ML19322B909

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Independent Spent Fuel Storage Installation - Emergency Plan Update
ML19322B909
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 11/18/2019
From: Ginn M
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML19323D588 List:
References
DCL-19-093, DIL-19-013
Download: ML19322B909 (31)
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Text

Pacific Gas and Electric Company**

November 18, 2019 PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 Michael A. Ginn Manager Emergency Planning Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424 805.545.3446 Internal: 691.3446 Fax: 805.545.6265 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 10 CFR 50.54, 10 CFR 72.32 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Docket No. 72-26, Materials License No. SNM-2511 Diablo Canyon Independent Spent Fuel Storage Installation Emergency Plan Update

Dear Commissioners and Staff:

In accordance with 10 CFR 50.54(q)(5) and the requirements of 10 CFR 72.32, Pacific Gas and Electric Company (PG&E) is providing a summary of the analysis of changes to Emergency Plan (E-Plan). The revised E-Plan section and the associated enclosures are listed below:

  • - Summary of the Analysis of Changes to Emergency Plan Section 7, Revision 4.22, "Emergency Facilities and Equipment"
  • - Emergency Plan Section 7, Revision 4.22, "Emergency Facilities and Equipment" PG&E evaluated the changes for a reduction in effectiveness, as defined in 10 CFR 50.54(q), and concluded that the changes do not reduce the effectiveness of the E-Plan. The E-Plan continues to meet the requirements in Appendix E of 10 CFR 50 and the planning standards of 10 CFR 50.47(b). Therefore, prior NRG approval of the associated changes was not required.

This update does not contain any privacy and proprietary information in accordance with NRG Generic Letter 81-27, "Privacy and Proprietary Material in Emergency Plans."

A member of the STARS Alliance Callaway

  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

Document Control Desk November 18, 2019 Page 3 PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.

If there are questions regarding this update, please contact me at (805) 545-3446.

Michael A. Ginn Emergency Planning Manager armb/4 7 43/51053443 Enclosures cc/enc: William C. Allen, NMSS Project Manager Scott A. Morris, NRC Region IV Administrator Christopher W. Newport, NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager Senior Emergency Preparedness Inspector (RGN-IV/DR)

A member of the STARS Alliance Callaway

  • Diablo Canyon
  • Palo Verde

Rev.

Title E-Plan Coversheet 4.01 Emergency Plan E-Plan Table of 4.05 Table of Contents Contents E-Plan Section 1 4.08 Definitions and Abbreviations E-Plan Section 2 4.05 Scope and Applicability E-Plan Section 3 4.00 Summary of Emergency Plan E-Plan Section 4 4.17 Emergency Conditions E-Plan Section 5 4.18 Organizational Control of Emergencies E-Plan Section 6 4.19 Emergency Measures E-Plan Section 7*

4.22 Emergency Facilities and Equipment E-Plan Section 8 4.16 Maintaining Emergency Preparedness E-Plan Section 9 4.02 Recovery E-Plan Section 10 4.03 References E-Plan Appendix A 4.08 Procedures E-Plan Appendix B 4.02 Offsite Agency Support Documents E-Plan Appendix C 4.00 Non-Applicable NUREG-0654 Standards E-Plan Appendix D 5.02 EAL Technical Basis Manual E-Plan Appendix E 4.00 Evacuation Time Estimates E-Plan Appendix F 4.07 ERO On-Shift Staffing Analysis Report E-Plan Appendix G 4.02 Protective Action Recommendation (PAR) Strategy Bases

  • Revised Document Page 1 of 1 PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 Summary of the Analysis of Changes to Emergency Plan Section 7, Revision 4.22, "Emergency Facilities and Equipment"

Change Original Content (Rev 4.21)

Revised Content (Rev 4.22) 1 7.1.2.1 7.1.2.1 Each unit is provided with a hot shutdown panel Each unit is provided with a hot shutdown located in the Auxiliary Building at the panel located in the Auxiliary Building at the 100' elevation as shown below. Each hot 100' elevation as shown below. Each hot shutdown panel is a single control panel.

shutdown panel is a single control panel with two sub-panels.

2 7.1.2.4 7.1.2.4 Chemical and Volume Control System Chemical and Volume Control System N/A - added new content

23. Cold leg loop charging motor operated valve 8107
24. Cold leg loop charging motor operated valve 8108
25. Charging to loop 4 cold leg air operated valve 8146
26. Refueling water supply to charging pump suction header valve 8805A pressure indicator 3

7.1.2.4 7.1.2.4 Containment Fan Coolers Containment Fan Coolers

1. Containment Fan Cooler transfer switch
1. Containment Fan Cooler transfer switch
2. Containment Fan Cooler control switch
2. Containment Fan Cooler control switch Containment Fan Cooler ON/OFF status
3. Containment Fan Cooler ON/OFF status 4

7.1.2.4 7.1.2.4 Makeup Water Makeup Water Page 1 of 8 PG&E Letter DCL-19-093 PG&E Letter DI L-19-013 Description of Change Modified content.

Added in "with two sub-panels." Sub-panels were added to the Unit 1 and Unit 2 hot shutdown panels (HSDPs) as part of the National Fire Protection Association (NFPA) 805 project.

10 CFR 50.54(q) Effectiveness Evaluation 2019-13 documents the detailed analysis of this chanae.

Modified content.

Added in four (4) new chemical and volume control system (CVCS) controls available at the HSDPs. These controls were added to the Unit 1 and Unit 2 HSDPs as part of the NFPA 805 project.

10 CFR 50.54(q) Effectiveness Evaluation 2019-13 documents the detailed analysis of this change.

Modified content.

Editorial change to number the last item for consistency.

This change does not affect how the current Emergency Plan (E-Plan) meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.

Modified content.

Editorial change to number the last item for consistency.

Change Original Content (Rev 4.21)

Revised Content (Rev 4.22)

1. Condensate Storage Tank level indicator
1. Condensate Storage Tank level indicator Raw Water Reservoir level indicator
2. Raw Water Reservoir level indicator 5

7.1.2.4 7.1.2.4 NIA - added new content Reactor Coolant System

8. Hot Leg loop 4 pressure indicator
9. Hot Leg loop 4 wide range temperature indicator
10. Cold Leg loop 4 wide range temperature indicator 6

7.1.4.3 7.1.4.3 The TSC structure is designed to Seismic The TSC structure is designed to the Hosgri Class I criteria.

seismic criteria.

7 7.1.4.3 7.1.4.3 Under accident conditions, the supply to the Under accident conditions, the supply to the TSC is transferred to the Control Room TSC is transferred to the Control Room pressurization system that maintains the TSC at pressurization system that maintains the TSC a positive pressure.

at a minimum positive pressure of 1/8" water gage.

Page 2 of 8 PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 Description of Change This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.

Modified content.

Added in three (3) new reactor coolant system (RCS) indicators available at the HSDPs.

These indicators were added to the Unit 1 and Unit 2 HSDPs as part of the NFPA 805 project.

10 CFR 50.54(q) Effectiveness Evaluation 2019-13 documents the detailed analysis of this change.

Modified content.

Updated the Technical Service Center (TSC) description of seismic design for the TSC from Class I to Hosgri to align with content of Section 7.1.4.1 of the E-Plan which states that the TSC structure is designed to the Hosgri seismic criteria.

10 CFR 50.54(q) Effectiveness Evaluation 2019-12 documents the detailed analysis of this change.

Modified content.

Added in "a minimum" and "of 1/8" water gage" to restore language from the safety evaluation report (SER) approved E-Plan that was previously removed.

This change restores verbatim NRC approved language from the SER E-Plan to the current E-Plan. This change ensures all originally approved licensing requirements continue to

Change Original Content (Rev 4.21) 8 7.5.2.1 Site meteorological conditions are monitored continuously by the two on-site meteorological towers that are in close proximity to the plant structures. A primary 76-meter tower system is located about 200 meters SSW of the plant structures. Measurements have been taken and used from this site since July 1967. The following data are provided: wind speed, wind direction, wind direction standard deviation at the 10-meter and 76-meter levels; temperature at 10-meters; temperature difference ( delta T) between 10-meter and 46-meter and between 10-meter and 76-meter levels; precipitation and dew point near the tower base; and 10-meter, 46-meter and 76-meter aspirator currents.

Meteorological data at the primary site is recorded continuously on strip charts and digitized electronically at two-second intervals.

Fifteen-minute mean values are computed from the 2-second values by microprocessor within the primary met facility and are sent to the Unit 1 Transient Recording System (TRS). The Unit 1 TRS is interfaced to the Unit 1 Plant Process Computer (PPC). TRS transmits data to the PPC where they are archived and alarm processed.

Revised Content (Rev 4.22) 7.5.2.1 Site meteorological conditions are monitored continuously by the two on-site meteorological towers that are in close proximity to the plant structures. A primary 76-meter tower system is located about 200 meters SSW of the plant structures. Measurements have been taken and used from this site since July 1967. The following data are provided:

Wind speed, wind direction, wind direction standard deviation at the 10-meter and 76-meter levels Temperature at 10-meters, 46-meters, and 76-meters Temperature difference (delta T) between 10-meter and 46-meter and between 10-meter and 76-meter levels Precipitation and dew point near the tower base 10-meter, 46-meter and 76-meter aspirator frequency Meteorological data at the primary site is recorded continuously on a multi-point recorder and digitized electronically at least once every two-seconds. A primary meteorological digital processor is located in the primary meteorological facility that communicates data to redundant meteorological computers located in the Technical Support Center (TSC)

(FSAR 2.3.4). Fifteen-minute mean values are computed from the transmitted data by the Page 3 of 8 PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 Description of Change be clearly documented.

This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation reauired.

Modified content.

Updated onsite met tower descriptions.

10 CFR 50.54(q) Effectiveness Evaluation 2019-14 documents the detailed analysis of this change.

Change Original Content (Rev 4.21)

Primary Met data are sent to the Unit 2 PPC via the backup Met tower computer (FSAR 2.3.3.7) and the Unit 2 TRS.

The 15 minute values are also sent to the EARS Computer System, and select meteorological parameters to both unit's Emergency Response Data System (EROS).

9 7.5.2.1 A backup 60-meter tower system is located about 1.2 KM ESE of the primary tower with two levels of measurement at 10-meters and 60-meters. Measurement, reduction, storage, recording and transmission of backup tower data are continuous with and similar to that of the primary system. The backup Met system measures 60m - 1 Om temperature difference and sum of aspirator currents and battery voltage (FSAR 2.3.3.6.).

10 7.5.2.1 The backup Met computer is located in the TSC (FSAR 2.3.3.7.).

11 7.5.2.1 To minimize required battery capacity, further backup is provided by a spring-wound strip-chart with mechanically driven pens.

Revised Content (Rev 4.22)

TSC meteorological computers.

The redundant TSC meteorological computers provide data to redundant meteorological data servers which provide Unit 1 & 2 network communication of the 15 minute values to the Plant Data Network (PON), the Emergency Assessment and Response System (EARS),

the Plant Process Computers (PPC) and select meteorological parameters to the Emergency Response Data System (EROS).

7.5.2.1 A backup 60-meter tower system is located about 1.2 KM ESE of the primary tower with two levels of measurement at 10-meters and 60-meters. Measurement, reduction, storage, recording and transmission of backup tower data are continuous with and similar to that of the primary system. The backup Met system measures (FSAR 2.3.4):

Aspirator frequency.

Battery condition.

Temperature difference (delta T) between 10-meter and 60-meter 7.5.2.1 A backup meteorological digital processor is located in the backup meteorological facility that communicates data to redundant meteorological computers located in the TSC (FSAR 2.3.4).

7.5.2.1 N/A-content removed Page 4 of 8 PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 Description of Change Modified content.

Updated onsite met tower descriptions.

10 CFR 50.54(q) Effectiveness Evaluation 2019-14 documents the detailed analysis of this change.

Modified content Updated onsite met tower descriptions.

10 CFR 50.54(q) Effectiveness Evaluation 2019-14 documents the detailed analysis of this change.

Removed content.

Removed description of spring-wound strip chart.

10 CFR 50.54(q) Effectiveness Evaluation

Change Original Content (Rev 4.21) 12 7.5.2.1 In the event of failure of all electronic measurement systems, a portable weather station is available. This unit is battery powered for independent operation. The instrument provides recording of wind speed, wind direction and ambient temperature, which can be used to estimate off-site effects through manual calculation procedures in the event of failure of the automated assessment process.

13 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table Beta Gamma count rate meter, with the following detectors Range 0-600, 0-6000, 0-60,000 CPM 14 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table Count rate meter (RM-15) for use with GM probes listed above, and:

Range 0-500, 0-5K, 050K, 0-500K CPM 15 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table Revised Content (Rev 4.22) 7.5.2.1 In the event of failure of both the primary and backup electronic measurement systems, a portable weather instrumentation package is available for deployment. This instrumentation package is battery powered for independent operation and provides recording of wind speed, wind direction and ambient temperature, which can be used to estimate off-site effects through manual calculation procedures in the event of failure of the automated assessment process.

7.5.7 Typical Portable Count and Dose Rate Meters Used - Table Beta Gamma count rate meter, with the following detectors Range 0-600 CPM 0-6,000 CPM 0-60,000 CPM 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table Count rate meter (RM-15) for use with GM probes listed above, and:

Range 0-500 CPM 0-5,000 CPM 0-50,000 CPM 0-500,000 CPM 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table Page 5 of 8 PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 Description of Change 2019-14 documents the detailed analysis of this change.

Modified content.

Updated language to reflect actual capability for the tertiary met tower.

10 CFR 50.54(q) Effectiveness Evaluation 2019-15 documents the detailed analysis of this change.

Modified content.

Editorial change to improve readability.

This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.

Modified content.

Editorial change to improve readability.

This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.

Modified content.

Change Original Content (Rev 4.21)

Count rate meter (PRM-6) for use with GM probes listed above AC-3B-7 and SPA-3 probes Range 0-500, 0-5K 050K, 0-500K CPM 16 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table Beta Gamma dose rate meter (HP 270 shielded hand probe)

Range

.1 -10KmR/hr (HP-270 probe 0-3000 mR/hr) 17 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table Portable REM Counter (PNR-4)

Range 0-5,0-50,0-500,0-5000 mR/hr 18 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table T eletector 6112 OR Equivalent (Johnson Extender, Telescan)

Revised Content (Rev 4.22)

Count rate meter (PRM-6) for use with GM probes listed above AC-3B-7 and SPA-3 probes Range 0-500 CPM 0-5,000 CPM 0-50,000 CPM 0-500,000 CPM 7.5.7 Typical Portable Count and Dose Rate Meters Used -Table Beta Gamma dose rate meter (HP 270 shielded hand probe)

Range 0.1-10,000 mR/hr 0-3000 mR/hr (HP-270 probe) 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table Portable REM Counter (PNR-4)

Range 0-5 mR/hr 0-50 mR/hr 0-500 mR/hr 0-5000 mR/hr 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table Teletector 6112 OR Equivalent (Johnson Extender, Telescan)

Page 6 of 8 PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 Description of Change Editorial change to improve readability.

This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.

Modified content.

Editorial change to improve readability.

This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.

Modified content.

Editorial change to improve readability.

This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.

Modified content.

Editorial change to improve readability.

This change does not affect how the current E-Plan meets any planning

Change Original Content (Rev 4.21)

Range 0-2 mR/hr 0-50 mR/hr 0-2 R/hr 0-50 R/hr 0-1000 R/hr 19 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table RO-2 or equivalent Range Dose rate: 0-5, 0-50, 0-500 mR/hr, 0-5R/hr 20 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table RO-2A or equivalent Range 0-50, 0-500 mR/hr 0-5, 0-50 R/hr 21 7.5.8 Hospital Kit Contents Disposal Coveralls Dosimeter Charger Personnel Decon. Records (69-9392)

Revised Content (Rev 4.22)

Range 0-2 mR/hr 0-50 mR/hr 0-2 R/hr 0-50 R/hr 0-1000 R/hr 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table RO-2 or equivalent Range 0-5 mR/hr 0-50 mR/hr 0-500 mR/hr 0-5 R/hr 7.5.7 Typical Portable Count and Dose Rate Meters Used - Table RO-2A or equivalent Range 0-50 mR/hr 0-500 mR/hr 0-5 R/hr 0-50 R/hr 7.5.8 Hospital Kit Contents Disposable Coveralls N/A-content removed N/A-content removed Page 7 of 8 PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 Description of Change standard functions, elements, or site-specific commitments. No additional evaluation required.

Modified content.

Editorial change to improve readability.

Removed "Dose rate:" as it is implied in the units of measure.

This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.

Modified content.

Editorial change to improve readability.

This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.

Modified content and removed content Editorial change to correct "Disposal" to "Disposable".

Removed "Dosimeter Charger" from the kit contents as the type of dosimeters used now do not require a charger.

Change Original Content (Rev 4.21)

Revised Content (Rev 4.22)

Page 8 of 8 PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 Description of Change Removed "Personnel Decon. Records (69-9392)" as it was replaced by "Radiation and Contamination Survey Sheet (Form 69-20786)".

This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.

PG&E Letter DCL-19-093 PG&E Letter DIL-19-013 Emergency Plan Section 7, Revision 4.22, "Emergency Facilities and Equipment"

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment Table of Contents Page 1 of 68

7.

EMERGENCY FACILITIES AND EQUIPMENT.................................................................... 2 7.1 Emergency Response Facilities.................................................................................. 3 7.1.1 Control Room................................................................................................ 3 7.1.2 Hot Shutdown Panel..................................................................................... 5 7.1.3 Dedicated Shutdown Panel........................................................................... 8 7.1.4 Technical Support Center (TSC)................................................................. 10 7.1.5 Operational Support Center........................................................................ 17 7.1.6 Emergency Operations Facility................................................................... 19 7.1.7 PG&E Energy Education Center................................................................. 24 7.1.8 San Luis Obispo Service Center................................................................. 25 7.2 Communications Equipment..................................................................................... 26 7.2.1 Plant Telephone Network............................................................................ 26 7.2.2 Communication Interface with Public Switched Telephone Network (PSTN)27 7.2.3 Power Supplies........................................................................................... 27 7.2.4 Control Room Telephone Communication................................................... 27 7.2.5 Telephone Communications for the Technical Support Center (TSC)......... 28 7.2.6 Operational Support Center Telephone Communications........................... 28 7.2.7 Telephone Communication at the Emergency Operations Facility (EOF).... 28 7.2.8 Data Communication System...................................................................... 29 7.2.9 Nuclear Regulatory Commission Communication Lines.............................. 29 7.2.1 O Satellite Telephones................................................................................... 30 7.2.11 UHF and VHF Radio System...................................................................... 30 7.2.12 Joint Information Center.............................................................................. 31 7.2.13 News Services Office San Francisco.......................................................... 31 7.3 On-Site Signals and Alarms...................................................................................... 31 7.3.1 Site Emergency Signal................................................................................ 31 7.3.2 Fire Signal................................................................................................... 32 7.3.3 Criticality Monitor Signal.............................................................................. 32 7.3.4 Containment Evacuation Signal.................................................................. 32 7.4 Off-Site Early Warning System................................................................................. 33 7.4.1 Outdoor Warning......................................................................................... 33 7.4.2 Indoor Warning........................................................................................... 34 7.4.3 Early Warning System-Area of Coverage.................................................... 34 7.4.4 Siren Location............................................................................................. 36 7.4.5 Early Warning System Activation................................................................ 36 7.5 On-Site Assessment Systems and Equipment.......................................................... 36 7.5.1 Seismic Monitoring System (SMS).............................................................. 36 7.5.2 Meteorological Systems.............................................................................. 37 7.5.3 Area Radiation Monitoring System.............................................................. 39 7.5.4 Process Radiological Monitoring System.................................................... 41 7.5.5 Radiological Counting Room....................................................................... 44 7.5.6 Analytical Facilities Associated with On-Site Technical Support Center...... 44 7.5.7 Portable Survey and Dose Rate Instruments..............................................48 7.5.8 Field Monitoring and Evacuation Kits.......................................................... 49 7.5.9 Fire Detection and Trouble Alarm System................................................... 51 7.5.10 Sampling and Analysis Capability............................................................... 51 7.5.11 Miscellaneous Post Accident Assessment lnstruments............................... 51 7.6 Off-Site Monitoring Equipment.................................................................................. 53 7.6.1 Off-Site Geophysical Monitors..................................................................... 53 7.6.2 Off-Site Meteorological Data....................................................................... 53 E-Plan_Section_7u3r22.DOC 1002.1 61 O Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment Page 2 of 68 7.6.3 Environmental Direct Radiation Monitors and Air Sampling Devices........... 53 7.6.4 Off-Site Radiation Monitoring System......................................................... 57 7.6.5 Off-Site Laboratories................................................................................... 59 7.6.6 Off-Site Emergency Laboratory (OEL)........................................................ 60

7. 7 Miscellaneous Protective Facilities and Equipment................................................... 60 7.7.1 Installed Smoke, Flame & Heat Detectors................................................... 60 7.7.2 Fire Detection by Personnel........................................................................ 61 7.7.3 Plant Fire Detection and Suppression and Respiratory Protection.............. 62 7.7.4 Halon 1301 Systems................................................................................... 62 7.7.5 Mobile Fire Fighting Equipment................................................................... 62 7.7.6 Respiratory Protection Equipment............................................................... 62
7. 7. 7 Self-Contained Breathing Apparatus T03689............................................... 63 7.7.8 Constant Flow Air Line Respirators............................................................. 63 7.7.9 Radiological Protective Clothing.................................................................. 63
7. 7.10 Containment Hydrogen Recombiners......................................................... 64
7. 7.11 Permanent Lighting Systems...................................................................... 65 7.7.12 Portable Lighting......................................................................................... 65 7.7.13 Transportation............................................................................................. 66
7. 7.14 Alternative Facilities.................................................................................... 67 7.8 First Aid and Medical Facilities.................................................................................. 67 7.8.1 Personnel Decontamination Facilities......................................................... 67 7.8.2 First Aid Kits and Stretchers........................................................................ 67 7.8.3 Whole Body Counters................................................................................. 67 7.9 Cross Reference To NUREG-0654........................................................................... 68
7.

EMERGENCY FACILITIES AND EQUIPMENT If corrective measures are to be promptly initiated in an emergency situation, it is important required emergency equipment and facilities be readily available. To the maximum extent possible, normal plant equipment and controls will be used to mitigate the consequences of an accident. In some instances, special emergency equipment and facilities have been provided. This section describes this special equipment in conjunction with normal plant equipment that has particular application in an emergency.

The Emergency Plan provides for a number of on-site and off-site facilities intended for use as accident management centers, and personnel staging and planning areas. These facilities are discussed briefly in the following paragraphs.

E-Plan_Section_7u3r22.DOC 1002.161 O Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment Page 3 of 68 7.1 EMERGENCY RESPONSE FACILITIES 7.1.1 Control Room 7.1.1.1 Location and Description The Control Room is common to Units 1 and 2 and is located at the 140' elevation of the Auxiliary Building as shown below. The Shift Manager's office is located adjacent to the Control Room. The Control Room has lavatory and kitchen facilities.

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i CALLED Na Rm 71-1 7.1.1.2 Emergency Function Prior to the time the Technical Support Center (TSC) is activated (and throughout the course of an emergency in which the TSC is not activated) the Control Room will serve as the headquarters for the Site Emergency Coordinator. All on-site activities are directed from this location, and all communication with off-site agencies will originate from the Control Room. The Control Room has the necessary equipment and instruments to perform accident assessment work involving possible or actual radiological releases and fuel barrier damage.

Following activation of the TSC, overall control of on-site activities will be transferred to the TSC. If the TSC is activated before the EOF, then the TSC will assume responsibilities for communications with off-site agencies until relieved by the EOF. The Control Room will then be headquarters of the on-site Operations Coordinator, and the major Control Room activity will be operation of plant equipment to mitigate the consequences of the emergency.

The Control Room also serves as the backup to the TSC should the latter be unavailable.

E-Plan_Sec1ion_7u3r22.DOC 1002.161 O Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment 7.1.1.3 Habitability Objectives Page 4 of 68 The Control Room is designed to be habitable throughout the course of a design-basis accident. The Control Room shielding and ventilation system is designed to limit post-accident doses to 5 rem TEDE for the duration of the accident.

The Control Room is provided with a Design Class I Criteria Ventilation System. The design of the system includes provisions for:

1)

Protection from smoke generated inside or outside the Control Room area.

2)

Protection from airborne radioactivity outside the Control Room and provisions for cleanup of activity trapped in the room.

3)

Protection from airborne toxic gas outside the Control Room.

4)

Provisions for limiting carbon dioxide buildup inside the Control Room during periods when airborne contaminants prevent use of outside makeup air.

7.1.1.4 Special Equipment The Control Room is the most completely equipped location in the plant in terms of provisions to monitor the status of plant systems and equipment. The Control Room has complete communication capability; as well as access to meteorological, seismic, and radiological monitoring data.

E-Plan_Section_7u3r22.DOC 1002.1610 Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment 7.1.2 Hot Shutdown Panel 7.1.2.1 Location and Description Page 5 of 68 Each unit is provided with a hot shutdown panel located in the Auxiliary Building at the 100' elevation as shown below. Each hot shutdown panel is a single control panel with two sub-panels.

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~* -- IJE'DIC:r1TED HOT SHUT DO Wl-l REMOTE COl'./TROL PA i\\TE/L The hot shutdown panel contains the essential indicator and controls to maintain a unit in hot standby condition for an extended time period. The hot shutdown panel is primarily intended to be used for a situation in which smoke or toxic gas makes the Control Room temporarily uninhabitable. In such a circumstance, the operators are instructed to trip the reactor as they leave the Control Room and proceed to the hot shutdown panel. From this location, the unit can safely be maintained in the hot standby condition until the Control Room can be reentered.

Any occurrence requiring the use of the hot shutdown panel would also involve activation of the TSC. Overall emergency response actions, including off-site communications, would be handled from the TSC, where the Site Emergency Coordinator would establish his headquarters. A licensed operator would be stationed at the hot shutdown panel.

E-Plan_Section_7u3r22.DOC 1002.161 O Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment Page 6 of 68 7.1.2.3 Habitability Objectives The hot shutdown panels are not intended for use in radiological release type accidents.

They are open to the room atmosphere in the "clean" (radiologically) portion of the Auxiliary Building. No special provisions have been made to assure habitability during radiological release emergencies.

7.1.2.4 Special Equipment Hot Shutdown Panel Instrumentation and Controls are listed below. Each panel has a telephone and an emergency UHF radio for operations frequency.

Auxiliary Feedwater

1.

AFW Pump discharge pressure

8.

Turbine Driven AFW Pump steam supply

2.

AFW flow indication valve control switch

3.

Turbine Driven AFW Pump Control Valve

9.

Turbine Driven AFW Pump steam supply transfer switch valve transfer switch

4.

Turbine Driven AFW Pump Control Valve

10.

Turbine Driven AFW Pump steam supply control switch valve position indication

5.

Turbine Driven AFW Pump Control Valve

11.

Motor Driven AFW Pump control switch position indicator

12.

Motor Driven AFW Pump mode selector

6.

Motor Driven AFW Pump Control Valve switch controller

13.

Motor Driven AFW Pump

7.

Motor Driven AFW Pump Control Valve START/STOP/LOCAL indicator position indicator Auxiliary Saltwater

1.

Auxiliary Saltwater Pump control switch

2.

Auxiliary Saltwater Pump mode selector switch

3.

Auxiliary Saltwater Pump START/STOP/LOCAL status Chemical and Volume Control System

1.

Centrifugal Charging Pump control switch

15.

Emergency borate valve control switch

2.

Centrifugal Charging Pump mode selector

16.

Emergency borate valve position indicator switch

17.

Emergency boric acid flow indicator

3.

Centrifugal Charging Pump

18.

Volume Control Tank level indicator START/STOP/LOCAL indicator

19.

Letdown flow indicator

4.

Boric Acid Transfer Pump transfer

20.

Charging header flow indicator

5.

Boric Acid Transfer Pump control switch

21.

Charging header pressure indicator

6.

Boric Acid Transfer Pump ON/OFF

22.

Reactor Coolant Pump Seal No. 1 pressure indicator indicator

7.

Reactor Coolant Pump seal injection back

23.

Cold leg loop charging motor operated pressure control valve controller valve 8107

8.

Centrifugal Charging Pump flow control

24.

Cold leg loop charging motor operated valve controller valve 8108

9.

Reactor Coolant Pump seal injection back

25.

Charging to loop 4 cold leg air operated pressure control valve position indicator valve 8146

10.

Centrifugal Charging Pump flow control

26.

Refueling water supply to charging pump valve position indicator suction header valve 8805A pressure

11.

Letdown Valve transfer switch indicator

12.

Letdown Valve control switch

13.

Letdown Valve position indicator

14.

Emerqencv borate valve transfer switch E-Plan_Section_7u3r22.DOC 1002.161 O Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment Page 7 of 68 Component Cooling Water

1.

Component Cooling Water Pump control switch

2.

Component Cooling Water Pump mode selector switch

3.

Component Cooling Water Pump START/STOP/LOCAL status Containment Fan Coolers

1.

Containment Fan Cooler transfer switch

2.

Containment Fan Cooler control switch

3.

Containment Fan Cooler ON/OFF status Makeup Water

1.

Condensate Storage Tank level indicator

2.

Raw Water Reservoir level indicator Reactor Coolant System 1.

Pressurizer liquid temperature indicator

7.

Pressurizer Power Operated Relief Valve

2.

Pressurizer pressure indicator emergency close switch

3.

Pressurizer level indicator (2)

8.

Hot Leg loop 4 pressure indicator

4.

Pressurizer heater transfer switch (2)

9.

Hot Leg loop 4 wide range temperature

5.

Pressurizer heater control switch (2) indicator

6.

Pressurizer heater breaker position

10.

Cold Leg loop 4 wide range temperature indicator (2) indicator Steam Generators

1.

Pressure indicator

3.

Steam dump valve controller

2.

Level indicator

4.

Steam dump valve position indication Other 1.

Source Range neutron flux indicator (2)

3.

4kV vital bus voltage indicator

2.

Site emerQency alarm switch E-Plan_Section_7u3r22.DOC 1002.1610 Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment 7.1.3 Dedicated Shutdown Panel 7.1.3.1 Location Page 8 of 68 Each unit is provided with a dedicated shutdown panel located in the 100' elevation of the Auxiliary Building, as shown below.

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7.1.3.2 Emergency Function The dedicated shutdown panel in conjunction with the Hot Shutdown Panel is used if the unit must be taken from the hot shutdown condition to the cold shutdown condition from outside the Control Room. The dedicated shutdown panel contains sufficient instrumentation to follow and direct the cooldown operation and has controls for the pressurizer auxiliary spray control valve operation. The actual manipulation of other controls and valves would be done by operators at appropriate local stations.

Any occurrence requiring the use of the dedicated shutdown panel would also involve activating the TSC. Overall recovery actions, including off-site communications, would be handled from the TSC, where the Site Emergency Coordinator would establish his headquarters. An operator would be stationed at the dedicated shutdown panel.

E-Plan_Section_7u3r22.DOC 1002.161 O Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment 7.1.3.3 Habitability Objectives Page 9 of 68 The dedicated shutdown panels are not intended for use in radiological release type accidents. They are open to room atmosphere. No special provisions have been made to assure habitability during radiological emergencies.

7.1.3.4 Special Equipment Instruments found on each dedicated shutdown panel are listed below. PG&E phone jacks are located near each panel. Portable, hand held radio units may also be used for communications if required.

Steam Generators

1.

Level indicator (each steam generator)

Reactor Coolant System

1.

Temperature indicator - RCS Loop 1 3.

RCS Loop 4 pressure indicator

2.

RCS Loop 1 Temperature selector

4.

Pressurizer level indicator switch Chemical and Volume Control System 1.

Auxiliary spray valve transfer switch

2.

Auxiliary spray valve control switch E-Plan_Section_7u3r22.DOC 1002.161 O Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment 7.1.4 Technical Support Center (TSC) 7.1.4.1 Location and Description Page 10 of 68 The purpose of the TSC is to provide a facility separate from but in close proximity to the Control Room. The TSC has the capability to display and transmit plant status to personnel responsible for engineering and management support of reactor operations in the event of an accident. This separate facility is needed to house data gathering equipment and the personnel required to assist in an emergency, primarily to reduce Control Room congestion.

The TSC serves both Units 1 and 2 and consists of six rooms. The TSC is sized to accommodate a minimum of 20 company and 5 NRC personnel. It is located at elevation 104' on the west side of the Unit 2 Turbine Building. It occupies space created as a result of the exterior concrete buttress seismic modification of the turbine building. The thickness of the concrete walls required to enclose the TSC were largely dictated by radiation shielding considerations and the structure is designed to the Hosgri seismic criteria.

The figure below shows the location of the TSC within the plant.

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E-Plan_Section_7u3r22. DOC 1002.161 O Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment Page 11 of 68 The room layout and description from North to South is:

1)

Command Center Desks, files and conference table provided for plant operations management, maintenance and technical staff personnel.

2)

Operations Center Plant parameter data gathering and display equipment is provided for the use of technical staff in assessing the plant condition. The Emergency Response Facility Data System (ERFDS) is located in this room.

3)

Computation Center Radiological and meteorological data gathering and display equipment and communications equipment is provided for the use of technical staff in assessing radiological conditions on and off-site.

4)

Records Management and Reproduction Plant manuals, emergency plans and procedures, access to microfilm drawings and other records, and certain hard copy drawings are provided.

5)

HVAC Room Heating, ventilating, and air-conditioning equipment for the TSC is located in this room.

6)

Laboratory (Radiological Counting Room)

In a room adjacent to the TSC, radiological laboratory equipment for analysis of samples is provided.

The radiological counting room is intended to be a backup location for this type of work in the event the norm'al counting room is unavailable.

It is equipped with a multi-channel gamma ray spectroscopy system using a high-resolution intrinsic germanium detector.

E-Plan_Section_7u3r22.DOC 1002.161 O Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment The following figures show the general floor plan of the TSC.

E-Plan_Section_7u3r22.DOC 1002.161 O COMMANIO CENTER 17 OPERA HONS CENTER B

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Page 12 of 68 I,

Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment

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Page 13 of 68 Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment TSC Continued LABORATORY a

D 7.1.4.2 Emergency Function Page 14 of 68 The TSC when activated serves as the headquarters for the Site Emergency Coordinator, Operations Advisor, Radiological Advisor, Agency/ENS Communicator, and Engineering Advisor and their staffs throughout an emergency. Provisions have also been made for the establishment of an on-site NRG emergency team co-located in the TSC.

Following activation of the TSC, the overall on-site assessment and recovery programs will be directed from this location. In addition, communications with off-site emergency response locations will be handled through the TSC.

E-Plan_Section_7u3r22.DOC 1002.1610 Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment 7.1.4.3 Habitability Objectives Page 15 of 68 The TSC is designed to be habitable throughout the course of a design basis accident. The outside walls, with steel bulkhead doors, form an airtight perimeter. The TSC shielding and ventilation system is designed, consistent with the criteria for the Control Room, to limit post-accident doses inside the TSC to 5 rem TEDE for the duration of the accident, provided normal ventilation is switched to emergency ventilation within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the onset of a radiological release from a design basis accident. The TSC structure is designed to the Hosgri seismic criteria.

The TSC is provided with its own ventilation system. The ventilation system is shown below.

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Under accident conditions, the supply to the TSC is transferred to the Control Room pressurization system that maintains the TSC at a minimum positive pressure of 1 /8" water gage. Intake air is conditioned and internally re-circulated through High Efficiency Particulate Air (HEPA) and charcoal filters within the TSC. The pressurization air filtrates from the TSC to the outside atmosphere. The pressurization portion of the ventilation system, including the duct work, redundant ventilation fans and filter units for the TSC, are designed to Seismic Class I criteria. The fans are powered from 480-volt non-vital buses but can be transferred to a 480-volt vital bus on either unit. The air conditioning units are not designed as seismic structures and are powered from normal AC sources.

E-Plan_Section_7u3r22.DOC 1002.161 O Rev 4.22

E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment Page 16 of 68 The TSC intake air is monitored by GM Detectors with alarm and control capabilities as part of the Control Room ventilation system. It also has area, particulate, iodine, and noble gas monitors with alarm capabilities, which may be backed up by portable equipment. The TSC is also provided with self-contained breathing apparatus and protective clothing for use in an emergency.

7.1.4.4 Special Equipment

1)

Safety Parameter Display System (SPDS)

The SPDS was designed to the guidelines specified in NUREG-0696 and NUREG-0737 Supp. 1. It is part of the Emergency Response Facility Data System (ERFDS).

The SPDS for each unit is a computer-based system consisting of a data acquisition system, server computers, and display computers.

There are two high-resolution color SPDS monitors in the TSC. The displays available for the monitors allow TSC personnel to view plant parameters in real time ("SPDS display"), primary and secondary system mimics, and decision trees.

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E-Plan Section 7 - Diablo Canyon Power Plant Emergency Plan Emergency Facilities and Equipment Page 17 of 68

2)

Emergency Response Data System (EROS)

The Emergency Response Data System is a direct near real-time electronic data link between a DCPP installed plant computer system and the Nuclear Regulatory Commission's Operations Center and Regional Office. This system provides for the automated transmission of a limited set of selected parameters and supplements the existing voice transmission over the NRC Virtual Private Network (VPN). Activation of this system occurs at an Alert or higher emergency classification.

3)

Communication The TSC is provided with full radio and telephone communications capability.

4)
  • Radiological Analysis The TSC contains radiological laboratory equipment. The TSC is also tied into the emergency radiological monitoring network.
5)

Plant Process Computer The TSC is provided with a display terminal and a printer for each unit's Plant Process Computer (PPC). This provides the ability to monitor and print plant parameters acquired by the PPC.

6)

Transient Recording System The ERFDS recall functionality is provided by the main plant historian hosted on the DMZ servers. The ERFDS data is available on at least two (2) display computers in the TSC.

7.1.5 Operational Support Center 7.1.5.1 Location and Description The Operational Support Center (OSC) provides locations functionally separate from the Control Room and Technical Support Center where designated support personnel assemble and await specific assignment during an emergency. The OSC command center is located in the buttress area on 104-foot elevation, adjacent to the west side of the Unit 2 Turbine Building and the south end of the TSC. Depending on the emergency events and plant conditions, personnel assigned to the OSC may be directed to assemble at the OSC command center, the 85' RCA Access Control, the site medical facility, the firefighters equipment storage area on the 140' elevation. OSC assembly areas serve as team dispatch locations and contain a variety of emergency support equipment immediately available for emergency use. The OSC command center is equipped with a dedicated tie line telephone extension to other facilities. Alternate backup locations for the OSC command center include:

Elevation 140' Turbine Building northeast corner Administration Building (Room 215)

E-Plan_Section_7u3r22.DOC 1002.161 O Rev 4.22

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