DCL-03-073, Emergency Plan Implementing Procedure Update
| ML031750849 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/19/2003 |
| From: | Tomkins J Pacific Gas & Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| DCL-03-073 | |
| Download: ML031750849 (143) | |
Text
WI Pacfic Gas and
'RI fElecric Company Diablo Canyon Power Plant June 19, 2003 PO. Box 56 Avila Beach, CA 93424 PG&E Letter DCL-3-073 800.545.6000 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 Ememency Plan Imolementini 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 (EP) implementing procedures for Diablo Canyon Units 1 and 2 as indicated in Enclosure 1.
As provided under 10 CFR 50.54(q), the changes have been made without prior NRC approval since they do not decrease the effectiveness of the EP. The EP, 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. Enclosure 2 provides the location of the privacy/proprietary information.
If there are any questions regarding this update, please contact Mr. Mark Lemke of my staff at (805) 545-4787.
Sincerely, James E. Tomkins Direcofr, Site Services ddm/1 345 Enclosures oc:
David H. Jaffe David L. Proulx
+
cclenc: Thomas P. Gwynn Senior Emergency Preparedness Inspector (RGN-IV/DRS)
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Calaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- South Texas Project
- Wolf Creek PG&E Letter DCL-03-073 DIABLO CANYON POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Table of Contents - Emergency Plan Implementing Procedures Volume 1A (OM10.JD3 only), Volume 1B (OMIO.DC1 only), and Volume 3B Proc. No.
Rev.
rtle OM10.1D3 OM10.DC1 EP G-1 EPG-2 EPG-3 EP G-4' EP G-5 EP R-2 EP R-3 EP R-7 EP OR-3 EP RB-1 EP RB-2 EP RB-3 EP RB-4 EP RB-5 EP RB-8 EP RB-9*
EP RB-10 EP RB-1 I EP RB-12 EP RB-14*
EP RB-15 EPEF-I EP EF-2 EP EF-3*
EP EF-4 EP EF-9 EP EF-10 6A Emergency Plan Training 2A Emergency Preparedness Drills and Exercises 32 Emergency Classification and Emergency Plan Activation 26 Interim Emergency Response Organization 40 Notification of Off-Site Agencies and Emergency Response Organization Personnel 20 Assembly and Accountability 9A Evacuation of Nonessential Site Personnel 21 Release of Airbome Radioactive Materials Inital Assessment 8C Release of Radioactive Uquids 13A Off-Site Transportation Accidents 6A Emergency Recovery 5B Personnel Dosimetry 5
Emergency Exposure Guides 4
Stable Iodine Thyroid Blocking 4A Access to and Establishment of Controlled Areas Under Emergency Conditions 4C Personnel Decontamination 16 Instructions for Field Monitoring Teams 11A Calculation of Release Rate 9
Protective Action Recommendations 12 Emergency Offsite Dose Calculations 6
Plant Vent Iodine and Particulate Sampling During Accident Conditons 7A Core Damage Assessment Procedure 11 Post Accident Sampling System 30 Activation and Operation of the Technical Support Center 27 Operational Support Center 23 Activation and Operation of the Emergency Operations Facility 14 Acfivation of the Off-Site Emergency Laboratory 8
Backup Emergency Response Facilities 5
Joint Media Center Activation and Operation
- Procedure Included In this submittal PG&E Letter DCL-03-073 LOCATION OF PRIVACY/PROPRIETARY INFORMATION IN EMERGENCY PLAN IMPLEMENTING PROCEDURES FOR DIABLO CANYON POWER PLANT, UNITS I AND 2 Procedure Number Privacyl Proprietary Information TitlelLocation of PrivacylProprietary Information EP G4, Revision 20 EP RB-9, Revision 11 A EP RB-14, Revision 7A EP EF-3, Revision 23 Yes No No Yes Assembly and Accountability Page 6 of 8.2, page 1 of 1.
Calculation of Release Rate Core Damage Assessment Procedure Activation and Operation of the Emergency Operations Facility Atachment 5.6, pages 1, 2, 3, and 5 of 5.
Atachment 5.7, page 1 of 1..8, page 1 of 1..12, page 1 of 1..13, page 1 of 1..17, page 1 of 1.
- ISSUED FOR USE BY:
DATE:
EXPIRES:_____
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G4 NUCLEAR POWER GENERATION REVISION 20 DIABLO CANYON POWER PLANT PAGE 1 OF 8 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE:
Assembly and Accountability 1
AND 2 05/29/03 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED SCOPE.1 DISCUSSION................................
1 DEFINITIONS.................................
2 RESPONSIBILITIES.................................
4 INSTRUCTIONS.................................
5 Initiation of Assembly and Accountability.................................
5 Assembly Areas.................................
6 Accountability.................................
6 Termination of Assembly and Accountability.................................
7 RECORDS................................
8 ATTACHMENTS8................................8 I.
SCOPE This procedure describes the process of assembling and accounting for onsite personnel in order to identify any missing individuals within the power block.
For the purposes of this procedure, onsite personnel refers to personnel within the protected area.
- 2.
DISCUSSION The assembly and accountability process should be initiated by the shift manager, or designee, or the site emergency coordinator any time there may be a need to account for personnel in the power block, or when it is desirable to relocate non-essential personnel outside the power block, or when an emergency is declared.
The assembly and accountability process is activated by sounding the site emergency signal and a public address announcement.
When the assembly and accountability process is activated, personnel are notified to report to assembly areas where they will receive further instructions.
The goal of accountability is to account for all personnel within the power block, for the purpose of identifying the existence of any missing individuals, within 30 minutes. The accountability 30 minute time starts when the announcement to assemble is made or the site emergency signal is sounded, whichever is first.
03B 0501.0300 00020820.DOA
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DL4BLO CANYON POWER PLANT REVISION 20 PAGE 2 OF 8 TITLE:
Assembly and Accountability UNITS 1 AND 2
- 3.
DEFINITIONS Accountability The process of determining the location of all individuals by name within the power block.
Accountability Coordinator The Diablo Canyon Watch Commander or designee.
Accountability List A list of all individuals within the power block. This list is generated from the Central Alarm Station (CAS) computer.
Assembly The process of assembling personnel at assigned areas.
Assembly Area The location where personnel report at the beginning of shift.
Continuous Accountability Maintaining accountability by name and location of individuals within the power block after initial accountability has been established.
Missing Personnel Individuals within the power block who can not be accounted for by the accountability process.
Search and Rescue Locating and recovering missing individuals through systematic walkdowns and entries into accessible plant areas by coordinated team efforts.
Sweep Walking through areas to determine if individuals are present.
00020820.DOA 03B 0501.0300
PACIFIC GAS AND ELECTRIC COMPANY DlABLO CANYON POWER PLANT NUMBER REVISION PAGE TITLE:
Assembly and Accountability UNITS EP G-4 20 3 OF 8 1 AND 2 Power Block For the purpose of this procedure the power block includes the following areas:
Unit-I & Unit-2 containment, #101 power block/auxiliary bldg., #1 17A laundry, #1 17B radwaste bldg. #11 8 auxiliary boiler enclosure, RCA.
00020820.DOA 03B 0501.0300
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DL4BLO CANYON POWER PLANT REVISION 20 PAGE 4 OF 8 TITLE:
Assembly and Accountability UNITS 1 AND 2
- 4.
RESPONSIBILITIES Accountability Coordinator Coordinates and maintains the accountability of personnel within the power block.
Ensures continuous accountability of individuals dispatched to within the power block until relieved.
Emergency Maintenance Coordinator Ensures Operations Support Center (OSC) assembly rosters are completed and sent to security, if the OSC is activated.
Ensures continuous accountability of individuals assigned to their area until relieved.
Security Advisor Ensures Technical Support Center (TSC) assembly rosters are completed and sent to security, if the TSC is activated.
Ensures continuous accountability of individuals assigned to their area until relieved.
Ensures personnel accountability is performed.
Provides Site Emergency Coordinator (SEC) with a list of missing personnel.
Updates the SEC on status of missing personnel.
Operations Support Team Asset Team Leader (OST ATL)
Ensures assembly rosters are completed and sent to security.
Ensures continuous accountability of individuals assigned to their area until relieved.
Operations Shift Manager Ensures control room assenbly rosters are completed and sent to security.
Ensures continuous accountability of individuals assigned to their area until relieved.
Recommends protective actions to the Diablo Canyon Watch Commander for security individuals prior to TSC activation.
Provides protective action instructions to individuals using public address announcements, or communications with supervisors.
Site Emergency Coordinator (SEC)
Directs assembly, accountability, site access control, and search and rescue of missing personnel.
Radiological Protection 85' Access Control Foreman Ensures 85' access assembly rosters are completed and sent to security.
Ensures continuous accountability of individuals assigned to their area until relieved.
00020820.DOA 03B 0501.0300
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DlABLO CANYON POWER PLANT REVISION 20 PAGE 5 OF 8 TITLE:
Assembly and Accountability UNITS 1 AND 2
- 5.
INSTRUCTIONS 5.1 Initiation of Assembly and Accountability 5.1.1 The shift manager or site emergency coordinator should initiate the assembly and accountability process when:
An event presents risk to personnel safety within the power block.
There is a need to detennine if there are any missing persons within the power block.
There is a declared alert, site area emergency, or generl emergency.
5.1.2 To initiate assembly and accountability, shift manager or site emergency coordinator should use the public address system to announce:
Attention all personnel. The assembly and accountability process has been activated.
All non-essential personnel, place al work in a safe condition, leave the power block, and return to your normal desks.
5.1.3 Sound the site emergency signal 5.1.4 Repeat the public address announcement.
Attention all personnel. The assembly and accountability process has been activated.
All non-essential personnel, place all work in a safe condition, leave the power block, and return to your normal desks.
5.1.5 When the site emergency signal has been sounded or when notified by a public address announcement to assemble, all personnel shall immediately:
- a.
Place work area in a safe condition.
- b.
Report to assembly areas, the place reported to at the beginning of the shift.
- c.
Await further instructions.
5.1.6 Personnel located outside the power block should remain outside until the assembly and accountability process has ended, unless directed otherwise by the shift manager or security watch commander.
5.1.7 Personnel engaged in critical operations or emergency response actions should call the control room as soon as possible, to be accounted for, then proceed to assembly areas.
5.1.8 Visitors and non-essential contractors shall exit the power block.
00020820.DOA 03B 0501.0300
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G-4 DIABLO CANYON POWER PLANT REVISION 20 PAGE 6 OF 8 TITLE:
Assembly and Accountability UNITS 1 AND 2 5.2 Assembly Areas 5.2.1 All plant personnel should consider their normal work reporting location (the place reported to at the beginning of shift) as their assigned assembly area.
Examples Personnel who report to the administration building #104 on a normal workday, should assemble at their normal reporting area in the admin building when the assembly and accountability process has been initiated.
Warehouse personnel should report to the warehouse.
ACRE personnel should report to building #102.
Operations personnel should report to the control room.
5.2.2 Personnel in the power block who are not able to report to their assembly area due to work in progress, shall immediately notify the control room to ensure they are accounted for.
5.2.3 Personnel working outside the power block, that normally report inside the power block, should remain outside the power block until the assembly and accountability process has terminated.
5.2.4 Non-essential contract personnel should assemble in an area where the public address announcements can be heard to await further instructions.
5.3 Accountability 5.3.1 Assembly Areas in the Power Block
- a.
Supervisors of personnel assigned to assembly areas within the power block shall ensure:
- 1.
Form 69-1323 1, Accountability Roster shall be completed with the names of all assembled personnel.
- 2.
Personnel inside the power block that are unable to immediately report to an assembly area, but have made verbal contact, should be considered accounted for and included on the form.
- 3.
Personnel outside the power block that are not able to enter the power block should not be included on the accountability roster.
- 4.
Form 69-13231 should be faxed to the accountability coordinator at rext. 31 15Jwithin approximately 15 minutes of the initiation of the assembly and accountability process.
5.3.2 Assembly Areas outside the Power Block Personnel assembled outside the power block shall remain outside the power block to wait for further instructions.
5.3.3 Accountability Coordinator
- a.
Ensure all personnel within the power block are accounted for within 30 minutes of the initiation of the assembly and accountability process, to ascertain the names of any missing persons.
00020820.DOA 03B 0501.0300
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP G4 DIABLO CANYON POWER PLANT REVISION 20 PAGE 7 OF 8 TITLE:
Assembly and Accountability UNITS 1 AND 2
- b.
Initiate accountability upon sounding of the site emergency signal or public address announcement directing accountability.
- c.
Initiate Form 69-13230.
- d.
Assign an officer to the bridge line and FAX machine to receive accountability information from assembly areas within the power block.
- e.
After receiving accountability forms from the following assembly areas, compare them to the computer generated emergency accountability listing:
Control Room Radiological Access Control 85' Elevation Operations Support Team Technical Support Center (at Alert or higher)
Operational Support Center (at Alert or higher) 5.3.4 Missing Personnel If there are missing personnel identified, security shall initiate the following additional actions:
- a.
Attempt to identify the last known location of the person through emergency accountability listing report or alternate security computer command.
- b.
Conduct sweeps of the following areas as needed:
Lube Oil and Dirty Lube Oil Storage Room A
Condensate Pump Pit U-1 A
Heater Drip Pump (DRP)
A Condensate Pump Pit U-2 A
Post LOCA Sample Room U-1 A
Post LOCA Sample Room U-2 A
85' AUX Building A
140' Turbine Bldg 5.4 Termination of Assembly and Accountability When the necessity to account for individuals within the power block has ended, the shift manager or site emergency coordinator should make a PA announcement to terminate the assembly and accountability process.
00020820.DOA 03B I
I 0501.0300
PACIFiC GAS AND ELECTRIC COMPANY NUMBER EP G4 DIABLO CANYON POWER PLANT REVISION 20 PAGE 8 OF 8 TITLE:
Assembly and Accountability UNITS 1 AND 2
- 6.
RECORDS When used during a drill, Form 69-13231 and Form 69-13230 are good business records and shall be retained by emergency planning for 3 years in accordance with ADI0.ID2.
When used during a real event, Form 69-13231 and Form 69-13230 are records of quality assurance and shall be permanently retained in accordance with AD10.ID1.
- 7.
ATTACHMENTS 7.1 Form 69-13230, "Missing Personnel Roster," 03/12/02 7.2 Form 69-13231, "Accountability Roster," 08/01/02 00020820.DOA 03B 0501.0300
I I,.
69-13230 03/12/02 DIABLO CANYON POWER PLANT EPG-4 ATTACHMENT 7.1 Page I of 1 12 TITLE:
Missing Personnel Roster
- 1.
Record accountability start time:
NOTE: Accountability starts at the activation of the assembly and accountability process by the sounding of the site emergency signal or public address announcement, whichever occurs first.
- 2.
Accountability Completion Time:
NOTE: Accountability is complete when all accountability forms are received, a comparison has been made against the Emergency Accountability Listing report, and individuals that are unaccounted for are identified as missing.
- 3.
Write the name and keycard number of any missing individual below.
- 4.
Notify Security to search for missing personnel.
- 5.
Forward list to the TSC Security Advisor or the ISEC in the control room if the TSC is not manned.
NAME KEYCARD 00020820.DOA 03B 0501.0300
DIABLO CANYON POWER PLANT EPG4 ATTACHMENT 7.2 1AND TITLE:
Accountability Roster
- 1.
Complete this checklist for accountability of assembly area personnel. Include personnel that may be performing a specific job.
- 2.
FAX this information to the accountability coordinator at ext. 115 or 545-311 5vithin 15 minutes.
- 3.
The accountability coordinator can be reached on[bridge phone ext. 200 1)
ASSEMBLY AREA LOCATION 00020820.DOA 03B 0501.0300 NAME I
KEYCARD 69-13231 08101/02 Page of
- ISSUED FOR USEBY:
DATE:
EXPIRES:____
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-9 NUCLEAR POWER GENERATION REVISION 11A DIABLO CANYON POWER PLANT PAGE 1 OF 42 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE:
Calculation of Release Rate 1
AND 06/03/03 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1.
SCOPE 1.1 This procedure describes the manual method to determine the release rate of airborne radioactive materials from a plant vent release, main steam line release, or containment leakage.
- 2.
DISCUSSION 2.1 Initial calculations of radiological release rates are performed in the control room in accordance with EP R-2, "Release of Airborne Radioactive Materials" by the emergency evaluation coordinator.
2.2 This procedure provides a manual methodology for performing release rate calculations as a backup to the Emergency Assessment and Response System (EARS) or the Excel application "Quick Dose."
This procedure in conjunction with EP RB-I 1, "Emergency Off-Site Dose Calculations" can be used to determine projected off-site TEDE and thyroid CDE doses.
- 3.
RESPONSIBILITIES 3.1 Dose assessment personnel perform this procedure when required.
- 4.
INSTRUCTIONS 4.1 To manually calculate Noble Gas and odine-131 Equivalent Release Rates for a Plant Vent Release follow the step-by-step instructions given in Attachment 7.1 -
Form 69-9260.
4.2 To manually calculate Noble Gas and Iodine-I 31 Equivalent Release Rates for a Main Steam Line Release follow the step-by-step instructions given in Attachment 7.2 -
Form 69-11105.
4.3 To manually calculate Noble Gas and Iodine-I 31 Equivalent Release Rates for a Containment Leakage Release follow the step-by-step instructions given in.3 - Form 69-10555.
- 5.
RECORDS All records generated by the utilization of this procedure for an exercise or emergency shall be forwarded the next working day to the supervisor, emergency planning, for review and retention.
0030331.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-9 DLBLO CANYON POWER PLANT REVISION 11A PAGE 2 OF 42 TITLE:
Calculation of Release Rate UNITS 1 AND 2
- 6.
APPENDICES 6.1 Table 1, Source Term For Various Postulated Accidents 6.2 Figure 1, Plant Vent Noble Gas Monitor Response RE-14/14R, Normal Range 6.3 Figure 2, Plant Vent Noble Gas Monitor Response RE-87, Extended Range 6.4 Figure 3, Plant Vent Gross Gamma Monitor Response RE-29, High Range 6.5 Figures 4.1,1-131 TEDE Correction Factor, and 4.2, I-13 1 Thyroid CDE Correction Factor (2 pages) 6.6 Figures 5.1, 5.2, and 5.3, Main Steamnline Monitor Response RE-71, RE-72, RE-73, RE-74, for Empty, Normal, and Flooded Conditions (3 pages) 6.7 Figures 6.1, Iodine TEDE Conversion Factor, and 6.2, Iodine Thyroid CDE Conversion Factor (2 pages) 6.8 Figure 7, Design Basis Containment Monitor Exposure Rate RE-30 and RE-31 6.9 Figure 8, Design Basis Noble Gas Release Rates 6.10 Figure 9, Design Basis I-131 Equivalent Release Rates 6.11 Accident Summary Sheets
- 7.
ATTACHMENTS 7.1 Forn 69-9260, "Noble Gas and I-131 Equivalent Release Rates for a Plant Vent Release,"
08/31/94 7.2 Form 69-11105, "Noble Gas and 1-131 Equivalent Release Rates for a Steam Release,"
08/31/94 7.3 Form 69-10555, "Noble Gas and 1-131 Equivalent Release Rates for Containment Leakage," 08/31/94
- 8.
REFERENCES 8.1 Diablo Canyon Power Plant Unit I and 2 Emergency Plan.
8.2 EP G-1, "Accident Classification and Emergency Plan Activation."
8.3 EP R-2, "Release of Airborne Radioactive Materials."
8.4 EP RB-I 1, "Emergency Off-site Dose Calculations."
8.5 EP RB-12, "Plant Vent Iodine and Particulate Sampling During Accident Conditions."
8.6 EP EF-1, "Activation and Operations of the Technical Support Center."
8.7 EP EF-3, "Activation and Operation of the Emergency Operations Facility."
8.8 EP EF-6, Operating Procedures for EARS Stations."
0030331.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-9 DIABLO CANYON POWER PLANT REVISION 1A PAGE 3 OF 42 TITLE:
Calculation of Release Rate UNITS 1 AND 2 8.9 PG&E, Nuclear Operations Support Calculation RA-93-04, EP RB-9, Calculation of Release Rate, Units 1 and 2, Rev. 7 - Validation and Verification.
8.10 EP RB-14, "Core Damage Assessment Procedure."
8.11 SH&ES Calculation No. EP-94-02, Rev 0, Validation and Verification of EP RB-9, "Calculation of Release Rate," Rev 10, and EP RB-I1, "Emergency Offsite Dose Calculations," Rev 11.
8.12 PG&E Calculation PAM-0-04-517, Rev. 4, 4/6/97 "Steam Generator Narrow Range Level Uncertainty."
- 9.
SPONSOR David Marsh 00303311.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.1 TABLE I SOURCE TERM FOR VARIOUS POSTULATED ACCIDENTS
- 1.
Major LOCA with Core Melt - RE-30/3 1 >300R/hr
- 2.
Major LOCA (Gap Release) - RE-30/31 >IRfhr, <300R/hr
- 3.
Small Break LOCA (No fuel damage) - RE-30/31 <lR/hr
- 4.
Blackout
- 5.
Major Steamline Break
- 6.
Major Feedwater Line Break
- 7.
Steam Generator Tube Rupture
- 8.
Locked Reactor Coolant Pump (RCP Rotor)
- 9.
Control Rod Ejection
- 10.
Gas Decay Tank Rupture
- 11.
Liquid Holdup Tank Rupture
- 12.
Volume Control Tank (VCT) Rupture
- 13.
Fuel Handling Accident in Fuel Handling Building (FHB)
Source Term Core Gap RCS RCS RCS RCS GAP GAP GAP - Noble Gas Only RCS - Noble Gas Only RCS - Noble Gas Only Spent Fuel (Highest Assembly Gap) 00303311.DOE 03B NUMBER REVISION PAGE UNITS EP RB-9 11A 4 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DLABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS TITLE:
Calculation of Release Rate EP RB-9 11A 5 OF 42 1 AND 2 APPENDIX 6.2 FIGURE I PLANT VENT NOBLE GAS MONITOR RESPONSE RE-14/14R, NORMAL RANGE 1
cuc cPM I---I.f I...
I-I--fI 1
1 I.
F-I I1111 111111 I
I--f 11111 f
I--f 111111
+
f-+--I---+---f-I--+--I 1000.0 Q1 1.0 1ao TInl3MerSutcbw l, Ft 1mo 0030331 I.DOE 03B 0530.0409
!__0'
- t-iX211
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE TITLE:
Calculation of Release Rate UNITS EP RB-9 11A 6 OF 42 1 AND 2 APPENDIX 6.3 FIGURE 2 PLANT VENT NOBLE GAS MONITOR RESPONSE RE-87, EXTENDED RANGE 1.COE.10 pCiIcc per 1.00E+09 Amp 1.00E"08 0.1 1.0 10.0 100.0 1000.0 Time After Shutdown, Mrs 00303311.DOE 03B 0530.0409
PACIIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS TITLE:
Calculation of Release Rate EP RB-9 11A 7 OF 42 1 AND 2 APPENDIX 6.4 FIGURE 3 PLANT VENT GROSS GAMMA MONITOR RESPONSE RE-29, HIGH RANGE 1.00E+00 1.0E-01 PCUcc per 1.00E.02 mR/Hr 1.00E03 IA.E-04 0.1 1.0 10.0 100.0 Time After Shutdown, Hrs 0030331.DOE 03B 1000.0 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE TITLE:
Calculation of Release Rate UNITS EP RB-9 IIA 8 OF 42 1 AND 2 APPENDIX 6.5 FIGURE 4.1 1-131 TEDE CORRECTION FACTOR 1-131 TEDE Correction Factor 2.20 2.10 2.00 1.90 1.10 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 0.1 0.2 0.4 1.0 2.0 4.0 10.0 20.0 40.0 100.0 200.0 400.0 1000.0 Time After Shutdown (Hrs) 0030331 I.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS APPENDIX 6.5 (Continued!
FIGURE 4.2 1-13 1 THYROID CDE CORRECTION FACTOR 1-131 Thyroid CDE Correction Factor
_ Accident Source Tern
=___
=
=_
Colant Fuel 4 l l
=
=
_- ~~~~~~~~~Core
=
1
=
_~~---
Sent F'ue=
AL~~~~~~ -\\ - -'\\-
YIC-,
I 0.1 0.2 OA 1.0 2.0 4.0 10.0 20.0 40.0 100.0 200.0 400.0 1000.0 Time After Shutdown (Hrs) 0030331 I.DOE 03B EP RB-9 11A 9 OF 42 1 AND 2 1.50 1.A 1.30 1.20 1.10 1.00 I
0530.0409
PACIFC GAS AND ELECTRIC COMPANY DLBLO CANYON POWER PLANT NUMBER REVISION PAGE TITLE:
Calculation of Release Rate UNlTS EP RB-9 11A 10 OF 42 1 AND 2 APPENDIX 6.6 FIGURE 5.1 MAIN STEAMLINE MONITOR RESPONSE - EMPTY GENERATOR RE-7 1, RE-72, RE-73, RE-74 1.0OE-01 1.00E-02 1.00E-03 PCIICC per 1.OOE-04 CPM 1.0E-05
- 1. OE-06 0.1 1.0 10.0 100.0 1000.0 Time After Shutdown, Hrs 0030331.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DLBLO CANYON POWER PLANT NUMBER REVISION PAGE TITLE:
Calculation of Release Rate UNITS EP RB-9 11A 11 OF 42 1 AND 2 APPENDIX 6.6 FIGURE 5.2 MAIN STEAMLINE MONITOR RESPONSE - NORMAL GENERATOR RE-71, RE-72, RE-73, RE-74 1.00E41 1.00E-02 1.00E-03 pci/cc per 1.00E-04 CPM 1.00E-05 1.00E06 0.1 1.0 10.0 100.0 1000.0 Time After Shutdown, Hrs 00303311.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE TITLE:
Calculation of Release Rate UNITS APPENDIX 6.6 (Continued)
FIGURE 5.3 MAIN STEAMLINE MONITOR RESPONSE - FLOODED GENERATOR RE-71, RE-72, RE-73, RE-74 1.00E-02 pC!/cc per 1.00E.04 CPM 0.1 1.0 10.0 100.0 Time After Shutdown, Hrs 0030331.DOE 03B EP RB-9 11A 12 OF 42 1 AND 2 1000.0 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE TITLE:
Calculation of Release Rate UNITS APPENDIX 6.7 FIGURE 6.1 IODINE TEDE CONVERSION FACTOR Iodine TEDE Conversion Factor 1.00 090 0.80 0.70 0.60 0.50 OAO 0.30 0.20 0.10 0.00 0.1 0.2 0.4 1.0 2.0 4.0 10.0 20.0 40.0 100.0 200.0 400.0 1000.0 Time After Shutdown (Hrs) 0030331 1.DOE 03B EP RB-9 11A 13 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE TITLE:
Calculation of Release Rate UNITS EP RB-9 11A 14 OF 42 1 AND 2 APPENDIX 6.7 (Continued)
FIGURE 6.2 IODINE THYROID CDE CONVERSION FACTOR Iodine Thyroid CDE Conversion Factor 1.00 0.10 0.80 0.70 0.60 0.60 0.40 0.30 0.20 0.10 0.00 0.1 0.2 0.4 1.0 2.0 4.0 10.0 20.0 40.0 100.0 200.0 400.0 1000.0 Time After Shutdown (Hrs) 0030331 1.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS TITLE:
Calculation of Release Rate EP RB-9 11A 15 OF 42 1 AND 2 APPENDIX 6.8 FIGURE 7 DESIGN BASIS CONTAINMENT MONITOR EXPOSURE RATE RE-30 AND RE-3 1 1.00E+ 06 1.00E4 06 R/Hr 1.00E+ 04 1.00E+ 03 6.00E- 01 6.00E. 00 1.20E+ 01 2.40E+ 01 4.80E+ 01 7.20E+ 01 1.68E. 02 Time After Shutdown (Hrs) 0030331 I.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS TITLE:
Calculation of Release Rate APPENDIX 6.9 FIGURE 8 DESIGN BASIS NOBLE GAS RELEASE RATES 7.00E+OO 6.00E+OO 5.00E.00 ci per Sec 4.OOE+00 3.00E+O 2.OOE+OO 1.00E+OO O.OOE+00 0
10 20 30 40 s0 60 70 80 90 100 Time After Shutdown, Hrs 00303311.DOE 03B EP RB-9 11A 16 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE TITLE:
Calculation of Release Rate UNITS EP RB-9 11A 17 OF 42 1 AND 2 APPENDIX 6.1 0 FIGURE 9 DESIGN BASIS 1-13 1 EQUIVALENT RELEASE RATES 1.00E+OO 9.00E-01 8.00E41 Based on 25% Core Iodine Released to Containment Containment Sprays Inoperable 7.001E-1 t.OE41 6.OOE41 4AOE41 3.00E41 I-lJ I 4 I1 ALENT 2.OOE-01 1.OOE-01 O.OOE+00 0
10 20 30 40 so 60 70 80 So 100 Time After Shutdown, Hm 0030331 1.DOE 03B Ci per Sec I
I --
I 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-9 DLBLO CANYON POWER PLANT REVISION 11A PAGE 18 OF 42 TITLE:
Calculation of Release Rate UNITS I AND 2 APPENDIX 6.11 ACCIDENT
SUMMARY
SHEETS This Appendix contains summary sheets for the various postulated accidents which have been analyzed in the FSAR. These sheets contain both the "design basis" and "expected" case variables which were assumed in the FSAR analyses. The sheets can be used to compare actual measurements with assumed numbers from the FSAR, in order to help evaluate how things are going in relation to predictions, or they can be used as a source of data to supply unavailable numbers in calculations which are performed at the time of the accident.
Two sets of data are included. The "design basis" case is expected to be highly conservative, where every variable is at a worst-case condition. The "expected" case is the best estimated prediction of what might actually occur. When FSAR values are used to make calculations or predictions at the time of the accident, the "design basis" values can be used to provide a quick upper limit result, but as soon as data becomes available which tends to confirm one case or the other, the one which best agrees with the data should be used.
The accident classifications identified in this Appendix are based on the analyzed off-site doses of the activity releases.
NOTE: Do not use these Summary Sheets to classify emergencies. Always refer to EP G-l to consider all possible EALs.
EP G-1 classifications based on plant conditions other than off-site doses are presented also to illustrate the relatively close and usually conservative declarations that would be made even before dose calculations were performed.
The summary sheets provided are:
A. MAJOR LOCA B. MAJOR STEAM LINE BREAK C. MAJOR FEEDWATER LINE BREAK D. BLACKOUT (OR PLANT COOLDOWN WITH ATMOSPHERIC DUMP)
E. SMALL LOCA F. TUBE RUPTURE G. LOCKED ROTOR H. FUEL HANDLING ACCIDENT IN FUEL HANDLING BUILDING I. FUEL HANDLING ACCIDENT IN CONTAINMENT J.
ROD EJECTION ACCIDENT K. GAS DECAY TANK RUPTURE L. LIQUID HOLDUP TANK RUPTURE M. VC T RUPTURE 0030331.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNlTS APPENDIX 6.11 (Continued)
SUMMARY
SHEET A MAJOR LOCA PARAMETER
- 1.
Total Release to Containment Free Volume, Ci
- a.
- b.
Other Noble Gases
- c.
1-131
- d.
Other Iodine
- e.
Source Term
- f.
Release Assumption
- 2.
Containment Spray Effectiveness
- a.
Removal half-life (hrs)
- b.
Number of operable spray pumps
- 3.
Containment Leak Rate (0/o/day)
- 4.
Total Release to Environs, First 2 Hours, Ci
- a.
- b.
Other Noble Gases
- c.
1-131
- d.
Other Iodine
- e.
Release Mechanism FSAR DBA 2.03x108 5.73x108 2.21x107 1.90x1O0 Core 100% of core N.G., 25%
of core iodines 0.022 I
0.1 for 1st day, 0.05 after I st day 16,840 25,930 191 1,325 Containment Leakage FSAR EXPECTED 1.36x106 4.27x105 1.82x105 2.73x105 Gap 100% of gap N.G., 25%
of gap iodines 0.0075 2
0.05 for 1st day, 0.025 after 1st day 56 21 0.05 0.08 Containment Leakage 00303311.DOE 03B 0
EP RB-9 11A 19 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS APPENDIX 6.11 (Continued)
SUMMARY
SHEET A MAJOR LOCA FSAR PARAMETER DBA 5-(x/Q) CL (sec/m3)
- a.
800m (site boundary) 5.29xl0-4
- b.
10000m (6 mi. LPZ) 2.20xl0-5
- 6.
Whole Body Dose Results
- a.
Total 800m dose for 5.6E+00 1 st two hours (Rem)
- b.
Total 10000mdosefor30days(Rem) 5.7E-01
- 7.
Thyroid Dose Results
- a.
Total 800m dose for 9.6E+01 1 st two hours (Rem)
- b.
Total 10000m dose for 30 days (Rem) 1.8E+01
- 8.
Accident Classification (Based on above Dose):
General Emergency (Based on EP G-1):
Site Area Emergency
- 9.
Miscellaneous
- a.
Containment-free volume cc 7.36x101 0
- b.
RCS Coolant Mass (gm) 2.4x108
- 10.
References
- a.
FSAR, September 1990, Revision 6, Section 15.5.
- b.
DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6.
FSAR EXPECTED 5.29x10-5 2.20xl06 3.7E-04 6.4E-05 1.3E-03 9.2E-04 Unusual Event Site Area Emergency 0030331.DOE 03B EP RB-9 11A 20 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS APPENDIX 6.11 (Continued)
SUMMARY
SHEET B MAJOR STEAM LINE BREAK PARAMETER Initial Conditions and Assumptions
- a.
Primary Coolant Activity (.LCi/gm)
- 1)
- 2) 1-131
- 3)
Other Iodine
- b.
Secondary Water Activity (Ci/gm)
- 1) 1-131
- 2)
Other lodines
- c.
Assumed Fuel Defects (%)
- d.
Primary to Secondary Leakage (gpm)
- e.
Steam Release, 1st Two Hours (Ibs)
- 1) Failed Generator
- 2)
Other generator (atmospheric dump)
- f.
Total Steam Release During 8-Hour Cooldown (Ibs)
- g.
Liquid Release Fraction for Iodine
- 1) Failed Generator
- 2)
Other generators
- 2.
Activity Release to Environs, First 2 Hours (Ci)
- a.
- b.
Other Noble Gases
- c.
1-131
- d.
Other lodines
- e.
Source Term FSAR DBA 270 2.6 7.9 FSAR EXPECTED 67.2 0.65 2.0 1.5E-02 3.7E-02 I
I 4.4E-05 9.OE-05 0.2 0.014 162,784 393,464 1,250,000 0.1 0.01 1.2E-03 1.9E-04 1.6E-05 1.3E-04 RCS 3.5E-07 5.2E-08 4.4E-09 3.6E-08 RCS 0030331.DOE 03B EP RB-9 11A 21 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 lA 22 OF 42 1 AND 2 APPENDIX 6.11 (Continued)
SUMMARY
SHEET B MAJOR STEAM LINE BREAK FSAR FSI PARAMETER DBA EXI 3-(x/Q) CL (sec/m3)
- a.
800m (site boundary) 5.29x10 4 5.25
- b.
10000m (6 mi. LPZ) 2.20x10-5 2.2(
- 4.
Whole Body Dose Results
- a.
Total 800m dose for 1.7E-03 5.41 1st two hours (Rem)
- b.
Total 10000m dose for 30 days (Rem) 2.6E-04 7.81
- 5.
Thyroid Dose Results
- a.
Total 800m dose for 8.8E-02 1.61 1 st two hours (Rem)
- b.
Total l0000m dose for 30 days (Rem) 5.3E-02 9.91
- 6.
Accident Classification (Based on above Dose):
Alert No (Based on EP G-1):
Unusual Event Unt
- 7.
Miscellaneous
- a.
Fluid Mass/Stm Gen (Ibs)
Water 81,500
- b.
Safety Valve and Steam Dump Valve Capacities (lb/hr/valve)
- 1)
S/G safety valve 800,000
- 2) 10% atmospheric dump 380,000
- 3) 35% atmospheric dump 597,000
- 8.
References
- a.
FSAR, September 1990, Revision 6, Section 15.5
- b.
DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-19.
AR SPECTED
)xlO-6 E-07 E-08 E-05
'E-06 Emergency isual Event 0030331.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-9 DIABLO CANYON POWER PLANT REVISION 11A PAGE 23 OF 42 TITLE:
Calculation of Release Rate UNITS 1 AND 2 APPENDIX 6.11 (Continued)
SUMMARY
SHEET C MAJOR FEEDWATER LINE BREAK The release from this accident comes from release of steam by safety valves and/or atmospheric steam dump of steam generator water during cooldown if the condenser is not available. The steam generator water is contaminated if there is tube leakage. The feedwater itself which is released has very little activity in it and is ignored.
This accident is basically the same as a major steamline break and Summary Sheet B can be used.
Note, however, that the steam release will be through relief valves and so the iodine liquid release fraction should be 0.01 for the entire release. This will reduce the thyroid dose somewhat from the steamline break case.
0030331.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER EP RB-9 REVISION 11A PAGE 24 OF 42 TITLE:
Calculation of Release Rate UNITS 1 AND 2 APPENDIX 6.11 (Continued)
SUMMARY
SHEET D BLACKOUT (PLANT COOLDOWN WITH ATMOSPHERIC DUMP)
The release from this accident comes from release of steam by safety valves andVor atmospheric steam dump of steam generator water which is contaminated if there is tube leakage.
This accident is basically the same as a steamline break and Summary Sheet B can be used.
Note, however, that the steam release will be through relief valves and so the iodine liquid release fraction should be 0.01 for the entire release. This will reduce the thyroid dose somewhat from the steamline break case.
0030331.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DLBLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET E SMALL LOCA (RELEASE OF COOLANT TO CONTAINMENT)
PARAMETER
- 1.
Initial Coolant Activity (Ci/gm)
- a.
- b.
Other Noble Gases
- c.
1-131
- d.
Other Iodine
- e.
Source Term
- f.
Fuel Defects (/O)
- 2.
Initial Release to Containment (Ci)
- a.
- b.
Other Noble Gases
- c.
1-131
- d.
Other Iodine
- e.
Assumption
- 3.
Containment Spray Effectiveness a-Removal Coefficient (hrl)
- b.
Number of operable spray pumps
- 4.
Containment Leak Rate (%/day)
FSAR DBA 270 30 2.62 7.88 RCS 1
65,430 7,950 63 193 100% of Coolant N.G.
activity +10% of coolant iodines 31 FSAR EXPECTED 45.7 5.6 0.45 1.35 RCS 0.2 16,280 1,980 16 48 100% of Coolant N.G.
Activity +10/o of coolant iodines 92 1
0.1 for 1st day, 0.05 after 1st day 2
0.05 for Ist day, 0.025 after 1st day
- 5.
(x/Q) CL (sec/m 3)
- a.
800m (site boundary)
- b.
10000m (6 mi. LPZ) 00303311 DOE 03B NUMBER REVISION PAGE UNITS EP RB-9 11A 25 OF 42 1 AND 2 5.29xlO4 2.20xlO-5 5.29xl0-5 2.20x106 0530,0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 lA 26 OF 42 1 AND 2 APPENDIX 6.11 (Continued)
SUMMARY
SHEET E SMALL LOCA (RELEASE OF COOLANT TO CONTAINMENT)
- 6.
Whole Body Dose Results
- a.
Total 800m dose for 1 st two hours (Rem) 1.8E-04 4.4]
- b.
Total I 0000m dose for 30 days (Rem) 5.OE-05 1.41
- 7.
Thyroid Dose Results
- a.
Total 800m dose for 1st two hours (Rem) 2.0E-04 9.0]
- b.
Total 10000m dose for 30 days (Rem) 3.0E-05 1.0
- 8.
Accident Classification (Based on above Dose):
Unusual Event No (Based on EP G-1):
Site Area Emergency Site
- 9.
Miscellaneous
- a.
Containment-Free Volume (cc) 7.36x1010
- b.
RCS Coolant Mass (gm) 2Ax108
- c.
Liquid Release Fraction for Iodine 0.1
- 10.
References
- a.
FSAR, Table 15.5-11.
- b.
DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-17.
TR PECT'ED E-06 E-06 E-07 E-07 Emergency t Area Emergency 0030331.DOE 03B 0530.0409
PACIFIC GAS AND ELECTRIC COMIPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS T1TLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET F TUBE RUPTURE PARAMETER Initial Conditions and Assumptions (Pre-accident Iodine Spike Case)
- a.
Primary Coolant Activity (glCi/gm)
- 1)
- 2) 1-131 (equivalent)
- 3) 1-131
- 4)
Other Iodine
- b.
Secondary Water Activity (gCi/gm)
- 1)
- 2)
Other lodines
- c.
Assumed Fuel Defects (%)
- d.
Primary to Secondary Leakage (gpm)
- 1) Pre-existing
- 2)
Tube Rupture
- e.
Steam Release, 1st Two Hours (Ibs)
- 1) Failed generator
- 2)
Other generators (atmospheric dump)
- f.
Total Steam Release During 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Cooldown (Ibs)
- g.
Liquid Release Fraction for Iodine
- 1) Failed generator
- 2)
Other generators (1) 0.01 when rupture site is covered 1.0 when covered by less than 12" water FSAR DBA FSAR EXPECTED 270 60 41.4 110.4 67.2 0.65 2.0 6.9E-02 1.8E-01 I
4.4E-05 9.OE-05 0.2 1
160 146,700 445,000 0.014 31,000 380,000 1,530,000 1,500,000 0.01 *(I) 0.01 *(1) 0.01 0.01 00303311.DOE 03B EP RB-9 1IA 27 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET F TUBE RUPTURE PARAMETER
- 2.
Total Release to Environs First 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (Ci)
(Pre-Accident Iodine Spike)
- a.
- b.
Other Noble Gases
- c.
1-131
- d.
Other lodines
- e.
Source Term FSAR DBA FSAR EXPECTED 2.8E+04 2.OE+03 5.5E+02 1.4E+03 RCS 2.4E+03 2.4E+02 1.4E-01 6.2E-0 1 RCS 3-(x/Q) CL (sec/m3)
- a.
800 m (site boundary)
- b.
10000m (6 mi. LPZ)
- 4.
Whole Body Dose Results
- a.
Total 800m dose for 1st two hours (Rem)
- b.
Total 10000m dose for 30 days (Rem)
- 5.
Thyroid Dose Results
- a.
Total 800m dose for 1st two hours (Rem)
- b.
Total l0000m dose for 30 days (Rem)
- 6.
Accident Classification (Based on above Dose):
(Based on EP G-1):
5.29x104 2.20xl05 2.3E-01
.OE-02 5.29x1 0-5 2.20x10 4 7.7E-03 3.OE-04 1.9E+02 8.0E+00 4.3E-03 2.OE-04 General Emergency Site Area Emergency Alert Site Area Emergency 00303311.DOE 03B NUMBER REVISION PAGE UNITS EP RB-9 11A 28 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET F TUBE RUPTURE PARAMETER
- 7.
Miscellaneous
- a.
Fluid Mass/Steam Gen (Ibs)
- 1) Water
- b.
Safety Valve and Steam Dump Valve Capacities (lbs/hr/valve)
- 1)
S/G safety valve
- 2) 10% atmospheric dump
- 8.
References
- a.
FSAR, Revision 7, September 1991, Tables 15.5-64 thru 15.5-74.
- b.
DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-16.
0030331.DOE 03B 0530.0409 NUMBER REVISION PAGE UNlTS EP RB-9 11A 29 OF 42 1 AND 2
PACIFC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TILE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS APPENDIX 6.11 (Continued)
SUMMARY
SHEET G LOCKED ROTOR ACCIDENT PARAMETER
- 1.
Total Release to Environs, I st Two Hours (Ci)
- a.
- b.
Other Noble Gases
- c.
1-131
- d.
Other lodines
- e.
Source Term
- f.
Assumptions I )
Coolant Activity
- 2)
Primary to Secondary Leakage (gpm)
- 3)
Secondary Steam Release, I st Two Hours (Ibs)
- 4)
Total Steam Release During 8 Hour Cooldown (lbs) 2-(x/Q) CL (sec/m 3)
- a.
800m (site boundary)
- b.
1000m (6 mi. LPZ)
- 3.
Whole Body Dose Results
- a.
Total 800m dose for Ist two hours (Rem)
- b.
Total I10000m dose for 30 days (Rem)
- 4.
Thyroid Dose Results
- a.
Total 800m dose for Ist two hours (Rem)
- b.
Total l0000m dose for 30 days (Rem)
FSAR DBA 2.7E+02 5.5E+01 8.6E-01 1.3E+00 Gap FSAR EXPECTED 6.3E-06 9.6E-06 8.2E-08 2.8E-07 Gap 1% fuel defects
+3% of gap activity I
520,000 1,600,000 5.29x104 2.20xl0-5 0.2% fuel defects
+3% of gap activity 0.014 520,000 1,600,000 5.29x10-5 2.20x10 46 1.3E-02 I.IE-03 3.OE-01 7.2E-02 1.6E-05 1.2E-06 2.5E-04 6.2E-05 0030331.DOE 03B 0530.0409 EP RB-9 11A 30 OF 42 1 AND 2
PACIFIC GAS AND ELECTRIC COMPANY DlABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET G LOCKED ROTOR ACCIDENT FSAR FS.
PARAMETER DBA EX
- 5.
Accident Classification (Based on above Dose):
Alert No (Based on EP G-1)
Alert Ale
- 6.
Miscellaneous
- a.
Fluid Mass/Steam Gen (lbs)
- 1) Water 81,500
- b.
Safety Valve and Steam Dump Valve Capacity (lbs/br/valve)
- 1)
S/G safety valve 800,000
- 2) 10% atmospheric dump 380,000
- 3) 35% atmospheric dump 597,000
- c.
Liquid Release Fraction for lodines 0.01
- 7.
References
- a.
FSAR, Tables 15.541 and 42.
- b.
DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-14.
CR (PECT'ED Emergency ert 00303311.DOE 03B EP RB-9 11A 31 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET H FUEL HANDLING ACCIDENT IN FUEL HANDLING BLDG PARAMETER
- 1.
Initial Conditions
- a.
Radial Peaking Factor of Damaged Assembly
- b.
Elapsed Time Since Reactor Shutdown (hrs)
- c.
Type of Release to Pool
- d.
Bundle Submergence (ft)
- e.
Pool Decontamination Factor for Iodine
- f.
Total Assembly Gap Activity at Time of Accident I)
- 2)
Other Noble Gases
- 3)
- 4)
Other Iodines
- 5)
Source
- 2.
(x/Q) CL (sec/m3)
- a.
800m (site boundary)
- b.
1000m (6 mi. LPZ)
- 3.
Total Release to Environs, 1st Two Hours (Ci)
- a.
- b.
Other Noble Gases
- c.
- d.
Other lodines
- e.
Source Term FSAR DBA 1.65 FSAR EXPECTED 1.26 100 100 100% of assembly gap activity 26 100 100,000 4,500 52,670 7,000 Spent Fuel 5.29x1 0-4 2.20x1 0-5 100,400 4,100 80 10 Spent Fuel 100% of assembly gap activity 26 760 8,137 1,500 5,282 220 Spent Fuel 5.29x10 5 2.20x1 0-6 523 101 0.005 0.0002 Spent Fuel 0030331.DOE 03B NUMBER REVISION PAGE UNIrS EP RB-9 11A 32 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 11A 33 OF 42 1 AND 2 APPENDIX 6.11 (Continued)
SUMMARY
SHEET H FUEL HANDLING ACCIDENT IN FUEL HANDLING BLDG FSAR FSAR PARAMETER DBA EXPECTED
- 4.
Whole Body Dose Results
- a.
Total 800m dose for 1st two hours (Rem) 2.5E+00 1.5E-03
- b.
Total lOOOOm dose for 30 days (Rem)
.OE-01 6.1E-05
- 5.
Thyroid Dose Results
- a.
Total 800m dose for 1st two hours (Rem) 2.2E+01 8.2E-05
- b.
Total 10000m dose for 30 days (Rem) 9.2E-01 3.4E-06
- 6.
Accident Classification (Based on above dose):
General Emergency Alert (Based on EP G-1):
Site Area Emergency Site Area Emergency
- 7.
Miscellaneous a-Fuel Handling Building Volume (ft3 )
435,000
- b.
Fuel Handling Building Exhaust Rate 35,700 35,700 (cfm)
- c.
Filter Cleanup Factor 0.10 0.01
- 8.
References
- a.
FSAR, Tables 15.5-43 through 15.5-47.
- b.
DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-22.
0030331.DOE 03B 0530.0409
PACIMIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET I FUEL HANDLING ACCIDENT IN CONTAINMENT PARAMETER
- 1.
Initial Conditions
- a.
Radial Peaking Factor of Damaged Assembly
- b.
Elapsed Time Since Reactor Shutdown (hrs)
- c.
Type of Release to Pool
- d.
Bundle Submergence (ft)
- e.
Pool Decontamination Factor for Iodine
- f.
Total Assembly Gap Activity at Time of Accident (Ci)
I)
- 2)
Other Noble Gases
- 3) 1-131
- 4)
Other lodines
- 5)
Source Term 2-(x/Q) CL (sec/m3)
- a.
800m (site boundary)
- b.
1000m (6 mi. LPZ)
- 3.
Total Release to Environs, 1st Two Hours (Ci)
- a.
- b.
Other Noble Gases
- c.
- d.
Other lodines
- e.
Source Term FSAR DBA FSAR EXPECTED 1.65 1.26 100 100 100% of assembly gap activity 26 100 100,000 4,500 52,670 7,000 Spent Fuel 5.29x10 4 2.20x10-5 12,460 557 65 8.7 Spent Fuel 100% of assembly gap activity 26 760 8,137 1,500 5,282 220 Spent Fuel 5.29x10-5 2.20xlO6 38 7
0.033 0.0013 Spent Fuel 0030331.DOE 03B 0530.0409 NUMBER REVISION PAGE UNffS EP RB-9 11A 34 OF 42 1 AND 2
PACIFIC GAS AND ELECTRIC COMPANY DLIBLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET I FUEL HANDLING ACCIDENT IN CONTAINMENT PARAMETER
- 4.
Whole Body Dose Results
- a.
Total 800m dose for 1 st two hours (Rem)
- b.
Total 10000m dose for 30 days (Rem)
- 5.
Thyroid Dose Results
- a.
Total 800 m dose for 1 st two hours (Rem)
- b.
Total 10000m dose for 30 days (Rem)
- 6.
Accident Classification (Based on above Dose):
(Based on EP G-1):
- 7.
Miscellaneous Activity Release Mechanism FSAR DBA 3.1E-01 1.3E-02 1.8E+01 7.6E-01 FSAR EXPECTED I.OE-04 4.OE-06 6.OE-04 3.OE-05 General Emergency Alert Site Area Emergency Alert Activity released from cavity to containment atmosphere is confined directly above the cavity water level. It is picked up by the fan coolers and sent out through the containment purge.
- 8.
References
- a.
FSAR, Tables 15.5-48 through 15.5-50.
- b.
DCMNo. T-15, Radiation Protection, Rev. 0, February 1993, Section 4.6.7.21.
0030331 I.DOE 03B 0530.0409 NUMBER REVISION PAGE UNITS EP RB-9 11A 35 OF 42 1 AND 2
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET J ROD EJECTION ACCIDENT PARAMETER
- 1.
Total Release to Containment Free Volume (Ci)
- a.
- b.
Other Noble Gases
- c.
1-131
- d.
Other Iodine
- e.
Source Term
- f.
Release Assumption
- 2.
Containment Spray Effectiveness
- a.
Removal half-life (hrs)
- b.
Number of operable spray pumps
- 3.
Containment Leak Rate (%//day)
- 4.
(x/Q) CL (sec/m3)
- a.
800m (site boundary)
- b.
OOOm (6 mi. LPZ)
- 5.
Total Release to Environs, 1st 2 Hours (Ci)
- a.
- b.
Other Noble Gases
- c.
1-131
- d.
Other Iodine
- e.
Source Term
- f.
Release Mechanism FSAR DBA 2.01x105 6.82xI04 7.32x103 1.1 x104 Gap Coolant activity (1%
defects) plus 10% of core gap activity times a liquid release fraction of either 0.1 (for I) or 1.0 (for N.G.)
0.022 1
0.1 5.29x104 2.20x10-5 11.2 4.1 0.0098 0.015 Gap Containment Leakage FSAR EXPECTED 1.52x105 6.22x1 04 7.28xl03 1.09x104 Gap Coolant activity (0.2%
defects) plus 10% of core gap activity times a liquid release fraction of either 0.1 (for I) or 1.0 (for N.G.)
0.0075 2
0.05 5.29x10-5 2.20xI0 6 5.6 2.0 0.002 0.002 Gap Containment Leakage 0030331.DOE 03B NUMBER REVISION PAGE UNITS EP RB-9 11A 36 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITIE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET J ROD EJECTION ACCIDENT PARAMETER
- 6.
Whole Body Dose Results
- a.
Total 800m dose for I st two hours (Rem)
- b.
Total 1000m dose for 30 days (Rem)
- 7.
Thyroid Dose Results
- a.
Total 800m dose for 1 st two hours (Rem)
- b.
Total 10000m dose for 30 days (Rem)
- 8.
Accident Classification (Based on above Dose):
(Based on EP G-1):
- 9.
Miscellaneous
- a.
Containment free volume (cc)
- b.
RCS Coolant Mass (gm)
FSAR DBA FSAR EXPECTED 7.3E-04 3.6E-05 1.3E-04 3.3E-03 1.4E-04 6.4E-06 3.7E-05 1.6E-06 Unusual Event Site Area Emergency No Emergency Site Area Emergency 7.36x1010 2.4x108
- 10.
References
- a.
FSAR, Table 15.5-52.
- b.
DCM T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-13.
0030331.DOE 03B 0530.0409 NUMBER REVISION PAGE UNITS EP RB-9 11A 37 OF 42 1 AND 2
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS APPENDIX 6.11 (Continued)
SUMMARY
SHEET K GAS DECAY TANK RUPTURE PARAMETER
- 1.
Total Release to Environs, I st Two Hours (Ci)
- a.
- b.
Other Noble Gases
- 2.
(x/Q) CL (sec/m3)
- a.
800m (site boundary)
- b.
10000m (6 mi. LPZ)
- 3.
Whole Body Dose Results
- a.
Total 800m dose for I st two hours (Rem)
- b.
Total l0000m dose for 30 days (Rem)
NOTE: Thyroid doses are negligible.
- 4.
Accident Classification (Based on above Dose):
(Based on EP G-1):
- 5.
Miscellaneous
- a.
Tank Volume (cc)
- b.
Tank Press (psi)
- c.
Volume Released (cc)
FSAR DBA FSAR EXPECTED 65,400 7,300 16,300 2,140 5.29x1 04 2.20x1 0-5 2.OE+00 8.4E-02 General Emergency Alert 5.29x1 0-5 2.20x106 4.4E-02 1.8E-03 Site Area Emergency Alert 2.18x107 100 1.48x108
- 6.
References
- a.
FSAR, Table 15.5-53.
- b.
DCM T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-23.
0030331.DOE 03B EP RB-9 11A 38 OF 42 1 AND 2 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS APPENDIX 6.11 (Continued)
SUMMARY
SHEET L LIQUID HOLDUP TANK RUPTURE PARAMETER
- 1.
Activity in Holdup Tank (Ci)
- a.
- b.
Other Noble Gases
- c.
1-131
- d.
Other lodines
- e.
Source Term
- 2.
Cleanup Parameters
- a.
Liquid Release Fraction for odines from Tank to Auxiliary Building Atmosphere
- b.
Charcoal Filter Cleanup Factor
- c.
Release Duration (hrs)
- 3.
Activity Release to Environs, 1 st Two Hours (Ci)
- a.
- b.
Other Noble Gases
- c.
- d.
Other Iodines 4-(x/Q) CL (sec/m3)
- a.
800m (site boundary)
- b.
10000m (6 mi. LPZ)
- 5.
Whole Body Dose Results
- a.
Total 800m dose for 1st two hours (Rem)
- b.
Total 10000m dose for 30 days (Rem) 0030331.DOE 03B EP RB-9 11A 39 OF 42 1 AND 2 FSAR DBA FSAR EXPECTED 51,000 4,710 492 1,086 RCS 10,200 930 98.3 217 RCS 10-10-4 0.1 2
0.01 2
51,000 4,710 0.00492 0.01086 10,200 930 9.8E-5 2.17E-4 5.29x 10-4 2.20x10-5 5.29x10-5 2.20x10-6 I.4E+00 3.7E-02 6.OE-02 1.6E-03 0530.0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET L LIOUID HOLDUP TANK RUPTURE FSAR PARAMETER DBA
- 6.
Thyroid Dose Results
- a.
Total 800m dose for 1.9E-03 1 st two hours (Rem)
- b.
Total 10000m dose 8.OE-05 for 30 days (Rem)
- 7.
Accident Classification (Based on Dose):
Site Area Emergency (Based on EP G-1):
Alert
- 8.
Miscellaneous
- a.
Tank Volume (cc) 3.03x108
- 9.
References
- a.
FSAR, Table 15.5-56.
- b.
DCM T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-24.
FSAR EXPECTED 2.6E-06
.IE-07 Site Area Emergency Alert 03B 0530.0409 NUMBER REVISION PAGE UNITS EP RB-9 11A 40 OF 42 1 AND 2 0030331 I.DOE
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET M VOLUME CONTROL TANK RUPTURE PARAMETER
- 1.
Activity in VCT (Ci)
- a.
- b.
Other Noble Gases
- c.
- d.
Other lodines
- e.
Source Term
- 2.
Cleanup Parameters
- a.
Liquid Release Fraction for lodines from Tank to Auxiliary Building Atmosphere
- b.
Charcoal Filter Cleanup Factor
- c.
Release Duration (hrs)
- 3.
Activity Release to Environs, 1st Two Hours (Ci)
- a.
- b.
Other Noble Gases
- c.
- d.
Other Iodines
- 4.
(x/Q) CL (sec/m3)
- a.
800m (site boundary)
- b.
1000m (6 mi. LPZ)
- 5.
Whole Body Dose Results
- a.
Total 800m dose for 1st two hours (Rem)
- b.
Total 10000m dose for 30 days (Rem)
FSAR DBA 3,330 198 12.1 35 RCS FSAR EXPECTED 828 42 3.0 8.7 RCS 10-4 0.1 2
10-4 0.01 2
3,330 198 0.00012 0.00035 5.29x10 4 5.20x1 0-5 4.7E-01 828 42 3E-6 9E-6 5.29xl0-5 2.20x1 0-6 9.3E-03 I.9E-02 3.9E-04 00303311 DOE 03B NUMBER REVISION PAGE UNITS EP RB-9 11A 41 OF 42 1 AND 2 0530-0409
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate APPENDIX 6.11 (Continued)
SUMMARY
SHEET M VOLUME CONTROL TANK RUPTURE PARAMETER
- 6.
Thyroid Dose Results
- a.
Total 800m dose for 1 st two hours (Rem)
- b.
Total 10000m dose for 30 days (Rem)
- 7.
Accident Classification (Based on Dose):
(Based on EP G-1):
- 8.
Miscellaneous
- a.
Tank Volume (cc)
FSAR DBA 3.3E-05 1.4E-06 Site Area Emergency Alert FSAR EXPECTED 4.4E-08 1.8E-09 Alert Alert 1.Xl107
- 9.
References
- a.
FSAR, Table 15.5-57.
- b.
DCM T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-25.
0030331.DOE 03B 0530.0409 NUMBER REVISION PAGE UNlTS EP RB-9 11A 42 OF 42 1 AND 2
DIABLO CANYON POWER PLANT EP RB-9 ATTACHMENT 7.1 1AND TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Plant Vent Release SECTION 1 - GENERAL INFORMATION 1.1 Enter the following information: Unit #
Date Time of Readings Calculation #
Date _
Time of Rx S/D Calculation By:
(Rx S/D)
(name) 1.2 Determine the TIME AFTER RX S/D (Hrs)
Use Table I (Appendix 6.1) to determine Probable Source Term (circle one):
CORE GAP RCS SPENT FUEL SECTION 2 - PLANT VENT FLOW RATE Flow Rate Indicator FR-12 Operable 2.1 If FR-12 is operable, record below the flow rate reading indicated. Go to Section 2.3.
Plant Vent Flow Rate =
cfin 2.1 Flow Rate Indicator FR-12 Inoperable 2.2
- a.
If FR-12 is not operable. determine the Plant Vent Flow Rate by summing the operating fan flow rates below.
Number of Operating Fans Fan Exhaust Rate Pathway Flow Rate FHB x
35,750 cfm
=
cfm Aux Bldg x
73,500 cfm
=
cfm Containment Purge x
55,000 cfm
=
cfm GE/GW x
25,000 cfm cfm Containment H2 x
300 cfm
=
cfm Plant Vent Flow Rate = E Fan Flow Rates Plant Vent Flow Rate 2.3 Convert "Plant Vent Flow Rate" units:
Plant Vent Flow Rate Conversion Factor cfm x
472 cc/sec/cfm 2.1 or 2.2 cfin 2.2 Plant Vent Flow Rate cc/sec 2.3 0030331.DOE 03B 0530.0409 69-9260 08/31/94 Page I of 5
EP RB-9 (UNITS I AND 2)
ATTACHMENT 7.1 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Plant Vent Release SECTION 3 - NOBLE GAS RELEASE Noble Gas Concentration 3.1
- a.
Record the plant vent radiation "Monitor Reading" from the EARS, ARMS, or RMS panel* in the Control Room (see Note below). Use RE-29 only if the RE-14/14R/87 monitors are unavailable.
- b.
Calculate the "Noble Gas Concentration" using the Monitor Response Factor from Figure 1, 2, or 3.
- NOTE: Monitor Readings from the Control Room RMS Panel read in pCi/cc. If this reading is used in lieu of raw data, enter the value directly in 3.2 below.
Monitor Reading Monitor Response Factor Noble Gas Concentration cpm x
"Ci/cc/cpm
=
lCi/cc RE-14/14R Figure I Amps x
"Ci/cc/Amps
=
Ci/cc RE-87 Figure 2 mR/hr x
"LCi/ccmR/hr =
"LCi/cc RE-29 Figure 3 Noble Gas Release Rate 3.2
- a.
Enter below the "Noble Gas Concentration" from Section 3.1 and the "Plant Vent Flow Rate" from Section 2.3.
- b.
Calculate and record below "Noble Gas Release Rate."
Noble Gas Conversion Plant Vent Noble Gas Concentration Factor Flow Rate Release Rate pCi/cc x
IE-6 Ci/pCi x _cc/sec
=_Ci/sec 3.1 2.3 3.2 0030331 1.DOE 03B 0530.0409 69-9260 0813 194 Page 2 of 5
EP RB-9 (UNITS I AND 2)
ATTACHMENT 7.1 TITLE:
Noble Gas and I-131 Equivalent Release Rates for a Plant Vent Release SECTION 4 - IODINE RELEASE Iodine Monitors CAUTION: Do not attempt to access RE-24R or RE-87 without authorization from Radiation Protection.
4.1 Use the RE-24 or RE-24R iodine monitor (if on scale), or the extended range iodine sampler (RF-87), and go to the corresponding section to calculate the odine-131 equivalent release rate.
RE-24, RE-24R (Normal range monitoring)
Concentration Mode
->Section 5 RE-24R (High range monitoring)
Count Rate Mode
-*Section 6 RF-24R, RF-87 (High range sampling)
->Section 7 SECTION 5 - RE-24, RE-24R (Normal range monitoring) Concentration Mode 1-131 Release Rate 5.1
- a.
Calculate the "1-131 Release Rate" using the higher of RE-24 and RE-24R.
1-131 Plant Vent Plateout Conversion 1-131 Concentration Flow Rate Correction Factor Release Rate "Ci/cc x RE-24 or RE-24R cc/sec x
1.3 2.3 x 1E-6 Ci/ACi Ci/sec 5.1 I-131 Equivalent Release Rate 5.2
- a.
Calculate the "1-131 TEDE Equivalent Release Rate" and "I-131 Thyroid CDE Equivalent Release Rate" using Figure 4.1 and Figure 4.2 correction factors.
1-131 Release Rate Ci/sec 5.1 1-131 Release Rate Ci/sec 5.1 I-131 TEDE Correction Factor x
Figure 4.1 I-131 Thyroid CDE Correction Factor x
Figure 4.2 1-131 TEDE Equivalent Release Rate
=__________Ci/sec 5.2.A 1-131 Thyroid CDE Equivalent Release Rate
=____________Ci/sec 5.2.B 03B 0530.0409 69-9260 08/31/94 Page 3 of 5 0030331 I.DOE
EP RB-9 (UNITS I AND 2)
ATTACHMENT 7.1 TITLE:
Noble Gas and I-131 Equivalent Release Rates for a Plant Vent Release SECTION 6 - RE-24R (High range monitoring) Count Rate Mode Flow Rate Ratio 6.1
- a.
Calculate "Flow Rate Ratio." Normal flow rate ratio is 1.3E5.
Plant Vent Flow Rate
_ cc/sec 2.3 RE-24R Flow Rate cclsec Local indication Flow Rate Ratio Default Ratio or 1.3E5 6.1 1-131 Collection Rate 6.2
- a.
Record the "CPM Change Rate" as reported by personnel operating the RMS panel. (This data is gathered using EP RB-12 Section 6.1.3)
- b.
Calculate and record below the "1-131 Collection Rate."
Conversion Factor cpm/min x
1.4E-7 pCi min/cpm sec
=
1-131 Release Rate 6.3 I-131 Concentration Flow Rate Ratio Plateout Correction Conversion Factor 1-131 Collection Rate 6.2 "Ci/sec 6.2 1-131 Release Rate "Ci/sec x 6.2 x
1.3 x 1E-6 Ci/pCi 6.1 Ci/sec 6.3 1-131 Equivalent Release Rate 6.4
- a.
Calculate the "1-131 TEDE Equivalent Release Rate" and "1-131 Thyroid CDE Equivalent Release Rate" using Figure 4.1 and Figure 4.2 correction factors.
1-131 Release Rate Ci/sec 6.3 1-131 Release Rate Ci/sec 6.4 1-131 TEDE Correction Factor Figure 4.1 1-131 Thyroid CDE Correction Factor x
Figure 4.2 I-131 TEDE Equivalent Release Rate
= ___________ C i/sec 6.4.A I-131 Thyroid CDE Equivalent Release Rate
= _________
Ci/sec 6.4.B 0030331.DOE 03B 0530.0409 CPM Change Rate 69-9260 08/31/94
-Page 4 of 5
EP RB-9 (UNITS I AND 2)
ATTACHMENT 7.1 TITLE:
Noble Gas and I-131 Equivalent Release Rates for a Plant Vent Release SECTION 7 - RF-24R, RF-87 (High range sampling) 1-131 Release Rate 7.1
- a.
Record below the 1-131 Concentration for the RF-24R or RF-87 silver zeolite cartridge determined by EP RB-12, Section 6.2 (RF-24R) or 6.3 (RF-87).
- b.
Calculate and record "I-131 Release Rate."
1-131 Concentration
'Ci/cc x
EP RB-12 Plant Vent Flow Rate cc/sec 2.3 Plateout Conversion I-131 Correction Factor Release Rate x
1.9 x E-6 Ci4lCi
=_
Ci/sec 7.1 1-131 Equivalent Release Rate 7.2
- a.
Calculate the "I-131 TEDE Equivalent Release Rate" and "I-131 Thyroid CDE Equivalent Release Rate" using Figure 4.1 and Figure 4.2 correction factors.
1-131 Release Rate Ci/sec 7.1 I-131 Release Rate Ci/sec 7.2 1-131 TEDE Correction Factor Figure 4.1 I-131 Thyroid CDE Correction Factor x
Figure 4.2 I-131 TEDE Equivalent Release Rate Ci/sec 7.2.A I-13 1 Thyroid CDE Equivalent Release Rate
=_________Ci/sec 7.2.B 0030331.DOE 03B 69-9260 08131/94 Page 5 of 5 0530.0409
DIABLO CANYON POWER PLANT EP RB-9 ATTACHMENT 7.2 1AND TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Steam Release SECTION 1 - GENERAL INFORMATION 1.1 Enter the following information: Unit #
Date Time of Readings Calculation #
Date Time of Rx S/D Calculation By:
(Rx S/D)
(name) 1.2 Determine the TIME AFTER RX S/D (Hrs)
Use Table 1 (Appendix 6.1) to deternine appropriate Source Term. (circle one):
CORE GAP RCS SPENT FUEL 1.3 Indicate the faulty steam generator by placing a check mark in a box below. Go to Section 2.1 or 2.2.
Faulted MSL MSL Flow Narrow 10%
Safety Steam Radiation Rate Range Steam Relief Generator Monitor Indicator Recorder Dumps Valves 1] SG-1 RE-71 FI-512 LR-517 PCV-19 RV-3,4,5,6,222
[
SG-2 RE-72 FI-522 LR-527 PCV-20 RV-7,8,9,10,223
[
SG-3 RE-73 FI-532 LR-537 PCV-21 RV-1 1,12,13,14,224
[
SG4 RE-74 FI-542 LR-547 PCV-22 RV-15,16,17,18,225 SECTION 2 - STEAM FLOW RATE MSL Flow Rate Indicator Operable 2.1 If the MSL Flow Rate Indicator on the faulty steam generator in Section 1.3 is operable. record below the greater of the reading indicated, or 4E5 lb/hr. Go to Section 2.3.
MSL Flow Rate FR-512,522,532,542
=
lb/hr 2.1
- If less than 4E5 lb/hr, record and use 4E5 lb/hr.
MSL Flow Rate Indicator Inoperable 2.2
- a.
If the MSL flow rate indicator on the faulty steam generator in Section 1.3 is not operable, deternine and record the "Number of Valves Open" releasing steam. ONLY INCLUDE VALVES OPEN ON THE MSL WITH THE FAULTY STEAM GENERATOR IN SECTION 1.3.
0030331.DOE 03B 69-11105 08/31/94 Page of 6 0530.0409
EP RB-9 (UNITS I AND 2)
ATTACHMENT 7.2 TITLE:
Noble Gas and I-131 Equivalent Release Rates for a Steam Release SECTION 2 - STEAM FLOW RATE (Continued) 2.2
- b.
Calculate the "MSL Flow Rate" by summing the "Valve Flow Rates." Go to Section 2.3.
Number of Valves Open Flow Rate Valve Flow Rate 10% Steam Dumps x
4.0 E5 lb/hr
=
lb/hr Safety Reliefs x
8.5 E5 lb/hr
=
lb/hr MSL Flow Rate = E Valve Flow Rates
=
lb/hr 2.2 Steam Flow Rate 2.3 Calculate and record the "Steam Flow Rate" using the "MSL Flow Rate," from Section 2.1 or 2.2. Go to Section 3.1 or 3.2.
MSL Flow Rate Conversion Factor Steam Flow Rate lb/hr x 3.1 cc hr/lb sec =
2.1 or2.2 2.3 cc/sec SECTION 3 - ISOTOPIC STEAM ACTIVITY FRACTIONS Isotopic Steam Activity Fractions - RCS Sample Analysis NOTE: If RCS Sample is not available, then skip Section 3.1 at this time and proceed with Section 3.2 (Page 4).
3.1
- a.
Record the date and time the Reactor Coolant System (RCS) sample was collected.
RCS Sample Collection Date and Time:
/
I
- b.
Record in Section 3.1.h below the "RCS Sample Activity Concentrations" for noble gases, iodines, and particulates.
- c.
Deterrnine the faulty steam generator water level using the Narrow Range Level indication:
Steam Generator Water Level 3.1.c
[ I Empty S/G Level Narrow Range
<4%
[ ] Normal 4% - 96%
[ ] Flooded 296%
00303311.DOE 03B 69-11 105 08131194 Page 2 of 6 0530.0409
EP RB-9 (UNITS I AND 2)
ATTACHMENT 7.2 TITLE:
Noble Gas and I-131 Equivalent Release Rates for a Steam Release SECTION 3 - ISOTOPIC STEAM ACTIVITY FRACTIONS (Continued) 3.1
- d.
Determine the "Steam Partition Factors" for iodines and particulates using the water level indicated in Section 3.1.c. Record the "Steam Partition Factors" in Section 3.1.h below.
Steam Partition Factors Empy Normal Flooded Iodines 0.10 0.01 1.00 Particulates 0.01 0.01 1.00
- e.
Determine the "Density Correction" using the water level indicated in Section 3.1.c. Record the "Density Correction" below.
Density Correction Empty Normal Flooded All 0.056 0.056 1
- f.
Calculate and record below the "Steam Activity Concentrations" for noble gases, iodines, and particulates by multiplying each "RCS Sample Activity Concentration," times each "Steam Partition Factor" times "Density Correction."
- g.
Calculate and record below the "Total Steam Activity Concentration" by summing the "Steam Activity Concentrations" for noble gases, iodines, and particulates.
- h.
Calculate and record below the "Steam Activity Fractions" for noble gases, iodines, and particulates by dividing each "Steam Activity Concentration" by the 'Total Steam Activity Concentration." Go to Section 4 or 5.
(For Section 4.2)
RCS Sample Activity Steam (For Section 5.1)
Steam Concentration Partition Density Steam Activity Activity Factor Correction Concentration Fraction Noble Gases pCi/cc x 1.00
=
_Ci/cc a
a.d lodines JLCi/cc x_
x
=
Ci/cc b
b.d Particulates JLCi/cc x
=
,Ci/cc c
c.d Total Steam Activity Concentration =
4Ci/cc d = a+b+c 0030331 1.DOE 03B 0530.0409 69-11105 08/3 1/94 Page 3 of 6
EP RB-9 (UNITS 1 AND 2)
ATTACHMENT 7.2 TITLE:
Noble Gas and I-131 Equivalent Release Rates for a Steam Release SECTION 3 - ISOTOPIC STEAM ACTIVITY FRACTIONS (Continued)
Isotopic Steam Activity Fractions - FSAR Design Basis - Use only if RCS Sample is not available 3.2
- a.
Determine the faulty steam generator water level using the Narrow Range Level indication:
Steam Generator Water Level
[]Empty
[ ] Normal
[ ] Flooded S/G Level
<4%
4% - 96%
>96%
Narrow Range
- b.
Determine the FSAR "Steam Activity Fractions" for noble gases, iodines, and particulates using the water level indicated in Section 3.2.a. Record the "Steam Activity Fractions" in Section 4.2.c.
FSAR - Steam Activity Fractions Empty Normal Flooded Noble Gases 9.96E-01 9.99E-01 9.5 1E-01 Iodines 3.36E-03 3.37E-04 3.20E-02 Particulates 1.78E-04 1.79E-04 1.70E-02 SECTION 4 - RELEASE RATES - MSL RADIATION MONITORS OPERABLE NOTE: If there appears to be no net RE-7x indication, but the Control Room verifies that the monitor iK--
showed an initial Nitrogen-1 6 response or currently responds to check-source actuation, the monitor is OPERABLE. In this case the entire "background" reading may be used for this calculation to establish an "upper-bound" release estimate, but the method of Section 5.2 should be used to determine release rate if possible.
MSL Activity Concentrations 4.1
- a.
Record the "MSL Monitor Reading" for the faulty steam generator indicated in Section 1.3.
- b.
Calculate and record the "MSL Activity Concentration" using the appropriate "MSL Monitor response from Figure 5.1, 5.2, or 5.3.
MSL Monitor MSL Monitor Conversion MSL Activity Reading
Response
Factor Concentration
_cpm x m'Ci/cc/cpm x 1E-6 Ci/pCi =
Ci/cc RE-71,72,73,74 Appendix 6.6 4.1 0030331.DOE 03B 69-11105 08/31/94 Page 4 of 6 0530.0409
EP RB-9 (UNITS I AND 2)
ATTACHMENT 7.2 TITLE:
Noble Gas and I-131 Equivalent Release Rates for a Steam Release SECTION 4 - RELEASE RATES - MSL RADIATION MONITORS OPERABLE (Continued)
Isotopic Release Rates 4.2
- a.
If a RCS sample is available, enter the "Steam Activity Fraction" from Section 3.1. If a RCS sample is not available, enter below the FSAR "Steam Activity Fraction" from Section 3.2.
- b.
Enter the "MSL Activity Concentration" from Section 4.1 and the "Steam Flow Rate" from Section 2.3.
- c.
Calculate and record "Isotopic Release Rate" for noble gases, iodines, and particulates. Go to Section 6.1.
Steam Activity MSL Activity Steam Isotopic Fraction Concentration Flow Rate Release Rate Noble Gases
_Ci/sec 3.1 or3.2 4.2 Iodines x
Ci/cc x cc/sec=
Ci/sec 3.1 or3.2 4.1 2.3 4.2 Particulates Ci/sec 3.1 or 3.2 4.2 SECTION 5-RELEASE RATES-MSL RADIATION MONITORS INOPERABLE-RCS ANALYSIS RCS Sample Analysis - Known Steam Flow Rates 5.1
- a.
Calculate and record "Isotopic Release Rate" for noble gases, iodines, and particulates using the "Steam Activity Concentrations" from Section 3.1. Go to Section 6.1.
Steam Activity Steam Conversion Factor Isotopic Concentration Flow Rate Release Rate Noble Gases j+/-Ci/cc Ci/sec 3.1 5.1 Iodines gCi/cc x
cc/sec x IE-6 Ci/j.Ci =
Ci/sec 3.1 2.3 5.1 Particulates jCi/cc Ci/sec 3.1 5.1 03B 0530.0409 69-11105 08/3 1/94 Page 5 of 6 0030331 I.DOE
EP RB-9 (UNITS I AND 2)
ATTACHMENT 7.2 TITLE:
Noble Gas and I-131 Equivalent Release Rates for a Steam Release SECTION 5 - RELEASE RATES - MSL RADIATION MONITORS INOPERABLE -
RCS ANALYSIS (Continued)
RCS Sample Analysis - Known Primary to Secondary Leak Rate 5.2
- a.
Enter the "RCS Sample Activity Concentrations" and "Steam Partition Factors" for noble gases, iodines, and particulates recorded in Section 3.1.h (Page 3).
- b.
Enter the "Primary to Secondary Leak Rate."
- c.
Calculate and record "Isotopic Release Rate" for noble gases, iodines, and particulates. Go to Section 6. 1.
RCS Sample Steam Primary to Activity Partition Secondary Conversion Isotopic Concentration Factors Leak Rate Factor Release Rate Noble Gases jiCi/cc x
3.1 lodines j
Ci/cc x
____x gpm x 6.3E-05 3.1 (Ci cc min)
(PCi gal sec)
Particulates y
Ci/cc x
3.1
= _______Ci/sec 5.2
=
_______Ci/sec 5.2
= ________Ci/sec 5.2 SECTION 6 - NOBLE GAS AND 1-131 EQUIVALENT RELEASE RATES 6.1
- a.
Enter below the "Noble Gases Release Rate" and "Iodine Release Rate" from Section 4.2, 5.1, or 5.2.
- b.
Determine "Iodine TEDE Conversion Factor" using Figure 6.1 and "Iodine Thyroid CDE Conversion Factor" using Figure 6.2 and record below.
- c.
Calculate and record "1-131 TEDE Equivalent Release Rate" and "I-131 Thyroid CDE Release Rate."
Enter result of 4.2, 5.1 or 5.2 Iodine Release Rate Iodine TEDE Conversion Factor Ci/sec x 4.2, 5.1, or 5.2 Iodine Release Rate Cil/sec x 4.2, 5.1, or 5.2 Figure 6.1 Iodine Thyroid CDE Conversion Factor Figure 6.2 Noble Gas Release Rate 1=
Ci/sec 6.1 II -131 TEDE Equivalent Release Rate
=____________ C/sec 6.1 1-13 1 Thyroid CDE Equivalent Release Rate
=______________Ci/sec 6.1 0030331.DOE 03B 0530.0409 69-1 1105 08/31194 Page 6 of 6
69-10555 08/31/94 DIABLO CANYON POWER PLANT EP RB-9 ATTACHMENT 7.3 1PAND2 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for Containment Leakage SECTION 1 - GENERAL INFORMATION 1.1 Enter the following information: Unit #
Date Time of Readings Calculation #
Date _
Time of Rx S/D Calculation By:
(Rx S/D)
(name) 1.2 Determine the TIME AFTER RX S/D (Hrs)
Use Table I (Appendix 6.1) to determine appropriate Source Term. (circle one):
CORE GAP RCS SPENT FUEL SECTION 2 - FSAR DESIGN BASIS NOBLE GAS AND I-131 EQUIVALENT RELEASE RATES Average RE-30 and RE-31 Monitor Reading 2.1 Calculate the "Average Monitor Reading" for RE-30 and RE-3 1.
NOTE: If RE-30 and RE-31 are INOPERABLE, record the "EQUIVALENT RE-30/31 READING" from EP RB-14, 4.3.3.
RE-30 RE-31 Average Monitor Reading Monitor Reading Monitor Reading R/hr x
R/hr)/2=
_R/hr 2.1 Average Monitor Reading to FSAR Design Basis Exposure Rate Ratio 2.2 Calculate the "Monitor to Design Basis Ratio" using Figure 7.
FSAR Monitor to Average Design Basis Design Basis Monitor Reading Exposure Rate Ratio R/hr B
=hr
=
2.1 Figure 7 2.2 00303311.DOE 03B Page of 2 0530.0409
EP RB-9 (UNITS I AND 2)
ATrACHMENT 7.3 TITLE:
Noble Gas and 1-13 1 Equivalent Release Rates for Containment Leakage SECTION 2 - FSAR DESIGN BASIS NOBLE GAS AND 1-131 EQUIVALENT RELEASE RATES Noble Gas Release Rate 2.3 Calculate the "Noble Gas Release Rate" using Figure 8.
Monitor to Design Basis Ratio x
2.2 Design Basis Noble Gas Release Rate Ci/sec Figure 8 1-131 Equivalent Release Rate 2.4
- a.
Determine the "Design Basis 1-131 TEDE and Thyroid CDE Equivalent Release Rate" using Figure 9 and record below.
- b.
Calculate and record "I-13 1 TEDE Equivalent Release Rate" and the 1-131 Thyroid CDE Equivalent Release Rate.
Monitor to Design Basis Ratio x
2.2 Design Basis 1-131 TEDE Equivalent Release Rate Ci/sec Figure 9 Monitor to Design Basis Ratio x
Design Basis I-131 Thyroid CDE Equivalent Release Rate Ci/sec Figure 9 I-13 1 Thyroid CDE Equivalent Release Rate
=___________Ci/sec 2.4 00303311.DOE 03B Noble Gas Release Rate Ci/sec 2.3 1-13 1 TEDE Equivalent Release Rate Ci/sec 2.4 2.2 69-10555 08/31/94 Page 2 of 2 0530.0409
- ISSUED FOR USE BY:
DATE:
PACIFIC GAS AND ELECTRIC COMPANY NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE TITLE:
Core Damage Assessment Procedure EXPIRES:____
NUMBER EP RB-14 REVISION 7A PAGE 1 OF 20 UNITS 1
05/30/03 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED SCOPE 1.1 This procedure is used to estimate the extent of clad and/or core failure following an emergency situation involving inadequate core cooling. Westinghouse Owner's Group "Post Accident Core Damage Assessment Methodology" was used as a reference for preparing this procedure.
- 2.
DISCUSSION 2.1 Fuel damage resulting in the release of radioactive material can occur following a loss of coolant accident (LOCA) or loss of available heat sinks. These events, if uncorrected, can lead to localized or widespread overheating of the fuel and eventual clad and/or core failure.
2.2 This procedure provides an initial detection of potential core damage and a preliminary and a long-term methodology for assessing core damage.
2.2.1 The initial detection of core damage can be done by measuring the radiation level at a distance of one foot from the center of the letdown line in the letdown heat exchanger room as shown in Attachment 8.3. Should the radiation level exceed 15 R/hr then fuel damage is indicated at the Alert #2 emergency action level.
2.2.2 The preliminary assessment uses parameters such as reactor vessel water level and core temperatures to confirm that conditions exist which can lead to clad and/or core failure. This is quantified through the use of containment hydrogen and area radiation monitor readings.
2.2.3 Long-term methodology uses reactor coolant and containment air sample analysis to determine the extent of clad and/or core failure more accurately.
Long-term sampling will require about 30 days.
- 3.
RESPONSIBILITIES 3.1 The Emergency Radiological Advisor (ERA) is responsible for the implementation of this procedure. The preliminary assessment can be initiated while awaiting sample analysis results necessary for the long-term assessment. Refer to Table 1 for recommended sample locations.
00408207.DOE 03B 0530.1123 AN
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS T1TLE:
Core Damage Assessment Procedure 4.
EP RB-14 7A 2 OF 20 1 AND 2 PRELIMINARY ASSESSMENT (FORM 69-10422) 4.1 GENERAL INFORMATION Record the information requested.
4.2 INADEQUATE CORE COOLING 4.2.1 Indication of Conditions - Check the appropriate response to the questions.
4.2.2 Evaluation of Conditions - The more boxes checked the greater potential for inadequate core cooling. Proceed to step 4.3 and continue monitoring the situation.
4.3 CONTAINMENT RADIATION LEVELS If loss of Reactor Coolant is not occurring skip this and the next section and proceed to step 5, LONG TERM ASSESSMENT.
4.3.1 Containment Area Radiation Monitors Operable
- a.
Record containment area radiation monitor readings, RIhr, in the spaces labeled RE-30 READING and RE-3 1 READING.
- b.
Multiply the RE-30 and RE-31 monitor readings. Record the results (RIHr)2 in the space labeled READINGS PRODUCT.
- c.
Take the square root of the READINGS PRODUCT and record the result (R/Hr) in the space labeled AVERAGE READING. If only one monitor is operable, use that monitor's reading as the AVERAGE READING.
4.3.2 Containment Area Radiation Monitors Inoperable
- a.
Obtain exposure rate, R/hr, outside the equipment hatch concrete shield or personnel hatch (outside airlock). Use a portable dose rate instrument capable of measuring radiation fields up to and including IOOOR/hr.
- b.
Record the exposure rate into the space labeled EQUIPMENT or PERSONNEL HATCH READING.
4.3.3 Percent Clad and/or Core Failure Estimate
- a.
Containment Area Radiation Monitors Operable
- 1.
Obtain the 100% Gap and Core Release exposure rates, R/hr, from Figures 2 and 3. Record these values into the spaces labeled 100%
GAP RELEASE AND 100% CORE RELEASE. Use step 4.1.2 time after reactor shutdown.
- 2.
To determine the percent clad failure multiply the AVERAGE READING by 100 and divide the result by the 100% GAP RELEASE. Record the result (%) in the space labeled PERCENT CLAD FAILURE.
- 3.
To determine the percent core failure multiply the AVERAGE READING by 100 and divide the result by the 100% CORE RELEASE. Record the result (%) in the space labeled PERCENT CORE FAILURE.
00408207.DOE 03B 0530.1123 I
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14 DIABLO CANYON POWER PLANT REVISION 7A PAGE 3 OF 20 TITLE:
Core Damage Assessment Procedure UNITS 1 AND 2
- b.
Containment Area Radiation Monitors Inoperable
- 1.
Perform step 4.3.3a.1. above, recording the values in spaces F and H.
- 2.
Obtain the 100% Gap and Core Release exposure rates, R/hr, from Figures 4 or 5 for the location selected in step 4.3.2. Record these values into the spaces labeled 100% GAP RELEASE and 100%
CORE RELEASE. Use step 4.1.2 time after reactor shutdown.
- 3.
To determine the percent clad failure multiply the EQUIPMENT HATCH or PERSONNEL HATCH READING from step 4.3.2, by 100 and divide the result by the 100% GAP RELEASE. Record the result (%) in the space labeled PERCENT CLAD FAILURE (G and K).
- 4.
To determine the percent core failure multiply the EQUIPMENT or PERSONNEL HATCH READING from step 4.3.2, by 100 and divide the result by the 100% CORE RELEASE. Record the result
(%) in the space labeled PERCENT CORE FAILURE (I and M).
- 5.
If the PERCENT CLAD FAILURE is <100%, multiply F x G and enter the result in space N. If the PERCENT CLAD FAILURE is
>100%, multiply H x I and enter the result in space N.
4.4 CONTAINMENT HYDROGEN LEVELS If core failure was indicated in step 4.3, proceed to step 5.0, LONG TERM ASSESSMENT.
4.4.1 Percent Clad Failure Estimate NOTE 1: Hydrogen levels in containment are only a valid indicator of damage within the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the accident, assuming that the hydrogen recombiners are not operating. If assessment from the area radiation monitors and the H2 monitors differ, utilize data from Reactor Vessel Level Indication System (RVLIS), etc., to select the most representative assessment. If resolution cannot be obtained, use the highest estimated level of percent clad failure.
NOTE 2: Immediately notify the emergency evaluation and recovery coordinator of any increase in hydrogen reading. An increase requires the starting of the installed hydrogen recombiners in containment. If the hydrogen monitor reading exceeds 3%, evaluate using the hydrogen purge system and obtaining external recombiners. This action should be taken because internal recombiners may become an ignition source if hydrogen concentrations exceeds 4.0%.
- a.
Record containment hydrogen monitor readings, %, in the spaces labeled CEL-82 READING and CEL-83 READING.
0040S207.DOE 03B 0530.1123
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14 DIABLO CANYON POWER PLANT REVISION 7A PAGE 4 OF 20 TITLE:
Core Damage Assessment Procedure UNITS 1 AND 2
- b.
Get the monitor readings average and record the result in the space labeled AVERAGE READING. If only one monitor is operable, use that monitor's reading as the AVERAGE READING.
- 5.
LONG TERM ASSESSMENT (FORM 69-10423) 5.1 GENERAL INFORMATION Record the information requested.
5.2 EMERGENCY CORE COOLING SYSTEM (ECCS) VOLUME INJECTED 5.2.1 Reactor Coolant System (RCS) Sample
- a.
Use Table 1 to select the RCS sampling location (hot leg or cavity sump) corresponding to step 4.1.2 postulated accident.
- b.
Request an isotopic analysis of the selected RCS sample.
5.2.2 Density Correction Factor
- a.
Record the RCS TEMPERATURE, °F, in the space provided.
- b.
Use Figure 7 and the RCS TEMPERATURE to determine the DENSITY CORRECTION FACTOR. Record this value in the space provided.
5.2.3 Dilution Volume
- a.
Determine the Refueling Water Storage Tank (RWST) volume, gal, prior to the accident. Record this value in the space labeled PRIOR RWST VOLUME.
- b.
Obtain the current RWST volume, gal. Record this value in the space labeled CURRENT RWST VOLUME.
- c.
To determine the RWST volume injected, cc, subtract the CURRENT RWST VOLUME from the PRIOR RWST VOLUME and multiply the result by the CONVERSION FACTOR (3,785 cc/gal). Record this value in the space labeled INJECTED RWST VOLUME.
- d.
Determine the number of accumulators discharged. Record this number in the space labeled ACCUMULATOR QUANTITY.
- e.
To determine the accumulator volume injected multiply the number of accumulators discharged by the accumulator volume (4.28E7cc). Record the result, cc, in the space labeled INJECTED ACCUMULATOR VOLUME.
- f.
To determine the dilution volume, cc, sum the INJECTED RWST VOLUME, INJECTED ACCUMULATOR VOLUME, and the REACTOR COOLANT SYSTEM VOLUME (3.56E8 cc). Record the result in the space labeled DILUTION VOLUME.
00408207.DOE 03B 0530.1123
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14 DIABLO CANYON POWER PLANT REVISION 7A PAGE 5 OF 20 TITLE:
Core Damage Assessment Procedure UNITS 1 AND 2 5.3 LIQUID INVENTORY
- a.
Obtain the selected RCS sample analysis results (step 5.2.1) for the specified isotopes (off gases must be included). Record the sample activity concentration, uCi/cc, in the spaces labeled SAMPLE ACTIVITY CONCENTRATION.
- b.
Record the DENSITY CORRECTION FACTOR (step 5.2.2) and the DILUTION VOLUME (step 5.2.3) into the spaces provided.
- c.
To determine the liquid inventory, Ci, multiply the SAMPLE ACTIVITY CONCENTRATION, DENSITY CORRECTION FACTOR, DILUTION VOLUME, and the CONVERSION FACTOR (1E-6 Ci/uCi). Record the result in the space labeled LIQUID INVENTORY.
5.4 PRESSURE AND TEMPERATURE CORRECTION FACTOR 5.4.1 Containment Atmosphere Sample
- a.
Use Table 1 to select the containment atmosphere sampling location corresponding to step 4.1.2 postulated accident.
- b.
Request an isotopic analysis of the selected sample.
5.4.2 Pressure and Temperature Correction Factor
- a.
Record the containment atmosphere pressure, psig, and temperature,°R, in the spaces labeled CONTAINMENT ATMOSPHERE PRESSURE and CONTAINMENT ATMOSPHERE TEMPERATURE (psia = psig + 14.7, and R = OF + 460).
- b.
Record the containment atmosphere sample pressure, psia, and temperature, OR, in the spaces labeled SAMPLE PRESSURE and SAMPLE TEMPERATURE (psia = psig + 14.7, and °R = °F + 460).
- c.
Divide the CONTAINMENT ATMOSPHERE PRESSURE by the SAMPLE PRESSURE. Record the result in the space labeled PRESSURE RATIO.
- d.
Divide the SAMPLE TEMPERATURE by the CONTAINMENT ATMOSPHERE TEMPERATURE. Record the result in the space labeled TEMPERATURE RATIO.
- e.
To determine the pressure and temperature correction factor multiply the PRESSURE RATIO and the TEMPERATURE RATIO. Record the result in the space labeled PRESSURE TEMPERATURE CORRECTION FACTOR.
00408207.DOE 03B 0530.1123
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14 DIABLO CANYON POWER PLANT REVISION 7A PAGE 6 OF 20 TITLE:
Core Damage Assessment Procedure UNITS 1 AND 2 5.5 GASEOUS INVENTORY
- a.
Obtain the selected containment atmospheric sample analysis result (step 5.4.1) for the specified isotopes. Record the activity concentration, uCi/cc, in the spaces labeled SAMPLE ACTIVITY CONCENTRATION.
- b.
Record the PRESSURE TEMPERATURE CORRECTION FACTOR (step 5.4.2) into the space provided.
- c.
To determine the gaseous inventory, Ci, multiply the SAMPLE ACTIVITY CONCENTRATION, PRESSURE TEMPERATURE CORRECTION FACTOR, CONTAINMENT VOLUME (7.36E10 cc),
and the CONVERSION FACTOR (IE-6 Ci/uCi). Record the result in the space labeled GASEOUS INVENTORY.
5.6 INVENTORY CORRECTION - CONSTANT POWER HISTORY This section is to be used when the power level has remained relatively constant (within X 10 percent) for 30 days prior to reactor shutdown. If the power level has not been relatively constant, proceed to section 5.7.
5.6.1 Power Level
- a.
Determine the average power level (%) for the 4 days prior to reactor shutdown. Record this value into the space labeled POWER LEVEL,.
- b.
Determine the average power level (%) for the 30 days prior to reactor shutdown. Record this value into the space labeled POWER LEVEL2.
- c.
Determine the operation time (days) since the previous reactor shutdown.
Record this value into the space labeled OPERATION TIME.
- d.
Determine the average power level (%) for the operation time. Record this value into the space labeled AVERAGE POWER LEVEL.
5.6.2 Power Correction Factor
- a.
Divide the POWER LEVELI (step 5.6.1) by 100 and record the result in the space labeled POWER CORRECTION FACTOR,.
- b.
Divide the POWER LEVEL2 (step 5.6.1) by 100 and record the result in the space labeled POWER CORRECTION FACTOR2.
- c.
Obtain the Cs-134 power correction factor from Figure 8. Use step 5.6.1 operation time and average power level. Record the obtained value into the space labeled Cs-134 POWER CORRECTION FACTOR.
5.6.3 Corrected Inventory - Gap
- a.
To determine the gap corrected inventory multiply the GAP EQUILIBRIUM INVENTORY by the applicable POWER CORRECTION FACTOR (FACTOR,, FACTOR2, OR Cs-134).
00408207.DOE 03B 0530.1123
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14 DIABLO CANYON POWER PLANT REVISION 7A PAGE 7 OF 20 TITLE:
Core Damage Assessment Procedure UNITS 1 AND 2
- b.
Record the results, Ci, into the space labeled GAP CORRECTED INVENTORY.
5.6.4 Corrected Inventory - Core
- a.
To determine the core corrected inventory multiply the CORE EQUILIBRIUM INVENTORY by the applicable POWER CORRECTION FACTOR (FACTOR,, FACTOR2, or Cs-134).
- b.
Record the results, Ci, into the spaces labeled CORE CORRECTED INVENTORY.
5.7 INVENTORY CORRECTION FOR VARIABLE POWER HISTORY When the power level has not remained relatively constant for 30 days prior to reactor shutdown, the effects of power changes must be taken into account.
5.7.1 Power Level
- a.
Determine the operation time (days) since the previous reactor shutdown.
Record this value into the space labeled OPERATION TIME.
- b.
Determine the average power level (%) for the operation time. Record this value into the space labeled AVERAGE POWER LEVEL.
5.7.2 Power Correction Factor
- a.
Obtain the Cs-134 power correction factor from Figure 8. Use step 5.7.1 operation time and average power level. Record the obtained value into the space labeled Cs-134 POWER CORRECTION FACTOR.
00408207.DOE 03B 0530.1123
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS TITLE:
Core Damage Assessment Procedure EP RB-14 7A 8 OF 20 1 AND 2
- b.
Use the following equation to determine the power correction factor for other isotopes.
=
j P(1 - eAt,j)e-It2J Eq. I RP 5.7.3
5.7.4 Where
PFi = 30 day Power Correction Factor for nuclide i, Pj = average power level (Mwt) for time tlj, RP = rated power level of the core (Mwt),
RP = 3411 Mwt Unit RP = 3411 Mwt Unit 2
,=
decay constant (days') nuclide i, t,j= time (days) where power does not vary more than +10%, and t2j = time (days) from end of t]j to 30-days.
Gap Corrected Inventory
- a.
To determine the gap corrected inventory multiply the GAP EQUILIBRIUM INVENTORY by the applicable POWER CORRECTION FACTOR (step 5.7.2).
- b.
Record the results, Ci, into the spaces labeled GAP CORRECTED INVENTORY.
Core Corrected Inventorv
- a.
To determine the core corrected inventory multiply the CORE EQUILIBRIUM INVENTORY by the applicable POWER CORRECTION FACTOR (step 5.7.2).
- b.
Record the results, Ci, into the spaces labeled CORE CORRECTED INVENTORY.
00408207.DOE 03B 0530.1123
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14 DLABLO CANYON POWER PLANT REVISION 7A PAGE 9 OF 20 TITLE:
Core Damage Assessment Procedure UNITS I AND 2 5.7.5 Power Correction Factor Sample Calculation:
Unit 1 has operated for the 30 days prior to reactor shutdown with the following power history:
100 Mwt for 10 days 70 Mwt for 5 days 0 Mwt for 7 days 70 Mwt for 8 days 100 70 Power
- Level, Mwt 0
0 10 15 22 30 Time, days Unit I rated power level =3411 Mwt Period I PI = 100 Mwt, t = 10 days, t2 = 20 days Period 2 P 2= 70 Mwt,t2 5 days, t22= 15 days Period 3 P 3 = 0.0 Mwt, t3 7 days, t23 8 days Period 4 P4 = 70 Mwt, t 4 = 8 days, t24 =0 days The equation for Nuclide i would be:
PF, = ([ 100 (I -e i
))e-'i (20)1
+ [ 70 (I-ei (5)ei (151
+ [0.0 (I-esi ( 7 )e4i (
+ [ 70 (-e"i (8 )de i ())
+ 3411 00408207.DOE 03B 0530.1123
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14 DIABLO CANYON POWER PLANT REVISION 7A PAGE 10 OF 20 TIlLE:
Core Damage Assessment Procedure UNITS 1 AND 2 5.8 RELEASE PERCENT, IODINE RATIO, AND NOBLE GAS RATIO 5.8.1 Gap Released Percent
- a.
Obtain the LIQUID INVENTORY, Ci, from step 5.3 and record into the spaces provided.
- b.
Obtain the GASEOUS INVENTORY, Ci, from step 5.5 and record into the spaces provided.
- c.
Add the LIQUID INVENTORY and the GASEOUS INVENTORY.
Record the result into the space labeled RELEASED INVENTORY.
- d.
Obtain the CORRECTED INVENTORY from step 5.6.3 or 5.7.3 and record into the spaces provided.
- e.
To determine the release percent divide the RELEASED INVENTORY by the CORRECTED INVENTORY and multiply the result by 100.
Record this value into the spaces labeled RELEASE PERCENT.
5.8.2 Core Release Percent
- a.
Obtain the LIQUID INVENTORY, Ci, from step 5.3 and record into the spaces provided.
- b.
Obtain the GASEOUS INVENTORY, Ci, from step 5.5 and record into the spaces provided.
- c.
Add the LIQUID INVENTORY and the GASEOUS INVENTORY.
Record the result into the space labeled RELEASED INVENTORY.
- d.
Obtain the CORRECTED INVENTORY from step 5.6.4 or 5.7.4 and record into the spaces provided.
- e.
To determine the release percent divide the RELEASED INVENTORY by the CORRECTED INVENTORY and multiply the result by 100.
Record this value into the spaces labeled RELEASE PERCENT.
5.8.3 Iodine Ratio
- a.
Obtain the I-133 and 1-131 RELEASED INVENTORY from step 5.8.1.
Record these values, Ci, into the spaces provided.
- b.
To determine the iodine ratio divide the I-133 RELEASED INVENTORY by the 1-131 RELEASED INVENTORY. Record the result into the space labeled IODINE RATIO.
5.8.4 Noble Gas Ratio
- a.
Obtain the Kr-87 and Xe-133 RELEASED INVENTORY from step 5.8.1. Record these values, Ci, into the spaces provided.
- b.
To determine the noble gas ratio divide the Kr-87 RELEASED INVENTORY by the Xe-133 RELEASED INVENTORY. Record the result into the space labeled NOBLE GAS RATIO.
00408207.DOE 03B 0530.1123
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14 DIABLO CANYON POWER PLANT REVISION 7A PAGE 11 OF 20 TITLE:
Core Damage Assessment Procedure UNITS 1 AND 2
5.9 ASSESSMENT
WORKSHEET 5.9.1 Assessment Worksheet
- a.
Obtain the RELEASE PERCENT (step 5.8.land 5.8.2) for the specified isotopes and mark the applicable Assessment Worksheet box.
- b.
Obtain the IODINE and NOBLE GAS RATIOS (step 5.8.3 and 5.8.4) and mark the applicable Assessment Worksheet box.
- c.
Determine damage category base on mark distribution on the Assessment Worksheet.
- 6.
REFERENCES 6.1 Westinghouse Owners Post Accident Core Damage Assessment Methodology.
6.2 PG&E Calculation PAM-0-07-065, Rev. 2, 2/22/97 "Core Exit Temperature Indication Uncertainty".
6.3 PG&E Calculation PAM-0-07-403, "RCS Wide Range Pressure Indication Uncertainty".
- 7.
APPENDICES 7.1 Table I Recommended Sample Locations 7.2 Figure I Saturation Curve 7.3 Figure 2 Post LOCA Exposure Rate Inside Containment From Noble Gases (RE-30 and RE-3 1) - Gap Release 7.4 Figure 3 Post LOCA Exposure Rate Inside Containment From Noble Gases (RE-30 and RE-3 1) - Core Release 7.5 Figure 4 Post LOCA Exposure Rate Outside of Equipment Hatch From Noble Gases -
Gap and Core Release 7.6 Figure 5 Post LOCA Exposure Rate Outside of Personnel Hatch From Noble Gases -
Gap and Core Release 7.7 Figure 6 Percent H2 in Containment vs Percent Clad Failure 7.8 Figure 7 Density Correction Factor 7.9 Figure 8 Power Correction Factor for Cs-134
- 8.
ATTACHMENTS 8.1 Form 69-10422, "Preliminary Assessment," 05/30/03 8.2 "Long Term Assessment," 09/19/01 8.3 "Initial Detection of Potential Core Damage," 09/19/01
- 9.
SPONSOR Alex Taylor 00408207.DOE 03B 0530.1123
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS TITLE:
Core Damage Assessment Procedure EP RB-14 7A 12 OF 20 1 AND 2 Postulated Accident Small break LOCA Reactor Power> 1%
Reactor Power < 1%
Large break LOCA Reactor Power> 1%
Reactor Power < 1%
Steam Line break Steam Generator tube rupture Indication of significant Containment Sump Inventory Containment building Radiation Monitor Alarm Safety injection actuated Indication of High Radiation Level in RCS APPENDIX 7.1 TABLE I Recommended Sample Locations Sampling Locations RC Hot Log 1 or 4 (LSP)
Containment air (CASP)
RC Hot Leg I or 4 (LSP)
Reactor Cavity Sump (LSP)
Containment air (CASP)
RC Hot Leg 1 or 4 Reactor Cavity Sump (LSP)
Containment air (CASP)
RC Hot Leg 1 or 4 (LSP)
Containment air (CASP)
RC Hot Leg 1 or 4 (LSP)
Containment air (CASP)
Reactor Cavity Sump (LSP)
Containment air (CASP)
Reactor Cavity Sump (LSP)
Containment air (CASP)
RC Hot Leg 1 or 4 (LSP)
RC Hot Leg I or 4 (LSP) 00408207.DOE 03B 0530.1123
PACIFIC GAS AND ELECTRIC COMPANY DL4BLO CANYON POWER PLANT TITLE:
Core Damage Assessment Procedure NUMBER REVISION PAGE UNITS APPENDIX 7.2 FIGURE 1 SATURATION CURVE 300 400 500 600 700 CORE EXIT THERMOCOUPLE TEMPERATURE, OF 00408207.DOE 03B 0530.1123 EP RB-14 7A 13 OF 20 1 AND 2 2600 2400 2200 2000 1800 fe cc:
cc w
LU a
e 0
0 cc, 1600 1400 1200 1000 800 ACCEPTABLE AREA SATURATION CURVE CORRECTED FOR INSTRUMENT ERROR PUNACCEPTABLE AREA I-f PRESSURE ERROR
+/- 65 psig TEMPERATURE ERROR +/- 24°f J-IlIl 600 400 200 200
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Core Damage Assessment Procedure NUMBER REVISION PAGE UNITS APPENDIX 7.3 FIGURE 2 POST LOCA EXPOSURE RATE INSIDE CONTAINMENT FROM NOBLE GASES (RE-30 AND RE-3 1) - GAP RELEASE Gap Release I 0
=
I.OUE*03 I.OOE-C2 R/Hr 1.0OC-.S 1.0E-40 I.00-0t 00408207.DOE 03B 0530.1123 EP RB-14 7A 14 OF 20 1 AND 2 0.5 12 24 48 72 Time Ufter Shutdown, Hours 168
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Core Damage Assessment Procedure NUMBER REVISION PAGE UNITS APPENDIX 7.4 FIGURE 3 POST LOCA EXPOSURE RATE INSIDE CONTAINMENT FROM NOBLE GASES (RE-30 AND RE-31) - CORE RELEASE Core Retease 5
2 I--04 i.uar
+ss
- I A O C.0 I
T__
I I__
I/Hr l.O-03 1.Ot-02 1.o0E-e1 6
12 24 49 72 163 Time filter Shutdown. Hours 00408207.DOE 03B 0530.1123 EP RB-14 7A 15 OF 20 1 AND 2
PACIFC GAS AND ELECTRIC COMPANY DLBLO CANYON POWER PLANT TITLE:
Core Damage Assessment Procedure NUMBER REVISION PAGE UNITS APPENDIX 7.5 FIGURE 4 POST LOCA EXPOSURE RATE OUTSIDE OF EQUIPMENT HATCH FROM NOBLE GASES -
GAP AND CORE RELEASE Gap Core Release-_Releose 1 -
a 6
A 1"
1% 10 IAGEZ E.DGED1
.DOM 1.DC-01 lAE-02 R/Hr 1.6GE-63 IADE-04 IOE-OS IDGE-06 1.DOE-U?
IOGE-08 2
a___
2B
2I.
I 2
0 I
I 2
L C
____t I
2*
j I
I 2
1 OS 6
12 Time After Shutdown, Nours 24 48 00408204.3Bb 1811 00408207.DOE 03B 0530.1123 EP RB-14 7A 16 OF 20 1 AND 2 D.
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Core Damage Assessment Procedure NUMBER REVISION PAGE UNITS APPENDIX 7.6 FIGURE 5 POST LOCA EXPOSURE RATE OUTSIDE OF PERSONNEL HATCH FROM NOBLE GASES -
GAP AND CORE RELEASE Gap Release-Core Release L
e-v J1 1%
0% 100% 1%
10% I0o%
1.OOE+04 1.SOE.03 1.OOE+02 1.0.O1E+
1.0OE[00 R/Hr 1.OOE-01 I.OOE-02 1.OOE-03 1.OOE-04 1.OOE-05 1.0 QE-06 163 00408207.DOE 03B 0530.1123 EP RB-14 7A 17 OF 20 1 AND 2 0.5 6
12 24 48 72 Time Rtter Shutdown, Hours
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS TITLE:
Core Damage Assessment Procedure EP RB-14 7A 18 OF 20 1 AND 2 APPENDIX 7.7 FIGURE 6 PERCENT H2 IN CONTAINMENT VERSUS PERCENT CLAD FAILURE 16 15 14 13 12 2
11 w£ Z
le 91 2 9 8
v 2e 7
6 5
4 3
2 1
I H-e
-50%
50-100%
% CLAD FAILURE 00408207.DOE 03B 0530.1123 I
1 l r
__ _ _ 7-~~~~
_~~
/W
.~
I t
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Core Damage Assessment Procedure NUMBER REVISION PAGE UNITS APPENDIX 7.8 FIGURE 7 DENSITY CORRECTION FACTOR 700 600 500 ILC er cc2 400 LU 300 200 100 0
a 025 0.50 0.75 1.
DENSITY CORRECTION FACTOR 00408207.DOE 03B 0530.1123 EP RB-14 7A 19 OF 20 1 AND 2
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS TITLE:
Core Damage Assessment Procedure EP RB-14 7A 20 OF 20 1 AND 2 APPENDIX 7.9 FIGURE 8 POWER CORRECTION FACTOR FOR CS-134 100 200 300 400 600 600 700 g00 900 OPERATION TIME, DAYS 00408207.DOE 03B 0530.] 123 I
UDs POWER
-=5% POWER
-I0%
POWER 1.00 z0 t;
.80
.20 O.D 0.0
69-10422 05/30/03 DIAI3LO CANYON POWER PLANT EP RB-14 ATTACHMENT 8.1 A2 TITLE:
Preliminary Assessment I PART 4.1 GENERAL INFORMATION I
4.1.1 Date Time Unit Calculation #
Completed By 4.1.2 Time After Reactor Shutdown Hr Postulated Accident Table 1 I PART 4.2 INADEQUATE CORE COOLING 4.2.1 INDICATION OF CONDITIONS
- a.
Are five or more Core Exit Thermocouples (CETC) temperatures greater than 1,200°F?
- b.
Can Safety Injection (SI) and/or charging flow to the Reactor Coolant System (RCS) be verified?
- c.
Can Auxiliary Feed Water (AFW) flow to the steam generators and Component Cooling Water (CCW) and Auxiliary Salt Water (ASW) flow be verified?
- d.
Are RCS pressure and CETC temperature (T hottest) within the "Acceptable Area" of subcooling as determined by using Figure 1 ?
- e.
Are containment area radiation monitor (RE-30 or RE-31) reading greater than I R/hr?
f.
9 h.
Is containment pressure greater than 1.3 psig?
Is containment temperature greater than 120°F?
Is containment hydrogen level as indicated by monitors CEL-82 or CEL-83 up scale?
Yes I
No
[I
[ ]
[ I
[ 1 I I 4.2.2 EVALUATION OF CONDITIONS If any of the boxes (as opposed to line spaces) in step 4.2.1 were checked, proceed to section 4.3.
00408207.DOE 03B 0530.1123 Page of 3 I
I I
69-10422 05/30/03 EP RB-14 (UNITS 1 AND 2)
ATTACHMENT 8.1 TITLE:
Preliminary Assessment I PART 4.3 CONTAINMENT RADIATION LEVELS 4.3.1 CONTAINMENT AREA RADIATION MONITORS OPERABLE A
RE-30 READING B
RE-31 READING C
READINGS PRODUCT D
AVERAGE READING*
R/hr R/hr (R/hr)2 R/hr A&B SQRT (C)
OR 4.3.2 CONTAINMENT AREA RADIATION MONITOR INOPERABLE E
Equipment Hatch Reading*
R/hr OR E
Personnel Hatch Reading*
R/hr
- Use portable ionization chamber.
4.3.3 PERCENT CLAD ANDIOR CORE FAILURE ESTIMATE 4.3.3.a Containment Area Radiation Monitors Operable G
Percent Clad Failure DJF x 100 K if Monitors inoperable H
100% Core Release*
Percent Core Failure R/hr Figure 3 DIH x 100 M if monitors inoperable OR 4.3.3.b Containment Area Radiation Monitors Inoperable K
Percent Clad Failure L
100% Core Release*
M Percent Core Failure R/hr Figure 4 or 5 EIJ x 100 N
Equivalent RE-30131 Reading 00408207.DOE 03B 0530.1123 R/hr Figure 4 or 5 F
100% Gap Release*
R/hr Figure 2 OR J
100% Gap Release*
EIL x 100 FXG OR Hxl
- Step 4.1.2 Time After Reactor Shutdown Page 2 of 3 I
I I
I I
EP RB-14 (UNITS 1 AND 2)
ATTACHMENT 8.1 TITLE:
Preliminary Assessment PART 4A CONTAINMENT HYDROGEN LEVEL If Core Failure was indicated in step 4.3, proceed to step 5.1.
4.4.1 PERCENT CLAD FAILURE ESTIMATE A
B C
D CEL-82 CEL83 AVERAGE*
PERCENT READING READING READING CLAD FAILURE (A + B)12 Figure 6
- Use the operable monitor reading as the Average Reading if only one monitor is operable 00408207.DOE 03B 0530.1123 69-10422 05/30/03 Page 3 of 3
09/19/01 DIABLO CANYON POWER PLANT EP RB-14 ATTACHMENT 8.2 Page 1 of8 PN2 TITLE:
Long Term Assessment rarpnfk Orn mrd Ebrtrk CciM,a 11.6g-lnm ahsesiJe4t off u Diablo Canyon Power Plant Unit Nos. I and 2 m1040 4M Page 1 of 8 IPART 5.1 GENERAL INFORMATION 5.1.1 Date -
I Time Unit Calcutation #_
5.12 TimeAfterReaciorShutdown Hr Postulated Accident
_r Table I I PART 5.2 EMERGENCY CORE COOLING SYSTEM (ECCS) VOLUME INJECTED 5.21 REACTOR COOLANT SYSTEM RCS) SAMPLE' Check One: Hot Leg I Hot Leg 4 Reactor Cavity Stxnp Lke Sabb and Step 4.12 postrlted a ccdet V eleCt sWmo*g Abcalkn 5.2.2 DENSITY CORRECTION FACTOR Dens RCS Temperature 5.2.3 DILUTION VOLUME Prior RWST Current RWST Volume Volume
[
gal gal x
Accumulator Quantity Accumlators Injected x 4.28E7 cc Converslon Factor 3,785 cc/gal Ity CorrecUon Factor Figufre 7 A
Injected RWST Volume cc Injected Accumulator Volume cc C
RCS Volume 3.56 EB cc Dilution Volume =
cc A
c 00408207.DOE 03B 0530.1123
EP RB-14 (UNITS 1 AND 2)
ATTACHMENT 8.2 TITLE:
Long Term Assessment Page 2 o 8 PART 5.3 UUID INVENTORY A
Sample AcUvity 8
Density Correctlon C
Isotope Concentration^
Factor DllutlonVolume Kr-87 PciCc Xe-133
-sCUcc 1-131 iLcC 1-133 p1cvcc
-cc 5.22
.2.3 Te-132 Cicc Ba-140 11Ci/cc La-140 PC/CC Cs-134 p011cc hlckdes Off Gases.
PART 5.4 PRESSURE AND TEMPERATURE CORRECTION FACTOR 5.4.1 CONTAINMENT ATMOSPHERE SAMPLE*
Check One:
Containment Air Other
- VsA Table I and Step 4.12 poskiated accknt to select mphg bcatioxn 5.4.2 PRESSURE AND TEMPERATURE CORRECTION FACTOR F
Contalnment Atmosphere Pressure psia P&Ssg 14.?
J Pressure Ratio Fl G
Sample Pressure psba psi + 14.7 K
Temperature Ratio Nll H
Sample Temperature
~.4
'R
'F+
0 Converslon Factor iE-6 CI,LOI E
Uquld Inventory
~~ci A x x Cx ci A x IMx C x a Ax#xCxD O C Ax Ix Cx iCi A x x C x Ci
~~ci A x x C x I C A x x C x ci A C I
Containment Atmosphere Temperature
'R
'F + 4 L
Pressure Temperature Correction Factor Jx PART 5.5 GASEOUS INVENTORY At Sample Activity Concentration pCi/cc p~ICi/cc
~~pci/cc p1CVcc pCi/cc N
Pressure Temperature Correction Factor 54.2 L 0
Contalnment Volume 7.36E10 cc p
a Converslon Gaseous Factor Inventory H xNix O x tci Hx Nx Ox P IE6 Ci/jlCi mfxNxox7 Ci Hx Nwx O-x7 t
00408207.DOE 03B 0530.1123 Isotope Kr-87 Xe-133 t-131 1-133 09tl9/01
-Page 2 of 8
Page 3 of 8 EP RB-14 (UNITS I AND 2)
ATTACHMENT 8.2 TITLE:
Long Term Assessment Page 3 of 8 IPART 5.6 INVENTORY CORRECTION-CONSTANT POWER HISTORY l 5.6.1 POWER LEVEL" B
C Power Correctlon
- Factor, Operation Time days a
Power Correctlon
- Factor, Average Power Level operation r E
Cs-134 Power Correctlon Factor' Al 100 Use stop 5.6.1 &"rage power kve and cpwatIanS ne.
5.6.3 CORRECTED INVENTORY-GAP Isotope Kr-87 1-133 Xe-133 1-131 5.6.4 CORRECTED INVENTORY-CORE Isotope Kr-87 1-133 Xe-133 Te-132 Ba-140 La-140 1-131 Cs-134
- /1W F
Gap Equilibrium Inventory 3.9E4 Ci 5.1E5Ci 1.3E6 Cl 8.0E5 Cl Core Equilibrium Inventory 5.9E7Ci 1.9E8 Ci 1.9E8 C 1.4E8 Ci 1.8E8Ci 1.BEB CI 9.7E7 Ci 3.1E6 Cl 00408207.DOE 03B 0530.1123 A
Power Level Power Level2 Fhor 4 days ftir 30 days Por bwl mibh+/-h 1O% onvfsa proceed to Ste S.r.
5.6.2 POWER CORRECTION FACTOR Fiure 8 C
Gap Corrected Inventory x f ci C x ci CsF ci x
I Core Corrected Inventory ci Cs N Ci x N
~~~~
ci DxN
~~~~
Ci Ox Os x N Ci Ex N 09tl9/01
09/19/01 Page 4 of 8 EP RB-14(IJNITS 1 AND 2)
ATTACHMENT 8.2 TITLE:
Long Term Assessment Pag3 4 of 8 PART 5.7 NVENTORY CORRECTION-VARIABLE POWER HISTORY 5.7.1 POWER LEVEL Operation Time Average Power Level days Opatbn nk, 5.7.2 POWER CORRECTION FACTOR Cs-134 Power Correction Factor' Fgur 8 lUse the folowing equation to determine the power correction factor for other Isotopes.
PF, _ lPi (1-e-I tI)e it;2j RP Where:
PF 30 day Power Correction Factor for nuclide 1.
Pj average power level (Mwt) for periodt1J, X
decay constant (days -1) for nuclide 1.
tt time (days) where power does not vary more than
- 10% from Pi.
t2i time (days) rom end of period tj to tine of reactor shutdown.
RP rated power level of the core (Mwt).
I(&e Steo 5.7. oepera6m tnm and average power leel 0040S207.DOE 03B 0530.1123
EP RB-14 (UNITS 1 AND 2)
ATTACHIMENT 8.2 TITLE:
Long Term Assessment Page 5 of 8 Isotope A
B days days days-
.days days days days C
t2i days 30 -5 days days 30 -0 days 30.5 rdays
~days 30 -8 B
AxB AxJ lxi
_ x -
A x E
xt2j x
A x C A x C A x C A x C A x C H
e_~ 2i
-ww17-I PI*
Mwt
~Mwl
_ Mwt Mwt
~Mwt
_ Mwt J
Correcgon Factor x N x X N I 6 x x I x N x 6 x xI Correction Factor, =
Power vel orperbd j.
Correction Factor Rated Power Level*
Power CorrecUon Factor l-
_ _M w t =
'Use 3338 Mwt for Uht or 341 or l 2 00408207.DOE 03B 0530.1123 F
e4 ' t 11RTD G
I - r 1-f
-F 091101 Page 5 of 8
E,P RB-14 (UNITS I AND 2)
ATTACHMENT 8.2 TIT'LE:
Long Tenn Assessment Page 6 of 8 5.7.3 CORRECTED INVENTORY-GAP Decay Constant 1.31E 1 days' 1.3E-1 days' 8.62E-2 days' 8.0OE-1 days-'
5.7.4 CORRECTED INVENTORY-CORE Decay Constant 1.31E 1 days' 1.3E-1 days-'
2.13E-1 days-'
5.42E-2 days-'
4.1E-1 days' 8.62E-2 days-'
8.OOE-1 days-'
9.24E-4 days-'
00408207.DOE 03B 0530.1123 Isotope KrZ7 Xe-133 1-131 1-133 A
Power Correction Factor 5.72 5.72 5.72 5.72 B
Gap Equillbrium Inventory 3.9E4 Cl 1.3E6 Ci 8.0E5 Ci 5.1E5 Ci C
Gap Corrected Inventory ci A x CI
~Ci x
ci A x Isotope Kr-87 Xe-133 Te-132 Ba-140 La-140 1-131 1-133 Cs-134 0
Power Correction Factor 5.72 5.72 5.72 5.72 5.72 5.72 5.72 5.72 E
Core Equilibrlum Inventory 5.9E7 Ci 1.9E8 Ci 1.4E8 1.8E8 Ci 1.8EB Ci 9.7E7 Ci 1.9E8 Ci 3.1E6 Ci F
Core Corrected Inventory ci x
ci x E
~ci x E ci x E ci x
ci x E ci x E ci x F 09119/01 Page 6 of 8
Page 7 of 8 EP RB-14 (UNITS I AND 2)
A1TACHMENT 8.2 TITLE:
Long Tenn Assessment Page 7 o 8 PART 5.8 RELEASE PERCENT, IODINE RATIO, AND NOBLE GAS RATIO 5.8.1 GAP RELEASE PERCENT A
Uquld Isotope Inventory Kr-87 Cli 5.3 Xe-133 Ci 5.3 1-131 Ci S3 1-133 Ci 5.3 5.8.2 CORE RELEASE PERCENT A
Uqutd Isotope Inventory Kr-67 Ci 53 Xe-133 ci 5.3 1-131 Ci 5.3 1-133 Ci 5.3 Te-132 Ci 5.3 Ba-140 Ci 5.3 La-140 Ci 53 Cs-134 Ci 5.3 S.&3 IODINE RATIO F
1133 Released Inventory Ci 5.8.1C 5.8.4 NOBLE GAS RATIO H
Kr-87 Released Inventory Ci 5.81C B
Gaseous Inventory
~~ci 5.5 Ci 5.5 CI 5.5 I
Gaseous Inventory Ci 5.5 Ci 5.5 cI 5.5 5.5 ci 5.5 ci 5.S Ci 5.5 5.5 C
Released Inventory ci A +
c A.US Ci Released Inventory Ci Ci Cl A
Cl A,,5 ci
+
.,a Ci
~~ci at,,
1-131 0
Corrected Inventory Ci 5.6.305.7.3 ci 5..3 or&57.3 ci 5.6.3or S.73 Ci S.fi3or57.3 Corrected Inventory Ci-5.6.4 or 5.7.4 ci 5.f64or5.7.4 ci
.6.4 or &7.4 ci 5.6.4 or5.7.4 Ca 5.6.4 or 7.4 C
5.6.4 or 7.4 ci 5.6 o 5.4Z Cl 5.6.4orf7.4 Released Inventory Ci 5.6.1 C I
Xe-133 Released Inventory 5.. Ic 00408207.DOE 03B 0530.1123 E
Release Percent CRles M E
Release Percent C/oX 100 Clix 105 Clix 100 Clx 100 Clix 100 Cls 10X C igx 150 Iodine Ratio F. S Noble Gas Ratio N. I 09/19/01
EP RB-14 (UNITS I AND 2)
ATTACHMENT 8.2 TITLE:
Long Term Assessment Page 8 of 8 PART
5.9 ASSESSMENT
WORKSHEET 5.
9.1 ASSESSMENT
WORKSHEET Clad Failure*
Core Failure*
Overheat Melt Isotope 0.12 -10%
10-80 0.12-10%
10-5%
lSO%
0.12-10% 10*
C Kr-87 Xe-133 1-131 1-133 1-133 <.64
.64 < 1-133 < 1.94 11332 1.94 lodlne RatIo"*
1-131 1-131 1-131 Noble Gas Kr-87
<.03
.03 < Kr-87 c.31 Kr-87
>.31 Ratio" Xe-133 Xe-133 Xe-133 Percent Clad Failure:
Percent Core Failure:
Cs-134 Te.132]
I i I I I I Ba-140 La-140
- $eps 6. 1 and.8.2 Release Percent Steps 5.8.3 and 5.8.4 driAe nd Noble Gas Ratios 00408207.DOE 03B 0530.1123 09/19/01 Page 8 of 8
09/19/01 DIABLO CANYON POWER PLANT EP RB-14 ATTACHMENT 8.3 TlTLE:
Initial Detection of Potential Core Damage Page I of 1 12 Measure and record the radiation level one (1) foot from the center of line S1-26-2111P. A radiation level equal to or greater than 15 R/hr indicates core damage at the Alert emergency action level.
00408207.DOE 03B 0530.1123
ISSUED FOR USE BY:
DATE:
EXPIRES:____
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-3 NUCLEAR POWER GENERATION REVISION 23 DIABLO CANYON POWER PLANT PAGE 1 OF 4 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE:
Activation and Operation of the Emergency Operations AND Facility 1
2 05/23/03 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1.
SCOPE The scope of this procedure is to provide the Emergency Operations Facility (EOF) staff with checklists to be used as guidance for performing their assigned emergency response positions.
- 2.
RESPONSIBILITIES 2.1 Recovery Manager (RM) is responsible for:
2.1.1 The overall command and control of the emergency response effort, 2.1.2 Developing and approving Protective Action Recommendations (PARs),
2.1.3 Authorizing emergency worker exposures, 2.1.4 Recommending the issuance of potassium iodide (KI) to emergency workers, 2.1.5 Approving news releases, 2.1.6 Developing an accident recovery action plan, 2.1.7 Notifying/updating county, state and NRC on Emergency Action Levels (EALs) and PARs.
2.1.8 Modifying the Emergency Response Organization (ERO), based upon the specific needs for PG&E to mitigate the accident or response to the emergency.
2.2 Advisor to the County is responsible for:
2.2.1 Initial staffing and setup of the EOF, 2.2.2 Assisting the recovery manager, 2.2.3 Managing the EOF staff until the recovery manager arnives, 2.2.4 Interfacing between EOF and San Luis Obispo (SLO) County Sheriffs Watch Command and/or command staff.
2.3 Engineering Liaison is responsible for:
2.3.1 Providing and interpreting technical information on plant systems for the recovery manager.
2.3.2 Interfacing with the Technical Support Center (TSC) engineering advisor.
2.4 Agency Liaison is responsible for:
2.4.1 Generating emergency notifications.
2.4.2 Transmitting emergency notifications.
2.4.3 Facilitating the co-location of NRC representatives upon arrival with their EOF staff counterparts.
01323623.doa 03B 0522.0333
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-3 DIABLO CANYON POWER PLANT REVISION 23 PAGE 2 OF 4 TITLE:
Activation and Operation of the Emergency Operations UNITS 1 AND 2 Facility 2.5 Liaison Assistant 2.5.1 Perform emergency notifications to the county, state, and NRC.
2.6 Radiological Manager is responsible for:
2.6.1 The overall management and coordination of PG&E Unified Dose Assessment Center (UDAC) staff members with other personnel within the UDAC.
2.6.2 The radiation protection of the off-site PG&E emergency workers, 2.6.3 Coordinating field monitoring activities with the UDAC coordinator, 2.6.4 Reviewing dose calculations and field monitoring survey resuls with the UDAC Coordinator, 2.6.5 Briefing the recovery manager on UDAC PARs, 2.6.6 Making recommendations to the recovery manager on issuing KI and exceeding dose limits for emergency workers, 2.6.7 Formulating PARs with the UDAC coordinator and other UDAC staff based on dose projections, meteorological conditions, or field monitoring data, 2.6.8 Periodically conducting UDAC staff meetings on emergency status, or whenever a significant change of event occurs.
2.7 Emergency Supervising Engineer(ESE) is responsible for:
2.7.1 Directing field sampling activities and locations, 2.7.2 Communicating information between the radiological monitoring director, meteorologist, health physicist, and the radiological manager, 2.7.3 Coordinating dose assessment and monitoring activities, 2.7.4 Trending Radiation Monitor System (RMS),
2.7.5 Formulating PARs based on information received from EARS, TSC radiological advisor and field monitoring teams, 2.7.6 Keeping the radiological monitoring director informed of plant changes that would impact field team activities.
2.8 Radiological Monitoring Director is responsible for:
2.8.1 Communicating information between the UDAC staff and the FMTs, FMT runner, and the Off-site Environmental Laboratory (OEL),
2.8.2 Tracking and recording field data, 2.8.3 Converting FMTs and FMT Runner dosimeter readings to TEDE, 2.8.4 Informing the radiological manager when a FMT member is approaching an administrative dose limit.
01323623.doa 03B 0522.0333
PACIFIC GAS AND ELECTRIC COMPANY NUMIBER EP EF-3 DIABLO CANYON POWER PLANT REVISION 23 PAGE 3 OF 4 TITLE:
Activation and Operation of the Emergency Operations UNITS 1 AND 2 Facility 2.9 Health Physicist is responsible for:
2.9.1 Reviewing off-site dose projections performed by the TSC, prior to the EOF being activated, 2.9.2 Collecting dose projection input data, 2.9.3 Calculating off-site dose projections, and 2.9.4 Informing the radiological manager of dose calculation results.
2.10 UDAC Meteorologist is responsible for determining current and forecast meteorological information.
2.11 Health Physics Liaison to Congregate Care is responsible for:
2.11.1 Initiating the call-out of congregate care monitors, 2.11.2 Assisting other members of UDAC as necessary.
2.12 Emergency Public Information Manager (EPIM) is responsible for:
2.12.1 Writing news releases and bulletins for recovery manager review and approval, 2.12.2 Coordinating the dissemination of approved news releases and bulletins with the JMC, and 2.12.3 Managing the joint media center in coordination with the county.
2.13 Assistant EPIM is responsible for:
2.13.1 Providing assistance to the EPIM, 2.13.2 Reviewing new releases, and 2.13.3 Assume responsibilities of the EPIM in their absence.
2.14 EPIM Technical Advisor is responsible for:
2.14.1 Ensuring the technical accuracy of news releases.
2.15 The Nuclear Logistics Coordinator is responsible for:
2.15.1 Notifying the director of corporate security or the manager of emergency planning.
2.15.2 Coordinating the schedule and travel arrangements for ERO positions in the San Francisco Bay area.
2.15.3 Keeping the policy chair advised of the status of events.
2.15.4 Keeping the advisor to the county and recovery manager informed of all company liaison activities.
01323623.doa 03B 0522.0333
PACIFIC GAS AND ELECTRIC COMPANY DLIBLO CANYON POWER PLANT TITLE:
Activation and Operation of the Emergency Operations Facility NUMBER REVISION PAGE UNITS
- 3.
INSTRU(
3.1 3.2 3.3
- 4.
RECORD
,TIONS Obtain a current copy of the checklist for your assigned Emergency Response Organization (ERO) position.
Sign your initials on the checklist after each action is performed or reviewed.
Document important information received or actions taken using log sheets.
S 4.1 All checklists generated during activation of the EOF for drills and exercises are non-quality good business records and shall be retained by emergency planning group for three years.
4.2 All checklists generated during activation of the EOF for a real event are non-quality records and shall be retained in RMS in accordance with AD 1 0.ID2
- 5.
ATTACHMENTS 5.1 Form 69-20465, "Recovery Manager Checklist," 07/30/02 5.2 Form 69-20466, "Advisor to the County Checklist," 07/30/02 5.3 Form 69-20467, "Radiological Manager Checklist," 07/30/02 5.4 Form 69-20468, "Health Physicist Checklist," 07/30/02 5.5 Form 69-20469, "Emergency Supervising Engineer Checklist," 05/21/03 5.6 Form 69-20470, "Radiological Monitoring Director Checklist," 04/29/02 5.7 Form 69-20471, "UDAC Meteorologist Checklist," 10/30/02 5.8 Form 69-20472, "Engineering Liaison Checklist," 05/21/03 5.9 Form 69-20473, "Agency Liaison Checklist," 08/06/02 5.10 Form 69-20474, "Health Physics Liaison to Congregate Care Checklist," 05/02/03 5.11 Form 69-20475, "Emergency Public Information Manager Checklist," 07/30/02 5.12 Form 69-20476, "EPIM News Release Preparation Checklist," 06/04/01 5.13 Form 69-20477, "Assistant Emergency Public Information Manager Checklist," 08/06/02 5.14 Forn 69-20478, "Technical Advisor to the EPIM Checklist," 06/04/01 5.15 Form 69-20479, "Advisor to the County/Recovery Manager Turnover Checklist,"
06/14/02 5.16 Form 69-20482, "RMlAdvisor to the County Facility PA Announcement Template,"
08/06/02 5.17 Form 69-20483, "News Media Notification List," 06/04/01 5.18 Form 69-20484, "Records of News Media Inquiries," 06/04/01 5.19 Form 69-20485, "Nuclear Logistics Coordinator Guidance Checklist," 05/02/03 5.20 Forn 69-20486, "Liaison Assistant Checklist," 08/06/02
- 6.
REFERENCES 6.1 DCPP Emergency Plan.
01323623.doa 03B 0522.0333 EP EF-3 23 4 OF 4 1 AND 2 I
I I
I
69-20465 07/30/02 DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.1 12 TITLE:
Recovery Manager Checklist Print Name Date The steps in this attachment may be performed in any sequence, may be modified, or may be considered N/A at the discretion of the Recovery Manager, unless specifically prohibited.
EI 1.
Sign in on EOF sign-in board.
LI 2.
Use form 69-20479, Advisor to the County/Recovery Manager Turnover Sheet, to conduct a briefing with the Advisor to the County.
3I 3.
Use form 69-20437, ISEC/SECIRM Turnover Checklist, to conduct a briefing with the ISEC and SEC.
L] 4.
Within approximately 60 minutes of the initiation of the ERO notification, the EOF is required to be staffed by the following positions.
NOTE: Qualified individuals not already filling a minimum staff position may fill vacancies.
5.
6.
7.
8.
LI Advisor to the County
[]
EPIM L
Radiological Manager Ln Technical Advisor to the EPIM LI Agency Liaison L
Health Physicist LI Agency Liaison Assistant
]
4 - FMT Members When minimum staffng is achieved, declare the EOF activated. This may be completed by the Advisor to the County or the Recovery Manager.
NOTE: Prior to making any PA announcements, inform the County EOC Command.
Make a PA announcement (921 on the DIC phone) to declare the EOF activated:
"Attention allpersonneL Tke EOF has been activated Direct the Advisor to the County to schedule an initial staff meeting.
When all personnel have completed turnovers and have assumed the responsibilities for their positions, assume responsibility for overall management of Diablo Canyon's emergency response activities.
Make the following announcement over the Public Address system to the entire EOF building:
"T7is is
. As Recovery Manager, Iam assuming responsibilityfor overall management of Diablo Canyon's emergency response activities The EOFis nowfully activated and operational (go over current status).
01323623.doa 03B 0522.0333 1
L-I LI Page of 3
EP EF-3 (UNITS 1 AND 2)
ATTACHMENT 5.1 TITLE:
Recovery Manager Checklist Direct the Advisor to the County or another staff member to log the time of activation.
NOTE: The following responsibilities transfer from the SEC to the RM:
emergency classification PARs approval of emergency worker exposures recommendation of KI for off-site PG&E emergency workers approval of news releases Continuing Actions
[] 1.
When notified of the NRC Initial Site Team's Estimated Time of Arrival, determine if the Recovery Manager or Advisor to the County will brief the team. The Initial Site Team will be updated while in transit by Region IV and Bethesda, so prepare a short briefing on current plant status, radiological information, public information, and public impact. The following should attend or participate in the briefing:
Advisor to the County Engineering Radiological Manager Emergency Public Information Manager State Representative if present at the EOC County Emergency Services Director or Representative n
- 2.
When EOF Security announces the arrival of the NRC Initial Site Team, brief your NRC Co-locator (NRC Director of Site Operations) on the emergency developments, mitigating actions, and current activities. Ensure the NRC Co-locator is familiar with telephone use, infornation flow, and has copies of the same documents used for your position.
n] 3.
Evaluate plant conditions and escalate emergency classifications when appropriate.
[]
- 4.
Conduct, or direct the Advisor to the County to conduct, regular plant status briefings using the Public Address system (PA).
- 5.
Keep informed of school closings, evacuations, relocation centers, sirens, Emergency Alert System (EAS) messages and other pertinent information via the Advisor to the County.
D 6.
Obtain radiological information from the Radiological Manager and plant status information from the Engineering Liaison.
n
- 7.
Review PARs.
L 8.
Request a briefing from the EPIM on event media coverage.
- 9.
Review and authorize or direct the Advisor to the County to review and authorize press releases.
- 10.
Ensure evacuation of non-emergency response personnel from DCPP is coordinated with SLO County.
- 11.
Authorize administration of KI to PG&E off-site emergency workers, as needed.
Coordinate Field Team KI administration with the County Health Officer.
01323623.doa 03B 9
69-20465 07/30/02 Page 2 of 3 0522.0333
EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.1 TITLE:
Recovery Manager Checklist
- 12.
Provide, or direct a staff member to provide, periodic updates of off-site activities to the SEC.
[] 13.
Authorize emergency exposures, as needed.
[] 14.
Ensure event updates are periodically announced to EOF/UDAC 2nd Floor over the Public Address.
[II 15.
Conduct, or ensure periodic briefings are conducted with:
Advisor to the County Engineering Liaison Radiological Manager Emergency Public Information Manager
[] 16.
Upon request from SLO County or Santa Barbara County for PG&E Reception and Care Monitors, direct the Radiological Manager to begin monitor call-out.
Recovery
[] 1.
De-escalate the emergency classification using the guidance in EP OR-3, "Emergency Reentry and Recovery."
F] 2.
Establish a Recovery Organization in accordance with EP OR-3, "Emergency Reentry and Recovery."
01 323623.doa 03B 69-20465 07/30/02 Page 3 of 3 0522.0333
DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.2 AND TITLE:
Advisor to the County Checklist Print Name Date The steps in this attachment may be performed in any sequence, may be modified, or may be considered N/A at the discretion of the Advisor to the County, unless specifically prohibited.
Li 1.
Contact the Sheriff Watch Commander to obtain copies of any event notification and PAR forms.
[] 2.
If necessary, obtain a PAR I key for opening the EOF doors.
[] 3.
Sign in on EOF sign-in board.
- 4.
If it is outside of normal working hours, use the "Fitness-For-Duty Call-Out Form" 69-10448, to perform ERO FFD screening. Use the "Observed Behavior Checklist," Form 69-13222, for ERO personnel that have consumed alcohol within the past 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Li 5.
Within approximately 60 minutes of the initiation of the ERO notification, the EOF is required to be staffed by the following positions.
NOTE: Qualified individuals not already filling a minimum staff position may fill vacancies.
LI1 Advisor to the County n
EPIM LI Radiological Manager Li Technical Advisor to the EPIM C]
Agency Liaison r3 Health Physicist Li Agency Liaison Assistant
[]
4 - FMT Members LII 6.
When minimum staffng is achieved, declare the EOF activated. This may be completed by the Advisor to the County or the Recovery Manager.
NOTE: Prior to making any PA announcements, inforn the County EOC Command.
Make a PA announcement (921 on the DIC phone) to declare the EOF activated:
"Attention allpersonneL The EOF has been activated "
L 7.
Use form 69-20479, Advisor to the County/Recovery Manager Turnover Sheet, to conduct a briefing with the Recovery Manager.
Li 8. Assume the role of the Diablo Canyon point of contact for SLO County EOC staff.
Li 9.
Request the Site Emergency Coordinator to notify you immediately of changes in plant conditions, EALs, or PARs.
01323623.doa 03B 0522.0333 69-20466 07/30102 Page of 2
EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.2 TITLE:
Advisor to the County Checklist 10.
When UDAC positions are staffed, organize a tailboard meeting in the Recovery Manager's Office to brief the management staff with the current status of the emergency. The following should attend:
Radiological Manager Engineering Liaison UDAC Coordinator EPIM
- 11.
Upon activation of UDAC, notify the Control Room and Site Emergency Coordinator that UDAC will assume the responsibility for generating PARs based on dose.
- 12.
Advise the Control Room or SEC that notifications to the County will go through the Advisor to the County.
If the Recovery Manager has not arrived at the EOF - Continuing Actions
[] 1 Phone the Site Emergency Coordinator (SEC).
n] 2.
Upon the arrival of the NRC Initial Site Team, brief NRC Co-locator 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.
[] 3.
Prepare for the arrival of the Recovery Manager by maintaining current status information on the emergency.
- 4.
Until the Recovery Manager arrives, periodically make PA announcements to brief the EOF staff with the current status of the emergency.
After the Recovery Manager has arrived at the EOF - Continuing Actions 2.
3.
4.
periodically provide status reports to the Recovery Manager on PARs received and implemented by SLO County.
Review and maintain copies of forms faxed to the EOF from the TSC. Develop a sequence of events.
Periodically consult with the Engineering Liaison to determine affected plant systems and plant status.
Periodically consult with the Radiological Manager to determine status on the following:
Pressure Ion Chamber (PIC) readings FMT activities and assignments Off-site dose projections KI administration or other authorized emergency protective actions 01323623.doa 03B 0522.0333 LI E]
Fl nL1.
n LI 69-20466 07/30102 Page 2 of 2
DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.3 AND TITLE:
Radiological Manager Checklist
- 1.
INITIAL ACTIONS PRINT NAME DATE l
1.1 Sign in on the EOF sign-in board.
O 1.2 Notify the Advisor to the County of your arrival.
0 1.3 Once UDAC is operational, hold a tailboard briefing with the UDAC Coordinator and Emergency Supervising Engineer to discuss the following:
radiological release pathway wind speed & direction source term (coolant, gap, or core) forecasted weather expected duration of release assumptions for dose assessment plant radiation monitor readings PIC readings field monitoring locations & types of radiological protections for field samples teams (KI, respirators, PCs)
SRD correction factors (To be provided to the County Health Officer by UDAC Coordinator) 0 1.4 Notify the Radiological Advisor and the Advisor to the County when UDAC is ready to assume the responsibility for off-site dose assessment and field monitoring.
o 1.5 Obtain verbal turnover from STA on dose assessment and radiological status.
O 1.6 Direct the Emergency Supervising Engineer to ensure EOF, EOC, and JMC habitability surveys are performed as necessary.
O 1.7 If dose projections are greater than 100 mrem TEDE for PAZ 8, have the ESE issue dosimetry to the EOF staff and recommend the UDAC Coordinator to issue dosimetry to the EOC.
O 1.8 In the absence of the RMD, conduct the initial brief of the Field Monitoring Teams, using the RMD checklist in Form 69-20470, Part 2, FMT Briefing, Sections 5-6.
01323623.doa 03B 69-20467 07/30/02 Page of 2 0522.0333
EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.3 TITLE:
Radiological Manager Checklist
- 2.
CONTINUING ACTIONS O 2.1 Upon the arrival of the NRC Initial Site Team, brief your NRC Co-locator (NRC Protective Measures Coordinator) 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.
E 2.2 Provide periodic status reports to the Recovery Manager (or to the Advisor to the County),
on the following:
2.2.1 Off-site monitoring activities 2.2.2 Congregate Care activities 2.2.3 Radiological releases and dose assessment 2.2.4 Meteorological information 2.2.5 Protective Action Recommendations E
2.3 Discuss radiological assessment information with the UDAC Coordinator, as it becomes known. If a release becomes known, immediately inform the Recovery Manager or SEC.
E 2.4 Notify the Agency Liaison when a PAR is ready for approval. If time permits, malk with Agency Liaison into the Recovery Manager's office and brief the Recovery Manager (or the Advisor to the County) on the details of the PAR.
E 2.5 Provide radiological data to the EPIM.
O 2.6 If necessary, provide recommendations to the Recovery Manager on exceeding emergency worker dose limits and issuing Kl. Refer to RB-3 for issuing KI. KI for the EOF staff is stored in the file cabinet in the RMD's office.
O 2.7 If evacuation of PAZs is anticipated, direct the Health Physics Liaison to Congregate Care to begin Monitor call-out. If no evacuation of PAZs is anticipated, direct the Health Physics Liaison to Congregate Care to call and place Monitors on stand-by.
01323623.doa 03B 0522.0333 69-20467 07/30/02 Page 2 of 2
DIABLO CANYON POWER PLANT EP EF-3 AITACHMENT 5.4 1AND TITLE:
Health Physicist Checklist
- 1.
INITIAL ACTIONS PRINT NAME DATE o
1.1 Sign in on the EOF sign-in board.
O 1.2 Contact the TSC Rad Data Processor to determine plant status and radiological conditions.
Ask for a faxed copy of PEP EN-I, PLANT STATUS DATA NEED TO PERFORM EP RB-9 and EARS CALCULATIONS, or complete the PEP EN-1 form by relaying the infonnation via phone.
O 1.3 Obtain current and forecasted meteorological data from the UDAC Meteorologist.
0 1.4 Request the TSC Radiological Advisor provide isotopic sample results, when they become known.
El 1.5 Brief the Emergency Supervising Engineer on the assumptions used for your initial dose projection.
O 1.6 Notify the Radiological Manager or Emergency Supervising Engineer when you are ready to assume the responsibility for dose assessment.
- 2.
CONTINUING ACTIONS 0
2.1 Upon the arrival of the NRC Initial Site Team, brief your NIRC Co-locator (NRC Dose Assessor and/or HP Specialist) 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.
El 2.2 Perform dose projection calculations using EARS. If EARS is unavailable, use Quickdose or perform manual calculations using RB-9 and RB-I 1. Dose calculation updates should be perfonmed every 15 minutes. However, if plant and MET conditions are remaining constant, projections can be made every 30 minutes.
E 2.3 Discuss results of dose calculation with the Emergency Supervising Engineer.
El 2.4 Inform the Emergency Supervising Engineer or Radiological Monitoring Director (RMD) of any plant changes that may impact field team activities.
O 2.5 Immediately inform the Radiological Manager when initially determining a release is in progress.
01323623.doa 03B 69-20468 07/30/02 Page I of 5 0522.0333
EP EF-3 (UNITS 1 AND 2)
ATrACHMENT 5.4 TITLE:
Health Physicist Checklist Radiation Monitor Trending I. Click on WinTrend Icon and select DCPP.ARMSDATA Server. Maximum to full screen.
- 2. Highlight monitors for first graph (all must have same units; e.g., cpm) and then click the "GRAPH" button.
- 3. Dialog box for trend time appears. Default is back 24 hrs - Click OK.
- 4. Click 1 minute update button (labeled"l," next to button labeled "").
Graphs will not update if you don't do this.
- 5. For next group to trend, select Window, then DCPP.ARMSDATA.
- 6. Deselect the monitors highlighted from group 1 and highlight the monitors for group 2. Repeat steps 4 - 6.
- 7. When all monitors desired are in graphs, midsize all graph windows and go Windows - Tile.
- 8. To see any graph in detail, just maximize; midsize itto return to tile view.
Which radiation monitors do I select?
Scenario 1:
NO Release in progress, AND NO Indication of any one release path being more likely than another.
Plant Vent:
RE-14 RE-14R RE-87 Secondary:
RE15 RE-15R RE-23 Containment:
RE-2 RE-30 Scenario 2:
NO Release in progress, AND hi-rad on RE-2 Plant Vent:
RE-14 RE-14R RE-29 RE-87 Secondary:
RE-15 Containment:
RE-2 RE-30 RE-31 Scenario 3:
RE-14/14R indicate a Plant Vent release has started.
Plant Vent:
RE-14 RE-14R RE-29 RE-87 RE-24 Secondary:
None Containment:
RE-2 RE-30 Oter.
RE-34*
- Direct measure of Containment shine:
- 1. shows potential for false high rdg on RE-29
- 2. habitability check for PV sampling.
Scenario 4:
RE-I5/1 SR or RE-23 indicate primary-secondary leakage.
Plant Vent:
RE-14 RE-14R Secondary:
RE-71 RE-72 RE-73 RE-74 Containment:
RE-2 01323623.doa 03B 0522.0333 69-20468 07/30/02 Page 2 of 5
69-20468 07/30/02 Page 3 of 5 EP EF-3 (UNITS 1 AND 2)
ATTACHMENT 5.4 TITLE:
Health Physicist Checklist RADIATION MONITORING SYSTEM POWER SOURCES MONITOR Name/Description BUS E BUS F BUS G BUS H BUS I BAITERY BACKUP Plant Vent R-14 (LRP)
NR Noble Gas 0
R-14 (RDU)
R-14R (LRP)
RNR Noble Gas 0
R-14R (RDU) 0 0
R-24 (LRP)
NR lodine R-24 (RDU)
R-24R (LRP)
RNR Iodine R-24R (RDU)
R-28 (LRP)
NR Particulate R-28 (RDU)
R-28R (LRP)
RNR Particulate
- 0 R-28R (RDU)
R-29 PV Gross Gamma 0
area)
R-87 (LRP)
Extended Range Noble Gas Secondary R-15 (LRP)
Condenser Air Ejector (CAE)
R-15 (RDU) 0 0
R-15R (LRP)
Redundant CAE 0
R-15R (RDU)
-9 team Generator 0
0 Blowdown Sample Line R-23 team Generator 0
Blowdown R-71 ain Steamline #1 0
R-72 Main Steamline #2 0
R-73 Main Steamline #3 R-74 Main Steamline #4
- 0 01323623.doa 03B 0522.0333
EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.4 TITLE:
Health Physicist Checklist RADIATION MONITORING SYSTEM POWER SOURCES MONITOR Name/Description BUS E BUS F BUS G BUS H BUS I BATTERY BACKUP Containment R-2 Low Range Area S
R-7 Incore Seal Table Room 0
0 R-30 High Range Area 0
R-31 High Range Area R-44A (LRP) ontainment Purge xhaust (CPE) -
Class I E Train 'A R-44A (RDU)
- 0
-44B (LRP) ontainment Purge 0
Exhaust (CPE) -
Class IE Train 'B' R-44B (RDU)
Fuel Handling Building R-58 pent Fuel Pool Area 0
R-59 ew Fuel Pit Area NOTE 1: LRP = Local Radiation Processor; includes detector and local display.
RDU =Radiation Display Unit; this is the Control Room display.
NR =
Normal Range RNR = Redundant Normal Range NOTE 2: THERE ARE NO UNIT DIFFERENCES ON THIS TABLE 01323623.doa 03B 0522.0333 69-20468 07/30/02 Page 4 of 5
69-20468 07/30/02 Page 5 of 5 EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.4 TITLE:
Health Physicist Checklist 1
SGTR I
l 01323623.doa 03B 0522.0333
69-20469 05/21/03 DIABLO CANYON POWER PLANT EP EF-3 ATTACHIMENT 5.5 TITLE:
Emergency Supervising Engineer Checklist Page 1 of5 P12 Step ESE Initial Actions I
I Fill out Fitness For Duty Form (if called out from home) 2 Sign in on EOF sign in board 3
Report to the Radiological Manager 4
Obtain dose projection turnover from the STA Ext: 1224 - use EOF fax for G-2 calcs 5
To man the 6002 bridge, include the CR Liaison, TSC RX Eng, RDP Plant, and EOF HP 6
Trend monitors to bound possible release paths if no release is in progress (RE-2,14,& 15)
Step ESE Continuing Duties l
1 Complete applicable parts of the ESE Data Log Sheet (optional) - as needed to facilitate dose projections each time there is a significant change in status and input data often enough to facilitate PARs leave unnecessary portions blank - no comment necessary 2
Make copies of the ESE Data Log Sheet (optional) and distribute (if used) this STEP NOT REQUIRED - it is an aid for UDAC discussion of status and input data suggested distribution is at the bottom of the fact sheet 3
Discuss the applicable radioactive release information with UDAC (this is a briefing) agree upon status and input data for all dose assessment programs 4
Assist the HP with input for EARS/Midas as necessary 5
Assist UDAC with input for GAUSE and RASCAL as necessary 6
Review each PG&E generated off-site dose calculation to verify that the dose projection is:
consistent with known radiological data and plant status AND for 3 HOJRS (or less as agreed upon by UDAC based projected termination of release) 7 SAE ECL based on site boundary 3 hr dose projection?
0.1Rem TEDE 0.5 Rem CDE GE ECL based on site boundary 3 hr dose projection?
Compare PIC data and FMT data to latest EARS/MIDAS run rule of thumb: 1.3 E-6 uCi/cc 1-131 = 5 Rem CDE thoid projected 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> dose 9
Discuss EARS/MIDAS output with UDAC PAG = I Rem TEDE 5 Rem CDE get concurrence for next PAR input 10 Verify that the Agency Liaison has all input necessary for the next PAR 11 Perform EOF radiological habitability surveys as needed 12 Obtain permission for KI for field teams and ERO personnel - PAG: 25 Rem CDE 13 Determine the current TEDE and CDE Dose Correction Factors - see EARS TEDE plot ensure RMD communicates Dose Correction Factors (DCFs) to Field Monitoring Teams TEDE DCF TEDE DCF THY. DCF THY. DCF Source Term No KI With KI No KI With KI CORE 13 5
162 16 GAP 24 3
1 40 4
SG Normal 1
1 4
0.4 SG Empty 3
1 40 4
SG Flooded 15 2
285 29 01323623.doa 03B 0522.0333
EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.5 TITLE:
Emergency Supervising Engineer Cheklist ESE Data Log Sheet (Optional)
Emergency Supervising Engineer's Name Initials Date l Emergency Classification Alert SAE GE declared at:
I ESE Fact Sheet time:
(circle one) working on PAR #:
Reactor power:
(or) shutdown Next PAR due:
Start of Release:
EARS run number:
Source Term:
Core:
- /o Gap:
- /e Radiation RM-71 cpm l
Coolant (circle if applicable)
Monitors:
RM-72 cpm (fill in the RM-73 cpm Release Atmos. Steam Dumping...
applicable RM-74 cpm Pathway:
Safety:
- 1
- 2
- 3
- 4
- 5 values)
RM-15/15R cpm circle as applicabe) 10/o dump:
% Open (or) Shut RM-19 cpm min. 4E5 Ibm/hr
- FM5 2:
Ibn/hr RM-23 cpm gpm x 500 = Ibm/hr
- Pri<glSec:
gpm _
Ibm/hr RM-14/14R (NG) uCi/cc_
S/G level:
flooded normal empty RM-87 (NG-High)
Note: This data is Plant Vent...
RM-24124R (lod) uCi/cc Quickdose input Aux bldg fan:
E-1 E-2 RM-28128R(Part) uCi/cc
- FHB fan:
E-4 E-5 E-6 RM-29 (NG-Altrnt) mr/hr use 0" ctmt spray FM 12:
cfm RM-34 mr/hr pumps for RHR seal Ge/Gw:
On Off (unfiltered)
RM-44A/44B cpm leakage into aux Charcoal filters:
Yes No RM-30 R/hr bldg regardless of how many Ctmt Spray pumps:
0 1
2 RM-31 R/hr are actually running Containment Leakaee RM-2 mr/hr RM-7 mr/hr Wind direction (wind is from) 0 Wind Speed m/sec x 2.2=
mph PiCs:
Shooting Range mr/hr Vert.Stability ABCDEFG (1234567)
I mr/hr Hor. Stability ABCDEFG (1234567) mr/hr Precipitation Yes No mr/hr Team Location KI?
CDE DCF:
(uCi/cc)
(mr/hr)
Comments:
Alpha Yes No Bravo Yes No Charlie Yes No Runner Yes No UDAC EOF Yes No l
PAGs:
I Evacuation/Shelter: I Rem TEDE Copies to: Health Physicist (HP)
Radiological Monitoring Director (RMD)
UDAC table (3)
UDAC Coordinator Radiological Manager (RM) 5 Rem CDE I
I Administer KI: 25 Rem CDE 01323623.doa 03B 0522.0333 0521/03 Page 2ofS 69-20469 I
EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.5 TITLE:
Emergency Supervising Engineer Checklist Radiation Monitor Trending I. Click on WinTrend icon and select DCPP.HP9DRILL Server. Maximize to full screen.
- 2. Highlight monitors for first graph (all must have same units; e.g., cpm) and then click the "GRAPH" button.
- 3. Dialog box for trend time appears. Default is back 24 hrs - Click OK
- 4. Click -minute update button (labeled "," next to button labeled "5"). Graphs will not update if you don't do this.
- 5. For next group to trend, select Window, then HP9DRILL.
- 6. Deselect the monitors highlighted from group I and highlight the monitors for group 2. Repeat steps 4 - 6.
- 7. When all monitors desired are in graphs, midsize all graph windows and go Windows - Tile.
- 8. To see any graph in detail, just maximize; midsize it to return to the view.
Which radiation monitors do I select?
Scenario 1:
NO Release in progress, AND NO Indication of any one release path being more likely than another.
Plant Vent:
RE-14 RE-14R RE-87 Secondary:
RE15 RE-15R RE-23 Containment:
RE-2 RE-30 Scenario 2:
NO Release in progress, AND hi-rad on RE-2 Plant Vent:
RE-14 RE-14R RE-29 RE-87 Secondary:
RE-15 Containment:
RE-2 RE-30 RE-31 Scenario 3:
RE-14/14R indicate a Plant Vent release has started.
Plant Vent:
RE-14 RE-14R RE-29 RE-87 RE-24 Secondary:
None Containment:
RE-2 RE-30 Other:
RE-34*
- Direct measure of Containment shine:
- 1. shows potential for false high rdg on RE-29
- 2. habitability check for PV sampling.
Scenario 4:
RE-1 5/15R or RE-23 indicate primary-secondary leakage.
Plant Vent:
RE-14 RE-14R Secondary:
RE-71 RE-72 RE-73 RE-74 Containment:
RE-2 01323623.doa 03B 0522.0333 69-20469 05/21/03 Page 3 of 5
69-20469 05/21/03 Page 4 of 5 EP EF-3 (UNITS 1 AND 2)
ATTACHMENT 5.5 TITLE:
Emergency Supervising Engineer Checklist RADIATION MONITORING SYSTEM POWER SOURCES MONITOR Name/Descintion BUS E BUS F BUS G BUS H BUS I BATTERY BACKUP Plant Vent R-14 (LRP)
NR Noble Gas R-14 (RDU)
R-14R (LRP)
RNR Noble Gas R-14R (RDU)
R-24 (LRP)
NR Iodine R-24 (RDU)
R-24R (LRP)
RNR Iodine R-24R (RDU)
R-28 (LRP)
NR Particulate R-28 (RDU)
R-28R (LRP)
RNR Particulate R-28R (RDU)
S R-29 PV Gross Gamma 0
R-87 (LRP)
Extended Range Noble Gas Secondary R-15 (LRP)
Condenser Air Ejector 0
(CAE)
R-15 (RDU)
R-15R (LRP)
Redundant CAE R-15R (RDU)
-19 Steam Generator 0
Blowdown Sample Line R-23 Steam Generator 0
Blowdown R-71 Main Steamline #1 R-72 Main Steamline #2 R-73 Main Steamline #3 0
R-74 Main Steamline #4
- 0 01323623.doa 03B 0522.0333
Page 5 of 5 69-20469 05/21/03 EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.5 TITLE:
Emergency Supervising Engineer Checklist RADIATION MONITORING SYSTEM POWER SOURCES MONITOR Name/Description BUS E BUS F BUS G BUS H BUS I BATTERY BACKUP Containment R-2 Low Range Area R-7 Incore Seal 0
0 Table Room R-30 High Range Area 0
R-31 High Range Area R-44A (LRP)
Containment Purge 0
Exhaust (CPE) -
Class IE Train 'A' R-44A (RDU) 0 0
R-44B (LRP)
Containment Purge 0
Exhaust (CPE) -
Class IE Train 'B' R-44B (RDU)
Fuel Handling Building R-58 Spent Fuel Pool Area R-59 New Fuel Pit Area NOTE 1: LRP = Local Radiation Processor, includes detector and local display.
RDU =Radiation Display Unit; this is the Control Room display.
NR =
Normal Range RNR = Redundant Normal Range NOTE 2: THERE ARE NO UNIT DIFFERENCES ON THIS TABLE.
01323623.doa 03B 0522.0333
69-20470 04/29/02 DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.6 TITLE:
Radiological Monitoring Director Checklist Page 1 of 5 12 RMD Checklist - Part 1 - Monitoring Preparation 1 RMDNane I
I Date Time ARRIVAL AT EOF Sign in on the Recovery Manager's activation board 2
Obtain the RMD binder from the cabinet by the stairs Complete an FFD form (only if called out)
Synchronize watch with UDAC digital wall clock Time DETERMINE CONDITIONS 3
Contact ESE/Rad Manager - complete RMD Checklist - Part 2 - FMT Briefing, Sections 1-3 Contact meteorologist (or use the PPC) - complete RMD Checklist - Part 2 - FMT Briefing, Section 4 Time INITIAL FMT BRIEFING 4
RMD conduct briefing at EOF.
Complete RMD Checklist Part 2 - FMT Briefing, Sections 5-6 during the briefing Provide copy of RMD Checklist Part 2 - FMT Briefing to each FMT before departure.
Time EOF J EOC RADIOLOGICAL PROTECTION l Complete County Exposure Tracking Sheet and submit copy to EWEC via the UDAC Coordinator 5
Set up the air sampler but do not turn it on until plume arrives at the EOF / EOC Check the operability of the frisker and dose rate meter Check KI supply in RMD office Expires:
Quantity:
Time PREP FOR CONTROL OF FMT Turn on or verify on - HP Radio (OP K-9) and County Brown Net Radio Initiate RMD Checklist - Part 3 - FMT Control and RMp Check1st - Part 4 - Team Data 6
Establish phone contact with the TSC Radio peratori545-3252)1 Establish face contact with the county and state UDAC agencies working outside the RMD office Establish phone contact with the EWEC Desk(781-4452 or 781-4454)1 Discuss monitoring locations, DCF, and desire samples with ESE or had Manager ESTABLISH FM!IT RADIO I Alpha Bravo Charlie Time CELL PHONE CONTACT HP Brown Cell BP Brow Cell HP Brown Cell 7
Check PG&E Team communication l
l_
l Check County Team communication Verify all have TLD and SRD l
l l
NA Record Team cell phone number >>
i Time DEPLOY FMTl 8
Tim Deploy FMTs as needed and specify preferred route if applicable l
GOUpdate RMD and UDAC.status boards with team locations
>>>>>> GO TO the RMID Checklist - PART 3 -1 MT%
CONTROL 01323623.doa 03B 0522.0333 i
I I
EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.6 TITLE:
Radiological Monitoring Director Checklist RMD Checklist - Part 2 - FMT BRIEFING 1I[lRMDNAME IlI PAGER (1545-4666'i(
)
DATE I EVENT CLASS TIME ENTERED REASON Unusual Event 2
Alert Site Area Emergency General Emergency UNITI UNIT 2 3
Reactor Power Rx SD Reactor Power Rx S/D Release Start Time Time Release Start Time Time Release Source l
Release Source 4
WIND FROM J SPEED (mlss2.2=mph) l TIME ]
EXPECTED CHANGES 1
FMT MEMBERS (circle Team Leader on each team and verbally desi nate to all)
TEAM ALPHA TEAM BRAVO TEAM CHARLIE Team Nae PgrCurrent Avail Nae PgrCufrent Avail Nae PgrCurrent Avail Member Name Paer Dos Name Pager Dose Dose N
Pager Dose lDose PG&E l
l l
5 PG&E X
X X County
=
NA 1250
=
NA 1250 l
NA 1250 County
_______NA 1250 NA 1250 l
NA 1250 Available Dose Team A Available Dose Team B Available Dose Team C l Runner I
l I
l_
II Alert or Higher - TEDE Dose Limit - PG&E is 4500 mR minus Current - County is 1250 mR 01323623.doa 03B 0522.0333 I
69-20470 04129/02 Page 2 of 5
EP EF-3 (UNITS 1 AND 2)
ATTACHMENT 5.6 TITLE:
Radiological Monitoring Director Checklist CHECK 01 FMT BRIEFING QUESTIONS BRIEF START TIME I BRIEF END TIMEI YES NO Did at least 4 technicians sign in on the activation board? (If NO, do it NOW)
Did all PG&E personnel complete an FFD form (only required when called out)? (If NO, do it prior to leaving)
Does anyone have an allergy to shellfish or KI? (If YES, replace member or use for low dose areas)
Is everyone Respirator Qualified? (If NO, replace member or use for low dose areas)
Are there any Declared Pregnancies or other reasons to limit dose? (If YES, exclude member and replace)
CHECK 0 FMT BRIEFING POINTS Follow EP RB8/SOP HP-3 for deployment preparations & checklists-Be Prompt & report in when immediately ready Check communications with RMD on Channel 8 (PG&E Repeater), Channel II (County), and Cell Phones NOTE: County FMTPs use Channel I for County Brown Net.
Check car to car radio communications with each other using Channel 7 (PG&E Local)
Comm Protocol - Ch 8 first, then Ch I1, then Cell, if lose all comm, leave plume, if you get paged with I
F When All Team" announcements received, acknowledge in order, Team A, then Team B, then Team C PG&E and County should take separate vehicles for redundancy and in case Team needs to split PG&E and County work as a team, redundant samples are not required and only one set of paperwork is needed
_Read Kl procedure and complete forms after reporting ready to deploy, check expiration of KI Turn Back Value is 500 mRem/hr unless told otherwise County personnel should cover their probes prior to going into the field Protective Clothing - wear coveralls, keep remainder ready in the vehicle including respirators While traveling, keep meters on. Report any increase in count rate or dose rate immediately. Never Drive while wearing a respirator.
At each assigned monitoring location, report ground count rate and area dose rate immediately when arriving Set up and take one air sample at each location upon arrival unless told otherwise, remain ready to take air samples at all times Immediately report to EOF when dose rate or count rate starts increasing, then start air sample Remember to use ALARA, Three-Way Communication, Self Checking Safety Issues - Be Careful Driving, especially during an evacuation. Does anyone have any safety issues?
Synchronize Team watches with RMD (which has already been synchronized with the UDAC wall clock)
SC Rad 545_32521 OFRMD I
54.1-62 END OF BRIEFING - BE SAFE 01323623.doa 03B 0522.0333 6
69-20470 04129102 Page 3 of 5 I
EP EF-3 (UNITS 1 AND 2)
ATTACHMENT 5.6 TITLE:
Radiological Monitoring Director Checklist RMD Checklist - Part 3 - FMT CONTROL l I RMD Name Date WHEN TO BRIEF THE TEAMS WHAT TO BRIEF THE TEAMS ON Initial Event Status Hourly if no changes Plant Status When the wind changes appreciably Changes in Radiological Conditions 2
Major change in plant status Release information Event classification change Wind direction and speed When release starts or stops Order to take KI Announce END OF UPDATE when complete When a PAZ is evacuated Turn back values change TIME FMT BRIEFINGS CONDUCTED
.3I I
I I
I I
WHEN RELEASE STARTS Determine Source Term and Dose Correction Factor (DCF) from the ESE or Rad Manager 4
Coordinate with Rad Manager for PG&E FMT and CHO for County FMT for KI approval if needed Update FMTs when the release started and an estimated plume arrival time in their area Track FMT dose using RMD Checklist - Part 4 Tearn Data MONITOR EVENT PROGRESS Approximately every 15 minutes during a release, discuss the following with ESE or Rad Manager:
Plume direction Current Dose Correction Factor 5
Preferred monitoring locations Status of Issuing KI to the FMT Area evacuation status Monitor PIC readings downwind using the Intranet PPC Monitor On Site FMT radio reports and relay pertinent information to the ESE or Rad Manager Record pertinent information on the RMD Checklist or RMD Log WHEN FIELD MONITORING TEAMS REPORT DATA Teams will need to be in low dose area for sample counting - may need to move if in plume Record sample or SRD data on RMD Checklist - Part 4 - Team Data for the respective team 6
Provide data to the ESE or Rad Manager Provide copies of data to the State and County Determine if EARS and FMT data correlates (first set of data and periodically thereafter)
Record IPZ samples when reported on the RMD log Time SHIFT TURNOVER - OFF GOING RMD Copy RMD checklist and supporting paperwork for On-Coming RMD 7
Provide turnover to the On-Coming RMD using the checklist and supporting paperwork Notiy Rad anager and ESE that you are being relieved Determine from the Rad Manager or ESE when you start your next shift Orfiginal RMD checklist and supporting paperwork sved for recordTretention Time SFT TURNOVER - ON COMING RMD 8 _____
Notify Rad Manager and ESE that you are the new RMD Contact FMTs and inform them of the turnover 01323623.doa 03B 0522.0333 69-20470 04/29/02 Page 4 of 5
EP EF-3 (UNITS 1 AND 2)
ATTACHMENT 5.6 TITLE:
Radiological Monitoring Director Checklist RMD Checklist - Part 4 - TEAM (ALPHA / BRAVO / CHARLIE / RUNNER) DATA (circle team) l I RMDNAME I I DATE Turn Back Dose Rate (mR)
Team Cell Phone Number FMT Location Status - (update RMD and UDAC status boards when moving) 2 Location Sent Arrived Location Sent Arrived Location Sent Arrived I
1 1i1 1
1
- I1 1
1 Field Monitoring Activities
=
Monitor
~Ground Sky Dose Rate Smear Air antiuae Idn fond Monitor Time net Shine net mR/hr dpm /
Air net ue ESE Se Location cpm cpm WO/WC 100 cm ft uCilml cpm uCUml ESE State I~~~~
3 Particulate uCi/mI = (1.6E-10)
(net cpm) I Air ft3 Iodine uCi/ml = (5.6E-09) * (net cpm) Air
- If Particulate >3.0 E-9, County Personnel to leave or wear respirators I
Individual Team Member Dose Tracking using.RD Names>>>
<<<Names Time Dose Total Dose Total Dose Total Dose Total Limiting SRD 4
I Record highest on scale dosimeter reading for each team member - Limiting SRD is the highest of all team members If SRD is re-zeroed, circle Total and add to further Totals in that column Notify EWEC when County personnel reach 25OmR I 500 mR I 750 mR / 1000 mR / 1250 mlf781-4452 or 781-4454 Dose Correction Factors In Use 5
Time II Source DCF DCF Corrected Team Limiting Dose using DCF below Team Available Dose T
(mR)
Time KI Ordered Time KI Taken Time Team Limiting SRD l
TEDE Thyroid 6
(mR)
DCF Dose (mR) j DCF Dose (mR)
Self Reading Dosimeter Dose Conversion Factors (DCF)
Source Term TEDE DCF Thyroid DCF l
fi Source Term l
No KI With KI No KI With KI 7
RCS 3
1 40 4
GAP 24 3
515 52 CORE 13 5
162 16 (SGNormal I
1 4
0.4 SGEmpty 3
1 40 4
l SGFlooded 15 2
285 29 01323623.doa 03B 0522.0333 I
Page 5 of 5 69-20470 04/29/02
DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.7 1AND TITLE:
UDAC Meteorologist Checklist I.
INITIAL ACTIONS PRINT NAME DATE 0
1.1 Sign in on the EOF sign-in board.
O 1.2 Activate the Meteorology data terminals located in UDAC.
O 1.3 Contact the General Office Meteorologist (SAM-3PM) and unit supervisor (all times) and coordinate all meteorological activities.
1.3.1 Unit supervisor activates the General Office Meteorological support unit.
E 1.4 Contact the National Weather Forecast Office (NOAA) and obtain local and regional forecasts Monterey 1-831-656-1717 (back-up)
Oxnard 1-805-988-6618 (primary) ortland 1-503-326-3720 (back-up)
O 1.5 Obtain supplementary climate and meteorological information from the following sources:
I.5.1 PG&E Forecast Office 1-415-973-3224 or 3223)
- 2.
CONTINUING ACTIONS O 2.1 Brief Radiological Manager and UDAC staff on current and forecast weather conditions.
O 2.2 Provide meteorological updates to the Health Physicist at least every 15 minutes.
E 2.3 Maintain meteorological sections of status boards in UDAC and the EOC Command Room.
E 2.4 Periodically brief the following or as conditions change:
Recovery Manager County Emergency Services Director 01323623.doa 03B 0522.0333 69-20471 10/30102 Page of
DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.8 1AND TITLE:
Engineering Liaison Checklist I.
INITIAL ACTIONS PRINT NAME DATE
[
1.1 Sign in on the EOF sign-in board.
O 1.2 If, necessary turn-on the PPC & SPDS computer terminals.
Ol 1.3 Notify the Advisor to the County of your arrival.
E 1.4 Prepare for a Recovery Manager staff meeting by maintaining current information on plant status and efforts to recover the plant.
E 1.5 Contact the TSC Engineering Advisorfx3495)& obtain current plant status infornation O
1.6 Collect copies of plant status forms faxed to the EOF & review to determine a sequence of events (forrns are faxed to the UDAC to the County Clerk for distribution) 1.6.1 EP G-3, PLANT STATUS FORM 1.7 If time permits, dial into the Engineering BridgeEx60023to listen for real time plant parameters.
f 0
1.8 Establish contact with INPO. Advise the Recovery Manager if INPO support in the EOF is recommended.
- 2.
CONTINUNG ACTIONS 0
2.1 Upon the arrival of the NRC Initial Site Team, brief your NRC Co-locator (NRC Reactor Safety Coordinator) 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.
E 2.2 As time permits, keep a chronological Log for documenting the time of events & important actions taken.
E 2.3 Monitor current plant parameters using the PPC, SPDS, Plant Status Emergency Forms, and inforrnation communicated on the Engineering Bridge.
E 2.4 When requested by the Recovery Manager or the TSC Engineering Advisor, contact additional engineering NPG personnel to provide specific technical expertise.
0 2.5 Update INPO representative with major developments.
01323623.doa 03B 0522.0333 69-20472 05/21/03 Page I of
DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.9 AND TITLE:
Agency Liaison Checklist
- 1.
INITIAL ACTIONS PRINT NAME DATE 0
1.1 Sign in on the EOF sign-in board.
El 1.2 Notify the Advisor to the County of your arrival.
O 1.3 Review all emergency notifications that have been issued to SLO County.
O 1.4 Notify the UDAC Clerk that you are to immediately receive copies of all emergency notifications received by fax.
El 1.5 Establish contact with either the Control Room or the TSC Liaison Advisor.
O 1.6 Establish who has responsibility for ensuring completion of notification form distribution.
0 1.6.1 CR O
1.62 TSC 0
1.6.3 EOF O
1.7 Determine if SLO County Sheriff Watch Commander or EOC is receiving notification.
O 1.7.1 SLO County Sheriff Watch Commander - Call.
O 1.7.2 EOC - Call Advisor to the County and get speaker telecom with EOC.
- 2.
CONTINUING ACTIONS El 2.1 Route emergency notification forms to the Recovery Manager for approval of DCPP PAR.
El 2.2 Ensure DCPP emergency notification form is routed to the UDAC coordinator for concurrence.
El 2.3 Ensure follow-up emergency notifications are issued approximately every 45 minutes.
E 2.4 Maintain contact with the Advisor to the County, UDAC Coordinator, UDAC Clerk to track emergency notifications.
El 2.5 Periodically check with the UDAC Clerk and UDAC fax machine for notifications and PARs received by UDAC.
El 2.6 Make the following notifications:
County State OES NRC a
2.7 PHONE emergency notification information to the County (unless otherwise directed by the Advisor to the County), State OES, NRC.
NOTE: 15 minute time limit for classification level or PAR changes to the County and State, otherwise approximately 45 minute updates to each.
El 2.8 Send emergency notifications to the State OES until they are present at the EOF.
Send emergency notifications to the NRC throughout the event.
01323623.doa 03B 0522.0333 69-20473 08106/02 Page of
DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.10 AND TITLE:
Health Physics Liaison to Congregate Care Checklist
- 1.
INITIAL ACTIONS PRINT NAME DATE 0
1.1 Sign in on the Recovery Manager's sign-in board.
O 1.2 When directed by the Radiological Manager, notify reception and care monitors to standby or activate. Reception and care monitors are listed in the NERC.
E 1.3 Contact site C&RP personnel to ensure transport of Portable Portal Monitoring equipment to Congregate Care Centers.
D 1.4 Dispatch reception and care monitors as directed by the Radiological Manager.
E 1.5 Provide assistance to other UDAC staff as necessary.
El 1.6 Provide assistance to JMC staff if requested.
01323623.doa 03B 69-20474 05/02/03 Page of 0522.0333
DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.11 1AND TITLE:
Emergency Public Information Manager Checklist NOTIFICATION OF UNUSUAL EVENT PRINT NAME DATE NOTE: The San Luis Obispo County JMC will not be activated for a Notification of Unusual Event.
- 1.
Receive event notification from the Control Room 0 2.
If the notification occurs outside of normal working hours, provide information to the Shift Supervisor regarding your current and long term Fitness for Duty including any consumption of alcohol during the previous five hours.
E
- 3.
Determine from the Control Room the following information:
- a.
Emergency classification.
- b.
Plant status information.
- c.
Nature of any protective action recommendations made to the county.
- d.
Potential for plant release of radioactive materials.
- e.
Special instructions from the Interim Site Emergency Coordinator for the departmental emergency response effort.
O 4.
Notify the Company News Department of the emergency response effort.
El
- 5.
Prepare or direct the preparation of news releases and/or standby statements from the information provided by the Interim Site Emergency Coordinator (ISEC).
O 6.
Periodically distribute approved news releases. See Form 69-20476, "EPIM News Release Preparation Checklist."
O 7.
Determine if news media notice of the Notification of Unusual Event needs to be disseminated beyond San Luis Obispo County or Humboldt County, as appropriate.
01323623.doa 03B 69-20475 07/30/02 PagelI of 3 0522.0333
EP EF-3 (UNITS 1 AND 2)
ATTACHMENT 5.11 TITLE:
Emergency Public Information Manager Checklist ALERT, SITE AREA EMERGENCY OR GENERAL EMERGENCY IN ADDITION TO COMPLETING ACTIONS IDENTIFIED FOR UNUSUAL EVENT, O
- 1.
Receive event notification from the Control room.
O
- 2.
Proceed immediately to the EOF. Enroute contact the SF News Department to advise them of the emergency.
Ol
- 3.
If after hours, complete a Fitness for Duty form (available at the top of the stairs at the EOF) and give it to the Advisor to the County.
O
- 4.
Sign in on the Recovery Manager's sign in board. Notify the Recovery Manager (or Advisor to the County if the Recovery Manager has not arrived at the EOF) of your arrival.
O
- 5.
Go to EPIM office and turn on all computers and printers.
O
- 6.
Obtain faxed copy of the DCPP Event Notification Form from the fax machine in the EPIM's office. Confer with the ISEC, Advisor to the County or the TA, SEC, RM or the RMs designated alternates, if necessary, to clarify any questions about the content of the event notification form. (If the Event Notification Form is not in the fax machine check with the Advisor to the county or the RM).
O
- 7.
Prepare and distribute to the media an initial news release based upon the information contained in the DCPP Event Notification Form. Use the fax group lists 06,07,08 on the SEND fax machine in the EPIM's office.
El
- 8.
Ensure that the initial news release has been forwarded to the county Public Information Coordinator within two hours after declaration of an event classified as an "Alert" or higher emergency classification.
O
- 9.
Determine assignments of additional News Department personnel and Technical Advisors.
El
- 10.
Prepare or direct the preparation of news releases and/or standby statements from the information provided by the Interim Site Emergency Coordinator (ISEC), Site Emergency Coordinator (SEC) or Recovery Manager (RM) or their designated alternates. Coordinate all company news releases with the Technical Advisor to the Emergency Public Information Manager and county Public Information Manager, if available, before issuing.
O
- 11.
Receive release approval from SEC/RM(or the RMs alternate) for ALL news releases.
If you have difficulties contacting the SEC for news release/bulletin approval, go to the Advisor to the County for help. Directions for using the news templates and E-mail service are posted on the computers. Fax and E-Mail news releases to the JMC and other facilities.
E
- 12.
Periodically distribute approved news releases. See Form 69-20476, "EPIM News Release Preparation Checklist."
O
- 13.
Log all news media inquiries on Form 69-20484, "Record of News Media Inquiries," or delegate to EOF Clerical Assistant.
Ol
- 14.
Ensure continuous 24-hour emergency response operations.
D
- 15.
Monitor Emergency Alert System (EAS) broadcasts.
01323623.doa 03B 69-20475 07/30102 Page 2 of 3 0522.0333
EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.11 TITLE:
Emergency Public Information Manager Checklist ALERT. SITE AREA EMERGENCY, OR GENERAL EMERGENCY (continued)
[O
- 16.
Log all incoming and outgoing communications related to the emergency response effort and maintain a written record of emergency response activities using the "Emergency Communications and Activities Log Sheet," or delegate to Clerical Assistant.
NOTE 1: Completed log sheets should be forwarded to Emergency Planning, DCPP, 119/2/247 for permanent retention.
NOTE 2: If evacuation is ordered by competent authority, include a statement in the next news release that instructs evacuees to keep any lodging/travel receipts to streamline the compensation process if they prove eligible.
[O
- 17.
As events develop, provide the JMC Director/JMC Manager with (RM approved) bulletin-form printed information or telephone updates limited to event developments that occur between news releases or to answer event-related questions from the media at the JMC.
Ol
- 18.
When requested by the Recovery Manager, provide a briefing summary of news events that includes at a minimum:
- a.
JMC status
- b.
Questions from the media
- c.
Numbers and summary of press releases issued
- d.
Any interview requests Ol
- 19.
Upon the arrival of the NRC Initial Site Team, brief your NRC Co-locator (NRC Public Affairs Coordinator) 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.
O
- 20.
When requested by the JMC Director, coordinate with the EOF Radiological Manager to provide knowledgeable health physics personnel to go to the JMC and provide information regarding radiological conditions.
O
- 21.
Request authorization from the Site Emergency Coordinator and Recovery Manager for any news media visits to the plant site.
O
- 22.
Coordinate all SEC approved news media visits to the plant site.
o
- 23.
Upon direction by the Recovery Manager, deactivate the news department emergency response effort.
01323623.doa 03B 69-20475 07/30/02 Page 3 of 3 0522.0333
DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.12 1AND TITLE:
EPIM News Release Preparation Checklist
[O
- 1.
When notified, use templates to assemble information from the event notification form for initial news release. All releases shall be numbered beginning with #I and dated properly.
o
- 2.
Include basic information about the incident which may include: whether there have been any injuries, releases of radioactive materials, what is being done to solve the problem, that further information will be made available as soon as possible and where to call for further information.
NOTE: All subsequent news releases, after initial declaration of emergency classification, may include:
- a.
Chronological history of event.
- b.
Brief summary of what is being done to control or end the emergency.
- c.
Update on any radiological releases.
- d.
As events in an emergency quickly develop, the use of approved bulletins may be appropriate to update the media between scheduled news releases. Bulletins should be limited to confirmed event developments and must have at least verbal approval from the Recovery Manager. Bulletins should be numbered sequentially and dated.
The EOF copy should be initialed by the EPIM before release.
O
- 3.
Get approval of all news releases and bulletins by appropriate authorities. (SITE EMERGENCY COORDINATOR, RECOVERY MANAGER or the RMs designated alternates - have them sign and time the original EOF copy to be retained at EOF, clean copy sent to JMC) 0
- 4.
After receiving approval, contact wire services (AP and UPI) and local media, beginning with radio and television and then print outlets (Group dial #07, 08, then 06). Phone and FAX numbers for all media are also available in Attachment 5.20.
O
- 5.
Prepare next news release or bulletin as soon as first news release is completed and distributed. Include sequence of events and any new information that is available. News releases should be distributed to: (delegate this task to EPIM Clerical Assistant)
- a.
Recovery Manager/Advisor to the County
- b.
County Public Information Officer (PIO) at the JMC
- c.
County Public Information Manager at EOC command
- d.
County Public Information Coordinator at the EOC PIO room.
- e.
Joint Media Center
- f.
EOF Radiological Manager
- g.
UDAC
- h.
San Francisco News Department NOTE: Coordinate all subsequent news releases with the County PIM before issuing to the media. Distribution to media of approved news releases will also be made in San Francisco at the San Francisco Media Center.
0
- 6.
Update Diablo status telephone in805/546-5292l a
- 7.
Post all news releases and bulletins in the EPIM Office.
01323623.doa 03B 0522.0333 69-20476 06/04/01 Page of
69-20477 08/06/02 DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.13 12 TITLE:
Assistant Emergency Public Information Manager Checklist This position is filled by a second Emergency Public Information Manager upon arrival at the Emergency Operations Facility in San Luis Obispo.
PRINT NAME DATE O
- 1. Receive notification from the plant that the EOF/JMC is to be activated.
O
- 2.
Proceed to the EOF complete a Fitness for Duty form.
O
- 3.
Upon arrival at the EOF, inform the Emergency Public Information Manager and Advisor to the County of your presence.
O
- 4.
Sign in on the Recovery Managers sign-in board.
O
- 5.
Assist the Emergency Public Information Manager in the preparation of news releases and bulletins, or proceed to the MC to serve as JMC Director if directed by EPIM.
O
- 6.
Operate the E-Mail computer system at the Emergency Operations Facility.
O
- 7. Act as a liaison between the EPIM and the county PIM regarding press releases.
O
- 8. Log all incoming and outgoing communications related to the emergency response effort and maintain a written record of emergency response activities.
NOTE: Completed log sheets should be forwarded to Emergency Planning, DCPP, 119/2/247, for permanent retention.
0
- 9.
Monitor Emergency Alert System stations.
E
- 10. Update Diablo status telephone line805/546-52923umber as needed.
01323623.doa 03B 0522.0333 I
Page of
DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.14 1AND TITLE:
Technical Advisor to the EPIM Checklist PRINT NAME DATE a
- 1.
Receive event notification from the plant that the EOF/JMC is to be activated.
Ol
- 2.
Proceed to the EOF.
AT EOF O
- 1. Upon arrival at the EOF, inform the Emergency Public Information Manager and Advisor to the County of your presence.
El
- 2.
Receive directions from the EPIM on whether to report to the JMC or stay at EOF.
O
- 3.
If staying at the EOF sign in on the Recovery Managers sign-in board.
O
- 4.
Assist the Emergency Public Information Manager to ensure the technical accuracy of news releases and statements.
Ol
- 5.
Clarify technical information for county public information personnel if requested.
Ol
- 6.
Log all incoming and outgoing communications related to the emergency response effort and maintain a written record of emergency response activities.
AT JMC El
- 1.
Sign in on sign-in board.
E
- 2.
Assist the JMC Director or EPIM to ensure news release information is correct.
Ol
- 3.
Clarify technical information for county public information personnel, if requested.
O
- 4.
Log all communications and maintain a written record of emergency response activities.
NOTE: Completed log sheets should be forwarded Emergency Planning, DCPP, 119/2/247 for permanent retention.
01323623.doa 03B 69-20478 06/04/01 Page of I 0522.0333
69-20479 06/14/02 DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.15 P12 TITLE:
Advisor to the County/Recovery Manager Turnover Checklist Advisor to the County:
Status of EOF Activation Event Classification PAZs Evacuated 0 1 PAZs Sheltered I
School & Road Closures:
0 0
02 02 Name UDAC staffed NUE 0 Alert 03 04 5
03 04 05 I
/
Date 0 Field Teams dispatched O SAE GE 06 07 08 09 0 6 07 08 09 Time 0 OEL dispatched 010 010 011 Ol 012 012 Earthquake http://wwwnpg/eptNews/
CLICK Earthquake Map CLICK Geosciences Site Evacuation 0 Completed 0 In-progress Release of Radioactive Material 0 No release 0 Imminent Off-site dose at site boundary TEDE mrem Meteorological Data:
Wind Speed mph Direction _
Field monitoring teams locations:
KI issued to field monitoring teams 0 Yes 0 No Status Plant Systems & Vital Equipment:
Unit 1% power O_ Mode I O Mode 2 O Mode 3 Unit 2 % power El Mode I O Mode 2 0 Mode 3 Off-site power available 0 230 kV 0 500 kV 0 North 0 South 0 In-progress 0 Terninated Thyroid CDE mrem 0 rain predicted 0 rain occurring 0 Mode 4 0 Mode 4 0 Mode 5 0 Mode 5 0 Mode 6 0 Mode 6 Unit I Unit 2 Vital Bus O Bus F O Bus G OBus H O Bus F OBus G OBus H D/G 1-3 1-2 1-1 1-3 2-1 2-2 Si 1
2 1
2 RHR 1
2 1 1 2
CCP 1
2 1 1 2
PDP 3
3 AFW 3
r 2
3 2
ASW 1
2 1
2 CCW 1
2 3
1 2
2 T
1 2
CFCU 1&2 3&5 4
1&2 3&5 4
Summary of events:
01323623.doa 03B Page I of I 0522.0333
69-20482 08/06/02 DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.16 1
2AND TITLE:
RM/Advisor to the County Facility PA Announcement Template TIME OF ANNOUNCEMENT ATTENTION EOF PERSONNEL
[ THIS IS A DRILL.
[ ] THIS IS AN EMERGENCY ANNOUNCEMENT.
TiIS IS
, I AM THE
[ ] RECOVERY MANAGER.
[ ] ADVISOR TO THE COUNTY TIHE PLANT IS CURRENTLY IN:
[ ] AN ALERT
[ ] A SITE AREA EMERGENCY
[ ] A GENERAL EMERGENCY TIS EMERGENCY ACTION LEVEL IS BASED UPON: (STATE THE CONDITIONS)
INVOLVING:
[ ]UNIT NO. I
[ ] UNIT NO. 2
[ ] UNITS and 2
[ I OTHER THE FOLLOWING ACTIONS HAVE BEEN TAKEN TO MITIGATE THE EVENT:
THE FOLLOWING RECOMMENDATIONS HAVE BEEN MADE TO THE COUNTY:
[ ] THIS IS A DRILL
[ ] THIS HAS BEEN AN EMERGENCY ANNOUNCEMENT 01323623.doa 03B 0522.0333 Page I of
69-20483 06/04/01 DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.17 AND2 TITLE:
News Media Notification List ORGANIZATION TELEPHONE FAX Associated Press (AP)
San Francisco (415)621-7432 (415)552-9430 Los Angeles Area (213)626-1200 (213)346-0200 United Press International (UPI)
Los Angeles Area (213)580-9898 (213)580-9880 San Luis Obispo Telegram Tribune (805)781-7800 (805)781-7905 Five Cities Times - Press Recorder (805)4894206 (805)473-0571 Santa Maria Times (805)925-2691 (805)928-5657 KSBY -TV (805)597-8400 (805)597-8520 KCOY - TV (805)5434223 or (805)5434818 (805)925-1200 (805)349-9965 KEYT - TV (805)882-3933 (805)882-3931 KVEC - TV (805)543-8830 (805)781-2568 KKJL - TV (805)543-9400 (805)543-0787 KUHL - AM (805)922-7727 (805)349-0265 KSMA - AM (805)925-2582 (805)928-1544 KPRL - AM (805)238-1230 (805)238-5332 KKJG - FM (805)781-2750 (805)781-2758 Business Wire San Francisco Area (415)9864422 (415)788-5335 Boston Area (617)236-4266 (617)236-7740 Los Angeles Area (310)820-9473 (310)820-7363 New York Area 1-(800)221-2462 (212)893-5335 01323623.doa 03B Page of 0522.0333
69-20484 06/04/01 DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.18 Page I of I 12 TITLE:
Records of News Media Inquiries Date Time Name Organization Remarks I
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DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.19 1AND TITLE:
Nuclear Logistics Coordinator Guidance Checklist PRINT NAME DATE aI
- 1.
Sign in on the Recovery Manager's sign-in board.
l
- 2.
Notify the Chief Pilot or Aircraft Pilots of Bay Area personnel that need to be flown to San Luis Obispo County.
E
- 3.
Contact the Bay Area Recovery Manager and Near Site Meteorologist to coordinate travel arrangements with the Corporate Pilot.
a
- 4.
Contact the Director of Corporate Security to advise of the situation.
a) The initial notification may be very brief consisting of known information at the time.
Example: "The Emergency Operations Facility has been activated at the Alert level."
b) If the Director of Corporate Security is not available, contact the Manager of Corporate Emergency Planning. If the Manager of Corporate Emergency Planning is not available, call the PG&E Call Center to contact the On-Call Corporate Security Representative.
NOTE: The Director of Corporate Security is responsible to notify the Policy Group Chair, who determines what additional notifications are required and if other emergency centers need to be activated, including:
Company Emergency Operations Center (EOC,)
Operations Coordination Center (OCC,)
External Communications Coordination Center (EXCCC)
NOTE: If the Company EOC is not activated, the Policy Group Chair will provide a General Office contact to be the primary interface with the plant emergency staff.
El 5.
Contact the Highway Patrol to ensure that travel by Bay Area personnel to the Emergency Operations Facility (EOF) will not be impeded by traffic.
El
- 6.
Alert the following personnel:
Law Department Safety, Health and Claims Corporate Insurance El
- 7.
Notify another NLC to report to the General Office, if the Policy Group Chair, or designee, wants an NPG Coordinator at the Company EOC or EXCCC.
01323623.doa 03B 0522.0333 Page of 2 69-20485 05/02/03
EP EF-3 (UNITS I AND 2)
ATTACHMENT 5.19 TITLE:
Nuclear Logistics Coordinator Guidance Checklist CAUTION: All public information shall be authorized by the ISEC, SEC, or RM prior to release from the Joint Media Center and the Internal/External Communications Group in the Company EOC or the EXCCC.
El
- 8. Coordinate information requests related to corporate communications, insurance coverage, and general liability problems during the emergency.
Do not provide infornation to media personnel.
El
- 9.
Update the Advisor to the County and Recovery Manager of all Company liaison activities.
El
- 10.
Update the Policy Group Chair, or designee, and the EXCCC (if activated) of at least every classification change of:
Timeline of events (especially during initial call).
Current plant status (both units).
If a radioactive release is in progress and which direction it is going.
Site evacuation details.
Personnel accountability status.
Frequency of RMIEOF briefings.
Command and Control of the event (has the RM taken charge).
El
- 11.
Obtain information from the Policy Group Chair, or designee, regarding:
Status of and potential impact to the electric grid.
Status of and potential impact to Path 15.
Government interest in the event.
Press interest in the event.
Desired update frequency.
Any additional information needs.
El
- 12.
Communicate with the pilot regarding:
Wind direction.
Any radioactive release in progress.
Location of Company plane.
Estimated arrival times of Bay Area personnel.
Landing location - SLO, Paso Robles, or Santa Maria.
Transport alternatives (helicopter, etc.).
01323623.doa 03B 0522.0333 69-20485 05/02/03 Page 2 of 2
DIABLO CANYON POWER PLANT EP EF-3 ATTACHMENT 5.20 1AND TITLE:
Liaison Assistant Checklist Liaison Assistant - County/State, and NRC PRINT NAME DATE
- 1.
INITIAL ACTIONS El 1.1 Sign in on the Assembly and Accountability Checklist form as applicable.
El 1.2 Sign in on the EOF sign-in board.
- 2.
CONTINUING ACTIONS El 2.1 Make the following notifications per EP G-3:
SLO County Sheriff Watch Commander State Warning Center
- NRC
- INPO D]
2.2 PHONE emergency notification information to the SLO County EOC, State OES.
NOTE: 15 minute time limit for classification level or PAR changes to the County and State, otherwise updates should be made approximately every 45 minutes.
El 2.3 Send emergency notification information to the NRC. Update notifications should be made approximately every 45 minutes throughout the event.
El 2.4 Send emergency notifications to the NRC throughout the event.
El 2.2 Ensure notifications are completed and signed off.
El 2.3 Retain past notification forms and plant status forms.
- 4.
SIGNOFF Event terminated or turnover given Signature Date/Time 01323623.doa 03B 69-20486 08/06/02 Page of I 0522.0333