ML20057A292

Forwards Final Minutes of 930622 Nrc/Fema Steering Committee Meeting at FEMA

ML20057A292
Person / Time
Issue date:	07/21/1993
From:	Congel F Office of Nuclear Reactor Regulation
To:	Wingo C Federal Emergency Management Agency
References
NUDOCS 9309130331
Download: ML20057A292 (5)

Text

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JUL 211333 h

Craig S. Wingo Assistant Associate Director Office of Technological Hazards Federal Emergency Management Agency 500 C Street, S.W.

Washington, D.C.

20472

SUBJECT:

MINUTES FOR THE JUNE 22, 1993, NRC/ FEMA STEERING COMMITTEE MEETING Enclosed please find the final minutes for the NRC/ FEMA Steering Committee meeting, which was held at FEMA on June 22, 1993. Draft proposed minutes were reviewed and commented upon by your staff.

If you have any questions or additional comments, 'please have a member of your staff contact 1

Falk Kantor of the Emergency Preparedness Branch at (301) 504-2907.

1 Sincerely, l

Drfginal afgned by Frank J. Congel, Director l

Division of Radiation Safety and Safeguards Office of Nuclear Reactor Regulation

Enclosure:

As stated

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PEPB Staff TMurley JPStohr, RII RScarano, RV FCongel FMiraglia KBarr, RII RPate, RV EButcher WRussell CNorelius, RIII OFC SCE: BEPB:NRR C:PEPQMR D:DRSS:NRR

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V NRC/ FEMA STEERING COMMITTEE i

MEETING MINUTES i

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JUNE 22, 1993 f

i The NRC/ FEMA Steering Committee met at FEMA Headquarters on June 22, 1993 to discuss the items on the attached agenda. Attendees and highlights of the i

meeting were as follows:

i NRC FEMA R. Erickson M. Hepler j

F. Kantor V. Wingert j

R. Pedersen M. Lawless A. Mohseni M. Stangler l

J. Logsdon i

J. Keller (by phone) i i

HIGHLIGHTS i

i 1.

Revision to the NRC/ FEMA Memorandum of Understandina (MOU)

A new MOU was signed by the NRC Executive Director of Operations and sent to j

FEMA for signature en June 17, 1993. The MOU contains revisions approved by the Commission in February 1993 and an amendment approved by the Commission in l

May 1993. The new MOU will take effect when approved and signed by FEMA's Acting Associate Director for State and Local Programs and Support. Until l

then, the current (1985) version of the MOU remains in effect.

i 2.

FEMA Response to TMI 10 CFR 2.206 Petition issues 1

FEMA indicated that responses to the offsite concerns raised in the TMI 10 CFR' 2.206 petition are scheduled to be provided in September.

FEMA Region III is j

in the process of obtaining the necessary information from the State of Pennsylvania.

3.

Tro.ian Decommissioninc The NRC reported that the licensee briefed the NRC staff on the Trojan decommissioning. The licensee believes that the possibility of a spent fuel accident with offsite consequences is so remote that offsite. emergency planning is not required. The licensee intends to submit the technical basis for its position to the NRC for review. The NRC position continues to be that-offsite preparedness is required until relief is approved by the NRC.

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Watts Bar Licensina l

The FEMA Region IV RAC has met to discuss the review of the offsite emergency plans for Watts Bar.

FEMA provided comments to the State of Tennessee on July 9, 1993, concerning these plans, including the evacuation time estimates.

I FEMA has scheduled a meeting for July 19, 1993, to discuss their comments with the State. The full participation exercise ic to be conducted in October l

1993. The NRC indicated that the projected fuel load date remains early 1994.

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Wellesley Reception Center i

NRC emergency preparedness staff reported that they had met with NRC's Pilgrim and Seabrook Project Managers to discuss the impending loss of the Wellesley

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Reception Center facility. The NRC project managers agreed to prepare a

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letter to the licensees forwarding the FEMA letter of June 9,1993, on the i

subject with a request that the licensees provide the status and monthly I

schedule of their efforts to assist the State of Massachusetts in resolving the issue. The NRC staff will send FEMA a copy of the letter (s).

FFMA indicated that they plan to meet with the State and the licensees in July to discuss the Wellesley issue.

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Supplement 3 to NUREG-0654/ FEMA-REP-1 FEMA indicated that they intend to provide comments soon on the draft Supplement 3 to NUREG-0654/ FEMA-REP-1 on protective actions.for severe reactor accidents.

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NRC Commission Paper on Emeraency Plannina for 10 CFR Part 52 Acolications The NRC staff has developed a Commission paper on emergency planning for early site permits and combined licenses for reactor applications under 10 CFR Part-

52. The Commission paper is currently being reviewed by NRC management. The NRC staff plans to brief the Advisory Committee on Reactor Safeguards in August and invited FEMA staff to attend.

FEMA provided some additional comments on draft Supplement 2 to NUREG-0654/ FEMA-REP-1 on emergency planning criteria for early site permits. This document is included, as a draft,-in the Commission paper.

8.

Implementation of New EPA-400 Emeroency Worker Dose limits I

The issue of the implementation of the guidance concerning dose limits for emergency workers in the revised EPA Protective Action Guide manual (EPA-400) was addressed by the Steering Committee. The NRC discussed the background and rationale for the position on emeroency workers presented in the NUMARC white l

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. paper issued in April 1993. The FEMA representatives expressed reservations regarding the NUMARC approach and discussed an alternative approach involving the development of default adjustment factors.

The principal issue involves monitoring or accounting for the inhalation component of the dose during the emergency phase which cannot be measured directly with personal dosimeters.

FEMA presented a draft position paper on dose limits for emergency workers.

NRC agreed to review the FEMA paper and provide comments. Another meeting on this subject will likely be required.

9.

Portal Monitor Standard There was general agreement that the 1 pCi standard for offsite portal monitors, which was recently reaffirmed in a note to the FRPCC from the j

Subcommittee on Instrumentation, was an appropriate value.

There was some l

discussion of the location or point at which the standard should be measured.

l This aspect of the standard may be addressed further by the Subcommittee in the revision of the background information document in support of the final standard.

10.

Hurricane Andrew -- lessons learned The NRC staff promised to send FEMA a copy of the March 1993 joint NRC/INPO l

(Institute of Nuclear Power Operations) report entitled "Effect of Hurricane l

Andrew on the Turkey Point Nuclear Generating Station from August 20-30, 1992." FEMA staff had received a copy of Florida Power and Light suggestions for changes to NUREG-0654 -- in particular, one change reflecting increased licensee attention to possible effects of disasters on offsite preparedness infrastructure.

11.

Site-Specific Issues Indian Point 3 Restart. NRC informed FEMA that Indian Point 3 had been shut down since February 1993 and restart was projected for September 1993.

FEMA indicated that internal discussions concerning the most recent biennial exercise at Indian Point are still ongoing.

Cooper / Fort Calhoun EPZ Boundaries. The NRC stated that they had no objection to the draft FEMA letter to its Region VII on the adjustments to EPZ boundaries.

FEMA indicated that they would reflect coordination with the NRC in the letter.

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NRC FEMA AG.ENDA STEERING COMMITTEE MEETING June 22,1993 FEMA Headquarters 500 C Street Washington, DC 20472 1.

Commission-approved amendment t'o NRC/ FEMA Memorandum of Understanding (M30) 2.

Status / schedule for FEMA response to concerns identified in 10 CFR 2.206 petition regarding offsite issues at TMI 3.

Trojan decommissioning -- offsite emergency planning issues 4.

Watts Bar licensing -- status of emergency plan review including evacuation time estimates 5.

Pilgrim issues including status of Wellesley Reception Center and Massachusetts EBS system 6.

FEMA review of Supplement 3 to NUREG-0654, " Criteria for. Protective Action Recommendations for Severe Accidents" 7.

NRC Commission paper on emergency planning for reactor applications under 10 CFR Part 52, including Supplement 2 to NUREG-0654, " Criteria for Emercency Planning in an Early Site Permit Application," and illustrative examples of ITAAC (to be briefed at ACRS meeting in~ August) 8.

Sharing with licensees and States of Turkey Point lessons Learned as a j

result of Hurricane Andrew -- NRC/INPO Report and FEMA Disaster-Initiated Review report -- FP&L proposals for NI'rG-0654 j

9.

General discussion items /Other site-specific. concerns j

Indian Point 3 Restart Cooper /ft. Calhoun EPZ boundaries i

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Portal monitor standard j

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Implementation of EPA-400 Protective Action Guides i

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