ML20082N559
| ML20082N559 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/01/1983 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8312070225 | |
| Download: ML20082N559 (2) | |
Text
DUKE POWER GOMPANY
~
P.O. Box 33180 CFARLOTTE, N.C. 28242 HALH. TUCKER TELEPHONE m s mesman, (704) 373-4531 December 1, 1983 nuu. --
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370
Dear Sir:
Enclosed for NRC Staff use are tuo copies of the McGuire Nuclear Station Emergency Plan Implementing Procedures Index (Revision 6, dated November 1983). Please incorporate these into your Emergency Plan Implementing Procedures Manuals removing any earlier version pages. Also, delete procedure HP/0/B/1009/04 and tab.
This revision is being submitted in accordance with 10 CFR 50.54(q) and does not decrease the effectiveness of the Emergency Plan Implementing Procedures.
By copy of this letter, one copy of the above is being provided to the NRC, Region II.
Very truly yours,
- B u"A~/g Hal B. Tucker WHM/php i
Enclosures l
cc:
(w/1 copy of enclosure)
Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission l
Region II l
101 Marietta Street, NW, Suite 2900 i
Atlanta, Georgia 30303 ffY l
(w/o enclosure)
Mr. W. T. Orders
- O NRC Resident Inspector McGuire Nuclear Station 1
8312070225 831201 l
PDR ADOCK 05000369 F
pg
9 m
.g.
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE #
TITLE RP/0/A/5700/01 Notification of Unusual Event RP/0/A/5700/02 Alert
..RP/0/A/5700/03 Site Area Emergency RP/0/A/5700/04 General Emergency RP/0/A/5700/05 Care and Transporation of Contaminated Injured Individuals RP/0/A/5700/06 Natural Disasters
.RP/0/A/5700/07 Earthquake RP/0/A/5700/08 Release of Toxic or Flammable Gases RP/0/A/5700/09 Collisions / Explosions OP/1/A/6200/48
.. Operating Procedure for the Operation of the Post Accident Liquid Sample System, Unit 1 OP/2/A/6200/48 Operating Procedure for the Operation of the Post Accident Liquid Sample System, Unit 2 HP/0/B/1009/02' Alternative Methods for Determining Dose Rate within the Reactor Building HP/0/B/1009/03 Recovery Plan HP/0/B/1009/05 First Response Evaluation of Offsite Dose From a Reactor Coolant Leak Inside Containment HP/0/B/1009/06 Procedure for Quantifying High Level Gaseous Radioactivity Release During Accident Conditions HP/0/B/1009/08 Evaluation of a Reactor Coolant Leak i
Inside Containment
(~
HP/0/B/1009/09 Release of Reactor Coolant through Unit Vent Exceeding Technical Specifications l
HP/0/B/1009/10 Releases of Liquid Radioactive Exceeding Technical Specifications HP/1/B/1009/15 Unit 1 Nuclear Post Accident Containment Air Sampling System Operating Procedure HP/2/B/1009/15 Unit 2 Nuclear Post Accident Containment Air Sampling System Operating Procedure HP/0/B/1009/16 Tablets in the Event of a Radioiodine Release PT/0/A/4600/06 Exercises and Drills PT/0/A/4600/11 Functional Check of Emergency Vehicle-i and Equipment Station Directive 2.0.5 News Release Station Directive 2.5.1 Emergency Response Training Program Station Directive 3.7.3 Bomb Threat Station Directive 3.8.1 Site Assembly / Evacuation Station Directive 3.8.2 Station Emergency Organization Health Physics Manual Section:
18.1 Accident and Emergency Response 18.2 Environmental Monitoring for Emergency Conditions 18.3 Personnel Monitoring for Emergency Conditions l
J. O l
)
Rev. 6 4
November, 1983 i