ML20237C968

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Trip Rept of Attendance at State of Il 860213 Meeting Re Training Session on NRC Incident Response Program & NRC Participation in 860408 Plant Emergency Exercise.List of Attendees & Partial Agenda Encl
ML20237C968
Person / Time
Site: LaSalle, 05000000
Issue date: 02/19/1986
From: Phillips M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Hind J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20235G519 List: ... further results
References
FOIA-87-737 NUDOCS 8712220288
Download: ML20237C968 (9)


Text

[g* Rf 4 k NUCLEAR REGULATORY COMMISslON 9

UNITED STATES g

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CLEN ELLYN, ILUNOl$ 601 M February 19, 1986 MEMORANDUM FOR: Jack A. Hind, Director, Division of Radiation Safety and Safeguards THRU:

W. D. Shafer, Chief Emergency Preparedness and Radiological Protection Branch FROM:

Monte P. Phillips, Chief, Emergency Preparedness Section

SUBJECT:

TRIP REPORT - MEETING WITH STATE OF ILLINOIS DEPARTMENT OF NUCLEAR SAFETY - FEBRUARY 13, 1986 On February 13, 1986, Wayne D. Shafer, Pat Hyland, and I attended a meeting with representatives from the Illinois Department of Nuclear Safety. A copy of the attendance list and partial agenda are attached. During the meeting, I presented a training session on the NRC Incident Response Program. In addition, a discussion was held regarding NRC participation in the April 8, 1986 LaSalle emergency exercise. Emphasis, was placed on the various response modes of the A

NRC and which location, (Headquarters, Region, or Site), had the lead for the j

V agency in these various response modes.

i State DNS personnel presented a description of the REAC facility, including its capability to monitor over 1,300 individual data point parameters from each of the Nuclear units within the state. These data points were at least as comprehensive as all infomation available in any licensee's control room. The state was in the process of developing computer algorithms to provide an early alert to problems occurring at the plant, prior to the notification from the facility. NRC representatives cautioned them that, based on the number of LERs submitted, the state could expect a significant number of situations where their algorithms could indicate a significant emergency when, in fact, there was only a minor, non-emergency condition at the facility.

The various responsibilities for the State were clarified, as well as logistics and communications arrangements. Access to the REAC for an NRC liaison was l

discussed. The NRC liaison individual would reach the REAC by proceeding South 9

on Interstate 55 to the South Grand Avenue Exit. They would then proceed l

westbound until McArthur Avenue, where they would turn left (south); and then l

proceed to Outer Park Drive, where they would turn right (west) and travel one city block. The REAC is located on the fifth floor of 1035 Outer Park Drive.

i Access would be arranged by hav %g one of the members of the NRC's Base Team contact the REAC facility with the name and NRC badge number of the individual dispatched to the facility. All communications with the REAC would be made i

over the telephone number (217) 785-0600. This phone number should be used to talk with either then NRC liaison individual or any member of the REAC staff.

O I

f 8712220288 871210 8

PDR FOIA SHDLLYB7-737 PDR

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Jack A. Hind February 19, 1986 IDNS presented a brief discussion of how protective actions are fomulated at the REAC. Although the REAC Comander had the ultimate authority to issue a recommendation to the Head of IDNS, the decision was coordinated between the Reactor Analyst and Environmental Analyst. The Reactor Analyst would want i

to be in contact with NRC's Reactor Safety personnel to discuss the l

consequences of the event and potential for severity or recovery. Similarly, the Environmental Analyst would want to be in contact with the NRC's Protective Measures personnel to discuss dose assessment, environmental field readings, l

and protective action recommendations.

IDNS representatives were concerned I

that, although they now had the telephone numbers for Base Team counterparts, no such numbers were available for NRC Headquarters personnel, although the NRC Headquarters staff had the lead for the Agency decisions and coordination during the Initial Activation Mode.

The meeting concluded with a brief discussion of a proposal from Department o,f Nuclear Safety personnel to revise the flow-chart currently used by Commonwealth Edison to fonnulate default protective action recommendations for a General Emergency. A copy of the proposed flow chart is attached, along with copies of IE Information Notice 81-23, and the current CECO flow chart.

We stated that we would provide an advance copy to the NRC reviewer for CECO; however, no action to approve or disapprove of the proposal would be made until CECO submitted the request..for such action to the NRC.

O If you have any questions regarding this meeting please let me know.

%fPAA}

Monte P. Phillips, Chief Emergency Preparedness Section

Attachment:

As stated cc w/ attachment:

  1. f Perkins, IRB, 0IE R. Lickus, SGA, RIII L. Kers, ERC, RIII O

s.

NAME REPRESENTING

}

Monte P. Phillips NRC - Chief,.0perational Support Section I

Mike Parker IDNS - Chief. Engineering Division j

Andrea Pepper IDNS - Emergency Planning Steve Dunas

'IDflS - Chief. Emergency Planning Gene Field IDNS - Emergency Planning.

l l

Frank Sprague IDNS. - Emergency Planning.

Patrick L. Hiland NRC - Resident Inspector, Clinton Wayne D. Shafer NRC - Chief, Emergency Preparedness Jim Blackburn Assistant Manager, Office of Nuclear Facility Safety Gary Wright Manager, Office of Nuclear Facility Safety Denis Smiley Chief, Radiation Assessment r0 l

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.._________mm

Tentatative Agenda

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NRC - Region III February 13, 1986 10:00 a.m.

I.

Overview of DNS Emergency Organization; Capabilities Welcome - Terry Lash Overview - Gary Wright DNS Data Link - Mike Parker Remote Monitoring - Jim Blackburn Communications - Steve Dunas II.

Clarification of Communication Links (Entity / Position - Location / Telephone Number)

Information to be Exchanged Plant Status Data -* R*"6' bl d

/

kedRadn Protective Action Recomendatioh E komed./ A4,/ psf Public Infomation III. Proposed Revision to General Emergency Default Protective Action Recommendations t

l Goal - Achieve Consistency between:

- NRC - NUREG-0654

- Ceco - GSEP

- DNS - IPRA Attendees:

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1 FIGURE 6.3-1 LYCOMENDED PROTECTIVE ACTIONS - CENERAL EMERCDCY GENERAL EMERCDCY Od 1

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IIDWCHART IN CONJUNCTION WITH CSEP RECOMMEND 4D TABLES 6.3-1, 6.3-2, & 6.3-3 AND 4

NARS FORM 9C. I. J. & K CUIDANCE OF CSEP SECTIONS $ AND 6 (g) (g) (s) 9g (10 miles)

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I Evacuation, when noted. is the reconsunded protective action when evacuation can be completed prior to plume arrival; f

Shelter is then the protective action to be recommended.

1 Availability of. Dose Projections means the TSC or EOF g CCC are manned by Environmental Personnel.

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L-_-_____.___.________.-_-_______-___--_-._-.__-.-._.--_


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i FLOW CHART FOR GENERAL EMERGENCY OFFSITE PROTECTIVE DECISIONS q

The fonowine eetions win be bee.4 on predetermine.d oneervebie instrum.ntation end pient steeve indi et.,e.

(EALS) contained in the emergency plan and that have been reviewed by offefte officiele, tiowever, responsible offette off6ciale must decide the feasibility of implementing the protective actione et the time of the ace 6 dent.

Ab CONTROL ROOMSTAPF DETECT j

GENERAL EMERGENCY I

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PROTICityt ACTIONS IN ACCORDANCE WITH EPA PAGe 3 r q 7 RECOMME NO SHELTER POR eMutNEst?

AREAS THAT eMMimeNT PeOACTED CANTet PROJECTIO Yts EVACUATED' VES CONTAINMENT CONTAsNutNT SEFORE PLUME FAILURE OR rAILURt AND A A ATV AL -

RELEASE ComtDAMAGEOR tvACUATE UNDERWAY?

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  • 1114 4 1 f i f SOURCE; Appenes 1 NUREG4eW/ FEM A-REP.1. Rev. t
  • (11 SITUATIONS REQUIRING URGENT ACTION BY OFFSITE OFFICIALS Itseed on Control Room Indicators. No Does Projections Requirodi.,

- 15 Minute Declaionmaking, Activation of Alerting System and EBS Message

  • (2) Actuel et projected release of 20% gap from core.

'l3) " Puff" rolesee trate much greater then designed leek retel.

  • (4) For eR ovecussione, shelter the remainder of the plume EPZ end resecate the population effected by any ground contamination promptfy following plume passage.
  • (5) Concentrate en evecuation of stees near the plant (e.g., may be time to evacuate 2 mile radius and not the a -es.

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