Text

Units I and 2 - Emergency Plan Implementing Procedure Update
	ML003757955
Person / Time
Site:	Diablo Canyon
Issue date:	09/29/2000
From:	Becker J; Pacific Gas & Electric Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	-RFPFR, DCL-00-124, GL-81-027
	Download: ML003757955 (146)
	v • d • e

Pacific Gas and Electric Company Cian o Canyon Power Plant P 0 Box 56 Avila Beach, CA 93424 805/545-6000 September 29, 2000 PG&E Letter DCL-00-124 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units I and 2 Emergency Plan Implementing Procedure Update

Dear Commissioners and Staff:

In accordance with Section V, "Implementing Procedures," of 10 CFR 50, Appendix E, enclosed is an update to the emergency plan implementing procedures for Diablo Canyon Power Plant, Units 1 and 2.

As provided under 10 CFR 50.54(q), the changes in this update do not decrease the effectiveness of the emergency plan and, therefore have been made without prior NRC approval. The plan, as changed, continues to meet the standards of 10 CFR 50.47(b) and 10 CFR 50, Appendix E.

This update contains privacy/proprietary information that has been bracketed in accordance with NRC Generic Letter 81-27.

Ifthere are any questions regarding this update, please contact Mr. Mark Lemke of my staff at (805) 545-4787.

Sincerely, James R. er Manager - Operations Sen Enclosures

Document Control Desk PG&E Letter DCL-00-1 24 September 29, 2000 Page 2 cc: Steven D. Bloom Ellis W. Merschoff - wla (2)

David L. Proulx DDM/1345

Enclosure 1 PG&E Letter DCL-00-124 LOCATION OF PRIVACYIPROPRIETARY INFORMATION IN EMERGENCY PLAN IMPLEMENTING PROCEDURES FOR DIABLO CANYON POWER PLANT, UNITS 1 AND 2 Privacy/

Procedure Proprietary Number Information Title/Location of Privacy/Proprietary Information EP G-1 No Emergency Classification and Emergency Plan Revision 29 Activation EP G-2 No Activation and Operation of the Interim Site On The Spot Emergency Organization Change 8/30 EP G-4 Yes Personnel Assembly, Accountability and Site Revision 17 Access Control During Emergencies Page 11, 13, and 14 Page 1 of Attachments 9.3, 9.4, 9.5, 9.6, and 9.7 EP RB-8 Yes Instructions for Field Monitoring Teams Revision 13 Page 3 Page 1 of Attachment 7.6 EP RB-12 No Plant Vent Iodine and Particulate Sampling During Revision 6 Accident Conditions EP EF-2 Yes Activation and Operation of the Operational Revision 24 Support Center Page 1 of Attachment 6.8 EP EF-9 No Backup Emergency Response Facilities Revision 7 1

Enclosure 2 PG&E Letter DCL-00-124 DIABLO CANYON POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Table of Contents - Emergency Plan Implementing Procedures Volume 1A (OM10.1D3 only), Volume 1B (OM10.DC1 only), and Volume 3B Proc. No. Rev. Title OM10.1D3 6 Emergency Plan Training OM10.DC1 1B Emergency Preparedness Drills and Exercises EP G-1* 29 Emergency Classification and Emergency Plan Activation EP G-2* 21 Activation and Operation of the Interim Site Emergency OTSC Organization (Control Room)

EP G-3 33XPR Notification of Off-Site Agencies and Emergency Response Organization Personnel EP G-4* 17 Personnel Assembly, Accountability and Site Access Control During Emergencies EP G-5 8 Evacuation of Nonessential Site Personnel EP R-2 19C Release of Airborne Radioactive Materials Initial Assessment EP R-3 88 Release of Radioactive Liquids EP R-7 13 Off-Site Transportation Accidents EP OR-3 6 Emergency Recovery EP RB-1 5B Personnel Dosimetry EP RB-2 4B Emergency Exposure Guides EP RB-3 4 Stable Iodine Thyroid Blocking EP RB-4 4A Access to and Establishment of Controlled Areas Under Emergency Conditions EP RB-5 4C Personnel Decontamination EP RB-8* 13 Instructions for Field Monitoring Teams EP RB-9 11 Calculation of Release Rate EP RB-10 7 Protective Action Recommendations EP RB-11 11C Emergency Offsite Dose Calculations EP RB-12* 6 Plant Vent Iodine and Particulate Sampling During Accident Conditions EP RB-13** Rescinded EP RB-14 5B Core Damage Assessment Procedure EP RB-15 8 Post Accident Sampling System EP EF-1 24 Activation and Operation of the Technical Support Center EP EF-2* 24 Activation and Operation of the Operational Support Center EP EF-3 16XPR Activation and Operation of the Emergency Operations Facility EP EF-4 13A Activation of the Mobile Environmental Monitoring Laboratory EP EF-6 11 Operation of EARS EP EF-9* 7 Backup Emergency Response Facilities EP EF-10 4 Joint Media Center Activation and Operation

Procedure included in this submittal

"**Procedure rescinded remove from use

- - ISSUED FOR USE BY: DATE: EXPIRES: ***

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-1 NUCLEAR POWER GENERATION REVISION 29 DIABLO CANYON POWER PLANT PAGE 1 OF 3 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Emergenc y Classification and Emergency Plan Activation I AND2 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION PAGE SCO PE ......................................................................................................................... 1 D ISC U SSIO N ................................................................................................................. 1 DEFINITIONS ................................................................................................................ 1 RESPONSIBILITIES .................................................................................................... 2 INSTRUCTIONS ........................................................................................................... 3 RECORDS ..................................................................................................................... 3 ATTACHMENTS ......................................................................................................... 3 REFERENCES ........................................................................................................... 3

1. SCOPE 1.1 This procedure describes accident classification guidelines and Emergency Plan activation responsibilities.

1.2 This procedure was rewritten; therefore, revision bars are not included.

I

2. DISCUSSION 2.1 The steps required by this procedure are in addition to the steps required to maintain the plant in, or restore the plant to, a safe condition.

2.2 Events not meeting the minimum classification criteria contained in this procedure should be reviewed for reportability in XII.ID2, "Regulatory Reporting Requirements and Reporting Process."

3. DEFINITIONS 3.1 Emergency Classification Levels (ECLs) 3.1.1 Notification of Unusual Event (NUE) - characterized by off-normal conditions that:

a. May not in themselves be particularly significant from an emergency preparedness standpoint, but could reasonably 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 stand point. No releases of radioactive material requiring off-site response or monitoring are expected.

00223629.DOA 3B I 0818.1239

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-1 DIABLO CANYON POWER PLANT REVISION 29 PAGE 2 OF 3 TITLE: Emergency Classification and Emergency Plan Activation UNITS 1 AND 2 3.1.2 Alert - events in progress or having occurred, involving an actual or potentially substantial degradation of the plant safety level.

a. Small releases of radioactivity may occur (greater than Technical Specification limits for normal operation, but only a small fraction of the EPA Protective Action Guideline (PAG) exposure levels at the site boundary). It is the lowest level where emergency offsite response may be anticipated.

b. The lowest classification level where off-site emergency response is anticipated.

3.1.3 Site Area Emergency (SAE) - events which are in progress or have occurred involving actual or likely major failures of plant functions needed for protection of the public, but a core meltdown situation is not indicated based on current information.

a. Any releases are not expected to exceed EPA Protective Action Guides except near the site boundary. However, because the possible release is significant, care must be taken in alerting offsite authorities to distinguish whether the release is merely potential, likely, or actually occurring. Response of offsite authorities will be guided initially by this determination.

3.1.4 General Emergency (GE) - event(s) in progress or having occurred which indicate:

a. Imminent substantial core degradation or melting.

b. Potential for containment loss.

c. Radioactive releases can be reasonably expected to exceed EPA PAGs off-site for more than the immediate area.

4. RESPONSIBILITIES 4.1 Interim Site Emergency Coordinator (Interim SEC or ISEC) - Control Room Shift Manager is responsible for initial event classification and emergency plan activation.

The ISEC may upgrade the event classification until relieved by either the SEC or RM.

In addition, the ISEC may downgrade a NUE to no ECL.

4.2 Site Emereency Coordinator (SEC) - The SEC may upgrade the classification of an event until relieved by the Recovery Manager.

4.3 Recovery Manager (RM) - The RM, once staffed, is responsible for upgrading or downgrading ECLs, and may direct the SEC to change ECLs.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-1 DIABLO CANYON POWER PLANT REVISION 29 PAGE 3 OF 3 TITLE: Emergency Classification and Emergency Plan Activation UNITS 1 AND 2

5. INSTRUCTIONS 5.1 The Interim Site Emergency Coordinator shall:

5.1.1 Initially classify and declare the event using ONLY the guidance in Attachment 7.1 of this procedure.

NOTE: Simultaneous EALs that increase the probability of release require escalation of the ECL to one level above the higher EAL.

5.1.2 Formally announce all emergency classification declarations to the Control Room, TSC, or EOF, respectively.

5.2 The ISEC or SEC may:

5.2.1 Upgrade the event to a higher ECL until the Recovery Manager arrives at and assumes responsibility in the EOF. However, the ISEC and SEC shall not downgrade an event classified at the Alert or higher level at any time.

The ISEC may downgrade a NUE to no ECL.

5.2.2 Only the Recovery Manager may downgrade an ECL at the Alert or higher level according to the most current controlling EAL.

6. RECORDS 6.1 There are no quality or nonquality records generated by this procedure.

7. ATTACHMENTS 7.1 "Emergency Action Level Classification Chart," 08/18/00

8. REFERENCES 8.1 EP EF-1, "Activation and Operation of the Technical Support Center."

8.2 EP EF-2, "Activation and Operation of the Operational Support Center.

8.3 EP EF-3, "Activation and Operation of the Emergency Operations Facility."

8.4 EP OR-3, "Emergency Recovery."

8.5 EP G-3, "Notification of Offsite Agencies and Emergency Response Personnel."

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f 6

Ob., /OO Page 1 o, 9 DIABLO CANYON POWER PLANT EP G-1 ATTACHMENT 7.1 I AND 2 TITLE: Emergency Action Level Classification Chart UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I. FIRE 1. Fire not under control within 15 minutes 1. Fire not under control within 1. Fire causing the complete loss of 1. Site Emergency Coordinator judges (AN Modes) of initiating fire fighting efforts AND 15 minutes of initiating fire-fighting function of any one of the following that a fire could cause common affecting plant equipment or power efforts AND threatening the loss of safety related systems required for damage to plant systems which is supplies inor near the Protected Areals). function of any of the following safe shutdown: determined to have the potential to Safety Related systems required for Vital Power Supplies: DIGs, release radioactive material in safe shutdown: DFOT, Vital 4kV, 480V, 120VAC, quantities sufficient to cause Vital Power Supplies: DIGs, OFOT, or 125VDC exposures comparable to General Vital 4kV, 480V, 120VAC, or Primary Systems and Auxiliaries: Emergency #4.

125VDC RCS, CCW, RHR, or Charging and Primary Systems and Auxiliaries: Boration RCS, CCW, RHR, or Charging and Heat Sinks: AFW, ASW, Boration 10% Dumps, SIG Safeties, or Heat Sinks: AFW, ASW, MSIVs 10% Dumps, SIG Safeties, or Control Room, Cable Spreading MSIVs Rooms, or HSOP.

Control Room, Cable Spreading Rooms, or HSDP.

I1.FUEL DAMAGE 2. Indication of Fuel Damage as shown by: 2. Indication of Fuel Damage as shown See SAE #14 for Steam Line Break 2. Degraded core with possible loss of OR by: coolable geometry as indicated by:

VESSEL DAMAGE Confirmed RCS sample shows (Modes 1-4) > 1001E pCilgm specific activity Confirmed RCS sample > 300 pCilcc 5 or mere thermocouple readings ITech Spec 3.4.81 of equivalent 1-131 specific activity > 1200 deg. F.

OR OR equivalent fuel failure ismeasured OR Confirmed RCS sample shows dose by exposure rate from systems LOCA with no indication of ECCS equivalent 1-131 activity > Tech Spec carrying reactor coolant per EP RB-14 flow AND indication of fuel damage limit for Iodine Spike (Tech Spec OR (See Alert #21 Fig. 3.4-1). Confirmed RCS sample OR indicates > 1%fuel failure within LOCA with containment red levels 30 minutes or 5%total fuel failure. > values for 100% gap release in EP RB-14.

Category IIContinued on next page. Category IIContinued on next page. Category IIContinued on next page. Category IIContinued on next page.

NOTE: SIMULTANEOUS EALS THAT INCREASE THE PROBABILITY OF RELEASE REQUIRE ESCALATION OF THE CLASSIFICATION TO ONE LEVEL ABOVE THE HIGHER EAL.

091. 1239 00223629.DOA 3B 4 1

08/18/00 EP G-I (UNITS 1 AND 2) Page 2 of 9 ATTACHMENT 7.1 TITLE: EmerRency Action Level

~ ~ t Ci,.t- ,...-

- - ~

~ - ~.t'~J - -- V UNUSUAL EVENT ALERT 11.FUEL DAMAGE 3. Pressurized Thermal Shock is verified by SITE AREA EMERGENCY GENEI RAL EMERGENCY OR entry into EOP FR-P.1 VESSEL DAMAGE AND 3. B*

Lcarriers:

,ss of 2 of 3 Fission Prod-uct (Modes 1-41 Left of Limit Acurve (EOP FR-P.1 (Continued) A) Indication of fuel damage (See Alert 12)

AND Determination of a Steam Generator Tube Rupture (SGTRI which requires entry into EOP E-3 AND Steam release from ruptured SIG, either used for plant cooldown purposes or due to a steamline break.

B) Indication of Fuel Damage (See Alert 12)

AND Determination of a SGTR requiring entry into EOP E.3 AND Indication of a steam line break inside containment AND High potential for loss of containment integrity le.g., loss of function of both Containment Spray trains OR loss of function NOTE: SIMULTANEOUS EALS THAT INCREASE THE of one Containment Spray train PROBABILITY OF RELEASE REQUIRE ESCALATION OF and four CFCUs).

THE CLASSIFICATION TO ONE LEVEL ABOVE THE HIGHER EAL.

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6

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Page i vr 9 EP G-1 (UNITS 1 AND 2)

ATTACHMENT 7.1 TITLE: Emergency Action Level Classification Chart UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY i1. FUEL DAMAGE 3. Pressurized Thermal Sh*ck is verified by OR C) Indication of Fuel Damage (See entry into EOP FR-P.1 Alert 121 VESSEL DAMAGE AND (Modes 1-4) Left of Limit Acurve (EOP FR-P.1). AND Detenmnation of aSGTR which (Continuedl (Continuedl requires entry into EOP E-3 AND Indication of a steam line break outside containment with inability to isolate the break.

D) Potential fuel damage indicated by incore thermocouples > 700 dog. For RVLIS < 32%

AND LOCA as indicated by RCS leakage and SI AND Loss of containment integrity.

Ill. FUEL 3. Fuel Handling Accident causing a 2. Fuel Handling Accident causing a HANDLING release in Containment or the Fuel release inContainment or the Fuel ACCIDENT Handling Building Handling Building IAII Modes) WITH WITH The potential to exceed the criteria The potential to exceed the criteria listed in Alert 14 or 15. listed in SAE #3.

IV. LOSS OF 4. Projected dose rate at the Site Boundary 4. Projected dose rate at the Site 3. Projected dose at the Site Boundary 4. Projected dose at the Site Boundary CONTROL OR (800 meters) is Boundary 1800 metersl is (800 meters) is RELEASE OF (800 meters) is

- 0.057 mRam/hr TEDE 2 0.57 mRem/hr TEDE > 100 mRem TEDE > 1,000 mRem TEDE RADIOACTIVE OR OR OR MATERIAL OR

> 0.170 mRem/hr Thyroid CDE for actual > 1.7 mRemlhr Thyroid CDE for actual Ž 500 mRam Thyroid COE for actual or 2 5,000 mRam Thyroid CDE for (AN Modes) or expected release. or expected release. expected release. actual or expected release.

1 Category IVContinued on next page. Category IVContinued on next page. Category IVContinued on next page. Category IVContinued on nextpage.

NOTE: SIMULTANEOUS EALS THAT INCREASE THE PROBABILITY OF RELEASE REQUIRE ESCALATION OF THE CLASSIFICATION TO ONE LEVEL ABOVE THE HIGHER EAL.

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08/18/00 AND 2) Page 4 of 9 EP G-I (UNITS 1 ATTACHMENT 7.1 TITLE: Emergency Action Level Classification Chart UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY IV. LOSS OF 5. Avalid reading inexcess of the isolation 5. Valid alarm on plant vent high range CONTROL OR setpoint, which fails to isolate the noble gas monitor RE-29.

RELEASE OF release on any of the Radiological MUTE: ALARMS AT STATE DES RADIOACTIVE Process Effluent Monitors: SACRAMENTO.

MATERIAL RE-18 OR RE-23 IAll Modes) During discharge only.

IContinued)

6. An actual liquid release which exceeds 6. An actual liquid release which exceeds the limits of 10 CFR 20, Appendix B, lOx the limits of 10 CFR 20, Table 2, Col. 2 per CY2.1I0. Appendix B,Table 2, Col. 2 per CY2.1D11.

7. Radiological Effluent Process Monitor 7. Unplanned or unanticipated increase of High Radiation Alarm with valid reading 1 R/hr or greater in any of the inexcess of alarm setpoint on any of the following areas:

following monitors: Passageways, OR RE.14114R Normally occupied areas, OR RE-24124R Accessible areas normally RE-28128R. < 100 mR/hr, OR Outside boundaries of Radiologically Controlled Areas AND for any area above, a potential exists for EITHER an uncontrolled release to the environment OR a loss of ability to maintain plant safety functions.

8. Unplanned or uncontrolled release to the 8. Unexplained increase of 50 XDAC in environment exceeding alarm setpoints airborne radioactivity outside the on RE-3. boundary of the Rediologically Controlled Areas, but within the Plant Protected Area.

NOTE: SIMULTANEOUS EALS THAT INCREASE THE PROBABILITY OF RELEASE REQUIRE ESCALATION OF THE CLASSIFICATION TO ONE LEVEL ABOVE THE HIGHER EAL.

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0,o/00 Page 3 ,, 9 EP G-1 (UNITS 1 AND 2)

ATTACHMENT 7.1 TITLE: Emergency Action Level Classification Chart UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY V. LOSS OF 9. Entry into OP AP-8A, "Control Room 4. Entry into OP AP-BA, "Control Room CONTROL Accessibility," AND controls Accessibility," AND controls not ROOM established within 15 minutes. established within 15 minutes.

(All Modes)

VI. LOSS OF 9. Plant is not brought to required operating 5. Complete loss for greater than 5. Loss of Heat Sink indicated by:

ENGINEERED Mode within any applicable Tech Spec 15 minutes of any of the following Entry into EOP FR H.1 SAFETY Action Statement time limit (Modes 1-4). functions needed to reach or maintain AND FEATURE Hot Shutdown (while inModes 1-41: Loss of water inventory in3 SIGs I< 23% 134%] Wide Range).

10. Loss of function of both RHR trains for 10. Loss of function of both RHR trains AFW capability greater than 15 minutes while in for greater than 15 minutes in Steam Dump System and SIG Safety Mode 5.or 6. Modes 14. Valves

11. Aloss of function of all charging pumps 11. An unplanned shutdown of the RHR Loss of the capability to maintain RCS for greater than 15 minutes when System (while inMode 5 or 6)for inventory as evidenced by a loss of all normafly used for RCS inventory control > 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with no other normal means charging pumps coincident with the (Modes 1.41. of decay heat removal available inability to depressurize and inject with (e.g., flooded reactor cavity or steam the Safety Injection pumps generators with loops filled).

12. An unplanned loss of function of the Loss of capability to increase the Boric RHR System (Mode 5 or 6? for greater Acid concentration sufficient to than 15 minutes maintain Keff less than .99 inMode 4 AND with a loss of capability to trip control RCS thermocouple temperature is rods projected to exceed 200 deg.F within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of RHR loss (see Appendix Bof ASW or CCW Systems OP AP SD series) Loss of electrical power or I&C for any OR of the above listed systems, causing a RCS thermocouple temperature complete loss of function.

exceeds 200 deg.F.

NOTE: SIMULTANEOUS EALS THAT INCREASE THE PROBABILITY OF RELEASE REQUIRE ESCALATION OF THE CLASSIFICATION TO ONE LEVEL ABOVE THE HIGHER EAL.

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08/18/00 EP G-1 (UNITS I AND 2) Page 6 of 9 ATTACHMENT 7.1 TITLE: Emergency Action Level Classification Chart UNUSUAL EVENT AI FRT 1E

ITI* AIClirA rlLJrlrt*rslnu ALEFRT re.h,,, *11 aliT n

Aftra OIIEI: RNER M

AnrA FIVWflhtIEI.T M

rrMI*IIIJi'NET Y GENERAL EMERGENCY VII I

12. Loss of all off-site power for greater I

13. Loss of all off-site power for greater 6. Loss of all on-site AND off-site AC power LOSS OF POWER OR than 15 minutes AND at least 2 DIGs are See General Emergency Condition #5 than 15 minutes AND only 1 DIG is for > 15 minutes (Modes 141.

ALARMS OR supplying their vital busses (Modes 1-4). under LOSS OF ENGINEERED supplying its vital bus (Modes 1-4). SAFETY FEATURE.

ASSESSMENT OR COMMUNICATIONS 13. Loss of all off-site power for greater -4 14. Loss of a1 off-site and on-site AC than 15 minutes AND at least 1 DIG is power for greater than 15 minutes in supplying its vital bus (Modes 5 and 6I supplyin 5%or A

14. Loss of all its vitalbus-vital 5 and...6)

DC power as indicated v

15. Loss of all vital DC power as indicated 7. Loss of all vital DC power as indicated by by DC Bus 11(21), 12(22), and 13(23) by DC Bus 11(21, 12(221 and 13 (23) DC Bus 11(21), 12 (221 and 13 (231 undervoltage for > 15 minutes undervoltage for < 15 minutes undervoltage for > 15 minutes (Modes 5-and 6) (Modes 141. (Modes 14).

15. Loss of assessment capabilities as indicated by a total loss of SPDS inthe Control Room AND simultaneous loss of all displays for any "Accident Monitoring" variable in Tech Spec Table 3.3-10 for > 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months while in Modes 1.2 or 3.

1R Main rnntrnl Rn.- Ann..n.--' .^. 1 aa i n * ...... ,

16. mnlin bControl Room Anfiunciators 8. Main Control Room Annunciators PKs 1 PKs I through 5 AND CRT AND PKs 1 through 5 AND CRT AND through 5 AND CRT AND typewriter all typewriter aof do not respond to an alarm typewriter all do not respond to an do not respond to an alarm condition in condition inModes 1-4 for over alarm condition inMODES 14 for over MODES 1-4 for over 15 minutes 15 minutes.. 15 minutes AND AND the plant is ina significant transient AND the plant is ina significant transient backup, nonannunciating systems are not (plant trip, SI, or generator runback available (PPC, SPOS).

>25 Mwlminl, nonannunciating systonms availahbl.

sytmsaalal.I I NOTE: SIMULTANEOUS EALS THAT INCREASE THE PROBABILITY OF RELEASE REQUIRE ESCALATION OF THE CLASSIFICATION TO ONE LEVEL ABOVE THE HIGHER EAL.

IFTHE AFFECTED VARIABLE INTABLE 3.3-10 IS THE PLANT VENT RADIATION MONITOR-HIGH RANGE, REFER TO THE COMPENSATORY MEASURES INSTP G-16.

00223629.DO 3B 9 1 39

4. i0o C /

Page 9 EP G-1 (UNITS I AND 2)

ATTACHMENT 7.1 TITLE: Emergency Action Level Classification Chart UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY vii. 17. Total loss of communication capability LOSS OF POWER OR with off-site agencies (all Modes) as ALARMS OR indicated by the inability to communicate ASSESSMENT OR with SLO County (by telephone and COMMUNICATIONS radio)

{Continued) OR the NRC Operations Center.

18. Ground motion felt and recognized as an 17. Earthquake > 0.2 g verified by 9. Earthquake > 0.4 g verified by Seismic 6. Site Emergency Coordinator's earthquake by a consensus of Control Seismic Monitors. Monitors. judgment that major internal or Room operators on duty AND measuring external events (e.g.,

greater than 0.0 1g on the Earthquake earthquakes, wind damage, Force Monitor.

explosions, etc.) which could cause massive common damage to plant systems which is determined to have the potential to release radioactive material in quantities sufficient to cause exposures comparable to General Emergency A4.

19. Flooding of any plant structure that 18. High water exceeding Intake Structure 10. High water causing flooding of ASW causes initiation of entry to Mode 3 due main deck elevation or low water pump compartments or low water to a Tech Spec action statement. causing cavitation and shutdown of causing the shutdown of both ASW both ASW pumps for < 15 minutes. pumps for > 15 minutes.

20. Tsunami or Hurricane Warning from the 19. Sustained wind of 85 mph (38 mlsac) 11. Sustained wind speed > 100 mph State, NOAA, NWS, Coast Guard or at any elevation on the Met. Tower. (45 mlsec).

System Dispatcher OR Observation of low or high water levels at the Intake Structure indicative of a Tsunami or Hurricane.

21. Atomado sighted within Site Boundary. 20. Tornado strikes the plant protected area.

NOTE: SIMULTANEOUS EALS THAT INCREASE THE PROBABILITY OF RELEASE REQUIRE ESCALATION OF THE CLASSIFICATION TO ONE LEVEL ABOVE THE HIGHER EAL.

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08/18/00 Page 8 of 9 EP G-1 (UNITS 1 AND 2)

ATTACHMENT 7.1 TITLE: Emergency Action Level Classification Chart UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY IX. 22. Report of airplane crash within the Site 21. Confirmed missile, airplane crash or 12. Missile, airplane crash or explosion See General Emergency 16 above.

OTHER HAZARDS Boundary or unusual airplane activity explosion involving a plant structure in causing complete loss of a safety (All Modes) threatening the plant. the protected area. system function that causes entry into a Tech Spec Action Statement.

23. Confirmed explosion on-site.

24. Turbine failure causing casing 22. urbine failure generating missiles that penetration O.R damage to turbine or cause visual damage to other safety generator seals related structures, equipment, controls 011 power supplies.

25. Significant release of flammable OR 23. Release of flammable OR toxic gas OR toxic gas OR liquid that prevents, even liquid that Jeopardizes operation of with SCBAs, operations inside the safety related systems by either power block OR intake structure (ref. preventing required access OR by CP M-9a). threatening imminent damage.

X. 26. RCS unidentified OR pressure boundary 24. Primary leak rate > 50 gpm. 13. Known primary system LOCA during See General Emergency #3under Fuel PRIMARY OR leakage that exceeds 10 gpm OR which RCS subcooling cannot be or Vessel Damage.

PRIISEC OR identified leakage that exceeds 25 gpm. maintained >20°F OR PZR level cannot SECONDARY LEAK) be maintained >4% (28% with adverse containment).

(Modes 1-4 27. SI Actuation with ECCS injection into 25. Determination of a SGTR which 14. Determination of a SGTR coincident the RCS resulting from a valid signal results inentry into EOP E-3. with steam release from ruptured SIG, based on actual plant conditions. either used for plant cooldown purposes NOTE: SI ACTUATION ALSO ALARMS or due to a steamline break.

AT DES INSACRAMENTO.

28. Steam line break which results inSI 26. Determination of a steam line break actuation. with > 10 gpm Primary to Secondary leakage.

29. Failure of a PZR PORV AND Block Valve OR Safety Valve fails to reseat, excluding aflowable leakage, following a pressure reduction below the reset point.

NOTE: SIMULTANEOUS EALS THAT INCREASE THE PROBABILITY OF RELEASE REQUIRE ESCALATION OF THE CLASSIFICATION TO ONE LEVEL ABOVE THE HIGHER EAL.

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k &/0 Page 9 of 9 EP G-I (UNITS I AND 2)

ATTACHMENT 7.1 TITLE: Emergency Action Level Classification Chart UNUSUAL EVENT ALERT SITE AREA EMERGENCY X^. GENERAL EMERGENCY

27. Anticipated Transient Without Scram 15. An ATWS condition with no fuel damage 7. ATWS with Fuel Damage REACTOR IATWSI as indicated by: evident indications Isee Alert Condition PROTECTION Failure of an automatic reactor trip to AND 12 under FUEL DAMAGE)

SYSTEM FAILURE trip the reactor.

(Modes 14) An additional failure of a system OR required for Hot Shutdown ISee SAE #5) ATWS with potential Core Melt to actuate. indicated by incore thermocouples

> 700 deg. FAND XII. 30. Report by Security that a forcible entry 28. Security reports ongoing security RVLIS < 32%.

16. Security reports ongoing physical attack 8. Security reports ongoing security SECURITY THREAT or sabotage attempt has occurred or a threat involving physical attack on the (Modes 1-4) on the facility or a sabotage device threat which causes loss of credible bomb threat has been received facility or a sabotage device has been causing a confirmed loss of a safety control of the operations of the against the areas within the protected detected that threatens the operability system function that causes an entry plant to hostile forces.

area boundary. of safety related equipment (see into a Tech Spec Action Statement Isee Alert 1l). SAE11).

XIII. 31. Site Emergency Coordinator determines 29. Site Emergency Coordinator judges 17. Site Emergency Coordinator judges that 9. Site Emergency Coordinator SITE EMERGENCY conditions warrant increased awareness plant conditions exist that warrant conditions exist that warrant activation judges conditions exist which COORDINATOR'S on the part of off-site authorities of precautionary activation of the TSC JUDGMENT of the emergency centers and have a potential to release initiation of a plant shutdown per Tech and placing the EOF and other key monitoring teams or a precautionary IAN Modes) radioactive material inquantities Spec LCOs or involve other than normal emergency personnel on stand-by. notification to the public near the site.

controfled shutdown. sufficient to cause exposures comparable to General Emergency 14.

NOTE: SIMULTANEOUS EALS THAT INCREASE THE PROBABILITY OF RELEASE REQUIRE ESCALATION OF THE CLASSIFICATION TO ONE LEVEL ABOVE THE HIGHER EAL.

00223629.DOA 3B 12 1 0818.1239

PG&E/NPG Form 69-10709 (09/10/99)

Page 1 of 2 On-The-Spot-Change

1. PROCEDURE NO. 2. CURRENT REV. 3. UNIT

4. OTSC TYPE 0 Permanent El Temporary - Expiration Date/Event/Task:

5. If Temporary, do others using this procedure need to implement this change? [:]Y EDN

6. REASON FOR CHANGE: (REFERENCE AR, QE, NCR, ETC. ATTACH ADDITIONAL PAGES IF NECESSARY.)

-70 011,04V 0 dr/-.C 7"v -*Ae 4o i- 7fe

7. LIST PROCEDURE PAGES AFFECTED 8. LIST ATTACHMENTS AND PAGES OF ATTACHMENTS AFFECTED WU 9. Mark-up clean copy of affected pages (preferably using pen-and-ink) in a manner which ensures that users can a read and understand the changes.

. Affected pages shall include any previous OTSCs affecting that page. Leave previous OTSCs (including UJ dates) as is unless the content is being changed by the new OTSC.

a.

Include revision bars, the notation "OTSC" and today's date in the margin next to the change.

Highlighting techniques such as a hand drawn "balloon" should be used to clearly identify the change.

Additional pages to the procedure shall be given the appropriate page number followed by an alphabetic suffix (e.g., page 3A).

10. [ N/A - Cross Discipline Review(s) required if OTSC has significant impact on other organizations.

Organization: 0rC1W10__/_, _V._

Print Reviewer's Last Name: ,IA,.ij',SOA)._

11. Complete the Screen sections on page 2, sign and give to an ITR and if required, an SRO. After authorizations are obtained, process as shown at the bottom of this page.

12. Review change and LBIE screen for technical accuracy. Sign and date page 2.

t 13. SRO review and authorization required if procedure is (a) PGOM sponsored; (b) a Surveillance Test; (c) an t Emergency Plan Implementing procedure; (d) a change that affects equipment or system OPERABILITY or availability. If NOT, check SRO block N/A - OTSC is authorized by ITR.

14. This change does NOT adversely impact the operating license NOR have an adverse impact on the operating O status of plant equipment.

n 15. If the approving SRO is not the affected unit SFM, the a ropriate, otify affected unit SFM.

, N/A Si nt r:J fDae Print Last Name: __ _Sg rt PREPARER - Ensure original OTSC and mark-ups are immediatel. t nd carried to the drop box in the Clearance Coordinator's office or Procedure Services.

PROCEDURE SERVICES ACTIVITIES (REFERENCEAD3.1D5.)

16. DATE RECEIVED 17. OTSC FLAG SEI (INITIALS) 18. IMMEDIATE DIST (INITIALS) 19. SECONDARY I*T (INITIALSN

~~ El ~N/A /'A~& ElN/A

20. PSRC REVIEW? N E]Y- PSRC MTG#: 221.DATE CHANGE NOTICE SENT: __,,,,_/A

22. E] Approved OR [] Rejected Remarks:

Approval Authority: Date:

VP & NTS: __ N/A Date:

6910709.doc

Reference:

ADI.1D7 Attachment 7.2

Form 69-10709 (09/10/99)

Page 2 of 2 Rules for use:

DO NOT use an OTSC if any questions are answered "YES."

An OTSC may be used and the LBIE Screen box checked "NO" when a safety evaluation was conducted and documented for a related document and this OTSC is reflecting the approved change. Source document shall be referenced in the Reason for Change Block.

Does the OTSC:

Change the essential purpose, major activities, equipment, Operating Mode(s), performance flY E N frequency, or range of operation, which define the limits of the intended use of the procedure?

"* Cause safety-related equipment to become inoperable or unable to perform its intended safety --Y 0 N function?

"* Eliminate a step required to verify operability or functionality, or satisfy a commitment? '-Y W'N

"* Reduce quality verification requirements (e.g., hold points, independent verifications)? []Y Z N Licensing Basis Impact Evaluation Screen The term "SAR" is defined in TS3.1D2.

Does the OTSC:

"a Involve a change to the Facility Operating License (OL), including OL attachments (current and -]Y [Z N Improved Technical Specifications, Environmental Protection Plan, and Antitrust Conditions)?

"* Impact a regulatory commitment or obligation contained in the PCD? -lY [0 N

"* Involve a change to the facility design, function, or method of performing the function as flY [0 N described in the SAR?

"* Involve a change to procedures, system operation, or administrative control over plant activities f-]Y [ N as described in the SAR (except Chapter 17 of the updated FSAR)?

"* Result in a test, experiment, condition, or configuration that might affect safe operation of the [']Y j] N plant but was not anticipated, described, or evaluated in the SAR?

Rely on a vendor safety evaluation which has not been PSRC reviewed? [-lY [ N

"* Involve a change to the Fire Protection Program as described in the FSAR Update Chapter 9.5? flY 2] N

"* Involve a change to the QA Program as described in FSAR Update Chapter 17? -]Y [0 N Base the following reviews on the TS3.1D2 "pre-screens" and/or the actual plan(s). Document any assistance in the Reason for Change block.

Does this OTSC result in a change to the Emergency Plan, Security Plans (PSP, SCP, STQP), or f]Y [4 N Environmental Protection Plan, or create a situation that may be adverse to the environment?

I have a PIMS qualification title for procedure sponsor.

This change meets the OTSC rules for use and I have completed the LBIE Screen and determined than an LBIE is IL not required.

PFPINT LAST NAME PHONE I have been designated by the Plant Manager as an independent technical reviewer.

.X The 01, is techn lly correct, meets the OTSC rules for use, and does not require an LBIE.

DATE PRINT LAST NAME PHONE hgo V * /

6910709.doc

Reference:

ADI.ID7 Attachment 7.2

(02/09/00) EP G-2 Attachment I Units 1 & 2 Page 1 of I Notification of Unusual Event Checklist SIGNATURE DATE

1) E] Approve Emergency Classification.

2) E] Announce Emergency to Control Room staff and direct staff to assume their Emergency Response roles.

3) El Complete DCPPEvent Notification Form (EP G-3, Attachment 9.3).

4) El Complete PAR Form (EP RB-IO). I a"

5) El Direct CRA to initiate VANS (if required). 0 dAl.-r7 A,p/C A0 7/fjoC;A . j 00O

6) fl Direct the Emergency Liaison Coordinator"tO Off-Site Notification Log Sheet.

EP G-3, Attachment 9.4 Attention all personnel:

The Diablo Canyon Emergency Plan has been activated at the level for Unit __, due to

7) El Make PA Announcement.

No actions by emergency response personnel are required at this time.

8) El If a release of airborne radioactive materials may be occurring or has occurred, direct the Emergency Evaluation Coordinator to perform an off-site dose assessment per EP R-2.

9) El WHEN plant conditions no longer meet any emergency classification criteria, THEN terminate the emergency using the TERMINATION Checklist.

10) [] Route this completed checklist to the Emergency Planning Supervisor for retention.

PG&E Diablo Canyon

(02/09/00) EP G-2 Attachment 3 Units 1 & 2 Page 1 of 1 Alert Checklist SIGNATURE DATE

1) E] Approve Emergency Classification.

2) E] Announce Emergency to Control Room staff and, unless previously done, direct staff to assume their Emergency Response roles.

3) Ml Complete DCPP Event Notification Form (EP G-3, Attachment 9.3).

4) Ml Complete PAR Form (EP RB-10).

Note: If KI needs to be issued prior to the TSC being activated, then refer to EP RB-3.

6roc

5) Ml Direct CRAto initiate VANS (if required). M, dcs,,j 6 e

6) Ml Direct the Emergency Liaison Coordinatordto make Off-Site Agency Notifications.

(EP G-3, Attachment 9.4 Off-Site Notification Log Sheet.)

Attention all personnel:

7) El Make PA Announcement. The Diablo Canyon Emergency Plan has been activated (or upgraded) at the level

8) El Sound the Site Emergency Signal for 60 sec. for Unit due to

9) El Repeat the PA announcement. Emergency Plan position holders report immediately to your assigned response location.

10) El Contact DCPP Watch Commander (if required) to:

"* Implement Personnel assembly, accountability and Site Access control during emergencies (EP G-4).

"* Initiate Evacuation of non-essential personnel (EP G-5).

11) El If a release of airborne radioactive materials may be occurring or has occurred, direct the Emergency Evaluation Coordinator to perform an off-site dose assessment per EP R-2.

12) El Ensure emergency responsibilities are turned over to the Emergency Response Organization as soon as possible. Use ISEC I SEC I RM Turnover Checklist.

13) [ Announce to the Control Room that Emergency Response Facilities have been activated.

14) El Route this completed checklist to the Emergency Planning Supervisor for retention.

PG&E Diablo Canyon

(02/09/00) EP G-2 Attachment 4 Units 1 & 2 Page 1 of I Site Area Emergency Checklist SIGNATURE DATE

1) [] Approve Emergency Classification

2) [ Announce Emergency to Control Room staff and, unless previously done, direct staff to assume their Emergency Response roles.

3) [ Complete DCPP Event Notification Form (EP G-3, Attachment 9.3).

4) [] Complete PAR Form (EP RB-10).

Note: If KI needs to be issued prior to the TSC being activated, then refer to EP RB-3.

5) EJ Direct CRA to initiate VANS (if required). - ,/ "a 4 06

6) [:] Direct the Emergency Liaison Coordinator tlo make Off-Site Agency Notifications. I (EP G-3, Attachment 9.4 Off-Site Notification Log Sheet)

Attention all personnel:

7) E Make PA Announcement. The Diablo Canyon Emergency Plan has been activated (or upgraded) at the level

8) fl Unless already sounded, sound the for Unit _, due to Site Emergency Signal for 60 sec.

Emergency Plan position holders report

9) [ Repeat the PA announcement. immediately to your assigned response location.

10) E] Contact DCPP Watch Commander (if required) to:

"* Implement Personnel assembly, accountability and Site Access control during emergencies (EP G-4).

"* Initiate Evacuation of non-essential personnel (EP G-5).

11) E] If a release of airborne radioactive materials may be occurring or has occurred, direct the Emergency Evaluation Coordinator to perform an off-site dose assessment per EP R-2.

12) [] Ensure emergency responsibilities are turned over to the Emergency Response Organization as soon as possible. Use ISEC I SEC I RM Turnover Checklist.

13) E Announce to the Control Room that Emergency Response Facilities have been activated.

14) E Route this completed checklist to the Emergency Planning Supervisor for retention.

PG&E Diablo Canyon

(02/09100) EP G-2 Attachment 5 Units I & 2 Page 1 of I General Emergency Checklist SIGNATURE DATE

1) M Approve Emergency Classification.

2)fl Announce Emergency to Control Room staff and, unless previously done, direct staff to assume their Emergency Response roles.

3)Noe Complete DCPP Event Notification Form ( EP G-3, Attachment 9.3).

4) [ Complete PAR Form (EP RB-10).

Note: If KI needs to be issued prior to the TSC being activated, then refer to EP RB-3.

5) El Direct CRA to initiate VANS (if required). DA -,&.,4ff / 10'6

6) M] Direct the Emergency Liaison Coordinatorto make Off-Site Agency Notifications./ 0 (EP G-3, Attachment 9.4 Off-Site Notification Log Sheet.)

Attention all personnel:

7) El Make PA Announcement. The Diablo Canyon Emergency Plan has been activated (or upgraded) at the level

8) [ Unless already sounded, sound the Site for Unit _ , due to Emergency Signal for 60 sec.

Emergency Plan position holders report

9) E] Repeat the PA announcement. immediately to your assigned response location.

10) M] Contact DCPP Watch Commander (if required) to:

"* Implement Personnel assembly, accountability and Site Access control during emergencies (EP G-4).

"* Initiate Evacuation of non-essential personnel (EP G-5).

11) Ml If a release of airborne radioactive materials may be occurring or has occurred, direct the Emergency Evaluation Coordinator to perform an off-site dose assessment per EP R-2.

12) E] Ensure emergency responsibilities are turned over to the Emergency Response Organization as soon as possible. Use ISEC I SEC I RM Turnover Checklist.

13) Ml Announce to the Control Room that Emergency Response Facilities have been activated.

14) Ml Route this completed checklist to the Emergency Planning Supervisor for retention.

PG&E Diablo Canyon

- - ISSUED FOR USE BY: DATE.- EXPIRES:

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 NUCLEAR POWER GENERATION REVISION 17 DIABLO CANYON POWER PLANT PAGE 1 OF 15 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Personnel Assembly, Accountability and Site Access Control D wring Emergencies EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION PAGE SC O PE ................................................................................................................................. 1 D E FINIT IO N S ........................................................................................................................ 1 D ISC U SSIO N ......................................................................................................................... 2 Individuals A ssembly ............................................................................................................. 2 A ssem bly A reas .................................................................................................................... 3 Assembly Area Management .................................................................................................. 3 A ccountability ...................................................................................................................... 3 RESPONSIBILITIES ................................................................................................................ 3 PREREQUISITES .................................................................................................................... 4 IN ST R U C TIO N S ..................................................................................................................... 5 A ssem bly ............................................................................................................................ 5 A ccountability ...................................................................................................................... 6 R E CO RD S ............................................................................................................................. 6 A PPEN D IC ES ........................................................................................................................ 6 AT T AC H M EN T S .................................................................................................................... 7 RE F ER E N C E S ....................................................................................................................... 7

1. SCOPE

1. 1 This procedure describes emergency assembly of onsite personnel, accountability for individuals in the Protected Area and site access control during declared emergencies including radiological hazards and natural disasters.

2. DEFINITIONS

2.1 ACCOUNTABILITY

The process of determining the location of all individuals by name within the Protected Area.

2.2 ACCOUNTABILITY COORDINATOR: The Diablo Canyon Watch Commander or designee.

2.3 ASSEMBLY

The process of assembling Emergency Response Organization (ERO) personnel at assigned Emergency Response Facilities within the Protected Area and relocating nonessential site personnel to designated assembly areas outside the Protected Area.

2.4 This procedure was rewritten; therefore revision bars are not included. I 00020817.DOA 3B 1 VI 0817.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 2 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies 2.5 ASSEMBLY AREA: A designated area where personnel, after hearing the Site Emergency signal or public address announcement initiating assembly, are directed to report and wait for further instructions.

2.6 CONTINUOUS ACCOUNTABILITY: Maintaining accountability by name and location of individuals within the Protected Area after initial accountability has been established.

2.7 DESIGNATED ASSEMBLY AREA SUPERVISORS (DAAS): The senior person of a designated assembly area.

2.8 MISSING PERSONNEL: Individuals presumed to be within the Protected Area who cannot be located.

2.9 OWNER CONTROLLED AREA: The PG&E property enclosed by a fence to which access is protected. Access to this area is through the Avila Gate to the South and through Montana de Oro State Park to the North.

2.10 POTENTIAL ESSENTIAL PERSONNEL: Personnel awaiting assignments supporting the ERO. Essential Personnel are contacted by the OSC via pagers or through public address announcements.

2.11 EMERGENCY ACCOUNTABILITY LISTING: A listing generated by the Diablo Canyon Watch Commander that lists all individuals within the Protected Area.

2.12 PROTECTED AREA: The area of the plant encompassed by physical barriers and to which access is controlled. (For purposes of this procedure the Intake Area is excluded.)

2.13 SEARCH AND RESCUE: Locating and recovering missing individuals through systematic walkdowns and entries into accessible plant areas by coordinated team efforts.

2.14 STRAGGLER: Individual who reports late to an assembly area or is accounted for by the DAAS after the initial list of individuals has been sent to the Accountability Coordinator.

2.15 SWEEP: Walking through areas to determine if individuals are present.

3. DISCUSSION Assembly and accountability are initiated by sounding the Site Emergency signal or using a public address announcement and providing alternate Assembly Areas. Assembly and accountability are initiated using EP G-2, "Activation and Operation of the Interim Site Emergency Organization."

3.1 Individuals Assembly 3.1.1 In an emergency, site individuals (including visitors) must be notified of the emergency, given specified directions regarding their safety and accountability, and respond by reporting to predetermined Assembly Areas where they will receive further instructions.

3.1.2 If Assembly Areas or normal assembly routes become undesirable, directions for alternate assembly routes and areas will be provided by either public address announcements or Security Officers.

00020817.DOA 3B 2 vi 0817.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 3 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies 3.2 Assembly Areas 3.2.1 Signs posted inside the Protected Area direct individuals to Assembly Areas. These give instructions for the Site Emergency signal as well as the employee's specific assembly area location. Overhead views of assembly areas are depicted in Attachments 9.9 through 9.12.

3.2.2 Essential individuals responding to DCPP after callout shall report to their designated assembly area after arriving onsite, unless directed otherwise. The requirements regarding fitness for duty capability identified in OM 17.ID3, "Fitness for Duty Program," shall be followed.

3.3 Assembly Area Management 3.3.1 The DAAS:

a. Completes assembly/accountability checklists for Assembly Areas within the Protected Area and Assembly Area Rosters for Assembly Areas outside the Protected Area.

b. Notifies the Accountability Coordinator of individuals in Assembly Areas within the Protected Area.

3.4 Accountability 3.4.1 The goal of accountability is to identify all individuals within the Protected Area by name and location within approximately 30 minutes. Individuals within the Protected Area whose locations are unknown shall be considered missing.

3.4.2 The accountability 30 minute time starts when the announcement to assemble is made or the Site Emergency signal is sounded, whichever is first.

3.4.3 DAAS within the Protected Area report individuals by name and keycard number to the Accountability Coordinator.

3.4.4 Individuals leaving the Protected Area are logged out in the Security Building.

3.4.5 The Accountability Coordinator compares assembly reports received from the Protected Area DAAS to the Emergency Accountability Listing to identify missing personnel.

4. RESPONSIBILITIES 4.1 ACCOUNTABILITY COORDINATOR 4.1.1 Coordinates the accountability process for the Protected Area.

4.1.2 Assists Protected Area DAAS by maintaining continuous accountability during the emergency.

00020817.DOA 3B 3 vi 0817.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 4 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies 4.1.3 Establishes phone locations at the Protected Area access control point (Security Building) for individuals after Protected Area assembly areas are manned with DAAS.

4.1.4 Ensures individuals entering the Protected Area, phone the DAAS of their destination after assembly areas are established.

4.2 DESIGNATED ASSEMBLY AREA SUPERVISOR:

4.2.1 Completes assembly area roster.

4.2.2 Advises and controls individuals assigned to a designated assembly area.

4.2.3 Within the Protected Area, maintains continuous accountability of individuals assigned to their area throughout the emergency.

4.3 EMERGENCY MAINTENANCE COORDINATOR: Completes accountability checklist for the OSC organization.

4.4 SECURITY ADVISOR (TSC) 4.4.1 Ensures personnel accountability is performed.

4.4.2 Provides Site Emergency Coordinator (SEC) with a list of missing personnel.

4.4.3 Updates the SEC on status of missing personnel.

4.4.4 Performs accountability for the TSC.

4.5 OPERATIONS SHIFT MANAGER:

4.5.1 Maintains continuous accountability of Operations individuals assigned to the on-watch crew in the Control Room, plant, or the Operations Ready Room prior to OSC activation.

4.5.2 Recommends protective actions to the Diablo Canyon Watch Commander for Security individuals prior to TSC activation.

4.5.3 Provides protective action instructions to individuals using public address announcements, or communications with DAAS or the Accountability Coordinator.

4.6 SITE EMERGENCY COORDINATOR (SEC): Directs assembly, accountability, site access control, and search and rescue of missing personnel.

4.7 RADIOLOGICAL ADVISOR: Reviews radiological hazards in assembly areas and recommends protective action to the SEC and the Security Advisor for security personnel.

5. PREREQUISITES 5.1 The SEC has decided to initiate assembly and accountability or the Site Emergency signal has sounded.

00020817.DOA 3B 4 vi 0817.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 5 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies

6. INSTRUCTIONS 6.1 Assembly 6.1.1 All individuals shall report to their designated Assembly Areas when hearing the Site Emergency signal or public address announcement directing assembly and accountability for locations assignment. Individuals outside of-the Protected Area should sign in, or be listed, on Form 69-13236.

NOTE 1: Individuals working on a specific job should place work area in a safe condition before proceeding to designated assembly areas.

NOTE 2: Individuals in the RCA should proceed to Radiological Access Control and then to assigned assembly areas.

6.1.2 Bio Lab individuals should assemble at the Training Building and wait for instructions from announcements made over the plant public address system.

6.1.3 On-call Emergency Response Organization personnel shall report to the designated Emergency Response Facility.

6.1.4 500KV Switchyard Area personnel shall assemble at the switchyard area and wait for announcements over the public address system.

NOTE: Depending upon plant conditions, they may decide to relocate to San Luis Obispo Distribution Operations Facility with SEC permission.

6.1.5 Medical Staff shall remain in the Medical Facility during the Alert level of an emergency and relocate to the OSC during a Site Area or General Emergency.

Injured individuals at the facility, deemed by the medical staff to need offsite care, should be transported by an offsite ambulance.

6.1.6 Contractors and temporary additionals should report to Parking Lot #7 and wait for instructions from the public address system.

6.1.7 Designated Assembly Area Supervisors outside the Protected Area shall complete Form 69-13236, and fax to the Accountability Coordinator.

6.1.8 Radiological Controls Area (RCA)

a. On-watch Operations individuals should report to Radiological Access Control and then the Control Room unless otherwise directed by Control Room personnel.

b. Operations, Maintenance and Radiation Protection individuals engaged in critical operations or emergency response actions, as directed by the Interim SEC or Emergency Operations Coordinator, shall call or report to Radiological Access Control as soon as practical and then proceed to assigned assembly areas.

c. When hearing the containment evacuation signal, individuals in containment shall immediately leave and report to Radiological Access Control.

00020817.DOA 3B 5 vi 0817.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 6 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies 6.1.9 Security Personnel shall report into CAS via radio check or telephone.

6.1.10 Visitors shall be escorted to the Security Building lobby by the escort assigned to them for emergency accountability listing and further instructions regarding their movement depending on the level of emergency.

6.2 Accountability 6.2.1 Accountability Coordinator shall assist the Diablo Canyon Watch Commander with accountability by following Appendix 8.2. Complete accountability and report results to the Security Advisor in the TSC.

6.2.2 Operations personnel assigned to the on-watch crew shall report to the Control Room for accountability. The Shift Manager, or designee, shall report findings to the Accountability Coordinator on Form 69-13231.

6.2.3 Emergency Maintenance Coordinator shall direct one of the Maintenance Coordinators to act as the OSC DAAS and complete Form 69-13232.

6.2.4 Medical Staff shall complete Form 69-13234 and fax to the Accountability Coordinator.

NOTE: The Medical Staff shall relocate to the OSC upon declaration of a Site Area or General Emergency. The Medical Staff will become part of Emergency Safety Services.

6.2.5 The Security Advisor shall complete Form 69-13233.

6.2.6 Personnel within the Radiological Controls Area (RCA)

a. Maintenance and Radiation Protection individuals performing critical operations or emergency actions shall be accounted for by calling the OSC as soon as practical, or the radiological access control point when the OSC is not manned.

b. Individuals manning the radiological access control point shall complete Form 69-13235 for individuals within the RCA only and forward the list to the Accountability Coordinator. Individuals manning the radiological access control point shall instruct individuals exiting the RCA to proceed directly to their assigned assembly area.

7. RECORDS 7.1 Forms in this procedure completed for a drill, exercise, or actual emergency shall be forwarded the next working day to the Emergency Planning Supervisor for review and retention.

8. APPENDICES 8.1 Assembly Areas 8.2 Accountability Coordinator Checklist 00020817.DOA 3B 6 VI 0817.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 7 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies

9. ATTACHMENTS 9.1 Form 69-13229, "Assembly Area Roster Summary," 08/17/00 9.2 Form 69-13230, "Missing Personnel Roster," 07/27/00 9.3 Form 69-13231, "Control Room - Assembly And Accountability Checklist," 07/27/00 9.4 Form 69-13232, "Operational Support Center - Assembly And Accountability Checklist,"

08/02/00 9.5 Form 69-13233, "Technical Support Center - Assembly And Accountability Checklist,"

08/02/00 9.6 Form 69-13234, "Medical Facility - Assembly And Accountability Checklist," 08/02/00 9.7 Form 69-13235, "Radiological Access Control 85' Elevation - Assembly And Accountability,"

08/02/00 9.8 Form 69-13236, "Assembly Area Roster (Outside Protected Area)," 08/02/00 9.9 "DCPP Aerial View," 08/10/00 9.10 "Building 109, Training Center, First Floor," 08/10/00 9.11 "Building 109, Training Center, Second Floor," 08/10/00 9.12 "Building 119, Maintenance Center, First Floor," 08/10/00

10. REFERENCES 10.1 EP EF-1, "Activation and Operation of the Technical Support Center."

10.2 EP EF-2, "Activation and Operation of the Operational Support Center."

10.3 EP G-2, "Activation and Operation of the Interim Site Emergency Organization."

10.4 EP G-3, "Notification of Off-site Agencies and Emergency Organization Personnel."

10.5 EP G-5, "Evacuation of Nonessential Site Personnel."

00020817.DOA 3B VI 08 17.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 8 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies APPENDIX 8.1 ASSEMBLY AREAS Assembly Area # Assembly Area Location Assembly Area Personnel

1 Control Room **Shift Foreman Shift Manager Operators, STAs, Clerks Resident NRC Inspector

2 TSC "**Security Advisor TSC Emergency Response Organization Personnel

3 OSC "**Emergency Maintenance Coordinator OSC Emergency Response Organization Personnel

4 Radiological Access Control **RP Foreman, CHEM Foreman or Senior RP/Chemistry person present Individuals manning RAC.

5 Security Bldg Lobby Security Staff Officers not on patrol.

Visitors (Posted officers remain in position and respond to communications checks unless directed otherwise.)

6 Learning Center Training Building (109)

Room 107,108,109 All ASSET Teams Room 114 General Services Room 121 Engineering Services Room 122,123 C&TS, Human Resources and Other PG&E not listed Room 205 Outage Services Room 206 Plant Management Room 207, 212 Operation Services Room 237 Learning Services, Bio Lab personnel Room 243 Procedure Services

- Designated Assembly Area Supervisor 00020817.DOA 3B 8 Vl 0817.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 9 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies APPENDIX 8.1 (Continued)

Assembly Area # Assembly Area Location Assembly Area Personnel

6 Learning Center Maintenance Shop Bldg (119)

Room 144 (NPG Library) Materials/Services, Regulatory Services NQS

- Substation Operating Foreman

8 500 kV Switchyard System Operator Switchyard personnel

9 Parking Lot #7 Contractors/Temporary additionals

10 Medical Facility Medical personnel

- Designated Assembly Area Supervisor 00020817.DOA 3B 9 VI 0817.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 10 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies APPENDIX 8.2 ACCOUNTABILITY COORDINATOR CHECKLIST ACCOUNTABILITY COORDINATOR: DATE TIME/INITIALS Diablo Canyon Watch Commander assign "Accountability Coordinator," if needed.

I1. INCOMING INFORMATION:

Assign an officer to the bridge line and FAX machine to receive accountability information from Assembly Areas within the Protected Area.

2. HIGH TRAFFIC AREAS:

Assign an officer to expedite emergency egress (i.e., Doors 129, 517-2 and Security Building), as required.

3. SITE INGRESS AND EGRESS:

Notify Avila Gate of plant conditions and status of personnel, i.e.,

visitors, tour buses.

NOTE: Call the security advisor if TSC is manned and/or Control Room for instructions.

Instruct Avila Gate staff to control access and egress depending on site conditions.

Individuals with current valid DCPP automobile passes will be granted plant access. Authorization is implied for individuals called out for emergency response and they will be allowed access through Avila Gate. Other individuals will require SEC approval.

NOTE: If the Avila Gate is not manned, the Security Watch Commander will send a security mobile control unit to the gate.

4. CENTRAL ALARM STATION (CAS)

Security Personnel: Complete Accountability Radio Check

5. PROTECTED AREA ACCOUNTABILITY:

Initiate accountability upon sounding of the site emergency signal or public address announcement directing accountability.

Accountability Start Time:

(Accountability starts at the sounding of the Site Emergency signal or public address announcing assembly/accountability whichever occurs first.)

00020817.DOA 3B 10 Vi 0817.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 11 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies APPENDIX 8.2 (Continued)

TIME/INITIALS

5. PROTECTED AREA ACCOUNTABILITY (Continued):

After receiving accountability checklists from the following assembly areas, compare them to the computer generated Emergency Accountability Listing:

Control Room (x3377)3 /

Technical Support Center /

_3260_)_

Operational Support Center/(x2605) /

Medical Facility '(x4566, or x4516) /

Radiological Access Control 85' Elevation [x3247)!

CAS (Report of Accountability Radio Check) /

Late Badges:

When computer generates Emergency Accountability Listing, direct a Security Officer to collect keycards at the exit turnstyle. Mark these individuals off the Emergency Accountability Listing. /

Compare information received from Assembly Areas with Emergency Accountability Listing, complete Missing Personnel Roster, Form 69-13230, and forward to the TSC Security Advisor if TSC is activated. If TSC is not activated, forward to the Interim SEC (Operations Shift Manager).

Accountability Completion Time:

(Accountability is complete when all Protected Area accountability reports are received, a comparison has been made against the Emergency Accountability Listing report and missing individuals are identified.)

If facilities within the Protected Area are not activated prior to completion of accountability, a followup Emergency Accountability Listing shall be completed.

Establish phone locations at checkin counter for individuals entering Protected Area to call destination assembly area for accountability after facility activation.

After TSC and OSC are activated, ensure individuals entering Protected Area call destination Assembly Areas. If there is a loss of site power, dispatch a Security Officer to the main warehouse to alert individuals of the sounding of the site emergency alarm.

3B 11 Vi 0817.0750 00020817.DOA

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 12 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies APPENDIX 8.2 (Continued)

TIME/INITIALS

6. MISSING PERSONNEL:

If there are missing personnel, initiate the following additional actions:

Last Known Location:

Attempt to identify the last known location of the person(s) through Emergency Accountability Listing printout or alternate Security Computer command. /

Search and Rescue:

Check Assembly Area Rosters (Outside Protected Area), Form 69-13236 for names of missing personnel.

Provide names and potential locations of missing individuals to the TSC Security Advisor or the Control Room Interim SEC (if the TSC is not activated). Forward Missing Personnel Roster, Form 69-13230 to the TSC Security Advisor or the ISEC if the TSC is not manned. /

If individuals are missing within the Protected Area, sweeps of the following areas should be conducted:

Lube Oil and Dirty Lube Oil Storage Room (Door #193)

Inside Door 129, turn left; on west wall up a ladder next to Nash Vacuum Pump. /

Condensate Pump Pit U-1 Inside and north of Door 123-1; along west wall, three large yellow pumps. /

Heater Drip Pump (DRP)

Unit 1 - Inside and south of Door 123-1; along west wall (one pump). /

Unit 2 - Inside and north of Door 123-2; along west wall (one pump). /

Condensate Pump Pit U-2 Inside and south of Door 123-2; along west wall, three large yellow pumps. /

Post LOCA Sample Room U-I Door 116-1 (inside) /

Post LOCA Sample Room U-2 Inside Door 192-2 and then inside 197-2. /

00020817.DOA 3B 12 vi 0817.0750

NUMBER EP G-4 PACIFIC GAS AND ELECTRIC COMPANY REVISION 17 DIABLO CANYON POWER PLANT PAGE 13 OF 15 UNITS 1 AND 2 TITLE: Personnel Assembly, Accountability and Site Access Control During Emergencies APPENDIX 8.2 (Continued)

TIME/INITIALS

6. MISSING PERSONNEL (Continued):

85' AUX Building Primary Chemistry Lab /

Chemistry Foreman's and Decon Foreman's Office /

Security Building APs Offices behind break room /

ADMIN BUILDING ARA Office in NE comer of 1st floor I

/

Main Warehouse And Loading Dock 140' Turbine Bldg U-2 Maintenance crew trailer /

7. AREA RELOCATION:

The SEC may direct Assembly Area relocation(s) or evacuation(s).

Assist as necessary. /

8. VISITORS:

Assign an officer to initiate an Emergency Accountability Listing and provide further instructions to visitors assembled in the Security

/

Building Lobby.

9. ASSEMBLY AREAS:

NOTE: Assembly Areas may initiate communications usinJx2001 }bridge line).

I Provide plant status updates to Assembly Areas and assist areas as necessary.

Parking Lot #7 - x64993 /

500 KV Switchyard Operations Supervisor -x3519 / I 0817.0750 00020817.DOA 3B 13 VI

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 14 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies APPENDIX 8.2 (Continued)

TIME/INITIALS

10. NOTIFICATIONS:

Notify MAP groups or tours presently on site. Refer to MAP folder in DCPP Watch Commander's office for current information. /

Call Adjoining Property:

Inform individuals on properties north and south of the plant of conditions. Direct them to exit the Montana de Oro or Avila Gate. /

South Property:

Halfway House 595-2948 /

North Property Ranch House Kitchen 528-3514 /

Dining Area 528-3324 Downstairs Conference Room 528-3515 /

Upstairs Conference Room /

West 1528-3871 Upstairs Conference Room East 528-3324 Bob Blanchard In trailer near ranch house 534-9649 /

The Petersons House near North Gate 1528-8268 /

Point San Luis Lighthouse j 5 9 5 -2 9 3 6 /

Owner Controlled Area:

Notify temporary workers within this area and ensure they exit through the north or south gate as appropriate. /

Outside the Protected Area Sea Water Reverse Osmosis Facility near the Biology Lab. /

Hazardous Waste Area (Area 10) near the Marine Biology Lab. /

South bound mobile Marine Biology Lab - If tour group is present, ensure they are boarding the bus to proceed off-site. /

North bound mobile agriculture workers on the bench land will be alerted by dispatching a Security Officer to the area notifying them of the emergency and explaining what actions are expected of them. /

00020817.DOA 3B 14 VI 0817.0750

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 17 PAGE 15 OF 15 TITLE: Personnel Assembly, Accountability and Site Access UNITS 1 AND 2 Control During Emergencies APPENDIX 8.2 (Continued)

TIME/INITIALS

10. NOTIFICATIONS (Continued):

Fitness Trail /

Ionics Makeup Water Treatment Facility (next to raw water storage /

area or west of 230KV Switchgear Yard)

Pecho Ranch Property - If tour group is present, escort them to the /

Montano de Oro Park gate exit.

1I. SITE VEHICLE INFORMATION:

Assign a Security Officer to determine approximate number of vehicles on site. The Sheriff's Department will need this information to determine traffic control needs if evacuation occurs. I Report number of vehicles to the TSC Security Advisor. I All other units should contact CAS for status reports and instructions.

Secondary Alarm Station (SAS):

Marine Channel 7A: /

/

Check for TES individuals out on boats.

12. RELOCATING SECURITY PERSONNEL:

With the coordination of the Security Advisor and based on radiological conditions, relocate security individuals to safe positions, yet maintain security commitments (including those in the Security Building and the Central Alarm Station). Repositioning that reduces the effectiveness of commitments must be coordinated through the security advisor and approved by a senior reactor licensed person prior to implementation. /

3B 15 VI 0817.0750 00020817.DOA

69-13229 08/17/00 Page I of 1 DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.1 I1ND2 TITLE: Assembly Area Roster Summary Initial each line acknowledging receipt of accountability forms.

TRAINING BUILDING RECEIVED ACCOUNTABILITY FORM COMPLETED BY Room 107 Room 108 Room 109 Room 114 Room 121 Room 122 Room 123 Room 205 Room 206 Room 207 Room 212 Room 237 Room 243 MAINTENANCE SHOPS BUILDING Room 144 500 KV Switchyard Parking Lot #7 00020817.DOA 3B 16 VI 0817.0750

07/27/00 Page 1 of 1 69-13230 DIABLO CANYON POWER PLANT EP G-4 ATITACHMENT 9.2 1 AND 2

TITLE: Missing Personnel Roster PRINT LAST NAME PRINT FIRST NAME KEYCARD NUMBER 2.

3.

4.

5.

6.

7.

8.

9.

10.

ll.

12.

13.

14.

15.

16.

17.

18.

-19.

20.

Completed By: Date/Time /

NOTE: FORWARD THIS LIST TO THE TSC SECURITY ADVISOR OR THE INTERIM SEC IN THE CONTROL ROOM IF THE TSC IS NOT MANNED.

00020817.DOA 3B 17 VI 0817.0750

69-13231 07/27/00 Page I of 3 DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.3 12 TITLE: Control Room - Assembly and Accountability Checklist Shift Supervisor shall complete this checklist for accountability of Operations personnel. Include personnel/crews that may be performing a specific job. List Operations on-Shift crew individuals (including the Firefighters) in a timely fashion and FAX this information to the Accountability Coordinator at extf3115",or 545-3115 within 15 minutes. ý,The Accountability Coordinator can be reached on bridge phone extJ"200l-i

-RECORD NAME, KEYCA.RD, NUMBER AND SOCIAL SECURITY NO. OF STRAGGLERS AND FAX I IMMEDIATELY TO THE ACCOUNTABILITY COORDINATOR.

NAME KEYCARD SOCIAL SECURITY #

I 4 i i i i 4 4 i 4

4. 4

_______________________________________ J. ____________________________ I 3B 18 vi 0817.0'750 00020817.DOA

69-13231 07/27/00 Page 2 of 3 EP G-4 (UNITS 1 AND 2)

ATITACHMENT 9.3 TITLE: Control Room - Assembly and Accountability Checklist NAME KEYCARD SOCIAL SECURITY #

________ I ______ I _______ I

+ J

+ 4 i I 4- 4 i i 4 4 1 4 i i 4 4 A __________________________ I 00020817. DOA 3B 19 VI 0817.0750

07/27/00 Page 3 of 3 69-13231 EP G-4 (UNITS 1 AND 2)

ATTACHMENT 9.3 TITLE: Control Room - Assembly and Accountability Checklist NAME KEYCARD I SOCIAL SECURITY #

+ t

+ I i

+ I i i Completed By: Date/Time /

VI 0817.0750 00020817.DOA 3B 20

Page 1 of 4 69-13232 08/02/00 DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.4 AND2 TITLE: Operational Support Center - Assembly and Accountability Checklist The Emergency Maintenance Coordinator or designee shall complete this checklist for accountability of the OSC staff. List mdividuals.*ssigned to the OSC and FAX this information to the Accountability Coordinator at ext. 3115 or 545-3115 within 15 minutes. Accountability Coordinator can be reached on bridge phone 7ext. 2001 RECORDINAME, KEYCARD NUMBER, AND SOCIAL SECURITY NO. OF STRAGGLERS AND FA' IMMEDIATELY TO THE ACCOUNTABILITY COORDINATOR.

I NAME (Print Last Name) KEYCARD NUMBER SOCIAL SECURITY #

I i i i 4.

I. t 4.

4. t I4.

4. t

4. t I. i J. 9

4. I

+ I

.1. I

4. I 3B 21 VI 0817.0750 00020817.DOA

69-13232 08/02/00 Page 2 of 4 EP G-4 (UNITS 1 AND 2)

ATTACHMENT 9.4 TITLE: Operational Support Center - Assembly and Accountability Checklist NAME (Print Last Name) KEYCARD NUMBER SOCIAL SECURITY #

4.

4 4 4 4 4 4

$ 4 4 4.

t 4.

4 4.

t ¶ 4 4 t 4 4 4 i i 00020817.DOA 3B 22 VI 0817.0750

69-13232 08/02/00 Page 3 of 4 EP G-4 (UNITS I AND 2)

ATTACHMENT 9.4 TITLE: Operational Support Center - Assembly and Accountability Checklist NOTE: at a Site Area or General Emergency, if medical facility staff individuals have not physically relocated in the OSC, contact the Accountability Coordinator immediately. If medical staff is handling a medical emergency, they should be directed to continue and contact the OSC when situation becomes stable.

When medical staff relocates to the OSC, contact security and inform of relocation.

NAME KEYCARD NUMBER SOCIAL SECURITY #

(Print Last Name)

I 4

t.

I +

I 1 1 4.

4.

i I.

1 4.

i i.

I 4.

1 4 00020817.DOA 3B 23 VI 0817.0750

69-13232 08/02/00 Page 4 of 4 EP G-4 (UNITS 1 AND 2)

ATTACHMENT 9.4 TITLE: Operational Support Center - Assembly and Accountability Checklist NAME (Print Last Name) KEYCARD NUMBER SOCIAL SECURITY #

4 4 4 .9 4 I L 4 4 I

& I I t I I I I I I I I-Completed By: Date/Time /

00020817.DOA 3B 24 VI 0817.0750

69-13233 08/02/00 Page I of 3 DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.5 1

TITLE: Technical Support Center - Assembly and Accountability Checklist The Security Advisor shall complete this checklist for accountability of the TSC staff. List indivduals assigned to the TSC and FAX this information to the Accountability Coordinator at ext;3115 or 545-3115 ithin 15 minutes. Accountability Coordinator can be reached on bridge phone ext20If RECORD NAME, KEYCARD NUMBER, AND SOCIAL SECURITY NO. OF STRAGGLERS AND FAX IMMEDIATELY TO THE ACCOUNTABILITY COORDINATOR.

NAME (Print Last Name) KEYCARD NUMBER SOCIAL SECURITY #

4. 4 i w

4. 4 4.i

+

4. v i i i i

+ I

4. I 4 1

4. i 4 1

4. i

4. 9 S

0817.0750 00020817.DOA 3B 25 VI

69-13233 08/02/00 Page 2 of 3 EP G-4 (UNITS 1 AND 2)

ATTACHMENT 9.5 TITLE: Technical Support Center - Assembly and Accountability Checklist NAME (Print Last Name) KEYCARD NUMBER SOCIAL SECURITY #

4 4

+ 4

4. 9

.4.

1*

4.

4. .4

____ I___ I 4 .4 I +

4 .4 4 +

f +

9 4.

4 .4 4 4.

L ___________________ .4 Completed By: Date/Time /

00020817.DOA 3B 26 V! 0817.0750

69-13233 08/02/00 Page 3 of 3 EP G-4 (UNITS 1 AND 2)

ATTACHMENT 9.5 TITLE: Technical Support Center - Assembly and Accountability Checklist NAME (Print Last Name) KEYCARD NUMBER SOCIAL SECURITY #

I t I. 9

.4 4 I 4 9 4 I 4 i 4 9 4 I 4

4 9

.1. I

.9.

+ I i i 4 I

1. 9 4 I

- I

. Completed By: Date/Time I 00020817.DOA 3B 27 VI 0917.0750

Page I of 2 69-13234 08/02/00 DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.6 AND2 TITLE: Medical Facility - Assembly and Accountability Checklist The Senior Medical person shall complete this checklist for accountability of the Medical Facility. List individuals assigned to the Medical Facility and FAX this information to the Accountability Coordinator at 4it.

r3115 or 545-31 15vithin 15 minutes. Accountability Coordinator can be reached on bridge phone ext? 2001.2 At the Site Area or General Emergency relocate Medical staff to the OSC. If a Medical Emergency is in progress, continue treatment and contact the OSC when the situation stabilizes. RECORD NAME, KEYCARD NUMBER, i

AND SOCIAL SECURITY NO. OF STRAGGLERS AND FAX IMMEDIATELY TO THE ACCOUNTABILITY COORDINATOR AT EXTI[l15 OR 545-311IS.

NAME (Print Last Name) KEYCARD NUMBER SOCIAL SECURITY #

+ t 4 1*

4 4 4i i 4 +

4 4 4 t 4 t

.4 4 4

4 1 4 1 4-I i i If I 1 I i

__________________________________ a I Completed By: Date/Time /

3B 28 Vi 0817.0750 00020817.DOA

69-13234 08/02/00 Page 2 of 2 EP G-4 (UNITS 1 AND 2)

ATTACHMENT 9.6 TITLE: Medical Facility - Assembly and Accountability Checklist NAME (Print Last Name) KEYCARD NUMBER SOCIAL SECURITY #

.4. 1

4. 4

¶ t 4 4 4 4 4 4 4 .4.

4 .4.

4 +

+

Completed By: Date/Time /

00020817.DOA 3B 29 Vi 0817.0750

69-13235 08/02/00 Page 1 of 2 DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.7 I1ND2 TITLE: Radiological Access Control 85' Elevation - Assembly and Accountability The Senior Chem/Rad Technician present shall complete this checklist for accountability of the RCA. List individuals assigned to the RCA and FAX this information to the Accountability Coordinator at exti1 15 or]

(545-31 lwithin 15 minutes. Accountability Coordinator can be reached on bridge phone ext. 2001. RECORD I W'AME,9EYCARD NUMBER, AND SOCIAL SECURITY NO. OF STRAGGLERS AND FAX IMMEDIATELY TO THE ACCOUNTABILITY COORDINATOR AT EXT.[3115 OR 545-31157 i

NAME (Print Last Name) KEYCARD NUMBER SOCIAL SECURITY #

I 4 I 4 I

___ I 4

4 t I I 4 1

_________________________________ J ________________________ I Completed By: Date/Time /

0817.0750 00020817.DOA 3B 30 VI

69-13235 08/02/00 Page 2 of 2 EP G-4 (UNITS 1 AND 2)

ATTACHMENT 9.7 TITLE: Radiological Access Control 85 Elevation - Assembly and Accountability NAME (Print Last Name) KEYCARD NUMBER SOCIAL SECURITY #

4 &

i -

Completed By: Date/Time /

00020817.DOA 3B 31 VI 0817.0750

69-13236 08/02/00 Page I of I DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.8 1

TITLE: Assembly Area Roster (Outside Protected Area)

ASSEMBLY AREA LOCATION:

DATE:

PRINT LAST NAME KEYCARD NUMBER SOCIAL SECURITY #

1.

2.

3.

4.

5.

6.

7. _

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

Completed By: Date/Time /

00020817.DOA 3B 32 Vi 0817.0750

,1/00 Page I 1 2 DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.9 AND TITLE: DCPP Aerial View 00020817. DOA 3B 33 VI 0817.0750

4. _Oj00 Page 1,-. I DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.10 SAND 2 TITLE: Building 109, Training Center, First Floor LI II OHM ROOM IFU CLASS ROOM CLASSROOM 10w 121 t

I I CLASS ROOM 101 IIFIO CLASSROOM 122 A)yý--

CLASSROOM CLASSROOM 10v 123 I Il LLO.Y K., J 102 LI 125 00020817.DOA 3B 34 Vi 0817.0750

k J/&0 Page I - I 1 2 DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.11 AND TITLE: Building 109, Training Center, Second Floor DN i\ - i CLASSROOM CL.ASSROOM CLASSROOM 207A 2073 S. .. ....

CLASSROOM 206 CLA2SROOM

205 00020817.DOA 3B 35 Vl 0817.0Y750

JL Page Pi00 i 1 2 DIABLO CANYON POWER PLANT EP G-4 ATTACHMENT 9.12 AND TITLE: Building 119, Maintenance Center, First Floor 04

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gap Few

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El XJTDOOA STORAME

& WOAK WA LEA 00020817.DOA 3B 36 VI 0817.0750

- - ISSUED FOR USE BY: DATE: EXPIRES: ***

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-8 NUCLEAR POWER GENERATION REVISION 13 DIABLO CANYON POWER PLANT PAGE 1 OF 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Instructions for Field Monitoring Teams 1 AND 2 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION PAGE SC O P E ......................................................................................................................... 1 D ISC U SSIO N ................................................................................................................. 1 RESPO N SIBILITIES ..................................................................................................... 2 RADIOLOGICAL PRECAUTIONS ...................................................................................... 2 IN STRU CTIO N S ......................................................................................................... 3 RE C O RD S ................................................................................................................... 10 ATTACHM ENTS ....................................................................................................... 10 REFEREN C ES .......................................................................................................... 10

1. SCOPE 1.1 This procedure provides instructions for performing field monitoring during an emergency event.

1.2 This procedure does not provide instructions for duties routinely performed by individuals qualified in radiation protection procedures, e.g. performing radiation surveys, donning protective clothing and dosimetry. Instructions unique to field monitoring are included, such as collecting .soil and vegetation samples.

1.3 This procedure was rewritten; therefore, revision bars are not included.

2. DISCUSSION 2.1 For emergencies at the Alert, or higher level, Field Monitoring Teams (FMTs) are dispatched to designated field locations to determine general area dose rates, ground contamination count rates, and activity concentrations of airborne radionuclides.

Ingestion pathway samples may be collected. FMTs gather data and information to determine protective actions to protect public health and safety.

2.2 Offsite field monitoring is performed by San Luis Obispo (SLO) County and PG&E personnel to produce one set of FMT data. Redundant sampling is not necessary. SLO County may take additional measurements and samples. For convenience, each FMT has field monitoring equipment stored in kits. Kits contain sampling equipment and survey instruments. Dosimetry, protective clothing, radios, and miscellaneous supplies are stored on shelves next to the kits.

r

J ,-,,I£J.L".n , 0817.0759

%"'&j I I a J. LOW^ ,JIJ, II Idl

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-8 DIABLO CANYON POWER PLANT REVISION 13 PAGE 2 OF 10 TITLE: Instructions for Field Monitoring Teams UNITS 1 AND 2 2.3 Individuals trained in field monitoring techniques may transport field samples from FMTs to a counting facility for analysis.

2.4 Each FMT should be comprised of two individuals, a HP technician and another individual trained in field monitoring techniques to provide support.

2.4.1 Each offsite FMT should consist of one of the following:

a. (2) HP Technician and (1) SLO County Environmental Health Specialist, or

b. (1) HP Technician and (1) Decontamination Specialist or Utility Worker, or

c. (1) HP Technician and (1) SLO County Environmental Health Specialist.

2.4.2 Each onsite FMT should consist of one of the following:

a. (2) HP Technicians, or

b. (1) HP Technician and (1) Decontamination Specialist or Utility Worker.

3. RESPONSIBILITIES 3.1 HP Technicians assume responsibility as the FMT leader. If two HP Technicians are assigned as a FMT, the senior technician assumes the role as FMT Leader.

3.2 Initially Radiation Protection dispatches the FMTs directly from Access Control upon declaration of an Alert or higher event. The Control Room assumes the responsibility for command and control of FMTs until the TSC and UDAC staff can assume responsibility. Once the TSC is activated, command and control of onsite FMTs becomes the responsibility of the TSC. Once the UDAC is activated, command and control of offsite FMTs becomes the responsibility of UDAC.

3.3 Offsite Environmental Laboratory (OEL) operators coordinate dispatching offsite FMTs, including assigning individuals to teams and providing the initial team briefs. If the OEL operator is not present, team assignment and dispatch will be coordinated directly by UDAC.

4. RADIOLOGICAL PRECAUTIONS 4.1 500 mR/hr is the default turnback dose rate unless the controlling facility determines an adjusted turnback dose rate. If a turnback dose rate is approached, or exceeded, depart the area immediately to a lower dose rate area and report to the controlling facility for further instructions.

4.2 Potassium iodide (KI) should only be taken when authorized by the controlling facility.

4.3 Maintain exposures ALARA. Keep plume stay times to a minimum.

4.4 Always have survey instruments powered on and within your possession.

4.5 Report to the controlling facility at least hourly, whenever radiological conditions significantly change, or upon arrival at a new monitoring location.

00251713.DOA 3B 2 I1 0817.0759

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-8 DIABLO CANYON POWER PLANT REVISION 13 PAGE 3 OF 10 TITLE: Instructions for Field Monitoring Teams UNITS 1 AND 2 4.6 Self reading dosimeters should be read approximately every 15 minutes as a rule of thumb, depending on the general area dose rates. Dose should be reported to the controlling facility hourly or when the SLO County Environmental Health Specialist report their dose. Unexpected dose readings should be reported immediately.

4.7 When driving in the plume close all vehicle windows and turn off outside air ventilation.

4.8 Don respiratory protection whenever:

4.8.1 directed by the controlling facility, or 4.8.2 entering a plume of unknown or suspected high particulate or iodine concentrations.

5. INSTRUCTIONS 5.1 During the pre-deployment stage FMT members should:

NOTE: Use your personal vehicle to report to the OEL garage from offsite.

5.1.1 Obtain a company dedicated vehicle and fill with fuel.

5.1.2 Obtain a TLD.

a. If reporting from onsite, retain your TLD when exiting the Protected Area.

b. If reporting to the OEL garage from offsite, an estimating device and/or TLD will be issued by the OEL Operator.

5.1.3 Report to the assigned field monitoring staging area.

NOTE: The PG&E Service Center front gate will be locke* The Center can be accessed at the back entry gate using a *&E 909 ke9 or by obtaining the front gate access code from the Access Senior x3247)..'

a. Onsite FMT Kits are stored at the Learning Services Building, Room 126 (near the lobby elevator).

b. Offsite FMT Kits are stored at the OEL garage. The garage door has an Omnilock keypad. To obtain the Omnilock code, call the Access Senior x3247)j 5.1.4 Upon arrival at the staging area, immediately contact the controlling facility for Minimum Staff accountability (signs with the EOF and TSC phone numbers to use are on the OEL door and the onsite FMT Kit room door).

Perform a radio check and receive an initial briefing. The OEL Operator will organize the PG&E and SLO County personnel into the Offsite FMTs and will conduct an initial tailboard, prior to the teams being dispatched into the field.

,A,,-, T'A *n 0817.0759 Al..

Il A . * *D J u

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-8 DIABLO CANYON POWER PLANT REVISION 13 PAGE 4 OF 10 TITLE: Instructions for Field Monitoring Teams UNITS 1 AND 2

a. Board mounted radios (OEL only), and hand held radios are stored next to kits and are equipped with a 12V battery adapter (to be plugged into the vehicle cigarette lighter) along with an amplified gain antenna (to be attached to the vehicle roof).

b. When performing the radio check, verify communications can be established on field monitoring channels CH-7, CH- 8, and CH- 11. If a radio does not function properly, chose another. If adequate radio communications can not be established, telephone the controlling facility for instructions using the phone numbers in Attachment 7.6.

5.1.5 Obtain a kit and check for contents.

a. Read the kit label and take only the kits designated for your team.

b. If kits plastic seal(s) are broken perform a complete inventory.

5.1.6 Battery check and response check the survey instruments.

a. A copy of RCP D-900 is in the PG&E FMT position binder.

b. The check sources are mounted on the wall next to the kit storage shelves.

5.1.7 Obtain respirators and filter cartridges from the shelf.

a. Select the correct size respirator (Small-gray, Medium-black, or Large-orange).

b. Attach fresh cartridge filters and perform a respirator inspection.

5.1.8 Don coveralls from the storage shelves.

5.1.9 Place gloves, booties, hoods, and inspected respirators in vehicle for ready use when contamination is encountered.

5.1.10 Zero pocket ion chambers and don dosimetry (stored on the shelf next to the kits).

a. low range (0-200 mR) pocket ion chamber, and

b. high range (0-5 R) pocket ion chamber, and/or

c. TLD 5.1. 11 Operationally check the battery operated air sampler as follows.

a. Turn the vehicle off.

b. Attach the red cable of the air sampler to the (+) battery terminal.

c. Attach the black cable to a metal chassis ground (unpainted).

d. Position the air sampler away from the vehicle radiator fan. Do not place the air sampler on the ground.

00251713.DOA 3B 4 II 0817.0759

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-S DIABLO CANYON POWER PLANT REVISION 13 PAGE 5 OF 10 TITLE: Instructions for Field Monitoring Teams UNITS 1 AND 2

e. Start vehicle engine.

f. Attach the air sample head containing the particulate filter and iodine cartridge. Start the air sampler.

g. Check that air flow is in the readable range.

h. Obtain another air sampler if the check is unsatisfactory.

i. Turn off and disconnect the air sampler. Stop the vehicle engine if the check is satisfactory.

5.1.12 If time permits, pre-stage equipment (load air sampler heads, label coin envelopes, complete top of Attachment 7.8.).

5.2 Each FMT should follow the general instructions below.

5.2.1 Proceed to field monitoring location as directed by the controlling facility.

5.2.2 Periodically report dose rates and count rates inside the vehicle to the controlling facility as you travel, especially significant change.

5.2.3 Document field monitoring results using Attachment 7.8.

5.2.4 After receiving instruction from the controlling facility, perform the following field monitoring surveys.

NOTE: Dose rate survey results should be reported as soon as possible.

a. measure general area dose rates (open and closed window), and

b. collect an air sample

c. collect a minimum of 2 smears

d. if requested by the controlling facility, obtain a pressurized ion chamber reading if one is located at the monitoring location 5.2.5 Without stepping out of the vehicle,

a. Obtain a ground count rate with an E-140N or equivalent.

1. Probe should be held within 1 inch of the ground surface.

2. ncpm = (actual reading) - 60 cpm.

b. If greater than 100 ncpm:

1. inform the controlling facility, and

2. don appropriate protective clothing.

5.2.6 Move to a low background area (-60 ncpm) and perform field analysis of the particulate filter, iodine cartridge, and smears.

5.2.7 Place individually collected packaged and labeled samples into a large ziplock bag and label the outside using preprinted labels.

00251713.DOA 3B 5 II 0817.0759

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-8 DIABLO CANYON POWER PLANT REVISION 13 PAGE 6 OF 10 TITLE: Instructions for Field Monitoring Teams UNITS 1 AND 2 5.2.8 Take a smear survey of the large ziplock bag to verify the outside surface is uncontaminated. If contaminated, initiate actions to minimize the spread of contamination (e.g., wipe down the surface, rebag the item).

5.2.9 Upon completing monitoring activities, report results to the controlling facility.

5.2.10 Follow the instructions in the following sections as applicable.

SECTION ADDITIONAL INSTRUCTIONS PAGE 5.3 Collecting An Air Sample 6 5.4 Initial Count Rate Of The Air Sample Head 7 5.5 Determining Particulate Air Concentration 7 5.6 Determining Iodine Concentration 8 5.7 Determining Smearable Contamination 8 5.8 Pressurized Ion Chambers 9 5.9 Vegetation Samples 9 5.10 Liquid Samples 9 5.11 Soil Samples 9 5.12 Determining Skyshine 9 5.3 Collecting An Air Sample NOTE: DO NOT USE CHARCOAL CARTRIDGES. The air sampler is calibrated for TEDA-impregnated cartridges only.

5.3.1 Load the particulate filter and TEDA-impregnated cartridge in the air sampler head and attach the loaded head to the air sampler.

5.3.2 Attach the air sampler to the battery.

a. Turn the vehicle off.

b. Attach the red cable of the air sampler to the (+) battery terminal.

c. Attach the black cable to a metal chassis ground (unpainted).

d. Position the air sampler away from the vehicle radiator fan. Do not place the air sampler on the ground.

e. Start vehicle engine.

f. Start the air sampler.

1. Check for air flow.

2. Do not attempt to adjust the air flow set screw.

5.3.3 Record the air sample start time and flow rate on the Attachment 7.8.

5.3.4 Collect at least a 10 ft3 sample (a 30-50 ft3 sample is preferred).

00251713.DOA 3B 6 11 0817.0759

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-8 DIABLO CANYON POWER PLANT REVISION 13 PAGE 7 OF 10 TITLE: Instructions for Field Monitoring Teams UNITS 1 AND 2 5.3.5 Stop the air sampler. Record the air sample stop time on Attachment 7.8.

5.3.6 Calculate the air sample volume collected.

5.3.7 If required for contamination control or to prevent loss of radioactivity, place the loaded air sampler head in a unused ziplock bag. Place the sealed bag in the vehicle for analysis.

5.4 Initial Count Rate Of The Air Sample Head 5.4.1 Obtain a count rate on contact with the face of the loaded filter head. Noble gas retained in the filter and iodine cartridge may result in a higher than expected reading.

a. If in a normal background area (e.g., 60 cpm) and the sample indicates no ncpm, report the results to the controlling facility and skip Sections 5.5 and 5.6.

b. If in a normal or higher than normal background area (- 300 ncpm),

but the air sample activity is sufficient to obtain a valid ncpm reading, go to section 5.5 and 5.6.

c. If in a higher than normal background area and the air sample activity is too low to obtain a valid ncpm reading, go to another low background and proceed with 5.5 and 5.6.

5.5 Determining Particulate Air Concentration 5.5.1 Remove the filter from the sample head and then count it using the constant geometry jig. Record the particulate sample count rate on Attachment 7.8.

5.5.2 Label a coin envelope using the preprinted labels and place the particulate sample in the labeled coin envelope.

5.5.3 Using the particulate filter count rate and the air sample volume, calculate the gross particulate air concentration and record on the Field Monitoring Data Sheet.

MCi/cc - (1.6E - 10) x (ncpm)

V where:

ncpm = (gross cpm on filter paper in jig) - (bkg count rate)

V = volume of air collected (ft3) 5.6 Determining Iodine Concentration 5.6.1 In a low background area remove the particulate filter if it has not been done.

a. Remove the iodine cartridge, reverse it, and then place it back into the sample holder.

00251713.DOA 3B 7 lI 0817.0759

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-8 DIABLO CANYON POWER PLANT REVISION 13 PAGE 8 OF 10 TITLE: Instructions for Field Monitoring Teams UNITS 1 AND 2

b. Attach the sample head on the air sampler. Start the air sampler and purge the iodine cartridge for a minimum of 1 ft3 to remove entrained noble gases. This should take approximately 30 seconds at a flow rate of 2 cfm. Longer purge times may be needed if the sample was taken in high noble gas fields. Remove the iodine cartridge after the purge is done.

c. Count the iodine cartridge using the constant geometry jig. Record the iodine sample count rate on Attachment 7.8.

5.6.2 Label a small ziplock bag using the preprinted labels binder and place the iodine sample in the labeled bag.

5.6.3 Using the iodine cartridge count rate and the air sample volume, calculate the gross particulate air concentration and record on Attachment 7.8.

pCi/cc = (5.6E - 09) x (ncpm)

V where:

ncpm = (gross cpm on iodine cartridge in jig) - (bkg count rate)

V = volume of air collected (ft3) 5.7 Determining Smearable Contamination 5.7.1 In a low background area count the smear using the constant geometry jig.

Record the smear count rate on Attachment 7.8.

5.7.2 Label a coin envelope using the preprinted labels binder and place the smear sample in the labeled coin envelope.

5.7.3 Using the smear count rate, calculate the dpm per 100 cm2 and record on Attachment 7.8.

5.8 Pressurized Ion Chambers 5.8.1 Pressurized Ion Chambers may be read directly (some require pressing the "READ" push button installed on the front face of the instrument).

5.8.2 Review the strip chart for dose rate trending.

a. The trace which indicates the range (usually a straight line) matches one of the markings immediately below the chart. The PICs are auto-ranging units so normal readings are in units of gtR/hr. When the pR/hr range is exceeded, the actual dose rate is in units of mR/hr.

b. The second trace indicates the actual dose rate and should correspond with that shown on the digital display.

5.8.3 Record data on Attachment 7.8.

5.8.4 Report the reading to the controlling facility.

00251713.DOA 3B 8 II 0817.0759

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-8 DIABLO CANYON POWER PLANT REVISION 13 PAGE 9 OF 10 TITLE: Instructions for Field Monitoring Teams UNITS 1 AND 2 5.9 Vegetation Samples 5.9.1 Cut vegetation from at least a lm2 area of ground (approximately 1 to 2 pounds). Cut vegetation at a height of 1 to 2 cm from its base to approximate what a grazing animal would consume. Avoid contaminating the sample with dirt.

5.9.2 Place the vegetation in a plastic bag. Seal the bag and take an external contact count rate. Verify that the outside of the bag is uncontaminated. If contaminated, initiate actions to minimize the spread of contamination.

5.9.3 Label the bag (date, location, net contact count rate).

5.10 Liquid Samples 5.10.1 Collect and label a 1 liter sample and retain for later analysis. If readings 2_200 net cpm are obtained on contact or if general area contamination was noted, place the 1 liter sample in a sealed plastic bag.

5.11 Soil Samples 5.11.1 Sample the soil from a lm2 area. Using a trowel, collect on higher than the top 'A inch surface of soil.

5.11.2 Place the sample in a bag, seal, count and label. Verify the outside of the bag is uncontaminated. If contaminated, initiate actions to minimize the spread of contamination.

5.12 Determining Skyshine 5.12.1 Using an E-140 with a shielded HP-210 GM pancake probe or equivalent held at waist height, measure the count rate with the probe mylar window pointed UP, toward the sky. Record the WINDOW UP count rate Attachment 7.8.

5.12.2 Using an E-140 with a-shielded HP-210 GM pancake probe or equivalent held at waist height, measure the count rate with the probe mylar window pointed DOWN, toward the ground. Record the WINDOW DOWN count rate on Attachment 7.8.

5.12.3 To calculate skyshine, subtract the down count rate from the up count rate.

Record the skyshine net count rate on Attachment 7.8.

5.13 The FMTs should perform the following after field monitoring is no longer required.

5.13.1 Return the vehicle to the OEL, fill the tank, and return the key.

5.13.2 Inventory, replenish, seal, and return the field monitoring kit to ready status.

If supplies are unavailable to replenish the kit, notify the Safety and Fire Protection supervisor the next working day.

00251713.DOA 3B 9 11 0817.0759

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-8 DIABLO CANYON POWER PLANT REVISION 13 PAGE 10 OF 10 TITLE: Instructions for Field Monitoring Teams UNITS 1 AND 2

6. RECORDS 6.1 The FMT leader shall ensure completed Attachment 7.8 forms are sent to the controlling facility.

6.2 The attachments generated during an emergency drill or exercise should be sent to the Emergency Planning Group for review and retention.

7. ATTACHMENTS 7.1 "Offsite Field Monitoring Locations Map," 08/10/00 7.2 "Offsite Field Monitoring Locations Descriptions," 08/17/00 7.3 "Onsite Field Monitoring Locations Map," 08/10/00 7.4 "Onsite Field Monitoring Locations Descriptions," 08/17/00 7.5 "Pressurized ION Chamber Location Descriptions," 08/10/00 7.6 "Communication Guidelines," 08/17/00 7.7 "Exposure Tracking Guidance," 08/10/00 7.8 "Field Monitoring Data Sheet," 08/10/00

8. REFERENCES 8.1 RCP D-900, "Performance Tests For Radiation Protection Instruments" 8.2 Action Request #A0489282 8.3 Regulatory action technical basis and recommended response to Action Requests

A0489282 and #A0489299, Henry Fong, 2/29/2000.

00251713.DOA 3B 10 11 0817.0759

08/10/00 Page I of I DIABLO CANYON POWER PLANT EP RB-8 ATTACHMENT 7.1 1 AND 2

TITLE: Offsite Field Monitoring Locations Map (32-38) ,5I :So aO L 4.

SE'--. ... , *' 1.2 -* l'l.

51701 - I. ,

NA MA LgA

")NIORI G LOATON 4-14 J, WILLIllilll '6 ; IIlI"Ill*

El MC 002 00251713.DOA 3B 11 II 0817.0759

08/17/00 Page 1 of 3 DIABLO CANYON POWER PLANT EP RB-8 ATTACHMENT 7.2 I1ND2 TITLE: Offsite Field Monitoring Locations Descriptions NEAR DESCRIPTION NEAR ESE, 29 Arroyo Grande Market parking lot at corner Cecchetti and Lopez Lake Drive. Hwy. 101 south to Grand Ave. exit, east through old Arroyo Grande (Branch St.),

continue east (Lopez Lake Dr.) to Cecchetti. No phone.

ESE, 34 Arroyo Grande Intersection of Highway 101 S and Los Berros Road. No phone.

E, 11 Avila Beach See Canyon Road, 1.7 miles up from San Luis Bay Drive intersection.

Survey at intersection of See Canyon Road and Davis Canyon Road. Phone at nearby residences.

E, 15 Avila Beach PG&E Community Center, Ontario Rd, west Hwy. 101 frontage just south of the San Luis Bay Drive turnoff.

ENE, 8 Avila Beach See Canyon Road at intersection with Coon Creek Road (6.0 miles from San Luis Bay Drive on See Canyon Road).

ENE, 9 Avila Beach See Canyon Road, 4.2 miles up from San Luis Bay Drive intersection (intersection of See Canyon Road and Black Walnut Road). Phone at residences. Rattlesnake hazard.

ESE, 13 Avila Beach Pirate's Cove parking lot. West on Avila Beach Rd exit off Hwy. 101, turn east on Cave Landing Rd. No phone.

NNE, 13 Baywood Park Los Osos Middle School. Take Los Osos Valley Road west, turn north on South Bay Boulevard to El Morro Ave. Phone available during school hours.

NNW, 27 Cayucos Cayucos Pier. Going north on Highway 1, take second Cayucos exit marked Cayucos Drive. Phone available.

ESE, 10 DCPP DCPP access road at Gate, 6.2 miles from the Security Building. (Between mile markers 1.4 - 1.5.) Marked with red/white fence post. Phone available.

ESE, 11 DCPP South of DCPP front gate in boat storage lot. Phone at front gate guard shack.

ESE, 3 DCPP Turnout on DCPP access road, 1.6 miles from Security Building. Marked with red/white fence post. (At mile marker 5.8.)

ESE, 4 DCPP Turnout on DCPP access road 2.8 miles from Security Building. Marked with red/white fence post. (Between mile markers 4.5 - 4.6.)

0817.0759 00251713.DOA 3B 12

08 /17/00 Page 2 of 3 EP RB-8 (UNITS 1 AND 2)

ATTACHMENT 7.2 TITLE: Offsite Field Monitoring Locations Descriptions NEAR DESCRIPTION ESE, 7 DCPP By Ranch Road, 4.3 miles from Security Building along DCPP access road.

Marked with red/white fence post. Between mile markers 3.0 - 3.1.

SE, 1 DCPP Turnout on DCPP access road, 0.8 miles from Security Building near meteorological Tower A. Marked with red/white fence post. Between mile markers 6.5 - 6.6. Phone in tower building.

ESE, 24 Grover Beach Pismo State Beach. Grand Ave. at Highway 1. Hwy. 101 south to 4th St.

exit, south to Grand Ave., west to Hwy. 1. Phones at nearby commercial enterprises.

N, 11 Los Osos South Bay Park Fire Station. Take Los Osos Valley Road west, turn south off LOVR onto Bayview Heights Drive (up one block). Phone available.

N, 12 Los Osos Sea Pines Golf Course Clubhouse. Take Los Osos Valley Road to Pecho Valley Road. Turn west off Pecho Valley Road onto Monarch Lane. Right on Del None. Right on Howard. Phone at clubhouse.

NNW, 6 Los Osos Montana de Oro State Park. Take Los Osos Valley Road west, go south on Pecho Road through the park to the parking lot near end of road at southern park boundary. Phone at Ranger Station at Spooner Cove.

N, 18 Morro Bay Morro Bay Power Plant. Phone available.

NNE, 18 Morro Bay Take Hwy I north past Cuesta College, turn north on San Bernardo Creek Rd 0.3 miles north along San Bernardo Creek Road. Phone at nearby residences.

ESE, 28 Oceano Market on the comer of Halcyon and Highway 1 (Mesa View Drive intersection at top of hill). See directions to ESE, 24, then south on Hwy 1 to Halcyon.

SE, 30 Oceano Intersection at Highway 1 and Callender. See directions to ESE, 28.

Continue south on Hwy 1 past Halcyon towards Guadalupe to Callender Rd.

No phone.

E, 23 Pismo Beach Intersection of Price Canyon Road and Oromonde. Hwy 101 south to Price Canyon Rd (Hinds Ave. turnoff, turn left), then north to Oromonde.

ESE, 18 Shell Beach Shell Beach, Margo Dodd Park, Seaview and Ocean Blvd. Hwy 101 south to Spyglass exit, south on Shell Beach (frontage) Rd to Seaview, turn right.

Phone at nearby residences.

E, 22 SLO SLO Country Club. Take Broad St. (227) to Edna Rd, go west on Edna, turn right onto Los Ranchos Rd, then right on Country Club Dr. East side of club parking lot. Phone at club during working hours, otherwise at nearby residences.

00251713.DOA 3B 13 II 0817.0759

08/17/00 Page 3 of 3 EP RB-8 (UNITS 1 AND 2)

ATTACHMENT 7.2 TITLE: Offsite Field Monitoring Locations Descriptions NEAR DESCRIPTION NEAR E, 24 SLO Righetti Road at intersection of Coyote Canyon Road at metal gate. See directions to ENE, 20. Then go south on Orcutt Rd to Righetti, turn left on Righetti. No phone, but a few scattered residences in the area.

ENE, 15 SLO Laguna Middle School at intersection of Los Osos Valley Road and Prefumo Canyon Road, north side of LOVR. Phone available during school hours, otherwise at nearby residences.

ENE, 20 SLO PG&E Substation at corner of Orcutt and Johnson Streets. North on Higuera St., turn east on Tank Farm Rd, then north on 227 (Broad St.), then east on Orcutt Rd to intersection with Johnson Ave.

ENE, 21 SLO Cuesta County Park. 101 N, left on Grand, right on Loomis to Park. Phone in parking lot.

NE, 11 SLO Intersection of Los Osos Valley Road and Turri Road.

NE, 17 SLO EOF. Turn south off Highway 1 just north of SLO at sign indicating Sheriff's Operational Center. Phone available.

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08/10/00 Page I of I DIABLO CANYON POWER PLANT EP RB-8 ATTACHMENT 7.3 I1ND2 TITLE: Onsite Field Monitoring Locations Map 15 0.

0817.0759 00251713.DOA 3B

08/17/00 Page I of 1 2

DIABLO CANYON POWER PLANT EP RB-8 ATTACHMENT S~17.4 AND TITLE: Onsite Field Monitoring Locations Descriptions COORDINATE LOCATION DESCRIPIE ON E, A End of Skyline Drive at the top of the hill ENE, A South of switchyard fence next to Reservoir Road ESE, A On Hillside Drive road near ditch N, A South side of Water Tank road NE, A Junction of Tribar Road and Reservoir Road NE, B In front of water tank NNW, A Shore Cliff Road, SW of pond near intersection NW, A Top of hill on side road west of Shore Cliff Road S, A On Marina Road near breakwater gate SE, A On Reservoir Road by ditch, east end of parking lot #8 SE, B North end of Warehouse B, near pressurized ion chamber SE, C North-East comer of parking lot #1 SSE, A Helicopter pad SSE, B South end of parking lot #2 SSW, A On Breakwater Road outside intake area SW, A Near gate to breakwater WNW, A Near gate at end of side road west of Shore Cliff Road NW; B 1.1 miles North of North gate. West side of road on power pole, near farm buildings NW, C 2.1 miles North of North gate. West side of road on power pole, after pond NW, D 3.5 miles North of North gate. Near farm house on power pole, south of Montana de Oro.

00251713.DOA 3B 16 II 0817.0759

08/10/00 Page I of I 2

DIABLO CANYON POWER PLANT EP RB-8 ATTACHMENT S~17.5 AND TITLE: Pressurized ION Chamber Location Descriptions PIC # DESCRIPTION

1. DCPP North Gate Guard Post.

2. SSW Comer of Target Range (near onsite field monitoring location, SE,B).

3. Morro Bay Power Plant, near front gate.

4. Montana de Oro State Park. At the Park Ranger's residence, adjacent to the siren.

5. South Bay Fire Department.

6. Outside rear entrance to EOF east side of building (NE, 17 next to generator.

7. SLO Police Department. Intersection of Santa Rosa Street and Walnut Street. Behind fence SW of Walnut Street driveway.

8. SLO Service Center, 4325 So. Higuera St., SLO (OEL Garage).

9. PG&E Community Center (E, 15).

10. DCPP Front Gate.

11. Pismo Beach at the PG&E Pismo Warehouse on Price Canyon Road, about 0.5 miles NE of the Price Street intersection. PIC is located in the upper parking lot.

12. SLO County Building, Grover Beach. Exit Hwy. 101 at 4th street. Take 4th to Longbranch and proceed NE on Longbranch. County Social Services Building is on comer of 16th and Longbranch 00251713.DOA 3B 17 11 0817.0759

08/17/00 Page I of I DIABLO CANYON POWER PLANT EP RB-8 ATTACHMENT 7.6 AND TITLE: Communication Guidelines

1. Hand held radios are the primary mode of communication between FMTs and the controlling facility. If radios are not available, FMTs should use telephones.

2. Onsite FMTs will be assigned the team names FMT 1 or FMT 2. Offsite FMTs will be assigned one of the following team names: FMT Alpha, FMT Bravo, or FMT Charlie.

3. Radio Techniques a) Hold the radio upright, directly in front of the mouth.

b) Before transmitting, verify no one else is transmitting on the selected frequency.

c) After pushing transmit button, wait 1 to 2 seconds to allow for automatic radio encoding.

4. Backup communications is by telephone. The following table provides the controlling facility phone numbers.

CONTROLLING FACILITY PHONE #

Control Room 545-1234 545-2324 545-3377 TSC Radio Operator 545-3252 EOF RMD 545-3181 549-8070 OEL 546-3833

5. Each monitoring team should contact their controlling facility for the following:

a) Radio checks and initial team briefings.

b) Uponarriving at a monitoring location, to report initial radiological conditions.

c) After sampling at a monitoring location, to report results and to obtain additional instructions.

d) Reporting significant change in radiological conditions.

e) Hourly (about once an hour) to maintain communications.

6. Avoid use of acronyms that may be misunderstood, e.g., cpm v. dpm, PIC v. dosimeter. Use the complete words or phrases instead of an abbreviations.

7. Don't "walk over" other teams' transmissions.

00251713.DOA 3B 18 11 0817.0759

08/10/00 Page I of I 2

DIABLO CANYON POWER PLANT EP RB-8 ATTACHMENT S~17.7 AND TITLE: Exposure Tracking Guidance The tables below provides multipliers for estimating TEDE and Thyroid CDE from external self reading dosimeter readings. The multipliers tables are based on assumptions using FSAR isotopic mixes, thus are conservative values and should be only used when better information is not available.

FMTs SHOULD NOT REPORT CONVERTED PIC READINGS. The controlling facility is responsible for estimating internal exposures and tracking FMT doses.

[ PLANT VENT RELEASE Source Term TEDE THYROID CDE THYROID CDE (WITH KI) (WITHOUT KI)

Coolant 3 4 43 Gap 25 53 530 Core 22 16 160 ASSUMPTIONS:

Decay time = 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months since time of trip.

Release duration = 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Plant vent release is unfiltered.

Plant vent flow rate = 300,000 ft3 .

3 X/Q = 5.0 E-05 sec/mr.

SGTR WITH ATMOSPHERIC STEAM RELEASE SG Level TEDE THYROID CDE THYROID CDE (with KI) (without KI)

Empty 60 140 1,400 Normal 12 26 260 Flooded 110 250 2,500 ASSUMPTIONS:

Source term FSAR Gap dispersed in RCS Volume (12,560 ft3) with secondary coolant in equilibrium.

Decay time = 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months since time of trip.

Release duration = 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Steam flow rate = 4 E+05 Ibm/hr (10% Steam Dump).

3 X/Q = 5 E-05 sec/rn.

00251713.DOA 3B 19 II 0817.0759

08/10/00 Page I of 2 DIABLO CANYON POWER PLANT EP RB-8 ATTACHMENT 7.8 I1AN2 TITLE: Field Monitoring Data Sheet Instruction: Complete the following general information.

- - TURNBACK DOSE RATE = mR/hr (default = 500 mR/hr) ***

Date: FMT Leader:

[ ] FMT Alpha [ ] FMT Bravo [ ] FMT Charlie [ ] FMT 1 [ I FMT 2 E-140N RP # ASP-I RP # H809C RP #

Monitoring Location (circle below, or describe):

NW,A NNW,A N,A NE,A NE,B ENE,A E,A SSW,A WNW,A ESE,A SEA SE,B SE,C SSE,A SSE,B S,A SW,A NNW,6 N, 18 NE,17 ENE,20 E,22 ESE,4 ESE, 13 ESE,29 NNW,27 NNE, 13 ENE,8 ENE,21 E,23 ESE,7 ESE,18 ESE,34 N,11 NNE,18 ENE,9 E,11 E,24 ESE,10 ESE,24 SE, 1 N, 12 NE,11 ENE, 15 E, 15 ESE,3 ESE,11 ESE,28 SE,30 GROUND COUNT RATE (E-140N)

Instruction: While in vehicle, lean out and survey ground using an E-140N with a shielded HP-210 probe.

Report to controlling facility if ground contamination is greater than 100 net cpm.

SURVEY TIME GROSS CPM BKG CPM NET CPM

-- ___ 60 =

SKYSHINE (E-140N)

Instruction: Survey skyshine using an using an E-140N with a shielded HP-210 probe.

WINDOW DOWN SURVEY TIME WINDOW UP (CPM) (CPM) NET CPM GENERAL AREA DOSE RATE (ASP-i)

Instruction: Survey the general area dose rates at waist level using an ASP-1 with a HP-270 probe. Take window open and window closed reading. Report dose rate results to the to controlling facility as soon as possible.

WINDOW OPEN WINDOW CLOSED SURVEY TIME (mR/hr) (mR/hr) initial follow-up 00251713.DOA 3B 20 11 0817.0759

08/10/00 Page 2 of 2 EP RB-8 (UNITS 1 AND 2)

ATTACHMENT 7.8 TITLE: Field Monitoring Data Sheet Instruction: Collect two smears and calculate surface dpm/100 cm2.

SMEARABLE CONTAMINATION (E-140)

SURVEY GROSS CONV. dpm / 100 TIME CPM BKG CPM NET CPM FACTOR cm initial = x 10 follow-up = x 10 AIR SAMPLE VOLUME (11809)

Instruction: Calculate the average air volume collected.

RUN TIME AVG. FLOW STOP TIME START TIME (MIN) (FTW/MIN) VOLUME (FTI) initial x follow-up x PARTICULATE AIR CONCENTRATION (E-140)

Instruction: Calculate the particulate air concentration from the filter paper air sample.

SURVEY GROSS BKG NET CONV. VOLUME PARTIC TIME CPM CPM CPM FACTOR FT' PsCi/cc initial x 1.6E-10 +

follow-up x 1.6E-10 +

IODINE AIR CONCENTRATION (E-140)

Instruction: Calculate the iodine air concentration from the TEDA impregnated cartridge air sample.

SURVEY GROSS BKG NET CONV. VOLUME IODINE TIME CPM CPM CPM FACTOR FT 3 'sCi/cc initial = x 5.6E-09 - =

follow-up - = x 5.6E-09 - =

PRESSURIZED ION CHAMBER Instruction: If requested by the controlling facility, locally read the PIC. . Circle the correct units of measurement (pR/hr or mR/hr)

SURVEY TIME PIC ID # p.R/hr or mR/hr Instruction: Return completed form to controlling facility.

FORM COMPLETED BY:

00251713.DOA 3B 21 H 0817.0759

- - ISSUED FOR USE BY: DATE: EXPIRES: ***

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 NUCLEAR POWER GENERATION REVISION 6 DIABLO CANYON POWER PLANT PAGE 1 OF 34 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Plant Ven t Iodine and Particulate Sampling During Accident 4Conditions I EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION PAGE SC O PE ......................................................................................................................... 2 DISCUSSION .............................................................................................................. 2 RESPONSIBILITIES .................................................................................................... 5 PREREQUISITES ......................................................................................................... 6 PRECAUTIONS ........................................................................................................... 7 INSTRUCTIONS ........................................................................................................... 8 Method For Plant Vent Mid-to-High Range Iodine (1-131) Monitoring Using RE-24R .................. 8 Plant Vent Redundant Normal Range (RNR) Skid - Reactivation ......................................... 8 Mid Level Iodine "RCi/cc" Monitoring From the Control Room ......................................... 10 High Level Iodine "CPM" Monitoring From the Control Room (RE-24R Only) ..................... 12 Plant Vent Redundant Normal Range (RNR) Skid RE-24R's Cartridge (RF-24R) Changeout ........ 14 Method For Plant Vent High Range Iodine and Particulate Sampling Using RF-87A and RF-87B Filters 16 Plant Vent Extended Range (PVER) Skid Sampling - Initial Collection ................................ 16 Plant Vent Extended Range (PVER) Skid Sampling - Continued Collection ........................... 18 TSC Analysis of the RF-87's Sample Cartridge .............................................................. 20 Method For Plant Vent High Range Iodine Sampling Using RF-24R Cartridge ......................... 23 RF-24R - Initial Collection ...................................................................................... 23 RF-24R - Continued Collection ................................................................................. 26 TSC Analysis of the RF-24R Sample Cartridge .............................................................. 27 ACCEPTANCE CRITERIA ........................................................................................... 30 REFERENCES .......................................................................................................... 30 RECORDS ..................................................................... .......................... 31 APPENDICES ............................................................................................................ 31 ATTACHMENTS ....................................................................................................... 31 SPONSOR ................................................................................................................ 31 00283306.DOA 3B I II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 2 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

1. SCOPE This procedure provides the Plant Vent Iodine and Particulate Sampling (and/or monitoring)

Instructions for assessing radioactive iodine and particulate effluents in the event of a severe plant emergency.

2. DISCUSSION 2.1 Instructional steps are provided for intermediate range monitoring using RE-24R and high range sampling utilizing RF-87A and RF-87B or RF-24R.

2.2 When the Plant Vent Extended Range (PVER) skid's RE-87 "switchover" point occurs on the plant vent's RE-14, both the Plant Vent Normal Range (NR) and Plant Vent Redundant Normal Range (RNR) skids' sampling lines are isolated and their skid pumps shut down. This action also starts the PVER skid sampling pump directing the plant vent air sample through either the RF-87A or RF-87B filter then into the RE-87 noble gas detection chamber. Button switches for either of these filters will light up on the Remote Display Unit (RDU) in the Control Room and on the Local Radiation Processor (LRP) at the NR skid. At that time high range iodine and particulate sampling starts with either RF-87A or RF-87B. The sample pump light also switches from NR/RC-14 to ER/RC-87 on the NR's RDU and LRP.

2.3 Prior to severe accident conditions, the low (normal operations) to mid range radiation detectors RE-14, RE-24, and RE-28 on the NR skid and RE-14R, RE-24R, and RE-28R on the RNR skid monitor respectively noble gases, iodines, and particulates continuously. Their ranges are seen in Figure 6 (Attachment 11.6). RE-14/14R are 2" beta scintillators each viewing a pressurized chamber of continually flowing noble gases. RE-24/24R are 2" sodium iodide (AM-241 seeded for gain stabilization) gamma scintillators each viewing a fixed Ag Zeolite cartridge and "windowed" to see 1-131's photo peak. RE-28/28R are 2" beta scintillators each viewing a fixed filter paper. All of these detectors have their analog signals amplified, converted to digital pulses, mathematically smoothed and analyzed as well as archived at the nearby LRP.

2.4 In order to use RE-24R (and optionally RE-28R) for intermediate to high range monitoring, the shutdown of the RNR skid by RE-14 (during the switchover to the PVER skid) must be overridden, the RNR skid's sample line un-isolated, and the RNR skid's sample pump re-started.

2.5 Reactivating RE-24R (and optionally RE-28R) or RF-24R (with RF-28R) and the RNR skid pump after the high range "switchover" requires at least one visit to the plant vent skid room to perform this manual "switchback" operation.

00283306.DOA 3B 2 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 3 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 2.6 The "switchover" by RE-14 to the PVER skid is triggered by high noble gas activities.

The "switchover" protects RE-14 (and normally RE-14R). Activities of the iodines and particulates will probably not have reached similar high levels. So, RE-24R and RE-28R could probably still read on scale. RE-24 and RE-28 are isolated along with RE-14, but RE-24R and RE-28R can be brought back into service with disregard to RE-14R. When RE-24R (and optionally RE-28R) is used in this manner there are two possible paths of operation described in that which follows.

2.7 Using the 'RE-24R' method requires someone in attendance at the RDU in the Control Room after the RNR skid has been reactivated in order to relay readings and to turn the skid pump on and off. There are two advantages to this method. Obtaining iodine and, optionally, particulate release information via the Control Room is not only less manpower intensive, but also keeps personnel exposures to a minimum. Also recycling the skid pump on and off gets more use out of the cartridges and filters.

2.8 In the 'IACi/cc' readout (see EP RB-9) portion of the 'RE-24R' method there's the extra advantage of having the microprocessor automatically perform the calculation (i.e.,

integrations) of a release concentration directly in gtCi/cc. This makes the measurements the least labor intensive and the least error prone. However, it takes 20 minutes or more for the LRP's microprocessor to reach an integrated reading of RE-24R (and RE-28R) in j+/-Ci/cc. If the activity concentrations are high, a 20 minute collection interval (between turning on and off the skid pump) may not accommodate a detector reading 'on-scale' (i.e., < 1E7 cpm). Also, whenever RE-24R reads near 2 E-4 ýLCi/cc or the raw countrate on RE-24R or RE-28R reads 1E7 cpm it's time to change out the iodine cartridge and/or the particulate filter (RF-24R and/or RF-28R).

2.9 When the intervals between cycling the RNR skid pump (off-on-off) have to be less than 20 minutes then the 'RE-24R' method must shift to the '_pm' readout (see EP RB-9) operation. This requires a precise Control Room readout of not only the time but beginning cpm when the RNR skid pump is turned on then the time and ending cpm when the pump is turned off for each cycling of the pump. Also RE-24R must be in the "DISP OP", "31" "DISP" keypad readout option. Since releases of iodines are of a higher priority, a reading of the particulate channel RE-28R will not be pursued in the

'cpm' readout operation. This is because the left-most or 'particulate' channel display accommodates only one reading at a time for a "DISP OP" reading. Either iodine or particulate, but not both.

2.10 When the pump cycling intervals and cartridge changeout times become too short to keep ahead of detector countrate saturation then this method must shift away from Control Room operation and resort to sample collection and TSC counting with RF-87A&B or RF-24R (below).

00283306.DOA 3B 3 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 4 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 2.11 The High Range Plant Vent Sampling System using RF-87A&B or RF-24R is designed to reliably collect samples of plant vent iodine and particulate effluents. For RF-87A&B, a 1-inch diameter particulate filter pasted onto a 1-inch diameter Ag Zeolite cartridge is used to collect the samples. For RF-24R, the standard 2-inch filter/cartridge is used. These samples are then analyzed using the Gamma Spectroscopy System in the Technical Support Center (TSC) Laboratory.

2.12 High Range sampling with RF-87A/B is set up to give both iodines and particulate release assessments. If however, RE-87's sample pump is down, or RF-87A and RF-87B filters are unobtainable, or electrical Bus "G" is out, then RF-24R cartridge is available for high range iodine sampling only (see instructional Step 6.3.1).

2.13 High range sampling and analysis is to be performed within the General Design Criteria (GDC) 19 dose limits for Reg Guide 1.4 source terms referenced in Reg. Guide 1.97 and NUREG 0737 for PWRs. GDC 19 imposes a 5 rem whole body dose limit and a 75 rem extremity dose limit on any one individual. When these limits are approached, the procedure allows for more than one individual to perform the steps collectively.

The dose limits are also met for DCPP's most severe Design Base Accident (D.B.A.)

case as described in the FSAR. This case is the major LOCA with Reg. Guide 1.4 releases.

2.14 During a severe accident condition two high range radiation detectors also monitor the plant vent. These are RE-29, an 8 decade (0.1 to 1E7 mR/hr) ion chamber viewing directly the plant vent and RE-87, a cadmium sulfide scintillator viewing a sampled stream of noble gases from the plant vent. Their ranges are also seen in Figure 6 (Attachment 11.6) with an overlap shown to the low-(mid) range monitors. Their response curves are shown, respectively in Figures 4 and 5 (Appendix 10.2) and in Figure 3 (Appendix 10.1) as reproduced from EP RB-9. RE-29's readings are dominated by noble gases but could have small contributions due to the accompanying iodines and particulates, whereas RE-87's readings are confined strictly to the noble gases. However, both monitors are intended to accompany this sampling procedure for indications on the conditions. Their readings are formally utilized for quantitative analysis in EP RB-9 for release rate determinations.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 5 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

3. RESPONSIBILITIES 3.1 The Radiological Advisor (RA) has the ultimate responsibility for invoking this procedure.

3.2 The Site Chemistry Coordinator is responsible for coordinating and interfacing with the ERA or an appointed assistant to the ERA in invoking this procedure.

3.3 The Site Chemistry Coordinator (SCC) and the Site Radiation Protection Coordinator are responsible for interfacing with each other to ensure this procedure is properly performed.

3.4 The Site Radiation Protection Coordinator is responsible for accessing radiological conditions of the various plant locations used for the particular sampling method being executed by this procedure. Upon assessment the Site Radiation Protection Coordinator is responsible for providing radiological protection controls and ensuring a radiological briefing tailboard is conducted.

3.5 The Site Chemistry Coordinator (SCC) is responsible for the selection of qualified individuals to perform the tasks described in this procedure and that a technical briefing tailboard is conducted.

3.6 The Site Chemistry Coordinator (SCC) is responsible for reviewing the sampling and analysis data for verification and validation purposes.

3.7 Upon review of the sampling data and analysis results, the Site Chemistry Coordinator (SCC) is responsible for communicating this information to the ERA or an appointed assistant to the ERA.

3.8 Personnel assigned to collect samples and radiation monitor data or perform handling and analysis on the samples in the TSC lab are responsible for adhering to the procedural requirements described herein.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 6 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

4. PREREQUISITES 4.1 The personnel responsible for performing this procedure must have had prior training in its implementation.

4.2 The following tools and associated equipment must be available:

4.2.1 Equipment and tools kept in the TSC Laboratory

a. Modified carrier cask with large and small shield plugs

b. Transfer cage

c. Extractor bar

d. Push stick

e. Extra filter/cartridge ingot

f. Extra 1-inch (RF-87) and 2-inch Ag Zeolite cartridges, 1-inch particulate filter (RF-87), and 47mm particulate filters

g. Spare 0-rings for the ingot

h. Pair of pliers

i. Wipe rags

j. Small sample bags

k. Sample labels

1. Tape

m. Medium size screwdriver

n. RF-24R cartridge holder cap grip/removal tool NOTE: The next item may be kept in P.V. Skid Room.

o. Carrier cask for RF-24R 00283306.DOA 3B 6 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 7 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 4.2.2 Equipment and tools kept near the Chemistry Foreman's Office

a. Pair of pliers

b. Tongs

c. Keys to unlock transport dolly in the Plant Vent Skid Room (Key Id.

XAA)

d. Local Radiation Processor (LRP) keys

e. Wipe rags

f. Small sample bags

g. Sample labels

h. Tape

i. Medium size screwdriver 4.2.3 Equipment from Radiation Protection

a. One contamination survey meter (TSC Lab Use)

b. Two Dose Rate Meters (one for sample collection, one for TSC lab use) 4.2.4 Equipment and tools kept in the Plant Vent Skid Room

a. Carrier casks for RF-87A and RF-87B

b. An extractor bar

c. Push stick

d. Transport dolly

e. 2 inch Ag zeolite cartridges

f. 47mm filters NOTE: The next item may be kept in the TSC.

g. Carrier cask for RF-24R NOTE: The next item may be kept in the I&C Training Lab.

h. Spare RF-24R cartridge 'holder/plug' assembly

5. PRECAUTIONS 5.1 The RF-87A/B Carrier Cask, Modified Carrier Cask, and RF-24R carrier cask are heavy, 96 lbs and 55 lbs and 47 lbs respectively. When lifting or moving these items be especially careful to know the proper lifting techniques to avoid back strain.

5.2 The exposure levels on the route map, Figure 1 (Attachment 11.4) are from the Design Shielding Review with Reg. Guide 1.97 limits as inputs. When collecting samples using the transport dolly move as expeditiously as possible and assume these exposure rates do exist.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 8 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

6. INSTRUCTIONS 6.1 Method For Plant Vent Mid-to-High Range Iodine (1-13 1) Monitoring Using RE-24R NOTE 1: This part of the procedure requires a Chemistry Supervisor to be in the Control Room at the PV's RNR's RDU. It also requires Chemistry personnel to make at least one trip to the Plant Vent Skid Room in order to reactivate the RNR skid.

NOTE 2: All key pad entries involving "DISP OP," "?," "DISP" must include the program mode key switch going from "ENTER DATA" position to the "RUN" position after the entry, then back to "ENTER DATA."

6.1.1 Plant Vent Redundant Normal Range (RNR) Skid - Reactivation

a. Chemistry person in Control Room obtains keys from Shift Foreman to operate PV's RNR's RDU.

b. Insert keys into the RDU, ensuring the Local Power keylock switch is in the "ON" position and turn the program mode keylock switch to the "ENTER DATA" position.

c. Key in on the keypad:

1. "DISP OP"

2. "3"

3. "DISP" and read the raw countrate on RE-24R's cartridge, (RF-24R). (The analog output to an EARS reading may be sufficient.)

d. Read RE-34's recorder, (RR-34), on the PAM panel and report this reading along with RE-24R's raw countrate to the Site Chemistry Coordinator (SCC).

NOTE 1: RE-34 indicates the dose rate in the area of the PV skid room.

NOTE 2: The highest reading from RE-24R occurs at 1E7 cpm. If the raw countrate on RE-24R is greater than 5E6 the SCC may also want to request a cartridge change out.

NOTE 3: The following balance of steps apply to personnel going to the plant vent skid room.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 9 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS I AND 2 Accident Conditions

e. Obtain a dose rate meter to check radiation levels enroute to and at the PV skid room.

f. Obtain a set of keys from the Chemistry Foreman's office to operate the RNR skid's LRP panel in the event local operation of the skid pump is necessary.

g. Proceed expeditiously to the PV skid room (85' level - "L" area) upon receiving instructions from the SCC.

h. Check RE-34's remote readout (just outside the door) prior to entering the PV skid room.

i. Approach the termination enclosure (Panel BTR-P14) at the end of the LRP on the NR skid in the PV skid room.

j. Turn the switch labeled "RE-87/SS" from the "RE87 Norm-OFF" position to the "ER Calib'n-ON" position. This overrides the PVER switchover and removes isolation of the RNR skid.

k. Ensure the Control Mode keylock switch is in the "CR PNL" position.

1. Call Chemistry personnel at the Control Room PV RNR RDU to report the RNR skid is back in service but with the sample pump still turned off. Inquire as to whether the iodine cartridge or particulate filter need to be changed out at this time.

m. Go to Section 6.1.4, if the cartridge and or filter need to be changed out, OTHERWISE Continue.

n. Report to the SCC and leave the PV skid room.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 10 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 6.1.2 Mid Level Iodine "R.Ci/cc" Monitoring From the Control Room NOTE: The information determined here supports Section 5 of EP RB-9.

a. Inform the SCC when the PV RNR skid has been reactivated.

b. Go to Section 6.1.3 for "CPM" monitoring if the last "UCi/cc" RE-24R reading is greater than 2.OE-4 ýtCi/cc, OTHERWISE Continue.

c. Key in on the RDU keypad:

1. "CH"

2. "2"

3. "FUNC"

4. "13"

5. "DISP" and record from the left most LED (RE-28R's) the time in minutes the RE-24R existing cartridge sampled. Assume this is the same for particulates.

d. Start the RNR skid pump by depressing the "Skid Pump" button (after OK from PV skid room if cartridge and/or filter had to be changed out).

e. Key in on the keypad: (Only if the cartridge RF-24R was changed out.)

1. "CH"

2. "2"

3. "FUNC"

4. "13"

5. "DATA"

6. "0"

7. "0"

8. "0"

9. "EXP"

10. "0"

11. "0"

12. "ENTR" This restarts the iodine timer.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 11 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

f. Key in on the keypad: (Only if the filter RF-28R is changed out.)

1. "CH"

2. "0"

3. "FUNC"

4. "13"

5. "DATA"

6. "0"

7. "0"

8. "0"

9. "EXP"

10. "0"

11. "0"

12. "ENTR" This restarts the particulate timer.

g. Return the keylock switch for program mode back to "RUN".

h. Wait at least 20 minutes, then record RE-24R's and RE-28R's j+/-Ci/cc reading.

i. Key in on the keypad:

1. "DISP OP"

2. "3"

3. "DISP" and record the raw counts per minute reading RE-24R from the left most LED (RE-28R's).

j. Key in on the keypad:

1. "DISP OP"

2. "3"

3. "DISP" and record the sample flowrate reading from the left most particulate LED (RE-28's).

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 12 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

k. Depress the "skid pump" button to stog the sample flow through the cartridge and filter then wait until the SCC clears for another cycling of the sample flow pump.

1. Inform the SCC of the time sampled by RF-24R/28R and the ACi/cc and raw countrate readings on RE-24R and ptCi/cc reading on RE-28R.

NOTE 1: This information coupled with that from the TSC enables the SCC to decide whether this method can be utilized and/or whether the existing cartridge can still be used.

NOTE 2: Again, if the raw countrate on RE-24R is approaching (or exceeds) 1E7 cpm or the last 'jACi/cc' readout on RE-24R is near 2 E-4 AtCi/cc, then the cartridge needs to be changed out.

m. Go to Section 6.1.3 for "CPM" readings if the SCC decides or RE-24R indicates that the sample pump cycling time needs to be shorter than 20 minutes. OTHERWISE Continue.

n. Go to Section 6.1.4 if the SCC decides or RE-24R indicates the cartridge needs to be changed out. OTHERWISE Continue.

o. Return to Step c. if the SCC gives the clearance for another cycling of the sample pump.

6.1.3 High Level Iodine "CPM" Monitoring From the Control Room (RE-24R Only)

NOTE 1: The information determined here supports Section 6.0 of EP RB-9.

NOTE 2: Arriving at this point from 6.1.2 or 6.1.4 finds:

i.) the sample pump is already off.

ii.) interest is only on iodines (RE-24R) iii.) microprocessor derived "'tCi/cc"values are no longer relevant.

a. Key in on the keypad:

1. "DISP OP"

2. "3T

3. "DISP" and record a raw countrate in "cpm" on RE-24R from the left most LED (particulate) for an incremental countrate determination.

b. Immediately depress "Skid Pump" button to start the sample flow and record a beginning time toward an incremental time determination (after OK from PV skid room if the RF-24R cartridge was changed out).

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 13 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

c. Key in on the keypad:

1. "DISP OP"

2. "12"

3. "DISP" and record the sample flowrate (cfm) reading of RE-24R from the left most LED (RE-28R's).

d. Allow to run for a time recommended by the TSC, anywhere between 1 and 20 minutes while continually observing the flowrate at LED.

e. Depress the "Skid Pump" button switch to so the sample pump and record the increment ending time after running for an arbitrary length of time around the value recommended by the TSC's Rad. Data Processor.

f. Key in on the keypad:

1. "DISP OP"

2. "3"

3. "DISP" and record this increment's ending raw countrate in "cpm" on RE-24R from the left most LED (particulate channel).

g. Divide the difference in raw countrate readings between a. and f. by the difference in incremental time readings between b. and e. This gives the "cpm/min" value, CR (see Form 69-13226).

h. Call the Rad. Data Processor in the TSC and report the result of g. in "cpm/min" for a "1 min" time interval on the EP RB-9 Section 6.0 Data Sheet.

i. Repeat Steps a. through h. until:

1. the "DISP OP", "3", "DISP" reading indicates 1E7 cpm, or

2. the time intervals between the increments become too short to manage, or

3. the SCC instructs the changeout of the cartridge.

j. Go to Section 6.1.4 if the SCC decides or RE-24R indicates the cartridge needs to be changed out.

k. Terminate the "RE-24R" Method portion of this procedure and go to the instructional steps under 6.2 or 6.3 if the incremental time intervals are too short to manage, or if directed by the SCC.

1. Ensure the "Skid Pump" button switch was last depressed to so by checking the skid pump light being off.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 14 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 6.1.4 Plant Vent Redundant Normal Range (RNR) Skid RE-24R's Cartridge (RF-24R) Changeout NOTE 1: Arriving here from 6.1.1 skip over to Step d.

NOTE 2: Arriving here from 6.1.3 skip Step e.

a. Obtain a hand-held dose rate meter to check radiation levels enroute to the PV skid room. (Applies only to RP escort for Chemistry personnel changing out RF-24R cartridge and/or RF-28R filter).

b. Obtain from the Control Room an advance reading of RE-34.

c. Proceed to PV skid room.

d. Changeout existing RE-24R's cartridge (i.e., RF-24R):

1. Loosen the wing-bolts which secure the cartridge 'holder/lead plug' combination down at RE-24(R)s shielded "pig."

2. Rotate the 'holder/plug' until the four slotted retaining ears clear the studs with the wing-bolts.

NOTE: The 'holder/plug' is heavy and its O-ring makes a tight seal. It is difficult to pull out. Also loosened wing-bolts should be aligned parallel to the plug's edge so they won't snag on the

'holder/plug' and break off. If any wing-bolts are broken, replace with spares kept in Chemistry P.V. locker.

3. Firmly pull and support the 'holder/plug' out of the "pig.

4. Place the entire 'holder/plug' assembly on the slotted support platform.

5. Unscrew the cartridge holder end cap.

6. Dispose of the cartridge as directed by supervision.

7. Install cartridge into the holder end cap taking particular care to ensure that the airflow 'arrow' is lined up in the direction of flow (same direction as the cartridge that was just removed). The arrow should be pointed toward the handle of the holder.

8. Screw the holder end cap back onto the threaded 'plug' until just snug. The Molykote 55 lubricant may be needed for coating the O-rings.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 15 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

9. Slide the entire iodine 'holder/plug' back into RE-24(R)'s "pig" taking care that the O-ring seal is not damaged.

10. Rotate the 'holder/plug' until the slots in the four retaining ears engage the studs.

11. Tighten the wing-bolts finger tight.

12. Inform Control Room of cartridge changeout and return to the procedure step that initiated this changeout. _

e. Changeout existing RE-28R's filter (i.e., RF-28R) - (OPTIONAL):

1. Loosen the wing-bolts which secure the cartridge 'holder/lead plug' combination down at RE-28(R)s shield pig.

2. Rotate the 'holder/plug' until the four slotted retaining ears clear the studs with the wing-bolts.

NOTE: The 'holder/plug' is heavy and its O-ring makes a tight seal. It is difficult to pull out.

3. Firmly pull and support the entire particulate 'holder/plug' out of the "pig."

4. Place the entire 'holder/plug' assembly on the support slotted platform.

5. Unscrew the holder end cap taking care that the two concentric spacer rings holding the filter do not drop.

6. Dispose of the filter as directed by supervision.

7. Place a new filter paper on top of the grid face of the smaller spacer ring.

8. Slide outer (or larger) spacer ring over the smaller ring.

9. Screw the end cap back onto the threaded 'plug' until snug, taking care not to bump the two spacer rings or filter paper off-center.

The Molykote 55 lubricant may be needed for coating the 0-rings.

10. Slide the entire 'holder/plug' back into RE-28(R)'s "pig." Take care that the O-ring seal is not damaged.

11. Rotate the 'holder/plug' until the slots of the four retaining ears engage the studs.

12. Tighten the wing-bolts finger tight.

13. Inform Control Room of filter changeout.

f. Leave PV skid room and report to the SCC.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 16 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 6.2 Method For Plant Vent High Range Iodine and Particulate Sampling Using RF-87A and RF-87B Filters 6.2.1 Plant Vent Extended Range (PVER) Skid Sampling - Initial Collection NOTE: All actions described in this section are performed manually. This includes the switching to the redundant RF-87B filter (or RF-87A filter) and vice-versa.

a. Obtain from the Control Room and record the time of the NR to ER switchover (i.e., activation of RE-87's sample pump).

b. Obtain from the Control Room and record the reading of RE-34 (ALARA area monitor of the plant vent skid room). Communicates this to the Site Radiation Protection Coordinator.

c. Obtain a dose rate survey meter to keep track of dose rates.

d. Obtain a set of keys from Chemistry Foreman's office to operate the NR (and RNR) skid's LRP panel.

e. Obtain any special instructions and controls from the Site Chemistry Coordinator and the Site Radiation Protection Coordinator.

f. Proceed expeditiously to the plant vent skid room (85' level - "L" area) upon receiving instructions from the Site Chemistry Coordinator and the Site Radiation Protection Coordinator.

NOTE 1: Check RE-34's remote readout just outside PV skid room.

NOTE 2: If the PVER skid is unavailable then proceed to subsection 6.3 of the Instructions to use RF-24R.

g. Insert a key in the NR skid's LRP panel Control Mode switch and turn to Local in order to operate the pump and filter switches locally.

(Refer to Figure 2 of Attachment 11.5) 00283306.DOA 3B 16 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 17 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

h. Record:

1. the time

2. RE-87 reading

3. sample flowrate The latter can be obtained from either the Hastings flow meter LCD inside the Hoffman termination enclosure on the PVER skid or by:

1. Inserting other key in program mode switch and turning to ENTER DATA

2. Key in "DISP OP" on keypad

3. Key in "11" on keypad

4. Key in "DISP" on keypad

5. View from RE-28's LED (left most, data is in <units of liters/min).

i. At the NR skid's LRP panel push the RF-87B filter button switch if the sample is being collected via RF-87A or push the RF-87A filter button switch if the sample is being collected via RF-87B. This transfers the RE-87 pump on the PVER skid to stop collection on one filter cartridge and to start collection on the other filter cartridge (i.e., RF-87A vs.

RF-87B).

j. Check that:

1. The ER/RC-87 pump light is on,

2. The previous Filter used (A or B) light goes off,

3. The selected Filter (A or B) light comes on.

k. Mate the desired RF-87A (or B) filter carrier cask up to its respective filter holder on the PVER skid.

1. Lift the pin on the rear of the filter holder.

m. Screw in the extractor bar through the carrier cask and into the threads of the filter ingot of the desired RF-87A (or B) filter holder.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 18 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

n. Push down on the filter holder's orange handle located on the top rear of the filter holder. The top of the filter holder will pop up and release the filter ingot.

o. Using the extractor bar, transfer the filter ingot from the filter holder into the carrier cask.

p. Push the retaining pin (on front of carrier cask) into the slot of the ingot to hold the ingot in place while transporting.

q. Unscrew the extractor bar and place beside RF-87B's (or A's) filter holder.

r. Survey the carrier cask with the hand-held meter. The dose rate should be less than 0.4 R/hr at 1 foot from contact. If greater, inform the Site Chemistry Coordinator and obtain further instructions.

s. If the dose rate is less than 0.4 R/hr, lift the carrier cask and place in the transport dolly.

t. Unlock the dolly (if it is locked).

u. Proceed to the TSC with the dolly and cask along the route shown in Figure 1 (Attachment 11.4).

v. Unload the cask into the TSC's transfer cage with the restrained end pointing outward.

w. Transfer all initial sample collection data onto Form 69-13224.

x. For radionuclide analysis instructions proceed to Step 6.2.3 (unless directed otherwise by the Site Chemistry Coordinator).

6.2.2 Plant Vent Extended Range (PVER) Skid Sampling - Continued Collection

a. Obtain, in the TSC, the extra ingot, a fresh 1" silver zeolite cartridge, particulate filter and new O-rings.

b. Install the new silver zeolite filter cartridge into the ingot receptacle with the particulate filter on top, taking care that the smaller of the two 0-rings is inserted first and that the other larger O-ring is inserted last.

c. Slide the fresh ingot assembly into the empty carrier cask and reinsert the retaining pin.

d. Proceed back to the plant vent skid room with the carrier cask in the transport dolly.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 19 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

e. Check RE-34's local readout (just outside door) for exposure rate.

f. Mate the carrier cask up to the desired RF-87A's (or B's) filter holder.

g. Screw the extractor bar into the ingot of the carrier cask and lift the cask's retainer pin.

h. Push the ingot back into the desired RF-87A's (or B's) filter holder.

i. Restore the pin in the rear of the filter holder (may have to jostle the ingot until the pin drops into the ingot).

j. Pull up on the filter holder's orange handle to seal and secure the ingot into the desired RF-87A's (or B's) flow path.

k. Unscrew and withdraw the extractor bar.

1. Record the time and step up to the NR skid's LRP.

m. Push the RF-87A's (or B's) filter button switch and record the sample flowrate in cc/min. from the Hastings flow meter's LCD inside the Hoffman termination enclosure of the PVER skid, or key in "DISP OP," "11", "DISP" on the NR skid's LRP keypad and read RE-28's (left most) LED display for RE-87's flowrate (in liters/min).

n. Check that RF-87B's (or A's) filter light goes out and that RF-87A's (or B's) light comes on again.

o. Mate the RF-87B (or A) filter carrier cask up to its filter holder.

p. Lift the pin on the top rear of the filter holder.

q. Screw the extractor bar through the carrier cask and into the threads of the filter ingot of the RF-87B (or A) filter holder.

r. Push down on the filter holder's orange handle on the top rear of RF-87B's (or A's) filter holder.

s. Using the extractor bar transfer the filter ingot from the filter holder into the carrier cask.

t. Push the carrier cask's pin (on front of cask) into the slot of the ingot to hold ingot in place while transporting.

u. Unscrew the extractor bar and place beside RF-87A's (or B's) filter holder.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 20 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

v. Survey the carrier cask with the hand-held meter. The dose rate should be less than 0.4 R/hr at 1 foot from contact. If greater, inform the Site Chemistry Coordinator and obtain further instructions.

w. Lift RF-87B's (or A's) carrier cask and place in the transport dolly.

x. Proceed to the TSC with the dolly and cask along the route shown in Figure 1 (Attachment 11.4).

y. Unload the cask into the TSC's transfer cage with the restrained end pointing outward.

z. Transfer any sample collection data onto Form 69-13224.

aa. For radionuclide analysis instructions proceed to Step 6.2.3 unless directed otherwise by the Site Chemistry Coordinator to repeat the instructions of 6.2.2.

6.2.3 TSC Analysis of the RF-87's Sample Cartridge

a. Mate the carrier cask up flush against the modified carrier cask which already resides in the transfer cage ensuring that the unrestrained end meets the unrestrained end of the modified carrier cask.

b. Ensure the small shield plug is in the top of the modified carrier cask.

c. Lift the carrier cask's retaining pin.

d. Using the TSC's extractor bar or the push stick, push the ingot into the modified carrier cask.

NOTE: The cask might have to be rotated slightly to facilitate ingot transfer.

e. Insert the ingot retaining pin into the modified carrier cask.

f. Lift the carrier cask out of the transfer cage and give it to the personnel retrieving the samples from the PV Skid Room along with the extra ingot, cartridge, filter and 0-rings.

g. Lift the modified carrier cask out of the transfer cage and set it on the floor leaving the large shield plug aside.

h. Place the TSC's survey meter: first, in contact centered on top of the modified carrier cask; then one foot above it after lifting (temporarily) the small shield plug.

i. Record the readings and replace the small shield plug.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 21 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

j. Select the best collimating aperture out of the five from the following table based on the contact exposure reading or the 1 foot above (with the small shield plug removed) exposure reading.

Open Cask (small vlu2 Closed Cask (small plug Use Collimating removed) 1' above Reading in place) Contact Readin Aperture. "d" less than 32 mR/hr less than to 2.0 mR/hr 3/4" 32 mR/hr to 640 mR/hr 2.0 mR/hr to 45 mR/hr 1/4" 640 mR/hr to 8 R/hr 45 mR/hr to 560 mR/hr 1/8" 8 R/hr to 200 R/hr 560 mR/hr to 14 R/hr 1/16" greater than 200 R/hr greater than 14 R/hr 1/32"

k. Remove the lead plug (same size as a collimating aperture but without the hole) from the center of the GE detector's shield doors.

1. Insert the collimating aperture selected from Step j. into the vacated hole in the GE detector shield doors.

CAUTION: The modified carrier cask weighs approximately 55 lbs and may require 2 TSC personnel to provide the lifting.

m. Lift the modified carrier cask containing the ingot with the hot cartridge and place on top of the GE detector shield doors.

CAUTION: Steps n through o must be performed quickly and at arms length away from the body and face, since the highly radioactive sample cartridge is momentarily exposed while only partially shielded.

n. Remove the small shield plug and flip the modified carrier cask upside down and over the collimating aperture.

o. Place the large shield plug in the bottom cavity of the modified carrier cask.

p. If the collimating aperture is out of range based on the Canberra's count rate meter or dead time meter, then lift the modified carrier cask off of the collimating aperture and place to one side of the GE detector's shield doors. Immediately, reselect the next larger or smaller aperture, replace the modified carrier cask over it and continue.

q. Commence the radionuclide analysis using the Canberra System as per procedures CAP B-53 and CAP B-53:I.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 22 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions I

r. For each cartridge sampled, enter the following data as inputs in the Canberra program as extracted from Sample Collection Data:

1. Sample Description I

(from Form 69-13224)

(i.e., RF-87A or B, Cartridge #, etc.)

2. Sample start date/time (from Form 69-13224)

3. Sample stop date/time (from Form 69-13224)

4. Sample flowrate, F(lpm) (from Form 69-13224)

5. Collection factor (includes plate-out and cartridge retention combined) CF depending on sample flowrate, from the following table:

Sample Flowrate Collection Factor, CF nearest to 1 1pm 0.724 nearest to 0.79 lpm 0.678 nearest to 0.51 1pm 0.568 nearest to 0.41 1pm 0.508

6. Collimating aperture Geometry Code used, (i.e., "d").

CAUTION: High noble gas concentrations trapped in the cartridge may interfere with the resolution of iodine peaks. The cartridge may require a reverse purge using air or nitrogen. A minimum purge volume of 18 liters is needed to reduce the entrained gas concentration.

s. All results concerning high range iodine and particulate concentrations as determined by this procedure should be reviewed by the Site Chemistry Coordinator and should be communicated as soon as possible to the ERA's staff in the TSC.

t. At the end of the Canberra analysis remove the large shield plug, flip modified carrier cask over, restore small shield plug, and lift modified carrier cask off and onto the floor near the shielded radioactive sample storage pig at the Northeast entrance area of the TSC lab.

u. Lift the pin retaining the ingot.

00283306.DOA 3B 22 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 23 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions CAUTION: Steps v through z expose the iodine cartridge momentarily. This may cause a very High Radiation Area. Good ALARA practices are important.

v. Using the extractor bar or the push stick, push the ingot out of the modified carrier cask.

w. Lift the ingot to the edge of the shielded sample storage pig.

x. Using the push stick, push the iodine cartridge and particulate filter out of the ingot (even the O-rings) and into an opened pre-labeled bag that is in the radioactive sample storage pig. Then cover the sample storage pig.

y. Return the modified carrier cask to the transfer cage with the unrestrained end pointing outward.

z. Wipe the push stick and ingot clean; check the wipe for contamination, set the ingot (this becomes the extra ingot) aside with new 0-rings, cartridge, and filter for use by the personnel collecting the samples.

aa. Report to the Site Chemistry Coordinator for continued instructions.

6.3 Method For Plant Vent High Range Iodine Sampling Using RF-24R Cartridge 6.3.1 RF-24R - Initial Collection NOTE: Arrival here is either external because of RF-87A&B being un-available (i.e., RE-87 pump O.O.S., Bus "G" down, SCC preferred selection, etc.) or internal from instructional Step 6.1.3.

a. Obtain from Control Room or SCC (or TSC Rad. Data Processor) and record on Form 69-13225 the following:

1. Time of NR to ER "switchover" (i.e., isolation of NR and RNR skids) or time RNR skid pump was last shut off (if arriving here from Step 6.1).

2. Last known sample flowrate through RNR skid.

3. Estimate of time RE-24R began viewing this last increased level of iodine or time RNR skid pump was last cycled on (if arriving here from Step 6.1).

4. Cartridge # (if arriving here from Step 6.1) otherwise write cartridge #0.

5. Reading of RE-34 (As read on RR-34 on PAM panel.)

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 24 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

b. Obtain dose rate meter to check radiation levels enroute to and at the PV skid room.

c. Obtain a set of keys from the Chemistry Foreman's office to operate the RNR skid's LRP panel.

d. Obtain any special instructions, precautions, or controls from the SCC and SRPC.

e. Proceed expeditiously to the PV skid room (85' level - "L" area) upon receiving clearance from the SCC.

f. Check RE-34's remote readout (just outside the door) prior to entering the PV skid room.

NOTE: The next two steps apply to arriving here externally wherein the RNR skid has not vet been un-isolated and the NR to ER "switchover" has not been over-ridden. They do not apply to arriving here from Step 6.1.

g. Approach the termination enclosure (Panel BTR-P14) at the end of the LRP on the NR skid in the PV skid room. (Applies only if arrival here is not from Step 6.1).

h. Turn the switch labeled "RE-87/SS" from "RE87 Norm-OFF" position to the "ER Calib'n- ON" position. This overrides the PVER switchover and removes isolation of the RNR skid. (Applies only if arrival here is not from Step 6.1.)

i. Insert a key in the RNR skid's LRP panel Control Mode keyswitch and turn it to LOCAL in order to operate the skid locally.

j. Insert the other key in the RNR skid's LRP panel program mode keyswitch and turn it to ENTER DATA in order to key in for sample flowrate readings.

NOTE: The spare RF-24R cartridge "holder/shield plug" assembly may not be available in the PV skid room. In this case, the one kept in the I&C Training Lab must be retrieved before proceeding with the next step.

k. Fit the spare RF-24R cartridge "holder/plug" assembly with a fresh 2" Ag-Zeolite iodine cartridge and lay beside RE-24R.

1. Loosen the four wing bolts retaining the existing "holder/plug" assembly in RE-24R's detection chamber on the RNR skid.

m. Rotate the "holder/plug" assembly counterclockwise in RE-24R's detection chamber until the slotted ears clear the wing bolts.

00283306.DOA 3B 24 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 25 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions NOTE: The RF-24R carrier cask used in the next step may be stored in the TSC lab instead of the PV skid room. In this case, it must be retrieved before proceeding with the next step.

n. Pull the entire "holder/plug" assembly containing the existing RF-24R iodine cartridge out of RE-24R's detection chamber and place it, very quickly, in the RF-24R carrier cask (which is sitting in the transport dolly).

o. Slide the spare RF-24R "holder/plug" assembly containing the fresh iodine cartridge into RE-24R's chamber and turn clockwise until the slotted ears engage the wing bolts.

p. Tighten the wing bolts with fingers only.

q. Push the "skid pup" button on the RNR LRP panel to start the skid's sample pump.

r. Record the start/sample time on Form 69-13225 for this, the next sequential cartridge number (which will be cartridge #1 if arrival here is not from Step 6.1).

s. Key in on the RNR LRP keypad the following:

1. "DISP OP"

2. "12"

3. "DISP" This gives the RNR skid sample flowrate (cfm) displayed in the left most LED (i.e., the RE-28R - particulate window).

t. Read and record the beginning sample flowrate on Form 69-13225 for this new sampling cartridge.

u. Proceed to the TSC Lab with the dolly and cask along the route shown in Figure 1 (Attachment 11.4).

v. Unload the cask with RF-24R to the TSC counting personnel.

w. Go to Step 6.3.2 but wait for Continued Collection directions from the SCC.

00283306.DOA 3B 25 I1 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 26 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 6.3.2 RF-24R - Continued Collection

a. Proceed expeditiously to the PV skid room with the spare RD-24R "holder/plug" assembly containing the fresh Ag-Zeolite iodine cartridge furnished by TSC personnel, if the SCC directs that sample collection be continued.

b. Check RE-34's remote readout prior to entering the PV skid room.

NOTE: The keys were left in the RNR's LRP panel with LOCAL control and ENTER DATA program mode still selected; the skid's sample pump still running; and the left most LED (RE-28R window) still reading skid sample flowrate.

c. Read and record the ending sMale flowrate on the Form 69-13225 (from the previous trip to the PV skid room) relating to the existing RF-24R in RE-24R's chamber.

d. Push the "skid pump" button on the RNR LRP panel to son the skid's sample pump.

e. Record the stop/sample time on the same Form 69-13225 relating to the cartridge still in RE-24R's chamber.

f. Remove the spare RF-24R "holder/plug" assembly (containing the fresh iodine cartridge) from the RF-24R carrier cask (in the transport dolly) and lay beside RE-24R.

g. Loosen the four wing bolts retaining the existing "holder/plug" assembly in RE-24R's chamber.

h. Rotate the "holder/plug" assembly counterclockwise in RE-24R's chamber so the slotted ears clear the wing bolts.

i. Pull the entire "holder/plug" assembly containing the spent RF-24R iodine cartridge out of RE-24R's chamber and quickly place it in the RF-24R carrier cask.

j. Slide the spare RF-24R "holder/plug" assembly containing the new iodine cartridge into RE-24R's chamber and turn clockwise until the slotted ears engage the wing bolts.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 27 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

k. Tighten the wing bolts with fingers only.

1. Push the "skid pump" button on the RNR LRP panel to start the skid's sample pump.

m. Read and record on a new Form 69-13225 the beginning sampl flowrate for this new cartridge from the RNR's LRP left most LED (RE

-28R - particulate window.)

n. Record the sample/start time on this new Form 69-13225 for this sequentially next cartridge (now in RE-24R).

o. Return to the TSC Lab with the dolly, cask containing the spent RF-24R, and data sheets for turnover to TSC personnel and await SCC directions to return to Step a. and continue collection.

6.3.3 TSC Analysis of the RF-24R Sample Cartridge

a. Obtain from the Site Chemistry Coordinator (or PV sampling personnel) for each cartridge the following RF-24R sample information:

1. Sample collection start date/time.

2. Sample collection stop date/time.

3. Sample collection flowrates (default = 2.0 CFM)

b. Using the hand-held survey meter, obtain a contact dose rate measurement at the bottom of the carrier cask (opposite of the side with the handle) with the small lead shield plug in place.

c. Transfer this information onto Form 69-13225.

d. Select the initial collimating aperture based on the reading obtained from Step c. above using the following table:

Contact Reading of the Use Collimating Bottom of the Hand-held Pif Aperture, "d" less than 0.2 mR/hr 3/4" 0.2 mR/hr to 2 mR/hr 1/4" 2 mR/hr to 22 mR/hr 1/8" 22 mR/hr to 220 mR/hr 1/16" greater than 220 mR/hr 1/32"

e. Remove the lead plug (same size as a collimating aperture but without the hole) from the center of the GE detector's shield door.

f. Insert the collimating aperture selected from Step d. into the vacated hole of the GE detector's shield doors.

00283306.DOA 3B 27 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 28 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions CAUTION: Steps g thru k can cause a Very High Radiation Exposure. Keep the exposed cavity on the bottom of RF-24R carrier cask pointed away from the body and extremities.

g. Lift the RF-24R carrier cask containing RF-24R and its entire "holder/lead plug" assembly out of the transport dolly and up on the GE detector's shield doors.

h. Leave behind (in the dolly) the small shield plug covering the bottom cavity of the RF-24R carrier cask.

i. Quickly but carefully, place the RF-24R carrier cask with "holder/lead plug" assembly cavity side down and centered, on top of the collimating aperture on the GE detector's shield doors.

j. If the collimating aperture is out of range based on the Canberra's count rate meter or dead time meter reading on RF-24R, lift the carrier cask off of the aperture and place to one side on the GE detector's shield doors. Immediately, reselect the next larger or smaller aperture.

Replace the carrier cask with RF-24R centered over the new aperture then continue.

k. Commence the radionuclide analysis using the Canberra System as per procedures CAP B-53 and CAP B-53:I.

1. For each cartridge sampled, enter the following data as inputs in the Canberra program as extracted from the Sample Collection Data:

1. Sample Description (from Form 69-13225) (i.e., cartridge #, etc.)

2. Sample start date/time (from Form 69-13225)

3. Sample stop date/time (from Form 69-13225)

4. Sample flowrate (CFM) (from Form 69-13225)

(e.g., default 2.0 cfm)

5. Sample collection factor, 0.92 (includes plate-out and cartridge retention factors combined) depending on the sample flowrate.

6. Collimating aperture Geometry code used (i.e., "d").

00283306.DOA 3B 28 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 29 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions CAUTION: High noble gas concentrations trapped in the cartridge may interfere with the resolution of iodine peaks. The cartridge may require a reverse purge using air or nitrogen. A minimum purge volume of 18 liters is needed to reduce the entrained gas concentration.

m. All results concerning the high range iodine concentrations as determined by this procedure should be reviewed by the Site Chemistry Coordinator and should be communicated as soon as possible (not more than 10 minutes after the start of analysis) to the ERA's staff in the TSC.

CAUTION: Steps n. thru t. can cause Very High Radiation Exposure. Keep the exposed cavity of the hand-held pig pointed away from the body and extremities.

n. At the end of the Canberra Analysis perform the following:

1. Lift the RF-24R carrier cask with the "holder/lead plug" assembly off the GE detector's aperture and shield doors and place back in the transport dolly down over the small shield plug.

2. Rotate carefully counterclockwise the RF-24R "holder/lead plug" assembly by its handle in the carrier cask until the protruding lug of the "holder/lead plug's" end cap engages the slot in the small shield plug in the transport dolly.

3. Continue to rotate counterclockwise after the engagement until the "holder/lead plug's" end cap is loosened allowing easy removal of RF-24R.

o. Open the top of the radioactive sample storage pig at the Northeast entrance area of the TSC Lab.

p. Lift quickly the RF-24R "holder/lead plug" assembly out of the RF-24R carrier cask and transport dolly and place on the edge of the storage pig with the "holder's end cap" facing out and upward (but away from your face).

q. Grasp the RF-24R "holder end cap" with the RF-24R cartridge holder cap grip/removal tool keeping a handle's distance away from the end cap.

00283306.DOA 3B 29 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 30 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

r. Rotate counterclockwise with the handle until the "holder end cap" and RF-24R are free of the lead plug assembly.

s. Using the push stick, push the RF-24R cartridge out of the "holder end cap" and down into the storage pig.

t. Replace cover over the storage pig.

u. Wipe all tools and the RF-24R "holder end cap" assembly, decontaminating if necessary.

v. Reassemble the RF-24R "holder/lead plug" assembly with a fresh cartridge placed in the end cap and turn over along with the transport dolly to the personnel collecting samples.

w. Report to the SCC with the sample analysis results and for continued instructions.

7. ACCEPTANCE CRITERIA Satisfactory performance of data collection by procedural steps.

8. REFERENCES 8.1 Regulatory Guide 1.97, "Instrumentation for Light - Water Cooled Nuclear Power Plants to Access Plant and Environs Conditions During and Following an Accident."

8.2 Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors."

8.3 NUREG-0737, "Clarification of TMI Action Plan Requirements."

8.4 General Design Criteria 19.

8.5 Diablo Canyon Power Plant Unit 1 and 2 Emergency Plan.

8.6 CAP B-53, "Gamma Spectroscopy System Equipment (Canberra ProCount)."

8.7 CAP B-53:1, "Gamma Spectroscopy System (ProCount Technician Software Operation)."

8.8 CAP E- 19, "Plant Vent Radioactive Effluent Sampling."

8.9 EP EF-1, "Activation and Operation of the Technical Support Center (TSC)."

8.10 EP G-1, "Accident Classification and Emergency Plan Activation."

8.11 EP RB-2, "Release of Airborne Radioactive Materials."

8.12 EP RB-9, "Calculation of Release Rate."

8.13 Regulatory and Technical Basis and recommended response to AR A0489282 and A0489299, Henry Fong, 2/29/2000.

00283306.DOA 3B 30 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 31 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

9. RECORDS Data Sheets and records will be maintained in the Records Management System (RMS) in accordance with AD1O.IDl.

10. APPENDICES 10.1 Figure 3, RE-87 Response Curve 10.2 Figure 4 and Figure 5, RE-29 Response Curves

11. ATTACHMENTS 11.1 Form 69-13224, "RF-87A or B Sample Collection Data Sheet," 05/13/93 11.2 Form 69-13226, "RE-24R/RE-28R Monitor Data Sheet," 10/07/93 11.3 Form 69-13225, "RF-24R Sample Collection Data Sheet," 11/25/93 11.4 "Figure 1, Route Map," 08/22/00 11.5 "Figure 2, NR/PVER LRP/RDU Panel of Button Switches and Keypad," 08/22/00 11.6 "Figure 6, Plant Vent Radiation Monitor Ranges," 08/22/00 11.7 "Figure 7, Source of Power to Sampling Skids," 08/22/00

12. SPONSOR Keith Bieze 3B 31 II 0824.1039 00283306.DOA

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 32 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions APPENDIX 10.1 FIGURE 3, RE-87 RESPONSE CURVE I OOE-0 EIfeciv Age I~r 20:

40 -8 Amps per I 00E-o09 Ci/cc 1,00O-10 0.1 10 100 1000 Time After Shutdown, Hrs TAGRAPHICS\00283303 00283306.DOA 3B 32 II 0824.1039

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 REVISION 6 DIABLO CANYON POWER PLANT PAGE 33 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions APPENDIX 10.2 FIGURE 4 AND FIGURE 5, RE-29 RESPONSE CURVES FIGURE 4 1 ODE- 04 1.00E+ 03 m R/Hr per 1ODE+ 02 Ci/cc I 00.E+ 01 100E+ O0 0.1 10 100 IODO Time After Shutdown, Hrs 33 II 0824.1039 00283306.DOA 3B

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 6 PAGE 34 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions APPENDIX 10.2 (Continued)

FIGURE 5

.4, 105 Lo' 10 0 104 10 3 9

-a04 102 .*

E-E lO0 0

10- 10C ci 10~

10 46,r "Op 10-C.

-4r so

-0 E"2 10-4 5 10-1 107 106 10 102 101 100 Net Gross Gamma Monitor Response, Net ER (mR/hr) 00283306.DOA 3B 34 II 0824.1039

69-13224 05/13/93 Page 1 of I DIABLO CANYON POWER PLANT EP RB-12 IA 2 TITLE: RF-87A or B Sample Collection Data Sheet Unit No.: Performed by:

Date/Time NR Switched over to PVER: /

Initial RE-34 Reading (near time of switch): mR/hr Initial RE-87 Reading (near time of switch): _ _ Ci/cc Initial RF-87 Sample Flowrate: 1pm or cc/min (circle one)

Initial Sampling Started with RF-87A or RF-87B (circle one)

Cartridge No.: RF-87A or RF-87B (circle one)

Sample Flowrate: 1pm (1000 cc/min equals 1 lpm)

Filter Collection Start Date/Time: /

Filter Collection Stop Date/Time: I Cask Dose Rate: Method Used: A or B (circle one)

Method A: Contact Dose Rate Reading of Closed Cask (small lead plug in place)

Method B: 1 foot Dose Rate Reading of Open Cask (small lead plug removed)

Cartridge No.: RF-87A or RF-87B (circle one)

Sample Flowrate: 1pm (1000 cc/min equals 1 1pm)

Filter Collection Start Date/Time: /

Filter Collection Stop Date/Time: /

Cask Dose Rate: Method Used: A or B (circle one)

Method A: Contact Dose Rate Reading of Closed Cask (small lead plug in place)

Method B: 1 foot Dose Rate Reading of Open Cask (small lead plug removed)

Reviewed By: Date:

Site Chemistry Coordinator or designee 00283306.DOA 3B 35 II 0824.1039

69-13226 10/07/93 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-12 I1ND2 TITLE: RE-24R/RE-28R Monitor Data Sheet Unit No.:

Date/Time NR to PVER Switchover /

Initial RE-34 Reading mR/hr (i.e., near switchover)

Initial RE-14R Reading _iCi/cc (i.e., near switchover)

Initial RE-87 Reading (if available) _ _ Ci/cc (i.e., near switchover)

Previous sample flowrate (if available) cfm (i.e., near switchover)

Previous RE-24R reading _.Ci/cc (prior to but near switchover)

Previous RE-28R reading _.Ci/cc (prior to but near switchover)

Initial Raw Countrate Reading by RE-24R (prior to but near switchover)

(i.e., "DISP OP", "3", "DISP" cpm (if applicable)

Cartridge # Iteration # on this cartridge (if applicable)

a. RE-24R Start CPM _ _ _ cpm e. Skid pump stop time

("DISP OP", "m3"m DISP") (hr) : (min)

b. Skid pump start timiLe f. RE-24R Stop CPM cpm (hr) : (min) DISP OP", "Y3, "DISP")

c. RE-24R reading in gtCi/cc ______=_If-) _ -(a.)_

(if applicable) g. CR {e,} - {lb.}

d. Sample Flowrate cfm h. RE-34 Reading mR/hr RE-28R reading in j+/-Ci/cc (if applicable)

Filter #

Cartridge # Iteration # on this cartridge (if applicable)

a. RE-24R Start CPM cpm e. Skid pump stop time "DISP OPh "3", "DISP") (hr) : (min)

b. Skid pump start time f. RE-24R Stop CPM cpm (hr) *(min) DISP OP"t, "31', "DISP")

c. RE -24R reading in gtC i/cc (if a plica le)g=If.) g. CR = {f,) --lba.}

(if applicable) (a.) -p/i

{e,} - (b.})p/i

d. Sample Flowrate cfm h. RE-34 Reading mR/hr RE-28R reading in [tCi/cc (if applicable)

Filter #

00283306.DOA 3B 36 HI 0824.1039

69-13225 11/25/93 Page I of I DIABLO CANYON POWER PLANT EP RB-12 I1AN2 TITLE: RF-24R Sample Collection Data Sheet Unit No. Performed by:

Initial RE-34 Dose Rate Reading: Date/Time:

NR to PVER Switchover: Date/Time /

Increase in iodine activity prior to switchover: Date/Time Cartridge No.: RE-34

1. Begin Sample Flow: cfm 2. End Sample Flow: cfm Filter Collection Start Date/Time: /

Filter Collection Stop Date/Time: /

Average Sample Flowrate = +21.-

2 _em f2-}(default value equals 2.0 cfm)

Cask dose rate (bottom side)

Cartridge No.: RE-34

1. Begin Sample Flow: cfm 2. End Sample Flow: cfm Filter Collection Start Date/Time: /

Filter Collection Stop Date/Time: /

Average Sample Flowrate = 1.- + =2._ cfm (default value equals 2.0 cfm) 2 Cask dose rate (bottom side)

Cartridge No.: RE-34

1. Begin Sample Flow: mcfm 2. End Sample Flow: _cfm Filter Collection Start Date/Time: /

Filter Collection Stop Date/Time: /

Average Sample Flowrate =1.) + {2._ cfm (default value equals 2.0 cfm) 2 Cask dose rate (bottom side)

Reviewed By: Date:

Site Chemistry Coordinator or designee 00283306.DOA 3B 37 II 0824.1039

08/22/00 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-12 Attachment 11.4 I AND 2 TITLE: Figure 1, Route Map 3585 mRl Pr SKID ROOM 1472 in0 2045 mR/hr 2160 mR/hr ROUTE FROM ACCESS CONTROL OR CHEM FOREMAN'S OFFICE 1700 mR/hr 1700 mR/hr MAXIMUMPREDICTED DOSE RATES (mR/hr) AT 1 HOUR POST LOCA NOTE:

EXPOSURE RATES SHOWN FOR UNIT 1 ACCIDENT FOR UNIT 2 ACCIDENT USE MIRROR IMAGE OF UNIT 1 00283306.DOA 3B 38 0824.1039 84

( (1 08/22/00 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-12 Attachment 11.5 1 AND 2

TITLE: Figure 2, NRIPVER LRP/RDU Panel of Button Switches and Keypad TITE:Fiure2,NRPV RLR/D Pae ofBtowwthsadKya RM-28/25R RM-24/24R RM-14/14R RM-.-7(on NR)

PARTICULATE IODINE GAS rNULDAENR M[1E!n2 FRADIAONl STATUS f31147n wA t; (ýA SR Fr-6 n5 nIEn ng Eo 9 t I -.

INm 111L NO ON_[

RNR L.

I I

I U

III II SWJDL

II anw 4

S I

4

-AM 0=0m

. NOTE- ALL PERIPHERAL INFORMATION ON: CHANNELS. FUNCTIONS, AND DATA ARE READ IN THE LEFT MOST LED (NAMELY THE 'PARTICULATE' WINDOW) 00283306.DOA 3B 39 H 0824.1039

( /

08/22/00 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-12 Attachment 11.6 I1ND2 TITLE: Figure 6, Plant Vent Radiation Monitor Ranges MONITOR RANGES EFFLUENT TYPE NORMAL MIDRANGE HIGH RANGE I I I I I I 1 I- T I ~RE 14/14R NOBLE GAS RE-87 RE-29 RE 24/24R RADIOIODINES RX 40 (Grob sampler) Useful ronge depends on Tnmpi.

RF 87 A/B (Grob sampler) Useful range depends on T..o...

RE 28/28R PARTICULATES RX 40 (Grob sampler) Useful ronge depends on T lompie RF 87 A/8 (Grob sompler) Useful ronge depends an Tsompn SI I I I I I I II1I I I 4

10`2* 10"1 10-`0 lo-, 10 -8 10-7 10-6 10-5 10- 10-3 10-2 10- 10 0 101 10, 10, 10, 105 106 EFFLUENT CONCENTRATION ( /Ci/cc) 00283306.DOA 3B 40 H 0824.1039

(

08/22/00 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-12 Attachment 11.7 IAND2 TITLE: Figure 7, Source of Power to Sampling Skids From From Morro Meso Boy Sub No.22 Midwoy-

'--' ELT .j stot ion No. 3- "(J--" other it Midwoy-,

L-} 230 - KV Not 1. Switch yord other unit other unit Emergency Cross Over Stortup Tronsformer S.KIOS 240/120V _

.aJ...AJ 80

]Eo PV.

RE-14 RE-24 RX40 240/12V 4/120V RE-24R RE-28 smpler J'(RF-24R)

NR RE-87 RE-28R RF-87A/8)

(ER 00283308 00283306.DOA 3B 41 II 0824.1039

- - ISSUED FOR USE BY: DATE: EXPIRES: ***

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-2 NUCLEAR POWER GENERATION REVISION 24 DIABLO CANYON POWER PLANT PAGE 1 OF 4 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Activation and Operation of the Operational Support Center 1t 2 S.21.co EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED I1. SCOPE This procedure describes the activation and operation of the Operational Support Center (OSC).

2. DISCUSSION 2.1 Location and Description The OSC provides a place separate from the Control Room and Technical Support Center where designated support personnel assemble and receive specific assignments. The 119' OCC and OWCC location in the Turbine Building, Medical Facility, and 85' Access Control are designated as the primary OSC. Access to the Radiological Controls Area (RCA) will be through an established access control area as designated by the Site Radiation Protection Coordinator. At the Alert, medical personnel use the medical facility as an assembly area.

Medical personnel assemble in the 119' OCC and OWCC area at SAE and GE. These areas contain a variety of immediately available emergency support equipment.

2.2 OSC Functions 2.2.1 A staging area for personnel assigned to one of the following tasks:

a. Emergency maintenance, assessment, repair and damage control

b. Fire fighting, search and rescue and medical assistance

c. Post-accident sampling and radiological assessment 2.2.2 Emergency response equipment storage 2.2.3 Personnel decontamination facility 2.3 Minimum Staffing The minimum OSC staffing required to perform OSC functions per the DCPP Emergency Plan, is shown in Attachment 6.1. Vacancies may be filled by other qualified individuals not already filling a minimum staff position.

2.4 Activation of OSC The OSC is considered activated when all processes required for the OSC are fully operational. Fully operational means that the person assigned to a position has taken over the responsibility for those duties.

00045424.DOA 3B I 0817.0321

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-2 DIABLO CANYON POWER PLANT REVISION 24 PAGE 2 OF 4 TITLE: Activation and Operation of the Operational Support UNITS 1 AND 2 Center

3. RESPONSIBILITIES 3.1 Emergency Maintenance Coordinator 3.1.1 Directs activities of OSC personnel.

3.1.2 Develops, in cooperation with the SEC/Maintenance Logistics Advisor, a repair plan to recover from the emergency.

3.1.3 Fabricates and sets up any special equipment necessary at the direction of the SEC/Maintenance Logistics Advisor.

3.1.4 Coordinates the movement and accountability of maintenance teams.

3.1.5 Provides OSC status updates to the TSC.

3.1.6 Maintains proper records and logs.

3.2 Maintenance Coordinators (Mechanical, Technical, and Electrical Maintenance) 3.2.1 Plan and coordinate resources to conduct assessment, maintenance, repair or installation of special equipment.

3.2.2 Provide team status updates to the OSC Access Supervisor.

3.2.3 Maintain proper records and logs.

3.3 OSC Access Supervisor 3.3.1 Controls plant access and ensures personnel entering a potentially hazardous plant area are informed of:

a. plant status.

b. potential hazards.

c. safety and radiation protection provisions.

d. appropriate protective equipment required.

3.3.2 Maintains accountability of and communicates with personnel dispatched from the OSC.

3.3.3 Briefs dispatched response teams on plant conditions and emergency classification changes.

3.3.4 Assists the Control Room and OSC in communicating with response teams.

3.3.5 Maintains proper records and logs.

3.4 Site Radiation Protection Coordinator 3.4.1 Provides personnel exposure monitoring and record keeping.

3.4.2 Directs surveys and establishes radiation or contamination control area boundaries.

3.4.3 Determines radiological protection requirements for RCA access.

00045424.DOA 3B 2 0817.0321

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-2 DIABLO CANYON POWER PLANT REVISION 24 PAGE 3 OF 4 TITLE: Activation and Operation of the Operational Support UNITS 1 AND 2 Center 3.4.4 Determines when an emergency exposure authorization is required and provides justification to the SEC/RM.

3.4.5 Informs the Radiological Advisor, Emergency Maintenance Coordinator and the OSC Access Supervisor of team activities.

3.4.6 Coordinates with the OSC Access Supervisor to brief radiological conditions to personnel dispatched into affected plant areas.

3.4.7 Maintains proper records and logs.

3.5 Site Chemistry Coordinator 3.5.1 Directs sampling and radio-chemical and chemical analysis.

3.5.2 Informs the Radiological Advisor and Emergency Maintenance Coordinator of actions and findings.

3.5.3 Coordinates personnel dispatched for sampling or analysis with the Site Radiation Protection Coordinator and OSC Access Supervisor.

3.5.4 Maintains proper records and logs.

3.6 Operations Coordinator 3.6.1 Coordinates Operation's response outside the Control Room.

4. INSTRUCTIONS 4.1 Activate OSC per the appropriate attachment listed in Section 6.0.

4.2 At the discretion of the Emergency Maintenance Coordinator, Site Radiation Protection Coordinator or their discipline Maintenance Coordinator, maintenance teams may be directed to don protective clothing and prepare respiratory protection prior to actual team or task assignment.

4.3 The representative from Operations Department coordinates with their organizations to provide general OSC support (under the direction of the Emergency Maintenance Coordinator).

5. RECORDS 5.1 All attachments, logs, checklists and records, whether completed or not, will be collected in each facility and turned over to Emergency Planning for compilation, retention and filing.

5.2 Drill and Exercise records will be retained for five years.

5.3 Emergency event records will be retained as plant lifetime records.

6. ATTACHMENTS 6.1 "OSC Organization," 03/09/00 6.2 "Emergency Maintenance Coordinator Checklist," 08/17/00 6.3 "Team Predeparture Checklist," 02/18/00-00045424.DOA 3B 3 0817.0321

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-2 DIABLO CANYON POWER PLANT REVISION 24 PAGE 4 OF 4 TITLE: Activation and Operation of the Operational Support UNITS 1 AND 2 Center 6.4 "OSC Access Supervisor Checklist," 02/18/00 6.5 "Site Radiation Protection Coordinator Checklist," 02/18/00 6.6 "Site Chemistry Coordinator Checklist," 04/19/00 6.7 "Maintenance/Operations Coordinators Checklist," 02/18/00 6.8 "OSC Telephone Numbers," 02/18/00 6.9 "Maintenance Team Exposure Tracking Sheet," 10/01/98 6.10 "OPS Team Dispatch Decision Tree," 08/27/96

7. REFERENCES 7.1 DCPP Emergency Plan.

00045424.DOA 3B 4 0817.0321

03/09/00 Page 1 of I 1 2 DIABLO CANYON POWER PLANT EP EF-2 ATTACHMENT 6.1 AND TITLE: OSC Organization Clerical OSC Access Operations Supevisor Coordinator SERO Position Positions within ovals are the minmium staff positions required for facility activation 00045424.DOA 3B 5 0817.0321

08/17/00 Page I of 2 DIABLO CANYON POWER PLANT EP EF-2 ATrACHMENT 6.2 1AND TITLE: Emergency Maintenance Coordinator Checklist ACTIONS INITIAL

1. INITIAL ACTIONS PRINT NAME INITIALS DATE NOTE: The minimum staffing level is based on the assumption the on-site notification process has been completed and other OSC positions will be filled shortly.

1.1 Sign in on the Assembly and Accountability Checklist form as applicable.

1.2 Sign in on the OSC sign-in board.

1.3 Direct one of the Maintenance/Operations Coordinators to act as the LOG OSC Designated Assembly Area Supervisor (DAAS) and complete OSC accountability using the Assembly Area packet.

1.4 Determine minimum staffing status of the OSC. Vacancies may be filled by other qualified individuals not already filling a minimum staff position. If assistance is required, notify the TSC Administrative Advisor.

1.4.1 When minimum staffing is achieved, declare the OSC activated and notify:

a. Control Room

b. SEC/TSC Maintenance Logistics Advisor 1.4.2 Additional OSC Staffing:

a. Mechanical, Electrical and Technical Maintenance LOG personnel, the number required to support anticipated activities, must be called in from off-site or their assembly area.

b. Clerical support will be called in by the TSC LOG Administrative Advisor.

1.5 Establish communications with:

1.5.1 Maintenance Logistics Advisor and obtain permission to LOG waive administrative controls for emergency maintenance from the Site Emergency Coordinator.

00045424.DOA 3B 6 0817.0321

08/17/00 Page 2 of 2 EP EF-2 (UNITS 1 AND 2)

ATTACHMENT 6.2 TITLE: Emergency Maintenance Coordinator Checklist ACTIONS INITIAL

2. CONTINUOUS ACTIONS 2.1 If plant conditions warrant, direct the SRPC to establish periodic OSC LOG radiological habitability surveys.

2.1.1 Notify the TSC Radiological Advisor of this action. LOG NOTE 1: All dispatched teams will have an "OSC Predeparture Authorization Checklist" in process.

NOTE 2: Any team ill-prepared or ill-equipped will be denied departure permission by the OSC Access Supervisor and sent back for further instructions.

2.2 If a team must be dispatched without an SWP, permission from the LOG SEC must be obtained.

2.3 If the SRPC determines the need for an emergency exposure LOG authorization, refer to EP RB-2 for instructions and guidance on evaluating alternatives and providing support.

2.4 When a response team is required, direct the appropriate Maintenance LOG Coordinator and SRPC to brief the team prior to dispatch.

NOTE: Refer to Attachment 6.10 for operator dispatch.

2.5 Log and communicate to the TSC Maintenance Logistics Advisor the following information:

2.5.1 Significant accident mitigation LOG 2.5.2 Problem evaluation and team assignment LOG 2.5.3 Team dispatch times LOG 2.5.4 Update team status LOG 2.5.5 Team return time and results LOG 2.6 Perform periodic briefings to OSC staff. LOG 2.7 If OSC evacuation is necessary, transfer operations to the alternate OSC, refer to EP EF-9, "Activation of Backup Emergency Response Facilities."

2.8 Direct clerical assistants to:

2.8.1 Coordinate with the TSC Administrative Advisor to develop a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months shift schedule.

2.8.2 Update OSC status boards.

2.8.3 Assist in maintaining the EMC log.

2.9 Maintain a log of significant communications and decisions.

0K0045424.DOA 3B 7 0817.0321

02/18/00 Page 1 of 1 DIABLO CANYON POWER PLANT EP EF-2 ATTACHMENT 6.3 I1AN2 TITLE: Team Predeparture Checklist TEAM NUMBER Date: Time:

i~aintenaEl Priority:o F] Priority:

El El

1) Team: El El El El El El El Mech Elect OPS Chem RP Tech Sec High Med Low Maint

2) Members: Name Pager Name Pager Name Pager Name Pager Name Pager Name Pager

3) Pager or Radio:

4) Work Location: El Aux El Turb El Cont Other:

Unit [E] 1 2 5)

Purpose:

6) Tailboard Conducted: El Yes El No Raiaio Prtcto Coordinato

7) Rad brief needed? E] Yes El No SWP # E[ N/A

8) Verify Steps 1 - 8 Are Complete

9) j-ý Team Communications Established

10) F-1 EMC Notified of Team Dispatch

11) [f] JOBSITE, Phone # _______________

Tea Debie

12) Mission Status:

13) EMC Notified of Team Return & Status OSC Access Supervisor Signature

14) Rad Protection Debrief RP Coordinator Signature

15) Technical Debrief Maintenance Coordinator Signature

16) Team Return Time/Date OSC Access Supervisor Signature 00045424.DOA 3B 8 0817.0321

02/18/00 Page I of I DIABLO CANYON POWER PLANT EP EF-2 ATTACHMENT 6.4 AND TITLE: OSC Access Supervisor Checklist ACTIONS INITIAL I1. INITIAL ACTIONS PRINT NAME INITIALS DATE 1.1 Sign in on the Assembly and Accountability Checklist form as applicable.

1.2 Sign in on the OSC sign-in board.

1.3 IMMEDIATELY upon arrival determine if teams were dispatched into LOG the RCA. Provide this information to the EMC, SRPC and the OSC (DAAS) Designated Assembly Area Supervisor (OSC designated Maintenance Coordinator).

1.3.1 Verify with Maintenance, Operations, Chemistry and Radiation Protection Coordinators.

1.3.2 Contact Security (Watch Commander).

1.3.3 Contact the Medical Facility (#).

1.3.4 Provide available information to the EMC and the SRPC.

2. CONTINUOUS ACTIONS NOTE: Any team ill-prepared or ill-equipped will be denied departure permission by the OSC Access Supervisor and sent back for further instructions.

2.1 For each team, review the "Team Predeparture Checklist" for LOG completeness, provide a briefing for communications, and authorize departure.

NOTE: Refer to Attachment 6.10 for operator dispatch.

2.2 Maintain team accountability:

2.2.1 Log all team departures and returns. LOG 2.2.2 Inform the EMC of team departures and returns. LOG 2.3 Maintain communications with all teams.

2.3.1 Inform response teams of changes in emergency LOG classification or plant conditions.

2.3.2 Periodically update the EMC of team status. LOG 2.3.3 Periodically update the SRPC on team exposure status and LOG radiological problems, dose rates encountered.

2.4 Maintain a log of significant communications and decisions.

2.5 Ensure returning teams report to the SRPC to receive a debriefing on radiological conditions, personnel exposure, and other hazards or problems encountered.

00045424.DOA 3B 9 0817.0321

02/18/00 Page I of 2 DIABLO CANYON POWER PLANT EP EF-2 ATTACHMENT 6.5 1AND TITLE: Site Radiation Protection Coordinator Checklist ACTIONS INITIAL I1. INITIAL ACTIONS PRINT NAME INITIALS DATE 1.1 Sign in on the Assembly and Accountability Checklist form as applicable.

1.2 Sign in on the OSC sign-in board.

1.3 IMMEDIATELY upon arrival, coordinate with the SCC to determine if additional Technicians must be called in.

1.4 Establish communications with the TSC Radiological Advisor:

1.5 Obtain a computer printout record of current calendar year exposure for personnel who may be dispatched from the OSC.

2. CONTINUOUS ACTIONS 2.1 Upon the arrival of the NRC Initial Site Team, the NRC Co-locator (NRC HP Specialist) may come to the OSC. Upon arrival, brief him on the emergency developments, mitigating actions, and current activities. Ensure the NRC Co-locator is familiar with telephone use, information flow, and has copies of the same documents used for your position.

2.2 Perform a predeparture analysis of the anticipated TEDE and determine if any identified team member requires an emergency exposure authorization prior to dispatch.

2.2.1 If any team member may exceed the Federal Limit Calendar Year exposure criteria of 5 rem TEDE, an emergency exposure authorization is required for that individual.

2.2.2 Refer to EP RB-2, "Emergency Exposure Guides," for further instructions while continuing in this procedure.

00045424.DOA 3B 10 0817.0321

02/18/00 Page 2 of 2 EP EF-2 (UNITS 1 AND 2)

ATTACHMENT 6.5 TITLE: Site Radiation Protection Coordinator Checklist ACTIONS INITIAL 2.3 Brief teams prior to departure, including:

NOTE: Refer to Attachment 6.10 for operator dispatch.

2.3.1 Prepare an SWP prior to entry if time permits, although a LOG verbal SWP is permissible. Perform verbal SWP, to be followed up by the written SWP, in accordance with EP RB-4.

2.3.2 Brief teams on the radiological conditions they will LOG encounter and discuss travel routes.

2.3.3 Determine the requirements for personnel dosimetry in accordance with EP RB-1, "Personnel Dosimetry."

2.3.4 When a team has been briefed on the radiological hazards, LOG validate their predeparture checklist and direct them to the OSC Access Supervisor.

2.4 Initiate "Team Predeparture Checklist" for C&RP Personnel who are LOG not part of a maintenance team.

2.5 If plant conditions warrant, recommend periodic OSC radiological LOG habitability surveys to the EMC.

2.5.1 When the EMC directs, establish periodic radiological LOG habitability surveys as required.

2.6 Continuously track personnel emergency exposure and maintain LOG records to determine when individual limits are being approached.

Attachment 6.9 may be used to track exposures.

NOTE: Attachment 6.9 DCFs were developed for Field Monitoring Teams and DO NOT take credit for respiratory protection or other protective measures. If such protective measures are taken, DCF are not appropriate for in-plant use. All radiation protection measures in addition to DCFs should be taken in consideration for mitigating the emergency response.

2.7 If high airborne radio iodine conditions are present, coordinate the administration of Thyroid Blocking (KI) as directed by the TSC Radiological Advisor and in accordance with EP RB-3, "Stable Iodine Thyroid Blocking."

2.8 If any returning team personnel require decontamination and the normal access control decon facilities are not available, refer to EP RB-5, "Personnel Decontamination," for alternate locations during emergencies.

2.9 Provide a radiological debriefing of returning teams including LOG exposures, radiological conditions and other hazards or problems encountered.

2.10 Maintain a log of significant communications and decisions.

00045424.DOA 3B 11 0817.0321

04/19/00 Page I of 2 DIABLO CANYON POWER PLANT EP EF-2 ATTACHMENT 6.6 AND TITLE: Site Chemistry Coordinator Checklist ACTIONS INITIAL

1. INITIAL ACTIONS PRINT NAME INITIALS DATE 1.1 Sign in on the Assembly and Accountability Checklist form as applicable.

1.2 Sign in on the OSC sign-in board.

1.3 IMMEDIATELY upon arrival, if the SRPC has not arrived, determine if additional Technicians must be called in.

1.4 Establish communications with the TSC Radiological Advisor:

1.5 Obtain a record of current calendar year exposures for Chemistry personnel who may be dispatched from the OSC.

2. CONTINUOUS ACTIONS 2.1 Coordinate with the TSC Radiological Advisor to determine plant LOG chemistry sampling requirements.

2.2 Supervise radiochemical and chemical analysis. LOG 2.3 Perform a predeparture analysis of the anticipated TEDE and determine if any identified team member requires an emergency exposure authorization prior to dispatch.

2.3.1 If any team member may exceed the Federal Limit Calendar Year exposure criteria of 5 rem TEDE, an emergency exposure authorization is required for that individual.

2.3.2 Notify the SRPC to refer to EP RB-2, "Emergency Exposure Guides," for further instructions while continuing with the team briefing.

00045424.DOA 3B 12 0817.0321

04/19/00 Page 2 of 2 EP EF-2 (UNITS 1 AND 2)

ATTACHMENT 6.6 TITLE: Site Chemistry Coordinator Checklist ACTIONS INITIAL NOTE: If necessary, an emergency exposure authorization of 5 rem TEDE may be obtained from the RM/SEC to permit sampling activity to proceed. Any individual who receives an emergency exposure shall be relieved of further emergency response duties and a replacement obtained.

2.4 Brief personnel dispatched for sampling or analysis. LOG 2.5 If PASS is activated, make the necessary arrangements per EP RB-15, LOG "Post-Accident Sampling System."

2.6 Keep the EMC informed of actions and findings. LOG 2.7 Maintain proper records and logs.

00045424.DOA 3B 13 0817.0321

02/18/00 Page I of I DIABLO CANYON POWER PLANT EP EF-2 ATTACHMENT 6.7 I1AN2 TITLE: Maintenance/Operations Coordinators Checklist ACTIONS INITIAL INITIAL ACTIONS PRINT NAME INITIALS DATE 1.1 When the first Maintenance Coordinator arrives at the OSC, assume the responsibility of the OSC (DAAS) Designated Assembly Area Supervisor.

1.2 Sign in on the Assembly and Accountability Checklist form as applicable.

1.3 Sign in on the OSC sign-in board.

1.4 Determine the anticipated tasks, staffing and equipment requirements.

NOTE: During normal working hours maintenance personnel are assembled in the Learning Services Center. To obtain needed personnel from this facility, coordinate with Access Supervisor.

During off-normal working hours personnel must be called in from home.

1.4.1 Report staffing requirements to the EMC.

1.4.2 Maintenance mersonnel should be sta2ed on the mezzanine deck below the OSC.

2. CONTINUOUS ACTIONS 2.1 When assigned a task by the EMC, coordinate maintenance team LOG dispatch with the Access Supervisor.

NOTE: Refer to Attachment 6. 10 for operator dispatch.

2.2 Maintain a log of activities.

00045424.DOA 3B 14 0917.0321

02/18/00 Page 1 of I DIABLO CANYON POWER PLANT EP EF-2 ATTACHMENT 6.8 1ND2 TITLE: OSC Telephone Numbers Emergency Maintenance Coordinator x2605/2609 Mechanical Maintenance Coordinator x2606 Electrical Maintenance Coordinator x3689 Technical Maintenance Coordinator x2608 Operations Coordinator x2677 Site Rad Protection Coordinator x2663 Site Chemistry Coordinator x2664 OSC Access Supervisor x2696/2660 Emergency Conference Line x2609 00045424.DOA 3B 15 0817.0321

10/01/98 Page I of 2 DIABLO CANYON POWER PLANT EP EF-2 ATTACHMENT 6.9 I1ND2 TITLE: Maintenance Team Exposure Tracking Sheet Thyroid CDE Thyroid CDE TEDE DCF DCF Source Term DCF (KI taken prior to exposure) (KI not taken)

RCS Coolant 3 5 43 Fuel Rod Gap 25 53 530 Core Melt 22 16 160 SGTR- (empty) 60 140 1400 SGTR (normal) 12 26 260 SGTR (flooded) 10 250 2500 Use the tables above and below to convert PIC readings to Dose.

NOTE: Attachment 6.9 DCFs were developed for Field Monitoring Teams and DO NOT take credit for respiratory protection or other protective measures. If such protective measures are taken, DCF are not appropriate for in-plant use. All radiation protection measures in addition to DCFs should be taken in consideration for mitigating the emergency response.

1) Obtain the source term from the Radiological Data Processor - Dose Assessment in the TSC.

2) Record the time and readings for both the high and low range PICs.

3) Multiply by the dose conversion factors (DCFs). If the source term changes, use the new DCF multiplier.

4) If a PIC is re-zeroed, circle the last TEDE and Thyroid CDE values and add the circled values to determine the Cumulative TEDE and Thyroid CDE.

5) Refer to EP RB-2 for emergency worker PAGs.

Name of Individual:

Only use highest onscale PIC See table above. Only necessary when reading. PIC is re-zeroed.

Low Range High Range Thyroid Thyroid Cumulative Cumulative ime PIC PIC* TEDE CDE TEDE COE TEDE Thyroid CDE Reported (imR) (Rointgen) DCF DCF {mrem) (mrem) (mrem) (mrem)

Name of Individual:

... Only use highest onscale PIC Only necessary when

_reading. See table above. PIC is re-zeroed.

Low Range High Range Thyroid Thyroid Cumulative Cumulative Time PIC PIC* TEDE CDE TEDE CDE TEDE Thyroid CDE Reported {mR) (Rointgen) DCF DCF (mrem) (mrem) (mrem) (mrem)

4. .5. .& JI I 5. J.

I t 4 4 4 4 1 +

U - - i - I- m 00045424.DOA 3B 16 0817.0321

10/01/98 Page 2 of 2 EP EF-2 (UNITS. 1 AND 2)

ATTACHMENT 6.9 TITLE: Maintenance Team Exposure Tracking Sheet Name of Individual:

'* Only use highest onscale PIC Only necessary when reading. See table above. PlC is re-zeroed.

Low Range High Range Thyroid Thyroid Cumulative Cumulative Time PIC PIC* TEDE COE TEDE CDE TEDE Thyroid CDE Reported (mR) (Rointgen) DCF DCF (mrem) (mrem) (mrem) (mrem)

Name of Individual:

Only use highest onscale PIC Only necessary when

______ reading. See table above. PIC is re-zeroed.

Low Range High Range Thyroid Thyroid Cumulative Cumulative Time PIC PIC* TEDE COE TEDE COE TEDE Thyroid CDE Reported (mR) (Rointgen) DCF DCF (mrem) (mrem) (mrem) (mrem)

Name of Individual:

Only use highest onscale PIC Only necessary when to reading. See table above. PIC is re-zeroed.

Low Range High Range Thyroid Thyroid Cumulative Cumulative Time PIC PIC* TEDE CDE TEDE COE TEDE Thyroid CUE Reported (mR) (Rointgen) DCF DCF (mrem) (mrem) (mrem) (mrem)

NOTE: the high range PIC reading must be multiplied by 1,000 to convert from Roentgen to mR.

00045424. DOA 3B 17 0 817.0321

08/27/96 Page I of I DIABLO CANYON POWER PLANT EP EF-2 ATTACHMENT 6.10 I1AN2 TITLE: OPS Team Dispatch Decision Tree SISEC ISEC I*Trcs OPs Team Tck reports back RP portto OSC Nt support if adfivated (may phone)

OSC

/Ar the hazards CTracks Meet RP Tech

\NO___ by phone a NO OC bnfs eam eam in the field or at e~reme bythe S OSC? \.Access YES OSC Tracks OPS team OSC briefs team Meet RP Tech Team reports back face4D -aces in the OSC toOSC (may phone) 00045424.DOA 3B 18 0817.0321

- - ISSUED FOR USE BY: DATE: EXPIRES. ***

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-9 NUCLEAR POWER GENERATION REVISION 7 DIABLO CANYON POWER PLANT PAGE 1 OF 5

- EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Backup Emergency Response Facilities EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION PAGIE SC O PEE ......................................................................................................................... I DISC U SSIO N ................................................................................................................. I D E FINIT IO N S ................................................................................................................ 4 RESPONSIBILITIES ..................................................................................................... 4 INSTRUCTIONS ......................................................................................................... 5 RE C O RDS ..................................................................................................................... 5 ATTACHMENTS ......................................................................................................... 5

1. SCOPE 1.1 This procedure describes on-site backup Emergency Response Facilities (ERFs) availablh if a primary ERF cannot be activated or becomes uninhabitable.

2. DISCUSSION 2.1 Designated on-site ERFs and their backup facilities include the following:

ERF Function Primary Facility First Backup Second Backup Control Room Control Room Hot S/D Panel (None)

(SM/SFM);

TSC (SM, STA, CRA)

TSC TSC Control Room (Min. Hot S/D Panel (Min.

Staff.); TM/Trng. Bldg. Staff.); EOF (Support)

(Supp.)

OSC 119' OCC/OWCC 140' Turbine Building - Administration Building Area Turbine Bldg. Northeast Comer Room 215 Maint. Pool (OSC) 119' OCC/OWCC 140' Turbine Building - Canyon Rm/Trng Bldg Area Turbine Bldg. Northeast Comer N.O. Pool (CR/OSC) Control Room OPs Ready Room 119' Turbine Building Ofc/Cyn Rm Acc Cont/RPTs (OSC) 85' Access Control 140' Access Control TSC Lab 00822607.DOA 3B I 0824.0859

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-9 DIABLO CANYON POWER PLANT REVISION 7 PAGE 2 OF 5 TITLE: Backup Emergency Response Facilities UNITS 1 AND 2 2.2 The functions of each backup facility are the same as for the corresponding primary facility.

Listed below are available systems in the backup facilities corresponding to the primary ERF.

Note that these systems are a description at the time of this procedure revision and are NOT required to be in place by this procedure.

Second Backup Control Room Function Primary Facility First Backup Systems Control Room S/I) Panel TSC (SM, (None)

(SM/SFM) STA, CRA)

Plant inst/controls Yes Yes - - - - -

(limited)

Rolm phones Yes Yes Yes (limited, (#s differ)

s differ)

Black Net phone Yes Yes PPC Yes Yes LAN/WAN computer Yes - - - Yes - -

SPDS Yes --- Yes LAN/WAN printer Yes Yes - -

Radio transmitter Yes Yes Yes - -

(operations frequency only)

Plant P.A. Yes Yes Yes - -

Copier Yes Yes Fax Yes - - - Yes Rad. survey instruments Yes Yes 00822607.DOA 3B 2 1 0824.0859

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-9 DIABLO CANYON POWER PLANT REVISION 7 PAGE 3 OF 5 TITLE: Backup Emergency Response Facilities UNITS 1 AND 2 TSC Function Priitay First Backup Second Backup Facility _____________

Systems TSC CR I&CITrng. S/D Panel EOF (Mgmt.) (Support) (Mgxnt.) (Support)

Rohm Phones Yes Yes Yes Yes Yes

(#s differ) (#s differ) (limited) (#s differ)

Black Net Phones Yes Yes Yes EARS computer Yes Yes Yes (Trng.) - - Yes LAN/WAN Yes Yes Yes Yes computers LAN/WAN Yes Yes Yes Yes printer Radio transmitter Yes Yes - - - Yes, Yes (operations frequency only)

Plant PA Yes Yes - - - Yes ERDS computer Yes ......

SPDS Yes Yes - - - Yes PPC Yes Yes Plant manual & Yes Yes Yes (Trng.) Yes drawings Microfiche/film & Yes readers Copier Yes Yes Yes Yes Fax Yes Yes Yes Rad. survey Yes Yes - - - - - - Yes instruments Office supplies Yes Yes Yes Yes (limited) 00822607.DOA 3B 3 1 0824.0859

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-9 DIABLO CANYON POWER PLANT REVISION 7 PAGE 4 OF 5 TITLE: Backup Emergency Response Facilities 1 AND 2 OSC Function Primary Facility First Backup Second Backup Systems 119' OCC/OWCC 140' Turbine Administration Area Turbine Bldg Building (northeast Building Room corner) 215 Rolm Phones Yes Yes Yes (different #s)

LAN/WAN Yes Yes Yes computers LAN/WAN printer Yes Yes Yes Copier Yes Yes Yes Rad. survey Yes instruments Access Control Primary Facility First Backup Second Backup Function Systems 85' Access Control 140' Access Control TSC Lab CPDS/ACAS Yes (wiring in place) computer PCs/PICs/AlarmingYe dosixnetrylPCMs ____________________

3. DEFINITIONS 3.1 Habitability - a facility is deemed habitable when its occupants may perform their intended functions within (including, as applicable, access and exit) without undue risk from toxic, flammable, explosive, radiological or other hazards. Given the large potential variances in plant emergency risk and necessary facility occupancy times to respond appropriately, absolute numerical limits for these hazards are not pre-specified in this procedure. See RESPONSIBILITIES below for determination of habitability and relocation.

4. RESPONSIBILITIES 4.1 The Site Emergency Coordinator (SEC) shall, in general, determine relocation necessary for onsite ERFs. If time permits and the EOF is activated with the Recovery manager present, the SEC should obtain the RM's consent. However, in cases of rapidly escalating or highly dangerous or potentially dangerous conditions, the lead supervisor in each facility may order evacuation prior to receiving SEC/RM authorization.

00822607.DOA 3B 4 1 0824.0859

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-9 DIABLO CANYON POWER PLANT REVISION 7 PAGE 5 OF 5 TITLE: Backup Emergency Response Facilities UNITS I AND 2 4.2 The lead supervisor for each ERF who may determine habitability for that facility (subject to Section 5.2 below) is listed below:

ERF Lead Supervisor Control Room Interim SEC/Emerg. Ops Coord.

TSC Site Emergency Coordinator OSC Emergency Maintenance Coordinator Access Control RP Coordinator

5. INSTRUCTIONS 5.1 A backup ERF shall be activated when an ERF is determined uninhabitable or otherwise may not start up or continue operations. See Section 2.1 above for the recommended succession of ERFs.

5.2 An ERF shall be declared uninhabitable by the following:

5.2.1 The Recovery Manager (EOF is activated and time permits).

5.2.2 The SEC or ISEC (EOF not activated or time does not permit RM consent).

5.2.3 The ERF lead supervisor (time does not permit SEC/ISEC consent). See Section 4.2 above.

5.3 The backup ERF shall be activated using the references listed below.

5.3.1 Backup Control Room: OP AP-8A 5.3.2 Backup TSC: Attachment 7.1 5.3.3 Backup OSC: Attachment 7.2 5.3.4 Backup Access Control: Attachment 7.3

6. RECORDS 6.1 Checklists completed due to use of this procedure in a drill or actual event shall be forwarded to the Emergency Planning Supervisor for entry into Records Management System.

7. ATTACHMENTS 7.1 "Backup TSC Activation," 08/17/00 7.2 "Backup OSC Activation," 08/17/00 7.3 "Backup Access Control Activation," 08/17/00l 00822607.DOA 3B 5 1 0924.0859

08/17/00 Page 1 of 1 DIABLO CANYON POWER PLANT EP EF-9 ATTACHMENT 7.1 AND TITLE: Backup TSC Activation INSTRUCTIONS:

NOTE 1: Use this attachment in conjunction with EP EF-1.

NOTE 2: The TSC first backup facility is the Control Room for the minimum staff personnel and other appropriate facilities for the TSC support staff. The second backup is the Hot Shutdown Panel for the minimum staff personnel and the EOF for the TSC support staff. Circumstances may dictate using these out of order, or utilizing different facilities. In such a case, as much of the following instructions should be implemented as possible.

1. If time permits and the EOF is activated with the RM present, obtain SEC or RM consent for TSC relocation.

2. Declare the TSC evacuation and relocation to the TSC staff using the plant PA. Notify the EOF if activated. Notify the Control Room and, if activated, the OSC. Post the abandoned facility entrances with signs indicating the uninhabitable status and facility relocation.

3. Direct the minimum TSC staffing per EP EF-1 to the Control Room, Hot Shutdown Panel, or other appropriate facility, plus other essential personnel appropriate to the event response.

4. Direct TSC support staff to relocate to other appropriate facilities. Consider taking the survey instruments from the TSC.

5. When the backup TSC facility is operational, notify the Control Room and, as appropriate, the OSC and EOF. Make a plant PA announcement if possible. Direct notification of the County, State and NRC.

Completed By: SiteEmergencyCoordinatorDate:

Site Emergency Coordinator -

00822607.DOA 3B 6 I 0824.0859

08/17/00 Page I of I 2

DIABLO CANYON POWER PLANT EP EF-0 ATTACHMENT SI1 7.2 AND TITLE: Backup OSC Activation INSTRUCTIONS:

NOTE 1: Use this attachment in conjunction with EP EF-2.

NOTE 2: The OSC first backup facility is the office on the north end of the Turbine Building (140' elevation) and the second is the Administration Building Room 215. Circumstances may dictate using these out of order, or utilizing a different facility, such as the 85' Machine Shop. In such a case, as much of the following instructions should be implemented as possible.

1. If time permits, obtain SEC or ISEC consent for OSC relocation.

2. Declare the OSC evacuation and relocation to the OSC staff. Notify the Control Room and, if available, the SEC. Request the CR or TSC to make a PA announcement of the OSC relocation. Post the abandoned facility entrances with signs indicating the uninhabitable status and facility relocation.

3. Direct at least the minimum OSC staffing per EP EF-2 to the 140' Turbine Building (northeast comer), the Administration Building Room 215 or other appropriate facility. Consider taking the survey instruments and supplies from the 119' OCC/OWCC Area in Turbine Building.

4. Direct any extra OSC staffing to the Administration Building Room 215, Training Building or other appropriate facility.

5. When the backup OSC facility is operational, notify the Control Room and, if activated, the TSC.

Completed By: Date:

Emergency Maintenance Coordinator 00822607.DOA 3B 7 1 0824.0859

08/17/00 Page I of I DIABLO CANYON POWER PLANT EP EF-9 ATTACHMENT 7.3 AND TITLE: Backup Access Control Activation INSTRUCTIONS:

NOTE 1: Use this attachment in conjunction with EP EF-2.

NOTE 2: The 85' Access Control first backup facility is the 140' Access Control and the second is the TSC Lab. Circumstances may dictate using these out of order, or utilizing a different facility. In such a case, as much of the following instructions should be implemented as possible.

1. If time permits, obtain SEC or ISEC consent for Access Control relocation.

2. Declare the Access Control evacuation and relocation to the Access Control staff. Notify the Control Room and, if available, the SEC. Request the CR or TSC to make a PA announcement of the Access Control relocation. Post the abandoned facility entrances with signs indicating the uninhabitable status and facility relocation.

3. Direct at least the minimum Access Control staffing to the 140' Access Control, the TSC Lab, or other appropriate facility.

4. When the backup Access Control is operational, notify the Control Room and, if activated, the TSC and OSC.

Completed By: Date:

RP Coordinator _I 00822607.DOA 3B 8 1 0824.0859

DCL-00-124, Units I and 2 - Emergency Plan Implementing Procedure Update

Contents

Text

Dear Commissioners and Staff:

Reference:

Reference:

2.1 ACCOUNTABILITY

2.3 ASSEMBLY

Purpose:

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