ML20206R784

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Advises That 860701 Rev 13 to Emergency Response Plan Meets Planning Stds of 10CFR50.47(b) & Requirements of 10CFR50 App E.Items Re Training for Accident Assessment Team Members & off-normal Operating Procedures Closed
ML20206R784
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 09/15/1986
From: Verrelli D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Utley E
CAROLINA POWER & LIGHT CO.
References
NUDOCS 8609190194
Download: ML20206R784 (2)


Text

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.- arolina Power and' Light Company

.VATTN: Mr. E. E. Utley Senior Executive Vice President E . Power Supply and Engineering and Construction

~P.-0. Box 1551 Raleigh, NC 27602 Gentlemen:

SUBJECT:

DOCKET NO. 50-261 - H. B. ROBINSON STEAM ELECTRIC PLANT EMERGENCY PLAN REVIEW

' We have completed our. review of Revision 13 of the H. B. Robinson Steam Electric Plant Emergency Response Plan, dated July 1, 1986.

Our. review indicated that these changes to your H. B. Robinson Steam Electric Plant Emergency Response Plan meet the planning standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

Also during this review, the action taken on two of the Plan deficiencies issued l- on July'15, 1986, were evaluated. Specifically, the items concerned (1) the stated training requirement for the Accident Assessment Team members, and (2) the adequacy of the newly revised Off-normal Operating Procedures from an emergency planning standpoint. The action taken to change the Plan and the clarifying documentation submitted served to adequately resolve both of these issues. The subject items are closed.

.l 'Please be reminded that-10 CFR 50.47(b) requires NRC approval of any changes to i your Plan that may decrease the effectiveness of the Plan. However, if your safety review indicated no decrease in emergency preparedness, then changes can be made without NRC approval. In all cases, you should furnish copies of each

, change to the NRC in accordance with 10 CFR 50.54(q). Also, any changes to the

Emergency Plan Implementing Procedures should be made in accordance with the requirements of 10-CFR 50, Appendix E,Section V.

Should you have any questions regarding this letter, please contact Mr. Thomas R. .

i- Decker of the Region II staff at 404/331-2559.

i i Sincerely, i-David M. Verrelli, Chief Reactor Projects Branch 2 Division of Reactor Projects

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(See page 2) i 8609190194 860915 fDR ADOCK 05000261 I

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