BSEP-96-0312, Responds to NRC Re Violations Noted in Insp Repts 50-324/96-07 & 50-325/96-07.Corrective Actions:Appropriate Personnel Will Participate in Addl Training Re Emergency Classification & Exercise Weakness and Decision Making

Responds to NRC Re Violations Noted in Insp Repts 50-324/96-07 & 50-325/96-07.Corrective Actions:Appropriate Personnel Will Participate in Addl Training Re Emergency Classification & Exercise Weakness and Decision Making

ML20117E652
Person / Time
Site:	Brunswick
Issue date:	08/26/1996
From:	Levis W CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-96-0312, BSEP-96-312, NUDOCS 9609030017
Download: ML20117E652 (4)

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. CP&L SERIAL: BSEP 96-0312 i 10 CFR 50 Appendix E  !

AUG 261996 ,

1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 i BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 RESPONSE TO A WEAKNESS Gentlemen:

On July 10,1996, the Nuclear Regulatory Commission (NRC) identified an emergency preparedness exercise weakness for the Brunswick Steam Electric Plant, Units 1 and 2. The basis for the weakness is provided in NRC Inspection Report 50-325/96-07 and 50-324/96-07.

Enclosure 1 provides Carolina Power & Light Company's response to the weakness Carolina Power & Light Company believes the company is in compliance with NRC regulations related to the weakness and that no further actions are necessary.

Carolina Power & Light Company finds the inspection does not contain information of a j

proprietary nature. Please refer any questions regarding this submittal to Mr. G. D. Hicks at  !

(910) 457-2163.  !

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Sincerely, j f

Ad . i William Levis l Director - Site Operations CKC/sft Enclosures

1. Response To A Weakness

2. List of Commitments cc: Mr. S. D. Ebneter, Regional Administrator, Region il 1 Mr. D. C. Trimble, Jr., NRR Project Manager - Brunswick Units 1 and 2 -

Mr. C. A. Patterson, Brunswick NRC Senior Resident inspector The Honorable H. Wells, Chairman - Nort'.r Carolina Utilities Commission Q f

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9609030017 960826 I PDR ADOCK 05000324 )

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ENCLOSURE 1  !

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 and 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 RESPONSE TO A WEAKNESS 1

EXERCISE WEAKNESS:

During the NRC inspection conducted the week of May 20-24,1996, an emergency preparedness exercise weakness was identified. As required by Section IV.F of Appendix E to 10 CFR Part 50, any weakness that is identified shall be corrected.

During the Emergency Preparedness Exercise conducted on May 21,1996, the Site Area l Emergency declaration was made at 8:51 pm, which was at least 35 minutes later than it l reasonably should have been made. This failure to promptly recognize and classify a Site Area l Emergency was identified as an Exercise Weakness (IFl 50-325/96007-01,50-324/96007-010).

The licensee had identified the untimely emergency classification for the Site Area Emergency as an exercise deficiency requiring corrective action. i RESPONSE TO THE EXERCISE WEAKNESS: l Reason For The Weakness: f The untimely classification of the Site Area Emergency occurred because the key participants in the Technical Support Center, specifically the Plant Operations Director and the Site Emergency Coordinator, did not appropriately interpret plant conditions while classifying the Emergency Action Level. The Site Emergency Coordinator and his key advisers did not objectively examine the evidence that was available to them. The Siie Emergency Coordinator and his staff were also excessively preoccupied with the simulated medical emergency. Instead of being proactive in determining the status of failed equipment following the explosion, the Technical Support Center I staff focused on the status of the ambulance for transport during the simulated medical l emergency.  ;

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Corrective Actions Taken:

A root cause analysis to determine appropriate corrective actions was completed on June 25, i 1996. This analysis included extensive interviews of key players to provide information needed l to identify corrective actions to prevent recurrence. Also, the exercise critique report was distributed to the Emergency Response Organization participants for review of the untimely classification of the Site Area Emergency.

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. j Corrective Actions To Be Taken:

i To improve proficiency in Emergency Action Level classifications, qualified individuals filling the i Site Emergency Coordinator, Plant Operations Director, and Technical Assessment Director  ;

positions in the Technical Support Center will participate in additional tabletop training involving I emergency classifications by March 31,1997.

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Qualified Emergency Response Managers, Site Emergency Coordinators in the Technical Support Center, and Emergency Repair Directors, will attend a training session which addresses j the exercise weakness and decision making by October 1,1996. '

Insoection Report Comment:

Paragraph P4.8 b. of Inspection Report 96-07 indicates that non-essential personnel were evacuated (simulated) following declaration of the Site Area Emergency, and a protected area accountability was conducted. However, evacuation of non-essential personnel was actually performed and an accountability of the protected area satisfied in fifteen minutes.

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Enclosure List of Regulatory Commitments The following table identifies those actions committed to by Carolina Power & Light Company in this document. Any other actions discussed in the submittal represent intended or planned actions by Carolina Power & Light Company. They are described to the NRC for the NRC's.

information and are not regulatory commitments. Please notify the Manager-Regulatory Affairs

! at the Brunswick Nuclear Plant of any questions regarding this document or any associated regulatory commitments.

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l Commitment Committed .

date or outage Qualified individuals filling the Site Emergency Coordinator, Plant 3/31/97 )

Operations Director, and Technical Assessment Director in the Technical  !

Support Center positions will participate in additional tabletop training 1 involving emergency classifications.  !

Qualified Emergency Response Wnagers, Site Emergency Coordinators in 10/1/96 l

l the Technical Support Center, and Emergency Repair Directors will attend a j i training session which addresses the exercise weakness and decision

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