ML20090C416
| ML20090C416 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/11/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8407130291 | |
| Download: ML20090C416 (5) | |
Text
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DuxE POWEn GOMPANY P.O. I,0X !KHHH CHAl t.OTTE, N.C. WHS49 vem a n
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at Ju1y 11, 1984 Mr. Harold R. Denton, Diiector Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4
Subject:
Catawba Nuclear Station Docket Nos. 50-413 & 50-414
Dear Mr. Denton:
Catawba SER, Supplement 2 Section 13.3.2.1.(2) identified a deficiency in the Crisis Management Plan, Duke Power's corporate emergency alan.
Table P-2 of the document does not list the procedures used by t1e CMC Dose Assessment Group for Catawba.
(It should be noted that dose assessment procedures for Catawba have been incorporated into the Crisis Management Plan Implementing Plans.)
In Revision 13 of the Crisis Management Plan, Table P-2 will be revised as shown in the attached pages to list these procedures. This revision will be made by August 15, 1984.
Very truly yours,
$5 "Adr Hal 8. Tucker NAVsib Attachment cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Catawba Nuclear Station Robert Guild, Esq.
Attorney-At-Law P. O. Box 12097 Charleston, South Carolina 29412
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Mr. Harold R. Denton, Director l
July 11, 1984 Page 2 cc: Palmetto Alliance 21356 Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley l
Carolina Environmental Study Group l
854 Henley Place l
Charlotte, North Carolina 28207 1
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r Table P-2 IMPLEMENTING PLAN CROSS REFERENCE Procedures Required to Implement the Crisis Management Plan Crisis Management Plan - Implementing Plans:
- 5. 3.1 Recovery Manager and Immediate Staff
- 5.3.2 Oconee Crisis News Center Plan & McGuire/ Catawba Crisis News Plan
- 5.3.3 Administration and Logistics Group Plan
- 5.3.4 Scheduling / Planning Group Plan
- 5.3.5 Design and Construction Support Group Plan
- 5.3.6 Nuclear Technical Services Group Plan
- 5.3.7 Nuclear Engineering Services Group Plan
- 5.3.8 (0 pen)
Crisis Management Plan - Implementing Procedures:
- 5.3.9 (0 pen)
- 5.3.10 Oconee Crisis Phone Directory
- 5.3.11 McGuire/ Catawba Crisis Phone Directory
- 5.3.12 Transmission of Followup Emergency Information to Offsite Agencies -
Oconee Nuclear Station
- 5.3.13 Transmission of Followup Emergency Information to Offsite Agencies -
McGuire Nuclear Station / Catawba Nuclear Station
- 5.3.14 Environmental Monitoring For Emergency Conditions - McGuire Nuclear Station
- 5.3.15 Environmental Monitoring For Emergency Conditions - Oconee Nuclear Station
- 5.3.16 Quarterly Inventory
- 5.3.17 OAC Data Available In An Emergency
- 5.3.18 Environmental Monitoring For Emergency Conditions-Catawba Nuclear Station
- 5.3.19 Procedure For Estimating Food Chain Dose Under Post Accident Conditions
- 5.3.20 fionthly Communications Tests for the McGuire/ Catawba CMC Proceduros Used by CMC Dose Assesment Group (Contiolled Copies Maintained By Emergency Response Coordinator}
McGuire HP/0/0/1009/05 First Response Evaluation of a Reactor Coolant Leak Inside l
Containment HP/0/0/1009/06 Procedure For Quantifying High Level Radioactivity Releases During Accident Conditions HP/0/8/1009/08 Evaluation of a Reactor Coolant Release Inside Containment P-4 Rev. 13
Table P-2 (cont'd)
IMPLEMENTING PLAN CROSS REFERENCE Procedures Used by CMC Dose Assessment Group (Controlled Copies Maintained by Emergency Response Coordinator)(cont'd)
McGuire (cont'd)
HP/0/B/1009/09 Release of Radioactive Materials Thru the Unit Vent Exceeding Technical Specifications HP/0/B/1009/010 Releases of Liquid Radioactive Materials Exceeding Technical Specifications Oconee AP/0/B/1000/07 Procedure for Offsite Dose Calculation by Control Room Personnel or Emergency Coordinator During a Radiological Accident HP/0/B/1009/10 Procedure for Quantifying Gaseous Releases Through Steam Relief Valves Under Post-Accident Conditions HP/0/B/1009/ll Projection of Offsite Dose From the Uncontrolled Release of Radioactive Materials Through a Unit Vent HP/0/B/1009/14 Project Offsite Dose from Releases Other than a Vent Catawba RP/0/B/5000/ll Protectiva Action Recommendations Without the OAC HP/0/B/1009/06 Alternative Method for Determining Dose Rate Within the Reactor Building HP/0/B/1009/12 Quantifying Gaseous Releases Through Steam Relief Valves under Post-Accident Conditions HP/0/B/1009/13 Offsite Dose Projection - Uncontrolled Release of Gaseous Radio-active Material Through the Unit Vent HP/0/B/1009/14 Offsite Dose Projection - Uncontrolled Release of Liquid Radio-active Material HP/0/B/1009/15 Offsite Dose Projection - Uncontrolled Release of Gaseous Radio-active Material Other than Through the Unit Vent P-5 Rev.13
Table P-2 (cont'd)
Sections of the CMP implemented by these plans / procedures:
Plan / Procedure CMP Section Implemented 5.3.1 B.7, C., D., D.,
F.
5.3.2 B.7 5.3.3 8.7 5.3.4 B.7 5.3.5 B.7 5.3.6 B.7 5.3.7 B.7 5.3.8 (open) 5.3.9 (open) 5.3.10 F
5.3.11 F
5.3.12 E
5.3.13 E
5.3.14 I
5.3.15 I
5.3.16 P
5.3.17 I
5.3.18 I
Dose Assessment I
5.3.20 F, N e
ti p_5 Rev 13
..