ML20046D499

Forwards Public Version of Rev to Epips,Including Rev 12 to EP RB-15:A,Rev 8 to EP RB-15:B,Rev 15 to EP EF-1,Rev 14 to EP EF-2,Rev 3 to EP RB-10,Rev 1 to EP EF-3A & Rev 1 to EP EF-3B.W/930806 Release Memo

ML20046D499
Person / Time
Site:	Diablo Canyon
Issue date:	07/16/1993
From:	Sexton J PACIFIC GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20046D500	List: ML20046D499
References
DCL-93-175, NUDOCS 9308200272
Download: ML20046D499 (5)

Text

Pacific Gas and Electric Company Nxiear Reguirar> Semnes A1SA James A Seer -

333 f/ rte: $"et TArace' PO Ba< 77D330 f.ritd' REoAn 5' . : .

San Trr:s:o CA 9"77 r.5STJ2;ff fan 415'973 0374 July 16,1993 PG&E Letter No. DCL-93-175 U.S. Nuclear Regulatory Commission

' ATTN: Document Control Desk Washington, D.C. 20555 Re: Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Emergency Plan Implementing Procedures Update Gentlemen:

In accordance with Section V, " Implementing Procedures," of 10 CFR 50 Appendix E, PG&E is submitting one copy of the update to the Detailed Emergency Plan Implementing Procedures for the Diablo Canyon Power Plant Units 1 and 2 Emergency Plan. Two copies of the update are being submitted to the NRC, Region V office, and one copy is being submitted to the NRC Resident Inspector.

These updates contain privacy / proprietary information that are bracketed in accordance with NRC Generic Letter 81-27.

Sincerely, s

James A. Sexton cc: Bobby H. Faulkenberry (2)

Ann P. Hodgdon (w/o Enclosure)

Mary H. Miller Sheri R. Peterson (w/o Enclosure)

Enclosure 61825/85K/ RAY /1345 I

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9308200272 930716 I

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PDR ADOCK 05000275 F PDR i

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PG&E Letter No. DCL-93-175 ENCLOSURE f,

UPDATE TO THE DETAILED IMPLEMENTING PROCEB "iS FOR THE l

DIABLO CANYON POWER PLANT UNITS 1 AND 2 EMEi N ~ PLAN Procedure Proprietary Title Information Number l

1 EP RB-15:A No " Post-Accident Sampling System Initial Actions,"

l Revision 12, effective 06/25/93.

EP RB-15:B No " Post-Accident Sampling System - Stripped-Gas and  !

Diluted RCS," Revision 8, effective 06/25/93. l I'

EP EF-1 Yes " Activation and Operation of the Technical Support Center," Revision 15, effective 06/25/93.  ;

Proprietary information contained in the following:

Attachment 6.5, Radiological Advisor (RA) Checklist, Action 2.9, 05/25/93, page 4 of 4. l Attachment 6.13, Computer Technical Advisor (CTA)

Checklist, Ini' #al Action 1.1.6, 05/25/93, page 1 of 2.

Attachment 6.29, Radiological Medical Emergency Checklist, Actions 2.3 and 2.5, 04/14/93, page 2 of 4.  :

Attachment 6.29, Radiological Medical Emergency Checklist, Action 2.8, 04/14/93, page 3 of 4.

EP EF-2 Yes " Activation and Operation of the Operational Support r Center," Revision 14, effective 06/25/93. f Proprietary information contained in Attachment 6.9, OSC Telephone Numbers, 04/08/93, page 1 of 1.

EP RB 10 Yes " Protective Action Recommendations," Revision 3, effective 06/25/93.

Proprietary information contained in Form 69-13216,

" Protective Action Recommendations (CR/TSC),"

03/31/93, page 1 of 1.

EP EF-3A No " Interim E0F Activation and Operation," Revision 1, effective 06/25/93.

EP EF-3B es "Long-Term EOF Activation and Operation," Revision 1, effective 06/25/93.

Proprietary information contained in Attachment 6.15, Initial Actions 1.4.1, 1.6.1 and 1.6.2, 05/19/93, page 1 of 2. ,

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..-o PG&E Letter No. DCL-93-175 CURRENT EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 38 TITLE REV G-1 Accident Classification and Emergency Plan Activation 19 G-2 Activation and Operation of.the Interim Site Emergency Organization (Control Room) 14 G-3 Notification of Off-Site Agencies and Emergency Organization Personnel 23 G-4 Personnel Accountability and Assembly 12 G-5 Evacuatioq of Nonessential Site Personnel 5 R-1 Personnel Injury or Illness (Radiologically Related) 21 and/or Overexposure R-2 Release of Airborne Radioactive Materials -13 R-3 Release of Radioactive Liquids 7 R-4 High Radiation (In-Plant) 5 R-7 Off-Site Transportation Accidents 10 OR-2 Release of Information to the Public 7 OR-3 Emergency Reentry and Recovery 2

, RB-1 Personnel Dosimetry -4 RB-2 Emergency Expos;.e Guides 3 RB-3 Stable Iodine Thyroid Blocking 3 RB-4 Access to and Establishment of Controlled Areas Under Emergency Conditions 4 RB-5 Personnel Decontamination 4 RB-6 Area and Equipment Decontamination 3 RB-7 Emergency On-Site Radiological Environmental Monitoring 9 RB-8 Emergency Off-Site Radiological Environmental Honitoring 10 RB-9 Calculation of Release Rate 7 RB-10 Protective Action Recommendations 3 RB-Il Emergency Off-Site Dose Calculations 7 RB-12 Plant Vent Iodine and Particulate Sampling During Accident Conditions 2 RB-13 Improved In-Plant Air Sampling for Radioiodines 1 RB-14 Core Damage Assessment Procedure 4 RB-15 Post-Accident Sampling System 4 a

6182S/85K TABLE OF CONTENTS Volume 3B (Continued)

TITLE REV RB-15:A Post-Accident Sampling System - Ini'ial Actions 12 RB-15:B Post-Accident Sampling System - Stripped-Gas and Diluted RCS 8 RB-15:C Sentry Post-Accident Sampling System - Containment Air Sampling and Analysis 6 RB-15:D Post-Accident Sampling System Gas Chromatographic Calibrations 5-RB-15:E Post-Accident Sampling System - Sample Handling and Boron Analysis 6 RB-15:F Sentry Post-Accident Sampling System - Data Analysis 6 '

RB-15:G Sentry Post-Acsident Sampling System - Ion Chromatograph u Chloride Calibration 4 RB-15:H Sentry Post-Accident Sampling System - pH/ Dissolved Oxygen Calibrations 4 RB-15:I Sentry Post-Accident Sampling System - Sample Storage and Disposal 2 RB-15:J Sentry Post-Accident Sampling System - Undiluted Liquid Sampling from Reactor Coolant 1 i RB-15:K Sentry Post-Accident Sampling System - Diluted Liquid Sampling from Radwaste 1 i RB-15:L Sentry Post-Accident Sampling System - Undiluted Liquid i Sampling from Radwaste 1  ;

RB-15:M Sentry Post-Accident Sampling System - Undiluted {

Containment Air Sampling l '

RB-15:N Sentry Post-Accident Sampling System - Demin Module O RB-15:0 Sentry Post-Accident Sampling System - Undiluted Liquid Open Grab and Pressurized Sampling from Reactor Coolant 0 EF-1 Activation and Operation of the Technical Support Center 15 EF-2 Activation and Operation of the Operational Support Center 14 EF-3A Interim EOF Activation and Operation 1 EF-3B Long-Term EOF Activation and Operation 1 EF-4 Activation of the Mobile Environmental Monitoring Laboratory 11 EF-6 Operating Procedures for EARS Stations 8 EF-9 Activation of Back-Up Emergency Response Facilities 2 I

6182S/85K _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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,( 'o, UNITED STATES y )pr ' ,g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 i

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'<, 's ,o# August 6, 1993 Docket #50-275 Diablo Canyon, Unit 1 .

Docket # 50-323 Diabl o Canyon, Unit 2 MEMORANDUM FOR: Chief, Document Control Branch, IRM j FROM: Director, Division of Freedom of Information and Publications Services, ADM

SUBJECT:

REVIEW OF UTILITY EMERGENCY PIldi DOCUMENTATION The Division of Freedom of Information and Publications Services has reviewed the attached document and has determined that it may now be made publicly available.

kdt& 7 Donnie H. Grinsley, Dir tor Division of Freedom of Information and Publications Services  ;

Office of Administration  :

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090059 i; l

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