMPORARY (yeaow) n.auesnna oeoartrner. _.ncAnim i Anhtsnt % __L). h. ><ey,d. A Proposed change (Does mes aner the own of orgnal procedure? Yee h No)

. Add s. ps$e 9- 716 /e 3 " hed Sar{sca De**"t*~I"ti*~ EHW' A's in Peesaet", s.trsshed f &N(/Mb6A. h&& SW - > h Y $, s e $$

e a

2 -

1 t

m w cnonee 7,f j, ,g,gga,g,,,gj, ,,,g ,yj,,j,g ,y ,,7p ,yy p,,,,j,,,_

i s s u e. .

Aumoramene:

m ~~_~_ R

,. ~W _

),

w- _, -d, /d fM ..

!i!

Date Received by Document Control 2 9 2 5 PSRC Revow and Piant Manager's approval no later than h-ObSD name ahm *;*413 days d O~

no M esung Nune-0 0 - 0 0 0

- . _ O.

h To Retected On.tne-Spot ChangeO eooacasi iniorm===n O Acnon TamerVRomarts.

l I Si f9 OtSTRIBUTION: O S'""d% 0 O*=r.

m ==

=adooa****ts O

^

TABLE 3 HARD SURFACE DECONTAMINATION EFFICIENCIES IN PERCENT

Hi-Press. Utr.

Hi-Pressure Hi-Pressure Hi-Pressure Wtr. & Detergent Sand- Steam Vacuum Water Wtr.w/ Scrub & Detergrant with Scrub blasting Cleaning (D+2) (D+3) } }

Haterial (D+12) (D+4) (D+5) (D+9) (D+14)

Class 98.95 98.85 97.79 100.00 99.76 100.00 97.86 Stucco 48.00 97.94 95.22 100.00 99.59 100.00 27.00 Painted wood 99.28 98.43 96.77 99.69 99.97 100.00 91.61 Unpainted wood 36.00 85.00 93.18 99.54 95.54 99.90 85.00 Aluminum 89.00 99.45 97.33 99.62 100.00 98.49 84.00 Plate steel 93.04 97.26 94.19 100.00 93.83 99.72 91.46 Asbestos shingles 61.00 99.97 98.91 96.89 99.36 100.00 63.00 Unpainted wood 61.00 97.16 90.49 95.01 57.93 99.82 71.00 shingles 29.99 99.46 99.32 99.14 99.56 l

Brick 99.92 97.50 .

Tarpaper 55.00 98.66 95.04 95.32 95.83 99.51 52.00 l Calvanized roofing 89.00 99.36 97.19 99.73 99.86 100.00 85.00 liighway asphalt 32.00 99.90 96.25 90.82 99.48 99.90 44.00 111ghway asphalt 72.00 92.45 94.95 98.85 96.34 92.73 22.00

(lux 10 ft) .

Steel asphalt 71.00 98.67 90.00 100.00 99.72 99.61 84.00 Steel asphalt 64.00 90.00 82.00 96.31 97.54 , 90.42 48.00 (10x10 ft)

Steel trowel concrete 74.00 98.94 --

96.91 99.53 100.00 --

Steel trowel concrete --

73.00 97.34 --

99.58 98.96 27.00 8 (10x10 ft) !

Wood float concre.te --

98.00 92.03 100.00 97.47 100.00 65.00 j Wood float concrete 56.00 97.84 --

98.09 98.28 98.78' 85.00 g (10x10 ft) '

u Avg. of all surfaces 65.40 96.12 94.59 98.61 98.64 98.83 67.80 !

Decontamination factor (DF) = 100/[100 - decontamination efficiency (%)]

v m :o rn k (Den) - number of days between contamination and decontamination bM"'

W8 WASil 1400, Appendix VI, October 1975, " Reactor Safety Study." S~ En e

N wsER EP RB-7 l

(V .T. 3W3 Pacific Gas and Electric C0mpany REVISION 1 e DATE 1/28/82 DEPARTMENT OF NUCLEAR PLANT OPERATIONS I ) 1 OF 20 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE EMERGENCY PROCEDURE TITLE: EMERGENCY ON-SITE RADIOLOGICAL ENVIRONMENTAL PONIORING

.r f .

APPROVED:

' ' !I T PLANT MANAG?R DATE SCOPE This procedure describes an initial emergency radiological environmental monitoring crogram to determine gama anc beta dose rates and air particulate and radiciocine levels due to an accidental release of gaseous radionuclices.

This cata will be used to make initial assessments concerning the magnitude of the accident and decisions concerning evacuation of nonessential site personnel. This program can be undertaken early in the accident assessment process by a single team working on or near the site.

GENE 3AL INSTRUCTIONS

1. The on-site radiological environmental .nonitoring team (s) are unce tne direction of the Emergency Radiol @l Advisor (ERA). If the ERA has not arrived on-site, the Emergency Evaluations and Recovery Coordinator will direct the monitoring team (s).

2. As a minimum, the on-site radiological environmental monitoring team (s) will be comorised of two on-shif t personnel; a Chemical anc Raciation Protection Tecnnician (C&RP) (team leader) and an Auxiliary Operator (assigned by the Emergency Evaluations and Recovery Coordinator).

3. The on-site monitoring team (s) will maintain comunication with the Control Room and/or TSC :nrougn tne use of hand-held radios. Use the Health Physics onannel.

4. The team should have the following equipment:

a. A copy of this procedure - EP RB-7', " Emergency On-Site Radiological Environmental Monitoring."

b. A radiation monitoring instrument. At least one of the following should be used in order of preference:

1) HPI-1010 - located in emergency kit.

2) E-140 W/GM probe - in emergency kit.

3) Rad Owl - located in emergency kit.

4) Vitoreen Radgun - located in Control Room.

(O G'

c. Portaole air samoler HD-238.

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NUMBER EP RS-/

DIABLO CANYON POWER PLANT UNIT NO(S)- REVISION 1 EMERGENCY ONSITE RADIOLOGICAL DATE 1/28/82 ENVIRONMENTAL MONITORING p3ag , op 20 TITLE

d. Filter paper, charcoal cartridges and/or AgX cattridges.

e. Plastic bags, envelopes and labels for air samples, f.

Form 18-9259 " Emergency Environmental Monitoring Fie'id Data Sheet."

g. Hand-held radio from the TSC.

h. Vehicular transport.

1. Life jacket, if monitoring is to be done on the breakwater.

j. Paper and pen / pencil.

k. Flashlight.

1. Self-reading dosi=eters (low range and high range) and TLD.

5. When traveli"g from one location to another, always have a detector on so that if a porrion of the plume is traversed, it will be recognized i= mediately. If traveling in a vehicle, hold a detector out of the vindow. If any location is identified as being above background -

measurements should be taken and data recorded.

6. Prior to ensite out-of-plant =onitoring, readings from the fixed =onitors, PICS, should be obtained as well as information from any preliminary surveys conducted in-plant. This will provide some insight as to what ensite out-of-plant situations might be encountered.

PROCEDURE

1. Determine Affected Downwind Sectors

a. Raceive information from the Emergency Evaluations and Recovery Coordinator, or:

b. Determine wind direction from meteorological computer output or other suitable means. Wind directions are given as the direction f rom which the wind is blowing.

c. Figure 1, "Onsite Asse=bly and Monitoring Locations," shows a site map indicating sixteen 22.5* sectors. In general, the areas which may be affected include the 22.5* sector directly downwind plus the 22.5* sector on either side of the downwind sector.

2. Determine if Personnel Assembly Areas are Affected If any Figure 1 also shows the various personnel assembly areas.

occupied assembly areas are in an affected sector (s), make the measurements specified in Step 5 belew at the affected assembly area (s).

NUM8ER re ^a-#"-

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DIABLO CANYON POWER PLANT UNIT NO(S) "'V"""* 1 EMERGENCY ONSITE RADICLOGICAL DATE 1/28/92 TITLE ENVIRCNMENTAL MCNITORING ,

3. Check Size Monitoring Locations After checking the personnel asse=bly areas, =ake the =easure=ents specified in Step 5'below in each of the three affected sectors.

Measure =en:s should be =ade at as =any of the locations lhown on Figure 1 i as it is feasible to reach. Table 1 provides a descrip:1on of e=ergency onsite =enitoring locations.

a. Take the first =easure=ent a :he location which best approxima:es the direct downwind location, then take =easure=ents at the adjacen:

locations on either side of this location.

b. It =ay be necessary :o make =easure=ents at additional locations, depending upon =eceorological condi:icus. I NOTE: The ensi:e =eni:oring locations shown on Figure 1 are iden:ified by a white pole, approxi=ately six f eet high, topped vi:h a red circular di 1.

CAUTION: Do not atte=pt to =ake =easurements on the breakwaters if there is a hazard frr= high seas. At any time =easure=ents are =ade on the breakwater, the Liaison Coordinator should be infor=ed i==ediately before and after entry onto the breakwater. Life jackets should be wor =, if possible, vnenever a person goes onto the breakwater.

4 Initiate Population Cen:er Monitoring

a. If the seni:oring perfor:ed in Step 2 or 3 shows levels of 3 =r/hr of 9,000 cp=, then a =enitoring team should be dispatched :o the neares:

downwind population center as soon as possible.

b. Figure 2. "E=ergency Offsi:e Monitoring Locations," shows the standard offs 1:e environ = ental monitoring locations. Table 2,

" Description of E=ergency Offsite Moni:oring Loca:1ons," describes each location; and Table 3, " Preferred Monitoring Locations for Initial Population Center Monitoring Locations," reco== ends those

! which should be considered for initial population center =enitoring I as a function of wind direction.

l

) c. The =casure=ent sequence at each location for the ini:ial population center =onitoring progra= is su==ari:ed in Step 6.

l 5. Measure =ent Sequence at Onsite Locations I

l The following seasurements should be =ade at each onsi:e location. The data should be en:ered on Form 13-9259, "I=ergency Environ =ent Monitoring Field Data Sheet."

Deter =ine external ydose ra:e and/or count race. For : hose

) a.

instrumen:s with wincows (or beta shields), :ake both window open and s_ ,/

window closed readings.

l

NUMBER 'p gg,7 DI ABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY ONSITE RADIOLOGICAL DATE 1/28/82 ENVIRONMENTAL MONITORING TITLE PAGE $ OF 20 Use Table 4 to obtain appropriate instrument backgrounds.

b. Collection of Air Particulate and Radiciodine Sa=ples If t1=e and =anpower considerations per=it, collect 7n air sa:ple of at least 10 ft 3 (30-50 ft3 is preferred).

The sa=ple should be drawn through both a particulate filter and a halogen cartridge. Air sa:ples =ust be taken i==ediately if:

1) dose rate measurement 13 =R/hr, or 2) count rate measurement 19,000 cpm.

1) Equipment Required a) RADECO Model ED-28B (120V AC powered).

b) 2" diameter absolute particulate filter paper.

c) Coin envelope for retention of filter.

d) CESCO or HI-Q 2-1/4" diameter charcoal cartridge.

- e) AgX cartridge.

f) Plastic bag for retention of cartridge.

g) Gu==ed or other label for labeling cartridge container.

h) Wristvacch or stopvacch.

2) Procedure .

a) Assemble the filter and halogen cartridge in the sampling l head as shown in Figure 3. Draw an arrow on the cartridge to indicate the direction of flow, b) Place the filter head on the sa=pler.

l c) Plug in the sampler, turn on the power, and s1=ultaneously l

start a stopvacch.

l d) Quickly adjust the flow rate to the desired value (typically 2 cfm).

e) For a flow rate of 2 cfs, the sampling time should be at least 5 minutes.

o NUM8ER U no-/

DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY ONSITE RADIOLOGICAL E 1 82 O TITLE ENVIRONMENTAL NONITORING U '

f) Periodically check the flow indicators to verify that the flow race is being =aintained. If the flow race changes significantly during sa=ple collection, note the value at the end of the sa=ple period and determine the average value of the flow rate. Record the value of the flow' rate in ef=.

l g) Allow the sa=pler to run until at least 10 ft (preferably 3

30-50 ft3) is collected. The greater the volu=e sa=oled. the better. Record the sa=ple ti=e.

b) Stop the sampler and re=ove the filter head, i i) Place the particulate filter in the coin envelope and label the envelope.

j) Place the cartridge in a plastic bag and label the bag. !

Cartridges which are collected in the field shall be placed !

in a sealed plastic bag, and identified with a fir =1y ?

s tached label which states the folleving infor=ation:

(1) Date and time (note a.m. or p.m.) of collection.

(2) Name of person who collected the sa=ple !

(3) The time the sampling was started and the ti=e the sampling was ter=inated (4) Sa=pler flow rate I (5) Location of sample k) Deter =ine airborne I-131 concentration from air sample. It is preferred to return the halogen cartridge to the counting room or TSC lab if this can be done expeditiously.

Otherwise, use the field technique. Since the field technique gives you gross iodine, the easiest and =ost conservative approach is to assume it is all I-131. Record results on Form 18-9259.

6. Measurement Sequence for Initial Population Center Monitoring The following measurement progra= should be followed during the initial population center =enitoring phase. These measure =ents =ay be pree=pted should the Emergency Evaluations Coordinator deter =ine that an alternate schedule is appropriate,

a. External y Measure =ents

1) Measure y dose rate or count rate at the ti=e that =enitoring is O initially established.

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' MUMBER Ep Rg.7 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY ONSITE RADIOLOGICAL DATE 1/28 /82 TITLE ENVIc0Nt1 ENTAL MCNITCRING PAGEg OF ZU

2) For those locations where an instru=en: can be left unattended,

- leave a Rad Owl of HPI-1010 in the integrate mode. The integrated exposure should be recorded at lease every two hours.

3) For those locations where an instru=en: canno: b'3 lef t unat: ended, a dese-rate or coun:-rate seasurement should be =ade on an hourly basis.

b. Air Sa=ples

1) For those locations where ac pcuer is available and a sa=pler can be left unattended, place an ED-28B sa=pler and allow it to run continuously. Collect the firs: filters and deter =ine the iodine concentration after about 30 f: 3 have been collected. This is ten minutes on an ED-283 set at 3 ef=. Thereaf:er', collec: :he filters every two hours. !

2) For those locations where ac power is not available, or a sa=pler {

cannot be lef: unattended, collect a sa=ple every two hours of a: '

least 30 fc ,3 using a 12V de-powered sa=pler operated fre= an auto =obile.

SUPPORTING PROCEDURES R-2 -

Release of Airborne Radioactive Material RB-ll E=ergency Offsite Dose Calcula:1ons j RB- 8 Offsite E=ergency Radiological Environ = ental Monitoring i 1

EF-4 Ac:1vation of the Mobile Environ = ental Monitoring Laboratory TABLES

1. Description of E=ergency Onsite Monitoring Locatiens

2. Description of E=ergency Offsite Monitoring Locations

3. Preferred Monitoring Locations for Initial Population Center Monitoring Progra:

4. Instru=ent Background for Ga==a-Beta Dose Race Measure =ents and/or Counc l

l Rate Measurements (3' above ground)

FIGURES

1. Onsite Asse=bly and Monitoring Location

2. E=argency Offsite Monitoring Locaticus

3. Exploded view of Cartridge and Particulate Filter in Sa=pling Head l

e NUM8th ~J rO~o DIABLO CANYON POWER PLANT UNIT NO(S) " ' " " I EMERGENCY ONSITE RADIOLOGICAL M g/82 DATE

') TITLE E'4VIRONME'4TAL MONITORING PAGE 70F 20 FOR.MS l No. 69 -9259 "E=ergency Environ = ental Monitoring Field Data Sheet" r 1

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EP RE-7 DlABLO CANYON EMERGENCY POWEF)Cttstic P,1.Aff,7 ht.wIvec[$)

rev! gjy yg nrvision i DATE . 1/2-/52 NVIRCNMENTAL MCNITORING 20 TITLE PAGE CCF 1

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_ ,,u PAGE 10er 20 FIGURE 3 EIPLODED VIEW OF HAIAGEN CARTRIDCE AND PARTICC. ATE FILTER Di SAMPLING HEAD 2 I 4

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NUMBER EP RS 3, DIABLO CANYON POWER tt EMERGENCY ONSl u. vu ng (S) R EVISION 1 ENVIRONMENTAL MONITORING DATE I/28 /02 ITLE PAGEll CF 2U TABLE 1 DESCRIPTION OF Dd.ERGE';CY CMSITE MONITORING LOCATIONS Straight Line Distance Fron AC Power Coordinate Plant (Meters) Descrietion Available N,A 300 South side of road. No N,NE.A 700 In front of wooden water tank. No NE,A 3,000 Adjacent to east reservoir. Yes NE,3 800 North side.of road in the No gulley.

ENE,A 700 South side of switchyard at No fence.

SE.C 700 PIC unit, DER air sa=pler-- Yes

( behind fourth SEC of GC warehouse.

SE,3 800 Front of CC warehouse. Yes SE,A 800 40 feet off the road on the No vest side of road--no accessible by vehicle.

SSE A 700 Adjacent to guard shack on Yes bluff.

SSE,3 7G0 Adjacent to culvert on west No side of dirt road.

SSE.C 700 West side of sandblasting area. No S.A - On breakwater. No S,3 - On breakwater. No SSW.A 400 West of net tower--requires No 53 key for gate--not ac:essible by vehicle.

SSW,3 - On breakwater. No

NUMSER ' ^3 ~ '

EY1R NWb f& D yhG REVl51ON1 ENVIRONMENTAL MONITORING DATE IS" /82 TITLE PAGE 12 OF 20 TABLI l_ (Continued)

DESCRI? TION OF DERCD'CY ONSITE MONITORING LOCATIONS Straight Line Distance Fros AC Power Coordinate Plant (Meters) Descriotion Available

- On breakwater. No S SL', C 500 'Je s t of net cover-requires Yes S4,A 53 key for gate-not accessible by vehicle.

kT4,A 500 Near gulley on south side- No requires 53 key for gate.

40 feet in front g a t e- No LT4,3 600 '

requires 53 key.

North side of road in clearing. No

. LT4,C 600 600 North side of road in clearing No W, A area of bushes.

W,3 600 Northwest side of dirt road. No W,C 800 At gate on road leading to No north road.

800 30 feet north of steps leading No ST4,A to pond.

I I

NUMBER EP RB-7 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVislON 1 I~ /) EMERGENCY ON-SITE RADIOLOGICAL

\I TITLE ENVIRONMENTAL MONITORING DATE 1/23/C2 PAGE13 op 20 TABLE 2 DESCRIPTION OF EMERGENCY OFF-SITE MONITORING LOCATIONS Straight Line Distance From AC Power Coordinate Plant (KM) Descriotion' Available N,10,A 9.8 West of Montano de Oro State No Park sign (0.6 miles SW of Rodman Drive on Pecho Road.

. Good radio at path off road south of State Park sign.

Sign on oath reads "No Venicles".

N,15,A 10.0 End of Alamo Drive in Cab-illo Estates (Turn off 'racho Road at Rocman and go .o ?

top of the hill. Turn rignt onto Alamo and follow it to the end.) Good Radio. Phone available.

2 N,15,3 11.6 Sunset Terrance Golf Course Yes at clubhouse. Good radio at west end of Howard Drive or l on road running north of the golf course.

l N,15,C 11.3 Baywood Park Fire Station Yes (Turn south off of Los Osos Road onto Bayview Heights Drive. Has a TASC-4. DER's monitoring Station 10 is located at Sunnyside School next door.) Good radio.

Phone available.

N,20,A 18.0 Morro Bay Power Plant. DER's Yes monitoring Station 9 is located here. Good radio. Phone available.

rN

cumsER EP RS 7 )

DIABLO CANYON POWER PLANT UNIT NOIS) REvis ON 1 EMERGENCY ONSITE RADIOLOGICAL DATE 1/22/82 ENVIRONMENTAL MONITORING PAGE 1.DF 20 TITLE J )

TABLE 2 (Continued)

Straight Line AC Power Distance From Description Available Coordinate Plant (KM)

Intersection of Los Osos No NNE,15,A 11.3 Valley Poad and Clark Valley Road (under PG&E transmission lines) .

b Good radio.

NNE,15,3 12.9 Los Osos Jr. High School No on South Bay Boulevard i in the playing field.

F Good radio.

0.2 miles north along No NNE,20,A 17.6 San Bernardo Creek Road is on the northeast side of Highway 1.

b Good radio.

Intersection of Los Osos No NE.15,A 10.6 Valley Road and Turri i Road. DER's monitoring Station 11 is located nearby. Good radio at l

I intersection. .

Sheriff's headquarters. Yes NE,20,A 17.4 Turn south on Highway 1 at sign indicating Sheriff's Operational Canter. Good radio.

I Phone available.

PG&E substation near Yes NE,20,3 19.2 Men's Colony, adjacent to northeast side of High 1. Good radio reception. Phone available.

l I

8_ NUMBER EP RB-7 DIABLO CANYON POWER PLANT UNIT NO(S) 1 MID 2 R EVISION 1

(] DATE 1/28/82 TITLE EMERGENCY ON-SITE RADIOLOGICAL ENVIRONMENTAL MQiITORING PAGE 15 OF 20 TABLE 2 (Contineed)

Straight Line Distance from AC Power Coordinate _ Plant (KM) Description ~ Available ciE.8,A 9.0 See Canyon Road, 4.2 miles up Yesl from San Luis Bay Drive inter-f section. Good radio.

Telephone available. Rattle-snake hazard.

ETE,20, A 14.8 Laguna Jr. Righ School at inter- Yes3 section of Los Osos Poad and Perfumo Canyon Road. Good radio.

CiE.20,3 16.0 Fire Station at intersection of Is Los Osos Valley and Madonna Roads.

! Good radio.

ENE,20,C 18.6 PGandE Information Zone 1 substa- Yes tion at corner of Walker and

( Pacific Streets. DER's Station 12 is also located here.

I Good radio.

ENE,20,D 15.6 Corner of Foothill Boulevard and Yes l O' Conner Way. Good radio.

i ENE,20,E 15.8 Yancy's Restaurant (for=erly Hob Yes 2 Nob) parking lot. Good radio.

1 E,15,A 14.5 PGandE Information Center. Yes Good radio.

E,15,3 13.4 Bellevue-Santa Fe School. Yes 5

, , Good radio.

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NUM8ER EP RS.7 DIABLO CANYON POWER PLANT UNIT NO(S) g gy,gjog i EMERGENCY ONSITE RADIOLCGICAL oarE 1/28/82 TITLE ENVIRONMENTAL MONITORING PAGE!6 OF 20 { }

TABLE 2 (Continued) -

Straight Line '

Distance Frem -

AC Power Coordinate Plant (KM) Description Available E 15,C 11.3 See Canyon Road 1.7 Tesl miles up frem San Luis Bay Drive intersection.

Survey at intersection of See Canyon Road and Davis Canyon Road. Good radio.

E. 25 , A 20.2 SLO County Airport. The Yes field on the right of the road to the parking l lot. Good radio.

I

.. E.25,3 21.5 SLO Country Club. East - Yes2 i side of parking lot in the fairvay. Good radio, l

i ESE,4,A 2.6 Turnout on access road, No 1.6 miles from Security ,

I Building. Marked with red / white fence post. Radio near

- plant or near location ESE,10,A ESE,6,A 4.5 Turnout on access road No 2.8 miles from Security Building. Marked with red / white fence post. Radio l

i near plant or near location ESE.10,A ESE. 8, A 6.9 Cate next to shack at No road to ruins, 4.3 miles from Security 3u11 ding along access road.

Marked with red / white fence poet. DER station l 16 is near here. Radio rear plant or near location ESE. 10,A l

ESE.10',A 9.6 Top of San Luis Hills. No Gate at 6.2 miles frem the Security Su11 ding. g g

{ Sc=e radio.

NUMSER EP RB.7 DIABLO CANYON POWER PLANT UNIT NO(S) # 8" 1 EMERGENCY Ct4 SITE RADIOLOGICAL ENVIRONMENTAL MONITORING DAR I/28 /82 s

. TITLE ~1 PAGE 170F 20 TABLE 2 (Continued) -

Straight Line .

Distance From -

AC Pever Coordinate Plant (KM) Descrintion Available ESE 10,3 10.0 Port San Luis Gate. Yes TASC-l. and DER's Station 27 are located here.

Radio on road to Pirates Cove.

ESE.15,A 11.6 Parking lot behind Avila Yes Beach Post Office.

,I Radio on road to Pirates Cove. j ESE,20,A 15.3 Pismo Beach Fir Dept. Yes on Shell Beach Road.

r Good radie.

. ESE,20,3 19.2 0.5 miles northwest of Yes!

the Shorecliff Inn on Shell Beach Road. Good

(

F radio.

SE 2.A 1.3 Turnout on access road, No 0.3 =11es from Security 3 Building near meteo- I rological Tower A.

Marked with red / white fence post. DER Station 7 is near here. Good t- radio.

NW,2,A 1.6 0.6 miles north from No Field's property gate (1 mile north from plant, just ENE of Lion Rock).

NW.I..A 3.5 Fields' road near large No watering pond.

NW,8,A 6.1 Near residence by park Yesl gate.

NNW , l. . A 2.7 Near wood paneled house. Yesl 1

i e

NUMBER gp R3 7 DIABLO CANYON POWER PLANT UNIT NO(S) 1 A'O 2 REVISION 1 EMERGENCY CN-S!!E RADICLCGICAL DATE 1/'? *:' "a '

TITL.c E'r/IRG:. MENTAL MONITCRING PAGE18 OF 20 TA31E 2 (Continued)

Straight Line Distance Fron AC Power Plant (KM) Descrietion Available Coordinate

Cr.',3, A 5.3 Parking lot near end of Mo' road at southern park boundary (near gate to Fields' property). Good

' radio.

'C i,3,3 7.6 Ranger s:ation overlooking Spooner's Cove. Good radio en road south of ranger station at " Locked Gate Ahead" sign (near parking overlook of Spoon-i ers' Cove.)

NCTES:

1 Power is available at nearby residences.

During working hours. Also power is available at nearby residences.

3 0uring school hours. Also at nearby residences.

'During school hours.

5 A dirt road leads to the top of the hill. The intersec:1on of this road w1:h access road is sarked with a red / white fence post. A 90909 key is recuired on the gate. A four-wheel drive vehicle is preferred. Alternatively; take reading on the access road at the marked fence post.

' Power is available at nearby residence on Fields' property (NE.3,A) and monitoring can be perfor=ed at this latter location is practical.

During daylight hours.

' Radio co==ents refer to unaided handi-talkie use of Davis Peak Repeater (H.P. Frequency) only - other trans=1:ter si:es not considered.

O

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. I NUM8ER LP ^G '

DIABLO CANYON POWER PLANT UNIT NO(S) REvislON 1 1 l

2 EMERGENCY ONSITE RADIOLOGICAL A /28/S2 <

TIT 1.E ENv190NMENT4L MONITORING ,

v TABLE 3 ,

PREFERRED MONITORING LOCATIONS FOR INITIAL POPULATIO!' CENTER MON!!CRING PROGRAM DC'.S"JIND SECTOR LOCATIONSI WIND DIRECT!ON

- NONE CALM NONE 348*45' - 11*15' S NONE 11*15' - 33*45' SSW NONE 33'45' - 56'15' SW WSW NONE 56'15' - 78*45' W NONE 78*45' - 101'15'

!cN (MN,8,A) 101*25' - 123*45' NW (!a"J ,8 ,3) 123*45' - 146'15' NIN (NIN,8,3) 146'15' - 168*45' (N,15,3) i

N (N!N,8,3) 168*45' - 191*15' (N,15,3)

NNE2 (N,15 D) 191*15' - 213*45' (!BT ,15 , A)

(NE 15,A) 213*45' - 236'15' NE2 (ENE,8,A)

(ENE.20,C)

ENE2 (ENE.8,A) 236'15' - 258'a5' (ENE,20,A) l l

(ENE.20,C) 2 (ENE.S.A) 258'45' - 281'15' E (E.15,3)

(ESE.15,A)

ESE (E .15 ,3) 281'15' - 303*45' (E.15,A)

(ESE,20,3)

SE (ESE.8,A) 303*4!' - 326'15' (ESE,15,A)

(ESE.20,3)

SSE (ESE,15,A) f 326*15' - 348*45' l NOTES:

15ee Table and Figure 2.

2*his vind direction rarely persis:s for =cre than a few hours, so an:icipate IO vind :hange.

1

NUMBER tr Ad-I DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY ONSITE RADIOLOGICAL DATE 1/28/82 TITLE _ FNVIRON"ENIM "ONIIOEINO PAGE?O OF 20 TABLE 4 9

INSTRUMENT BACKGROUND FOR CAMW.A-BETA DOSE RATE. MEASURDiENTS AND/OR COUNT RATE MEASURDiENTS (3' ABOVE GROUND) ]

BACKGROU'ID DOSE RATE (:2R/hr)

WINDOW CLOSED WINDOW OPEN INSTRUMENT 0 0 Rad Owl Victoreen Radgun 0.02 0.02 EPI 1010 0.015 NA 3ACKGROUND COU'C RATE (c m)

SHIELD _0N SHIELD OFF GM PROBE 60 60 EP-240 NA 50

. HP-260 NA 50 HP-210 l

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NwsEa EP RB-8 3GEG Pacific Gas and Electric Company REVISION 1 m DATE 1/28/82 CEPARTMENT OF NUCLEAR PLANT OPERATIONS CIABLO CANYON POWER PLANT UNIT NO(S)1 AND 2 PAGE 1 CF 39 j EMERGENCY PROCEDURE 111 TITLE: EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING W

APPROVED:

' / 2-PLANT MANAGER 6 DATE SC0pE This procedure describes the emergency offsite radiological environmental monitoring program which would be undertaken in the event of an airborne release of radioactive materials from the Diablo Canyon Power Plant. The procecure provides instruction for implementation of the program. Also provicec are instructions to monitoring teams for locating sample points, collecting samples, and performing field analyses of samples.

INITIATING CONDITIONS The Site Emergency Coordinator declares a Site Area or General Emergency in accordance with EP G-1, " Accident Classification and Emergency Plan Acti vation. " Offsite envircnmental monitoring teams may be dispatched for an i Alert classification if judged appr'opriate by the Site Emergency Coordinator.

DIRECTION AND CONTROL Offsite monitoring teams and the Mobile Environmental Monitoring Laboratory (MEPL) will be dispatched at the direction of the Emergency Eva.luations and Recovery Coordinator (EERC). The offsite monitoring teams and MEML will receive operating instructions from the Emergency Radiological Advisor (ERA).

The ERA will keep the EERC infomed of the offsite monitoring team activities.

After the EOF has been fully manned and activated, the Radiological Emergency Recovery Manager (RERM), will assume control of and responsibility for offsite radiological assessemnt activities. This includes the emergency offsite radiological monitoring activities. The Radiological Monitoring Director will be responsible for comunication with the monitoring teams, the MEML, and provide them with operating instructions. The RERM will be kect informed of the offsite monitoring teams activities.

Transfer of control and resconsibility for offsite radiological assessment activities will be initiated by the Site Emergency Coordinator and the Recovery Manager. The decision to transfer control and responsibility shall be conveyed by the SEC and RM to their' respective staffs. This shall be done by direct comunication and entered on the status board.

The Emergency Liaison Coordinator, at the TSC, will then infom tha uffsite environmental moni toring teams and the MEPL, by racio, tnat :omunications anc cats will be transmittec to and from :ne EOF to the Radiological N nitoring h

V 04 rector.

NUMBER .r nu v DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY OFFSITE RADIOLOGICAL EfWIRONMENTAL DATE 1/ 2P/82 TITLE tiONITORING PAGE 2OF 39 00MYL'NICATIONS

1. The primary communication links between the TSC, EOF, MEML, and field monitoring teams will be by radio communications on tha. health physics The frequency. The field monitoring teams will use hand-held radios.

location and numbers are listed below:

Radio Type Number (Spares)

Location CSC (Security Building) H C (2)

P 2 H 2 Plant Gate H 6 (2)

PG&E Service Center (MEML) 2 (2)

H PG&E Information Center H 2 (2)

EOF 1 ,

P '

P 1 (1) ,

MEML 1 (1)

P DER Vehicle H Hand-held. P Per=anent.

NOTE: Field teams should obtain hand-held radios from the CSC or ME.ML.

Other locations should be used as a back-up only.

a. For ease of coc=unication with the radios, the field monitoring teams vill be given call names using the International (ICAO) Phonetic Alphabet:

A - Alpha E - Echo I - India F - Foxtrot J - Juliett B - Bravo C - Charlie G - Golf K - Kilo D - Delta H - Hotel L - Lima

b. Radio Technique

1) Hold the radio upright, directly in front of the mouth with l antenna oriented 90* from direction of receiving station (i.e. ,

l EOF).

2) Bef ore transmitting =ake certain that someone else is not already transmitting on the f requency.

3) Af ter pushing transmit button, wait two seconds to allow automatic radio encoding to occur.

4) Begin all communications per the f ollowing example:

"ECF, this is Alpha team. Do you read me?"

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5) Close all co=cunications per the following exa=ple:

"~his is Alpha team. Over."

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NUMBER tr no-o REVISION E REC N N N kbLN kbAL g 1 ENVIRONMENTAL MONITORING DATE 1/23/82 TITLE PAGE 3 or 39

2. Com=unications back-up would be by telephone:

/

DCPP: (i' )

EOF: (f ' ) ,

, TSC: ({ s) ,

3. Each monitoring team leader and the MEML shall contact the TSC or EOF under the following conditions:

a. Prior to beginning the monitoring program, in order to obtain initial in s t ruct ions ,

b. Upon co=pletion of monitoring at each location.

ur

c. At least once per hour.

MONITORING TEAMS

1. Composition

/' a. A minimum of four teams are available for offsite invironmental d;-]/ monitoring. ,

b. Each team will have two members. One team member will be designated the team leader.

c. Teams will be comprised of 1 (one) PG&E C&RP Technician as the team leader and 1 (one) additional PG&E Technician and/or 1 (one) SLO County (SLOCO) Environmental Sanitarian. .

a. Day Shift

1) Teams will be dispatched from DCPP.

2) Each team will be supplied with a hand-held radio and an emergency kit.

3) Mobilization and dispatch on the day shif t will take approximately 20 minutes.

b. Back Shifts

1) Teams notified on an on-call basis will be directed to assemble

! at the Operations Support Center (OSC) or other 1. estion where kits are available (PGLE Information Center, EOF ot Morro Bay P7eer Plant) .

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l NUMBER EP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) REv SION 1 EMERGENCY OFFSITE PAOICLCGICAL P TITLE E!MRO!NAL ENITORING PAGE4 OF 39 (

2) Mobilization and dispatch on a backshift will takh approxi=ately one hour,

c. The E=ergency Liaison Cocrdinator vill transmit the asserbly location to the SLCCO Emergency Crganization. ,

e' CENERAL INSTRUCTIONS

1. Locations to Monitor

a. Affected Sectors The 360* of the co= pass have been divided into sixteen 22.5* sectors

which are identified by the compass point of their centerlifie: 1.e.,

N, NNE, NE, ENE, E, etc. In this procedure, all directions are ref erenced to true north, so N means true north. If the vind direction has been reasonably steady, the monitoring program should e=phasize the sector 1::=ediately downvind plus one adjacent 22.5*

sector on either side of the downwind sector. If the vind direction is changing considerably, the sectors monitored vill have to be appropriately increased.

b. Distance Downvind The EERC vill use the EARS syste= or manual overlays as described in EP RB-11 to deter =ine distance affected dov=vind. Generally, it is best to send at least one team as far downvind as appropriate, and then have the= vork their way back in toward the plant.

c. Identification of Emergency Monitoring Locations

1) Monitoring locations used in this procedure are identified in Figure 1, "Onsite Asse=bly and Monitoring Locations" and Figure 2, "E=ergency Of fsite Monitoring Locations." Table 1

" Description of E=ergency Onsite Monitoring Locations," and Table 2, " Description of Emergency Of fsite Monitoring Locations" are included for reference. .

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NUMBER EP RS-8 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY OFFSITE RADIOLOGICAL

( ENVIRONMENTAL MONITORING DATE 1/28/82 TITLE PAGE g OF 7c

2) Coordinate System Each monitoring location is identified by three coordinates: a compass point, a distance in kilometers, and a letter designation, (i.e., NNE, 8. A).

The ecmpass point refers to the sector in which the sample was taken.

To help locate the distance frem the plant at which the sample was taken, concentric circles have been drawn on the map at the following distances from the plant: 0. 8 km (800 m) , 2 ks, 4 km, 6 km, 10 km, 15 km, 20 km, 30 ks, etc. This defines seg=ents of a circle which are 22.5* in arc, and either 0.8.1.2, 2 or 5 k=

deep, depending upon the particular location of the seg=ent. The km designation in the identification refers to the distance of the farthest seg=ent boundary, not the actual downwind distance.

In cases where sa=ples are taken at locations other than those previously labeled, some other identification means =ust be used.

Thus, the following might be typical sample location

. designations:

(ESE, 15, Avila Post Office)

(ENE, 20, corner of March and Broad Streets, SLO)

(NNW, 8, campground at =outh of Islay Creek)

d. Environmental Sampling Stations

1) There are a number of environ = ental monitoring and sa=pling stations which are part of the continuing program conducted by '

the Department of Engineering Research. For reference, these stations are shown in Figure 3, " Location of Departments of Engineering Research Environmental Monitoring and Sampling Stations."

NOTE 1: Field monitoring teams will not collect da a from DER monitors unless expressly directed by the Radiological Monitoring Director (located at the E07).

NOTE 2: The TLD's are located in a grey plastic container.

Opening the container requires a 1/8-inch Allen wrench and a ha==er which are in the emergency kits.

2) The Nuclear Regulatory Commission also has posted TLD's in the area. Infor=ation may be obtained f rom the. NRC Representative onsite. See Table 4. " Environ = ental Radiation Monitoring Network Stations - Nuclear Regulatory Co==issien." for locations of the TLD's.

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NUM8ER EP RS-8 '

DIABLO CANYON POWER PLANT UNIT NO(S) "E " 1 EMERGENCY OFFSITE RADIOLCGICAL AE !

TITLE ENVIRONMENTAL MONITORING 6 w 3j

e. Dairies Because the milk pathway is of ten the limiting pathway, it =ay be desirable to c'ollect milk sa=ples. The locations of dairies in the DCPP area are described in Table 5, " Locations of Telected Dairies."

2. Sa=ple Identification and Data Sheets

a. Identification and Retention of Samples Sa=ples or filters which are collected in the field shall be placed in a sealed plastic bag, envelope, or bottle, as appropriate, and identified with a fir =ly attached label which states the follcwing infor=ation:

1) Date of collection.

2) Ti=e o. collection (for air sample filters, record the ti=e the sampling was started and the. time the sa=pling was ter=inated) .

3) Sa=pler flow rate (air sa=ples only).

4) Location of sa=ple.

5) Team na=e and na=e of person who collected the sample.

All sa=ples and filters shall be taken to the MD1 for preliminary field screening.

b. Field Data Sheets Field data shall be recorded on the E=ergency Environ = ental Monitoring Field Data Sheets (For= 18-9259). Each =enitoring team shall maintain a notebook with the data sheets and other pertinent l instructions.

The data sheet contains provisions for entering the data frc= all of the various field monitoring techniques. At any given monitoring location, only a few of the possible types of =easure=ents may actually be perfor=ed. A new data sheet shall be started for each

(

series of measurements at each =enitoring location.

MJNITORING PROGRAM An external dose rate measurement shall be taken and an air sa=ple shall be collected at each offsite =enitoring location.

If the TASC-4 continuous environ = ental =enitors are in an affected sector, they shall be read. *he TASC-4 are located at the Avila 3each Gate (ESI, 10,

3) and the Los Csos fire station (N,15, C).

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NUMBER EP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) R EVISION 1 DiERGENCY OFFSITE RADIOLOGICAL

(N 1/ 28/^^

b TITLE ENVIRONMENTAL MONITORING E ,j 39

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If the Pressurized Ion Cha=bers (PICS) are located in an affected sector, they shall be read. PIC locations are described in Table 6.

Collection of any other types of samples (i.e. , ground deposition

=easure=ents, vegetation, soil, water of milk sa=ples) will be at the direction of the Emergency Evaluations and Recovery Coordinator or the Radiological Monitoring Director.

1. External Dose Rate and/or Count Rate Measurements

a. Equipment Required

1) Any of the following instruments can be used for external dose rate ceasurements:

i) Rad Owl.

IT Victoreen Radgun.

c) EPI-1010.

. For measuring an external count rate, use an Eberline E-140 -survey meter equipped with either an HP-240 standard GM probe and HP-260 pancake GM probe, or an HP-210 shielded pancake GM probe.

b. Procedure

1) Dose or Count Rate Measurements a) Make a dose rate and/or count rate measurement with the detector held about three feet off the ground (i.e.,

approximately at vaist level) . If the detector is so equipped, take the data both window (or shield) on and off.

NOTE: *4 hen using the HP-210 probe, take both shield up (GM window down) and shield down (GM window up) readings. These readings may be required later to account for sky shine.

b) Identify the type of instrument (or probe) used, ti=e survey was started, and calibration due date of the instru=ent on the Field Data Sheet.

c) Calculate the net dose or count rate values by subtracting the appropriate background values given in Table 7.

d) Report both the open window (or shield) on and off values and the type of instru=ent used, to the E=ergency Evaluations and

? wcovery Coordinator, or hadiological Monitoring Director.

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NUMBER EP RS-8 DI ABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY OFFSITE RADIOLOGICAL DATE ,

1/28/82 ENVIRONMENTAL MONITORING TITLE PAGE 80F 39

2) Integral Dose The Rad Owl and the HPI-1010 have the capability for dose integration if desired. If an integrated measurement is =ade, the data can be entered in Section 2.c. of the'~ Field Data Sheet.

Integral measurements with the Rad Owl should be made with the window open. Report the integral dose and the time period over which it was collected to the EERC or RMD, as a'ppropriate.

2. Collection of Air Sa=ples

a. Equipment Required

1) One of the following air samplers, equipped with sample head for two-inch filters:

a) RADECO Model HD-28B (120V AC-powered).

b) RADECO Model H-809B (12V DC-powered, with battery).

c) RADECO Model H-809C (12V DC-powered, without battery).

2) Two-inch diameter absolute particulate filter paper.

3) Coin envelope for retention of filter.

l l 4) CESCO or HI-Q 2-1/4"-dia=eter characoal cartridge or AgX cartridge.

5) Plastic sandwich bag for retention of cartridge.

6) Gummed or other label for labeling cartridge container.

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7) Wristvacch or stopwatch,

b. Procedure

1) Assemble the filter and halogen cartridge in the sampling head as shown in Figure 5. Draw an arrow on the cartridge to indicate the direction of flow.

2) Place the filter head on the sampler.

3) For an ED-283, proceed as follows:

a) Plug in the sa=pler, turn on the power, and simultaneously start a stopvacch (or reset the timer on the sampler itself, if a sampling ti=e of several hours is contemplated) .

b) Cuickly adjust the flew rate to the desired value (typically 2 cfs).

NUMBER dh Sd-c DIABLO CANYON POWER PLANT IJNIT NO(S) REVISloN 1

()

\/ TITLE EMERGENCY OFFSITE RADI] LOGICAL ENVIRONMENTAL MONITORING oATE 1/28/82 P 9 oF 39

4) For an H-809C, proceed as follows:

a) Attach the sampler to the car battery by attaching the red cable to the positive battery terminal and the black cable to a chassis ground.

NOTE: Close the hood and place the air sa=pler on top of it to avoid engine fan turbulence.

b) Turn the vehicle engine on. Start the sa=pler and quickly adj ust the flow rate to the desired value (typically 5 cf=) .

5) For an H-809B, proceed as follows:

a) If an automobile is available, put the toggle switch on the

. black battery pack in EXT. Connect the red cable to the positivt terminal of the battery and the black cable to a c1 is round.

N0iE: Close ' the hood and place the air sa=pler on top of it to avoid engine fan turbulence. (

b) If an automobile is not available, put the toggle switch on the black battery pack in INT.

NOTE: The unit will not run using 120V AC, so do not sample ,

while charging.

c) Dial in the appropriate sampling time, using the toggle switches provided.

d) Turn on vehicle engine. Start the sa=pler and quickly adjust the flow rate to the desired value (typically 5 cf=) .

NOTE: The maxi =um flow rate is 'l cf= when the unit is using its own battery.

6) Periodically check the flow indicators to verify that the flow rate is being =aintained. If the flow rate changes significantly during sa=ple collection, note the value at the end of the sa=ple period and determine the average value of the flow rate. This average value should be used to dater =ine the size of the sa=ple collected.

7) Allow the sa=pler to run until at least 10 ft3 (but preferably 30-50 ft3) is collected. The greater the volu=e sa= pled, the better.

3) Stop the vehicle engine. Stop the sa=pler and re=cve the filter head.

NUMBER EP RB-8 DI ABLO CANYON POWER PLANT UNIT NO(S) " IV "" 0" 1 EMERGENCY OFFSITE RADIOLOGICAL E 1 8/82 TITLE ENVIRONMENTAL MONITORING

9) Make the halogen and particulate measurements discussed in steps 3 and 4 below, if desired.

10) Label the envelope and then place the particulate filter in the ^

coin envelope. _

11) Place the iodine cartridge in a sandwich bag and label the bag.

12) Enter the collection data in Section 4 of the Field Data sheet.

3. Determination of Gross Iodine (Field Technique)

a. Equipment Required

1) Eberline E-140 survey meter equipped with either an HP-240 standard GM probe, an HP-260 pancake GM probe, or an EP-210 shielded pancake GM probe. The HP-210 probe is preferred.

- 2) Cylinder of dry air equipped with regulator.

3) Plastic bag.

b. Procedure i

1) Remove the iodine cartridge from the air sa=pler head.

2) Insert the cartridge into the adapter sample head shown on Figure 6.

3) Attach the air cylinder to the filter head as shown in Figure 6 and gently blow air through the head in the reverse direction until the bottle pressure drops 200 psi. Set the air discharge pressure at about 5 psig. This removes noble gases from the halogen cartridge.

NOTE: Check the pressure in the air cylinder before starting to see if there is enough to pernit this operation.

4) Make a background count rate measurement using the GM prebe (window open when using the HP-240 probe) . When using the EP-210 or HP-260 probe, the reading is taken with the detector f aced down. Record value on Field Cata Sheet.

5) Place the probe (window open when using the HP-240 probe) directly adjacent to the upstream side of the cartridge, as shown in Figure 7, and measure and count rate. Get the probe as close to the cartridge as possible without actually touching (in order to avoid contaminating the probe).

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R EP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) R EVISION 1 EftERGENCY OFFSITE RADIOLOGICAL 1/28 /82 (Q/ TITLE ENVIRONMENTAL MONITORING DATE PAGE OF

6) Rccord the count rate in Section 5 of the Field Data Sheet. Note time sample was started and calibration due date of the instrument.

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7) Bag and label the cartridge.

8) Calculate gross iodine concentration from the following expression:

pC1/cc = ( * } ( net}

(c 2) (E ) (V) where:

CR = net cpm on cartridge c2 = probe ency from Table 8 E = cartridge collection efficiency, assumed to be 0.8 V = volu=e of airborne sample (ft 3)

9) Report gross iodine concentration, probe used, and volume of sample to the E=ergency Evaluations and Recovery Coordinator or the Radiological Monitor ng Diractor.

4. Determination of Gross Particulate (Field Technique)

a. Equipment Required

1) Eberline E-140 survey meter equipped with either an HP-240 standard GM probe, an HP-260 pancake GM probe, or an HP-210 shielded pancake GM probe.

2) Coin envel.p.

3) Forceps.

b. Procedure

1) Remove the filter from the air sampler head.

2) Make a background count rate measurement using the GM probe (window open when using the HP-240 probe), and record this value in the appropriate location in See:1on 6 of the Field Data Sheet.

'aten using the "-210 or HP-260 probe, the reading is taken with the detector faced down.

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NUMBER cf Ko-o fS1 REVISION 1 DIABLO CANYON EMERGENCY POWER PLANT OFFSITt QNIT N()ICnl RrDIOLub DATE 1/28 /82 ENVIRONMEf4TAL MONITORING TITLE PAGE 120F 39

3) Place the probe (window open using the HP-240 probe, shield up using HP-210 probe) directly adjacent to the upstream side of the filter in an analagous manner to the counting of halogen cartridges shown in Figure 7. Filters should b_e handled with forceps, and the probe should not touch the filter, in order to avoid contamination of the probe.

Note

4) Record the count rate in Section 6 of the Field Data Sheet.

time sa=ple was started and calibration due date of the in s t ru=ent .

5) Label the envelope and place the filter in the coin envelope, using the forceps.

6) Determine the net count rate and calculate the gross particulate activity from the expressien:

uCi/cc = (1.59x10ll) (CRnet) (6)

(c3) (Ef ) (V) where:

CR " "*

CP * "** **#

net c3 = probe efficiency frem Table 9 E = filter collection efficiency, assu=ed to be 0.9 f

V = volu=e of airborne sample (ft3 )

7) Report the activity, type of probe used, and volume of sample, to the E=ergency Evaluations and Recovery Coordinator or Radiological F.onitoring Director.

5. Soil and Vegetation Sa=pling

a. Equip =ent Required

1) Trowel.

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2) Scissors or 'mif e.

3) 18"x24" plastic bags.

4) Masking tape.

5) Labels.

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6) Eberline E-1!.0 survey =eter with HP-240 standard GM probe.

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NUM8ER EP RB-8' i DIABLO CANYON POWER PLANT UNIT NO(S) REvis ON 1 O

'O TITLE EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING DATE PAGE13 op 1/28'82 W '

b. Procedure

1) Vegetatio'. Sampling and Counting 2

a) Cut the vegetation from the appro'ximately T m of ground; the aim being to collect approximately one pound. Cut the vegetation at a height of 1-2 cm from top of vegetation to approximate what a grazing cnimal would consu=e. Do not contaminate the sa=ple with dirt.

b) Place the vegetation in the plastic bag. Compress the air out of the bag and seal with tape. One pound of material will fill the bag about half full.

c) Label the bag.

d) Make a background count (window open) and enter in Section 7 of the Field Data Sheet.

e) Flatten the bag and lay the probe on the center of the bag.

f) Fold the bag over the probe and note the reading. Record the reading on the field data sheet along with time of survey and instrument calibration due date, g) The activity level in pC1/gm can be obtained om the following expression:

pCi/gm = 2.5x10 6 x CRnet where:

CR = net epm on a standard GM tube (HP-240) h) Report the type of vegetation sampled and the activity level to the E=ergency Evaluations and Recovery Coordinator or the Radiological Monitoring Directcr.

2) Soil Sampling a) Sample the soil from about a m2 area. Remove only the top surf ace (to a depth of = 1/4" or- less) using the travel.

b) Place the sample in a bag, seal, and label.

' c) No field counting of soil samples is required. The samples are taken for follow-up analysis only. Scan the bag to determine if there is a high count rate (>1,000 cpm) .

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NUM8ER EP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY OFFS!TE RADIOLOGICAL DATE 1/28/82 TITLE ENVIRONMENTAL MONITORING PAGE la OF 39

6. Liquid Sampling and Counting

a. Equipment Raquired l

1) Sample bottle (1 liter) -

2) Labels.

3) Eberline E-140 survey meter equipped with HP-240 standard GM probe.

4) Sheet plastic or p. astic bag.

b. Procedure 1

1) Wrap the GM probe (vindow open) in thin plastic to protect.it against liquid damage and contamination.

2) I=merse the probe in as large a body of liquid as is a*ailable (reservoir, cattle trough, 10-gallon milk can, etc.) r obtain the gross open vindow reading. Enter the reading in Section 8 of the Field Data Sheet along with the time of survey and calibration due date of the instrument.

3) Use 60 cpm as a background count rate to determine the net count rate. ,

4) Report the type of sample, volume of sa=ple counted, and net count rate to the E=ergency Evaluations and Recovery Coordinator or Radiological Monitoring Director.

5) Collect the label a 1-liter sample and retain for later analysis.

7. Ground Survees

a. Equipment Required Eberline E-140 survey meter equipped with either an HP-240 standard l GM probe and HP-260 pancake GM probe, or an HP-210 shielded pancake GM probe. *he HP-210 is the preferred detector because its shield reduces the influence of sky shine.

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b. Procedure

1) Hold the GM probe, vindow open using HP-240 probe (shield up when using HP-210 probe) not more than two inches above the ground, and measure the count rate. The following precautions should be taken when making this =easurement, a) Make the measure =ent over short grass on undisturbed land (co'=en grazing , per=anent pasture).

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NUMBERcP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY OFFSITE RADIOLOGICAL oATg 1/28 /82 r~

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% 3) 'lTLE ENVIRONMENTAL MONITORING PAGE ) S op Lo b) Make the measure =ent at least 20 yards ~from any building, road, railway, bridge, or heaps of material such as gravel, rubble, or road-cut. These all contain varying amounts of natural uranium and thorium. _ ._

c) Haystacks or silos should be avoided because they may contain in a concentrated form the total deposition on grass which originally covered a large area. Trees and hedges also act as collectors of Callout which is washed out to a variable extent by rain. In an emergency, they may trap large amounts of airborne particulate and give a falsely high reading.

d) Care =ust be tr. ken to avoid any contamination of the instrument.

2) Identify the type of probe used and enter the data in Section 3 of the Field Data Sheet. Include the time the survey was started and the calibration due date of the inrtreme. t.

3) Calculate the net count rate value by subtracting the background value given in Table 7.

NOTE 1: It is not possible to correct the background values for i sky shine if an RP-240 or HP-260 is being used. Significant sky shine will invalidate ground surveys taken with these probes.

NOTE 2: If an HP-210 is being used, the effect cf sky shine can be estimated. To do this, take a second measurement with the GM window facing the sky (shield dcwn reading) . Then add 1/10 of this figure to the normal background frem Table 7 and use this sum as *he corrected background. That is:

(Bckg) Corrected " I

8) Table 5+0.10(CP.M) Sky (3) where :

(Bckg) Corrected = background corrected for sky shine (cpm) l (CFM) sky = gr ss epm with detector window facing upward

4) Calculate the ground depositien from the following equation:

Ground Deposition (uC1/=2) = c1 x CR ,g (4) ;

l where:

c1 = probe efficiency factor given in Table 10 i I

CR = net count rate (in epm) from ground survey net l \--]

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NUMBER EP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) REvistoN 1 EMERGENCY OFFSITE RADIOLOGICAL DATE 1/28/82 TITLE ENVIRONMENTAL MONITORING PAGE1 A OF to i

5) Report location of measure =ent, ground deposition, and the type of instru=ent used to the E=ergency Evaluations and Recovery Coordinator or Radiological Monitoring Director.

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Determination of Smearable Contamination 8.

a. Equip =ent Required

1) Two-inch diameter filters.

2) Coin envelopes.

3) Eberline E-140 survey meter equipped with an HP-240 Standard Probe, an HP-260 pancake probe , or an HP-210 shielded pancake GM probe.

b. Procedure Exa=ples

1) Select a representative smooth surface to s sar-test.

are tops of cars, store windows or sills, c. valls of buildings.

2) Wipe the area with the side opposite from the backing, using a uniform, moderate fingertip pressure. Esti= ate the total area smeared, in square feet.

3) Take a background count rate measure =ent and then a count of the filter. Enter the data in Section 9 of the Field Data Sheet along with the ti=e of the survey and the calibration due date of the instru=ent.

4) Put the filter Lato a labeled coin envelope and save it for later analysis in the counting room.

5) Calculate the s=earable contamination as follows:

(0.11) (CR )

dpm/dm2 not (c3) A whe re :

CR , = net cps on filter c 3 = probe ef ficiency f actor f rom Table 9 A = area s= eared, in square feet

6) Report the type of surf ace smeared, instru=ent used, and the smearable contamination level to the E=ergency Ivaluations and Recovery Coordinator or Radiological Monitoring Direc cr.

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I NUM8ER EP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) " 'Y"" 0" 3

^

EMERGENCY OFFSITE RADIOLOGICAL DATE 1/23/82

-) TITLE ENVIRONMENTAL MONITORING PAGE 170F 30

9. How to Read the TASC-4 '

NOTE: For purposes of emergency =onitoring standardize the scaler-timer by using a ten-second count. -

a. On the NT-29 timer, set ten-seconds.

1) The top thunbwheel is set at 1; the middle and lower ones are set at 0 (i.e., a reading of 1.00).

2) The NEN-SEC toggle switch is set in SEC.

3' The RANGE MULTIPLIER is set at X10.

b. On the NS-12 scaler, set the TEST / SCALER toggle switch to SCALER.

c. Press the STOP pushbutton, then press the RESET pushiutton (*.he RESET pushbutton should never be depressed while counts are being oplied to the register; first stop the count by pressing the STOP pushbutton).

d. Press the START pushbutton to start a count.

e. Set the PRESET rotary switch to the OFF position.

f. The scaler will begin to accu =ulate counts and will continue doing so l until the preset ti=e period has elapsed. At this point, counting will auto =atically stop.

g. The dose rate is determined from the following expression:

' ( ta e unts) l DR (uR/hr) = (counting ette in seconds)

For a ten-second count, this becomes:

DR (pR/hr) = (* **10

h. Report dese rate to the Emergency Evaluations and Recovery Coordir.ator or Radiological Monitoring Director.

FIGURES

1. Onsite assenbly and Monitoring Locations.

2. Emergency Offsite Monitoring Locations.

3. Locations of DER Onsite Enviro == ental Sa=pling and Monitoring Locations.

bV

- NUMBER EP RS-8 DI ABLO CANYON POWER PLANT UNIT NO(S) REVislON 1 EMERGENCY OFFSITE RADIOLOGICAL DATE 1/28/82 TITLE ENVIRONMENTAL MONITCRING 18g 39

4. Locations of DER Of f site Environ = ental Sampling and Monitoring Locations.

5. Exploded View of Halogen Cartridge and Particulate Filter in Sa=pling Head. -

6. Method for Blowing Noble Gases fro = Halogen Cartridge.

7. Position of GM Tube and Cartridge for Gross Iodine Deter =ination, l

TABLES

1. Description of E=ergency Onsite Monitoring Locations.

2. Description of E=ergency Offsite Monitoring Locations.

3. DER Environ = ental Sa=pling Locations.

4. Environ = ental Radiation Monitoring Network Station of the NRC. 6

5. Locations of Selected Dairies.

I

. 6. Plc Locations.

1

7. Backgr.ound Data for S/ r Dose and/or Count Rate Measurenents.

8. GM Probe Ef ficiency Factors for Iodine Determinations.

1

0. GM Probe Efficiency Factors for Particulate Deter =inations.

10. GM Probe Efficiency Factors for Ground Surveys.

l ATTACHMENTS l

1. For= 09-9259, "E=ergency Environ = ental Monitoring Field Data Sheat."

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DIABLO CANYON POWER PLANT UNIT NO(S) REvlsioN 1 O TITLE EMERGENCY OFFSITE RADIOLOGICAL ENVIRONf1 ENTAL MONITORING DATE 1/28/82 PAGE23 OF 39 FIGURE 5 EXPLODED VIEW OF HALOGEN CARTRIDGE AND PARTICULATE FILTER IN SAMPLING HEAD

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NUMBER EP RS-8 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY OFFSITE RADIOLOGICAL DATE 1/25/82 TITLE ENVIRONMENTAL f10 NIT 041Nr' PAGE24 OF 39 FIG'JRE 6 METHOD FOR BLOWING NOBLE GASES FROM HALOGEN CARTRIDGE

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NUMBER tr no-o DIABLO CANYGN POWER PLANT UNIT NO(S) REVislON 1 EMERGEtiCY OFFSITE RADIOLOGICAL DATE 1/28 /82 TITLE EtiVIR0tiMEt4TAL M0?lITORING PAGE,c OF 1o FIGURE 7 POSITION OF GM TUBE A'ID CARTRIDGE FOR GROSS IODI"E DETERMINATION tCTECTC9- g DETECTCR 7

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NUMBER EP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY OFFSITE RADIOLOGICAL DATE 1/28/82 TITLE ENVIRONMENTAL _ MONITORING p 26 op 39 TABLE 1 DESCRIPTION OF EMERGENCY ONSITE MONITORING LOCATIONS Straight Line AC Power Distance From Available Plant (Meters) Description Coordinate South side of road No N,A 300 In front of wooden No N,NE,A 700 water tank Adjacent to cast Yes NE,A 300 rese rvoir North side of wood in No N'E , B 800 the gulley South side of switch- No ENE,A 700 yard at fence Air sampler-behind Yes SE,C 700 forth side of GC warehouse Front of GC warehouse Yes SE,B 800 SE,A 800 40 feet off the road No on the west side of road - no accessible by vehicle Adjacent to guard Yes SSE,A 700 shade on bluff Adjacent to culvert on No SSE,3 700 west side of dirt road West of sandblasting No SSE,C 700 area On breakwater No S.A On breakwater No S,3 West o f =e t tower - No SSW,A 400 requires key for gate - not accessible by vehicle

1 NUMBER EP RB-8 I DIABLO CANYON POWER PLANT UNIT NO(S) REVislON 1

/\ EMERGENCY OFFSITE RADIOLOGICAL DATE 1/ 28/~29' (s / TITLE ENVIRONMENTAL MONITORING p 27ap 39 TABLE 1 (Continued)

Straight Line

~ "

Distance From AC Power Coordinate Plant (Meters) De sc ript ion Avrilable SSW,3 On breakwater No SSW,C on breakwater No SW.A 500 West of met tower - Yes requires key for gate - not accessible by vehicle WNW,A 500 Near gulley on south No side - requires -

key for gate ,

l WNW,B 600 40 feet in f ront gate - No

, requires key WNW,C 600 North side of road in No clearing NW,A 600 North side of road in No clearing area of bushes NW,3 600 Northwest side of dirt No road NW,C 800 At gate on road No leading to north road NNW.A 800 30 feet north of steps No leading to pond l

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NUMBER EP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 EMERGENCY OFFSITE PJJ)IOLOGICAL DATE 1/23/82 TITLE M IRO N AL MONITORING PAGE23 OF 39 TABLE 2 DESCRIPTION OF EMERGENCY OFF-SITE MONITORING LOCATIONS Staight Line AC Power Distance From Plant (KM) Description' Available Coordinate West of Montana de Oro State No N 10,A 9.8 Park sign (0.6 =11es SW of Rodman Drive on Pechc Road.

Good radio at path off road south of State Park sign.

Sign on path reads "No Vehicles".

l End of Ala=o Drive in Cabrillo Yes N 15,A 10.0 Estates. (Turn off Pecho Road at Rod =an and go to the top of the hill. Turn right onto r Alamo and folicw it to the end.)

Good radio. Phone available.

Sunset Terrance Golf Course Yes 2 N,15,3 11.6 at clubhouse. Good radio at west end of Howard Drive or on road running t.crth of the golf course.

Baywood Park Fire Station Yes N,15,C 11.3 (Turn south off of Los Osos Road onto Bayview Meights Drive.

Has a TASC-4 DER's =enitoring Station 10 is located at Sunny-

side School next door.) Good radio. Phone available.

Morro Bay Power Plant. DER's Yes N,20,A 18.0

=onitoring Station 9 is located here. Good radio. Phone r available.

NUMBER EP RB-8 h DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1

(,)

(~~x TITLE EMERGENCY OFFSITE RADIOLOGICAL ENvio0N' DENTAL MONITORING DATE 1/28/82 PAGE 290F 39 TABLE 2 (Continued)

Straight Line ~

Distance From AC Power Coordinate Plant (KM) Description Available NNE.15,A 11.3 Intersection of Los Osos No Valley Road and Clark Valley Road (under PG&E transmission lines) .

Good radio.

NNE 15,B 12.9 Los Osos Jr. High School No on South Bay Boulevard in the playing field.

" Good radio.

NNT 10,A 17.6 0.2 miles north along No San Bernardo Creek Road is on the northeast side of Highway 1.

Good radio.

NE .15, A 10.6 Intersection of Los Osos No Valley Road and Turri I

Road. DER's monitoring Station 11 is located

' ' nearby. Good radio at intersection.

NE,20,A 17.4 Sheriff's headquarters. (EOF) Yes Turn south on Highway 1

( at sign . indicating I

I Sheriff's Operational Center. Good radio.

Phone available.

NE,20,B 19.2 PG&E substation near Yes Men's Colony, adjacent to northeast side of High 1. Good radio.

Phone available.

O 1

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NUMBER EP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY OFFSITE RADIOLOGICAL DATE 1/28/82 TITLE ENVIRONMENTAL MONITORING PAGE 300F 39

=r -r TABLE 2 (Continued)

Straight Line ~

Distance From AC Power Coordinate Plant (K:O Descriptien Available ENE,8,A 9.0 See Canyon Road, 4.2 Yesl miles up from San Luis Bay Drive intersection.

I Good radio.

Telephone available.

Rattlesnake hazard.

14.8 Laguna Jr. High School Yes3 ENE,20,A at intersection of Los Osos Road and Perfu=o Canyon Road. Good radio.

16.0 Fire station at inter- Yes ENE,20,B section of Los Osos Valley and Madonna Roads. Good radio.

18.6 PG&E Information Zone 1 Yes E::E ,20,C substation at corner of Walker and Pacific Streets. DER's Station 12 is also located here.

Good radio.

ENE,20,D 15.6 Corner of Foothill Yes!

Boulevard and O' Conner Way. Good radio.

1 15.8 Yancy's Restaurant (for=eriy Yes2 i ENE,20,E Hob Nob) parking lot. Good l

L radio.

I ~ i 14.5 PG&E Infor=ation Center Yes

. E,15,A l Good radio, r

13.4 Bellevue-Santa Fe School. Yes5 E .15 ,3 Goed radio.

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NUM8ER EP RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY OFFSITE RADIOLOGICAL f_3 s- / TITLE EN'/IRONMENTAL MONITORING DATE 1/28/82 PAGE31 OF y9 TABLE 2 (Continued)

Straight Line .

~

Distance Frem AC Power Coordinate Plant (KM) Descriptien Available E.15,C 11.3 See Canyon Road, 1.7 Yesl miles up from San Luis Bay Drive intersection.

Survey at intersection of See Canyon Raad and Davis Cany6n Road. Good .

P radio.

E,23,A 20.2 SLO County Airport. The Yes field on the right of the road to the parking lot. Good radio.

. E 25,3 21.5 SLO Country Club. East Yes2 side of parking lot in ;

the fairway. Good radio.

ESE,4,A 2.6 Turnout on access road, No 1.6 miles from Security Build ing. Marked with red / white fence post.

Radio near plant or near location ESE.10,A ESE,6,A 4.5 No u ou on access road mi5esfromSecurity Building. Marked with a

red / white fence post. Radio near plant or near location ESE.10,A.

6.9 Cate next to shack at No ESE S.A road to ruins, 4.3 miles from Security Building along access road. <

Marked with red / white fence post. DER station 16 is near here. oa dio near plant or near location ESE.10,A ESE,10,A 9.6 Top of San Luis Hills, yo s

Gate at 6.2 miles from I the Security Building.

\m / t Some radio.

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NUMBER EP RB-8 DIABLO Ct.NYON POWER PLANT UNIT NOIS) " I# 0" 1 EMERGENCY OFFSITE RADIOLOGICAL DATE 1/28/82 TITLE ENVIRONMENTAL fiONITORING PAGE32 or M

/

TABLE 2 (Continued)

Straight Line Distance From

- AC Power Coordinate Plant (!CO Descrietion Available ESE 10,3 10.0 Port San Luis Cate. Ies TASC-4 and DER's Station 27 are located here. Radio

( on road to Pirates Cove.

ESE,15,A 11.6 Parking lot behind Avila Yes Beach Post Office. Radio i on road to Pirates Cove.

ESE,'.0,A 15.3 Pismo Beach Fir Dept. Ys:

on Shell Beach Road.

F Good radio.

ESE,20,3 19.2 0.5 miles northwest of Yes1 the Shorecliff Inn on Shell Beach Road. Good f radio.

1.3 Turnout on access road, No SE,2,A '

O.8 miles from Security Building near metee-rological Tower A.

Marked with red / white fence post. DER Station 7 is near here. Good radio.

NW,2,A 1.6 0.6 miles north from No Field's property gate (1 mile north from plant, just ENE of Lion Rock).

Fields' road near large No

N,4,A 3.5 watering pond.

6.1 Near residence by park Yes I

G.S.A gate.

l N'N ,4 , A 2.7 Near wood paneled house. Yes1 l

NUMBER EP RS-5 DIABLO CANYON POWER PLANT UNIT NO(S) RE M ON 1 EMERGENCY OFFSITE RADIOLOGICAL T

('m TITLE ENVIRONMENTAL MONITORING p cE 330 , 3h TABLE 2 (Continued)

Straight Line Distance From AC Power Plant (01) Description Available Coordinate N:.J,8,A 5.8 Parking lot near end of No 6 road at southern park, boundary (near gate to

- Fields' property). Good I radio.

:.'J ,8 ,3 7.6 Ranger station over- Yes 7 looking Spooner's Cove.

Good radio on road south of Ranger Station at " Locked Cate Ahead" sign (near parking over-look of Spooner's Cove).

NOTES:

IPower is available at nearby residences.

2 During working hours. Also power is available at nearby re'sidences.

3 During school hours. Also at nearby residences.

"During school hours.

5A dirt road leads to the top of the hill. The intersection of this road with access road is marked with a red / white fence post. A 90909 key is required on the gate. A four-wheal drive vehicle is preferred. Alternatively; take readings on the access road at the marked fence post.

6Pos er is available at nearby residence on Fields' property (NW,8, A) and monitoring can be performed at this latter location.

7 During daylight hours.

l'Radiococ:mentsrefertounaidedhandi-talkiesuseofDavisPeakrepeater(H.P.

j Frequency) only - other transmitter sites not considered.

b) l V

NUMBER EP,RB-8 DIABLO CANYON POWER PLANT UNIT NO(S) REvisicn 1 Ef1ERGENCY OFFSITE RADIOLOGICAL

DATE 1/ 28/82 ENVIRONMENTAL MONITORING TITLE PAGE3a CF Jo TABLE 3 DER ENVIRONM ETAL SAMPLING LOCATIONS Radici Rstia. Distance Cede Descriotion Directi:- ~ (Miles) 325 3.6 031 Point Buchon (Streion ]S) - - - - - - - - - - - - -- 320 0.1 051 Exclusion Fence-Northwest Corner (Statien 3) 320 0.5 052 North Gate (Station 31) - - - - - - - - - - - - - 327 1.6 1A1 Crowbar Canyon (Station 13) - - - - - - - - - - - 4.7 Montana de Oro Ca=pground (Station 38) --- - 336 1C1 0.4 330 151 Wastewater Pond (Station 32) ---------- 10 6.9 2D1 Sunnyside School (Station 10) - - - - ----- ------ 0 10.9 l 2F1 Morro Bay (Station 26) ---- --

11.2 Moor Bay Power Plant (Station 9) -------- 353 2F2 0.2 0

251 Back Road-300 m North of Plant (Station 33) - - - 24 6.2 3D1 Clark Valley (Station 40) - - - - - - - - - - - -

Road NW of 230 kv Switchyard (Station 34) - - - - 23 0.4 3S1 5.8 Clark Valley - Gravel Pit - - - - - - - - - - - - 45 4C1 7.6 36 4D1 Los Osos School (Station 11) ---------- 43 0.5 4S1 Back Road Between Switchyards (Station 35) ---

Junction Perfuco/See Canyon Roads (Station 39) - 64 4.7 SC1 11.2 68 5F1 SLO Zone 1 Substation (Station 12) ------- 60 12.6 SF2 Cal Poly Farm (Station 25) ----------- 12.7 SLO County Health Department (Station 29) - - - - 70 l 5F3 0.4 400 kv Switchyard (Station 4) - - - - - - - - - - 58 551 0.6

65 5S2 Diablo Creek Weir (Station 20) 70 0.7 5S3 Microwave Tower Road (Station 8) -------- 89 7.5 6D1 Junction See/ Davis Canyon Roads (Station 41) --

94 0.5 6S1 Microwave Tower (5tatica 5) -------------------- 118 4.1

) 7C1 Pecho Creek Ruins (Station 16) 120 6.6

! 7D1 Avila Gate (Station 27)------------

110 7.6 7D2 Avila Beach (Station 14) 10.8 110 7F1 Shell Beach (Station 17) ------------ 115 12.6 7F2 Pismo Beach (Station 22) ------------ 16.8 l Arroyo Grande (Station 23) ----------- 115 7G1 1

118 17.3

! 7G2 Oceano Substation (Station 15) --------- 122 17.9 7G3 Woodland Dairy (Station 30) - - - - - - - - - - -

112 0.3 751 Overlook Road (Station 36) ----------- 103 1.1 7S2 Diablo Peak (Station 28) ------------ 125 0.5 SSI Target Range (Station 6) ------------ 1.1 Southwest Site Boundary (Station 7) - - - - - - - 128 8S2 0.4 167 l 951 South Cove (Station 37) - - - - - - - - - - - - - ---- 270 0.1 DCC Diablo Creek at Diablo Cove (Station 21) ----- 270 0.2 DCM Diablo Cove (Station 19) ----------------- 0 0.0 l ICO Iodine Cartridge Composite 4;,5

. ----- 134 Lo Lompoc --

Meteorological Tcwer (Station 1) -------- 185 0.2 MT1 29.7

- - - - - - - - - - - - - - - - - - 127 1 SM Santa Maria 56.7

- 144 SV Solvang - -

WN1 Northwest Guard- -Shack

- - -(Station

- - - 2) ------ - 290 0.2

NUMBER cf "D*C DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1

's EMERGENCY OFFSITE RADIOLOGICAL DATE 1/28/82 s ,/ TITLE envionNurNTM MONITODING PAGE 3bF 39 TABLE 4_

ENVIRONMENTAL RADIATION MONITORING NEL*0PX STATION OF THE NUCLEAR REGULATORY CotCIISSION SECTOR AZIMUTH ZE"ITH DESCRIPTION NRC STATION NO.

1 SE 125* 1.0 mi. Site entrance road 2 ESE 119' 4.2 mi. Site entrance road ESE 107* 6.9 mi. San Miguel Street, 3

Avila Beach 4 ESE 109* 10.6 mi. Corner of Nacci Avenue and Seacliff Drive Sunset Palisades area 5 ESE 113* 14.1 mi. Corner of Atlantic City Avenue and Front Street, Grover City 6 ENE 68* 9.6 mi. Parfumo Canycn Road, Laguna Lake Park Area 7 N 359' 11.1 mi. PG&E Morro Bay Power

' Plant 8 N 359' 6.6 mi. Pecho Valley Road, Cuesta by the Sea Area 9 NNW 339' 4.7 mi. Montana De Oro State Park 10 NNW 328' 3.5 mi. Private Property Road at end of Pecho Valley Road 11 NNW 332* 1.3 mi. Private Property Road North of Diablo Canyon Plant 12 NE 37* 21.4 mi. -San Diego Road, Atascadero 13 NE 37* 21.4 mi. San Diego Road, Atascadero 14 NE 37* 21.4 mi. San Diego Road, t.tascadero O

NUMBER cr 50-0 DIABLO CANYON POWER PLANT UNIT NO(S) " "

EMERGENCY OFFSITE RADIOLOGICAL DATE 1/28 /82 TITLE EN'/IRONMENTAL MONITORING PAGE36 or 39 TABEL 5 LOCATIONS OF SELECTED DAIRIES DAIRY HERD ' LOCATIC:* 5 ELATIVE TO OCPP L.F. Domenghini (500 cows) NNE, 12.5 niles

NE, 11 miles Roe =er and Jones (200 cows) NE, 8 miles Dutch Maid Farm (100 cows)

NE, 8 =iles Don 'Jarden (200 cows) E, 9.5 miles Jim Spreafico (150 cows)

SLO Cal Poly Fars ENE, 10 miles SE, 23.5 miles (Guadalupe)

Albertoni Farm l

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1 NUMBER gp pg_g l DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 EMERGENCY OFFSITE RADIOLOGICAL I oATE 5/ 2E/82 TITLE ENVIRONMENTAL f1CNITORING ,o P< AGE 370F TABLE 6 PIC LOCATIONS

'~

. LOCATICS DESCRIPTION Site 1 DCPP North Gate Guard Post.

Site 2 SSW corner of Target Range.

Site 3 715 Harbor Street, Morro Bay. Small fenced yard on NE corner of Earbor Street and Piney Street intersection.

Site 4 SLC County Sheriff's Office. South of EOF trailer behind retaining wall.

Sitn 5 SLO Police Departnent. Intersection of Santa Rosa Street and Walnut Street. Behind fe. TJ 'f Walnut Street driveway.

Site 6 SLO County Airport on HWY 227. At southern most co rner inside fenced airport annex area.

Site 7 PG&E Energy Inf or=ation Center. Take San Luis Bay Drive exit I. from U.S. 101. On hill above employee parking lot.

Site 8 Pismo Beach. From Bello Street go NE ento Main Street. Turn right at first road to the water storage tank. On top of hill N of pu=p house and W of water storage tank.

Site 9 SLO County Building, Grover City. SW corner of SLO County Social Services Building on Longbranch Street, Grover City, i

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NUMBER t r' KD-c f DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 E!1ERGENCY OFFSITE RADIOLOGICAL DATE 1/28/82 TITLE ENv i o0NMENT3.'_ MONITORING PAGE 3 EOF 39 TABLE 7_

BACKGR012.'D DATA FOR S/y DOSE AND/OR COUNT PATE MEASUREMENTS (3' ABOVE GROUND)

BACKGROL*SD OOSE RATE ( R/hr)

'JINDC'J CLOSED 'J:::D0'4 0?II:

t INSTRCfENT 0 0 Rad Owl 0.02

'lictcreen Radgun 0.02 RPI-1010 0.015 NA BACKGR0triD COUNT RATE (com)

SHIELD ON SHIELD OFF GM PROBE 60 60 HP-240 NA 50 HP-260 NA 50 HP-210

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NUMBER r.r no-o DIABLO CANYON POWER PLANT UNIT NOIS) REVISION 1 EMERGENCY OFFSITE RADIOLOGICAL DATE 1/28/82

) TITLE _ rNyTDONMENTAL MONITORING PAGE 390F 39 TABLE 8 -

G:t PROBE EFFICIENCY FACTORS, ts, FOR IODINE DETEPl!INATIONS C't PROSE c2 (count s /eis)

HP-240 0.013 F.P-260 0.09 HP-210 0.09 TABLE 9 GM PROBE EFFICIENCY FACTORS, c3. FOR PARTICULATE DETERMINATIONS CM PROBE c3 (counts / dis)

FP-240 0.018 HP-260 0.20 HP-210 0.18

(

TABLE 10 GM PROBE EFFICIENCY FACTORS. ci. FOR GROUND SURVEYS l

(C1/m2 /com)

GM PROBE ct HP-240 0.0041 HP-260 0.0012 l HP-280 0.0011 l l

1 l

C' l l

. 69-92S9 Rev. 6/81 (100;) Page 1 of 2

- DEPARTAENT OF NUCLEAR PLAfiT OPERATIONS DIABLO CANYON POWER PLANT EMERGENCY E.!VIPONMENTAL MONITORING FIELO DATA SHEET TEAM LEADER MEMBER MONITORING LOCATION

1. TASC-4 READING CAL DUE SCALER COUNT ; COUNT TIME SEC; DR(uR/hr)=(CDUNTS) (SECONDS) =

2. PIC READING CAL DUE DOSERATE(pRfhr)

3. BETA / GAMMA RADIATION FIELD MEASUREViHIS

a. DOSE RATE CAL DUE TIME OF SURVEY mR/hr (WINDOW OPEN) mR/hr (WINDOW CLOSED)

BCKG* NET GROSS NET INSTRUMENT GROSS _9CXG*

b. COUNT RATE CAL DUE TIME OF SURVEY

( cpm (SHIELD OFF) cpm (SHIELD ON)

TYPE 0F PROBE GROSS BCXG* .

NET ,_ GROSS BCXG* NET

c. INTECRAL DOSE g g g g g; DURATION DOSE RATE (HOURS) TOTAL DOSE (mr/hr)

INSTRUMEhi 'S ED CO . TED (mR) @ @

4. GROUND SURVEYS CAL DUE TIME @ @

(pCi/cm2) com (SHIELD OFF)

DESCRIPTION 0F LOCATION TYPE OF PROBE GROSS ~ BCXG* NET (I) Cl* *h

3. AIR SAMPLE DATA TIME TIME DURATION FLOW RATE SAMPLE VCL SAMPLER STARTED CCMPLETED (MINUTES) (CFM) (FT3)

'ueeri:al value found in E=ergency ? :cedure ?2 ' and 73-5.

Page 2 of 2 69 9259 Rev. 6/81 ,

CAL DUE @ @ @ (uCi/ml) ( )

6. IODINE DETERMINATION con (SHIELD OFF)

TYPE BCKG NET @ _

C2* Ec*

VOLU"':

(ft )

3 b*b*b OF PROBE GROSS g (C/

7.

PARTICULATE DETERMINATION CAL DUE g,g

OF R BE GROSS com (SHIELD OFF)

BCKG NETg c3* E* f fftf U

@x@x@

TINE OF SURVEY . _ _

CAL DUE

8. VEGETATION SAMPLES com (SHIELD OFF) (uCi/gm)7) x(.x0 GROSS BCKG NET (Y)

SAMPLE DESCRIPTION 1 -_.

TIME OF SURVEY 9: LIQUID SAMPLES CAL DUE _

! IW.ERSION DATA VOLUME OF NET CPM SAMPLE COUNTED _ GROSS CPM _. BCKS*

! SAMPLE DESCRIPTION _ __

10. SMEAR SAMPLES l

@ (dpm/dm2 )

CAL DUE AREA (0.11)x(Il TIME OF SAMPLE -

com (SHIELD OFF) SPIARED NET (I) 53* ( f tz)_ @X@ __

GROSS BCXG _

SAMPLE DESCRIPTION --

I

11. MISCELLANEOUS REMARKS l

O 1

CURRENT EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3A TITLE REV OP-0 Reactor Trip With Safety Injection 2 OP-1 Loss of Coolant Accident 4 OP-2 Loss of Secondary Coolant 1 OP-3A Steam Gen Tube Failure 3 OP-3B Minor Steam Gen Tube Failure 0 OP-4 Loss of Electrical Power 3 OP-5 Reactor Trip Without Safety Injection 4 OP-6 Emergency Boration 5 OP-7 Loss of Condenser Yacuun 1 OP-8 Control Room Inaccessibility 4 OP-9 Loss of Reactor Coolant Pump 2 OP-10 Loss of Auxiliary Salt Water 1 OP-ll Loss of Component Cooling Water 2 OP-12 11alfunction of Auto Reactor Control System 1 OP-12A Failure of a Control Bk to fbve in Auto 1 OP-128 Cont Withdrawal of a Control Rod Bank 2 OP-12C Cont Insertion of a Control Rod Bank 1 OP-12D Control Rod Pos Indication Sys Malfunc 2 OP-12E Control Rod Misalignment 2 OP-12F Dropped Control Rod 2 OP-13 Malfunction of Reactor Press Control System 1 OP-14 High Activity in Reactor Coolant 1 OP-15 Loss of Feedwater 4 OP-16 Nuclear Instrumentation fialfunctions 2 OP-17 Malfunction of RHR System 1 OP-18 Charging or Letdown Line Failure 2 OP-19 Malfunction of Reactor Makeup Control 2 OP-20 Excessive Reactor Coolant System Leakage 2 l

l l

l O

5077A

O TITLE REV OP-21 Loss of A Coolant Loop RTD 1 OP-22 Emergency Shutdown 0 OP-23 Natural Circulation of Reactor Coolant 1 OP-24 Loss of Containment 2:tegrity 1 OP-25 Tank Ruptures 0 OP-26 Excessive Feedwater Flow 0 OP-27 Irradiated Fuel Damage 0 OP-28 Startup of an Inactive Reactor Coolant Loop 0 OP-29 Excessive Load Increase 0 OP-30 Inadvertent Load Fuel Assly Improper Pos 1 OP-31 System Under Frequency 0 OP-32 Rod Ejection 1 OP-33 Loss of Instrument Air 1 OP-34 Generator Trip - Full Load Rejection 0 OP-35 Loss of Vital or Non-Vital Instr AC Sys 1 OP-36 Turbine Trip 0 OP-37 Loss of Protection System Channel 0

, OP-38 Anticipated Transient Without Trip (ATWT) 2 OP-39 RCP Locked Rotor Accident 1 OP-40 Accidental Depressurization of MS System 0 OP-41 Hydrogen " Explosion" Inside Containment 0 OP-44 Gaseous Voids in the RCS 2 R-1 Per Injury (Rad Related) And/Or Overexp 5 R-2 Rel of Airborne Radioactive Materials 3 R-3 Rei of Radioactive Liquids 3 R-4 High External Radiation 3 R-5 Radioactive Liquid Spill 3 R-6 Radiological Fire 5 R-7 Transportation Accidents 2 M-1 Employee Injury (Nonradiological) 5 M-2 Injury to Noneaployee (Third Party) 4 H-3 Chlorine Release 3 H-4 Earthquake 6 M-5 Tsunami Warning 3 M-6 Honradiological Fire 6 M-7 Oil Spill ISO and Clean Up Procedure 3 O

5077A

1 i

!O i

TITLE REY

{

G-1 Emergency Classification and Emergency Plan i Activation 2 G-2 Establishment of the On-Site Emergency

]

Organization 0 ,

{ G-3 Notification of Off-Site Organizations 0 t i G-4 Personnel Accountability and Assembly 1 l G-5 Evacuation of Nonessential Site Personnel 0 1

i i

r L

i i

l l

l 1

'O

.i i 5077A

1 i

CURRENT Ef1ERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Yolume 3B TITLE REY OR-1 Offsite Support & Assistance Not Issued OR-2 Release of Information to the Public 0 EF-1 Activation of the Technical Support Center 0 EF-2 Activation of the Operational Support Center 0 EF-3 Activation of the Emergency Operations Facility 0 EF-4 Activation of MEML 0 EF-5 Emergency Equipment, Instruments & Supplies 0 3

EF-6 Activation of the Emergency Assessment and Response System 0 EF-7 Activation of the Nuclear Data Communications Systems O RB-1 Personnel Dosimetry Not Issued RB-2 Emergency Exposure Guides O RB-3 . Stable Iodine Thyroid Blocking 0 RB-4 Access to & Establishment of Controlled Areas Under Emergency 0 RB-5 Personnel Decontamination 0 RB-6 Area & Equipment Decontamination 0 RB-7 Emergency On-Site Radiological Environmental Monitoring 1 RB-8 Emergency Off-Site Radiological Environmental Monitoring 1 RB-9 Calculation of Release Rate & Integrated Release O RB-10 Protective Action Guidelines 0 RB-ll Emergency Off-Site Dose Calculations 0 RB-12 Mid and High Range Plant Vent Radiation Montf ors 0 RB-13

proved In-Plant Air Sampling for Radiciodines 0 5077A

ML20049J002

Text

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