ML20070H972

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Forwards Responses to Requests for Addl Info Re Emergency Planning,Including Location of Plant Emergency Personnel & Plant Data Transmission & Control Room Locations.Encl Info Will Be Included in Amend 75 to PSAR
ML20070H972
Person / Time
Site: Clinch River
Issue date: 12/22/1982
From: Longenecker J
ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To: Check P
Office of Nuclear Reactor Regulation
References
HQ:S:82:159, NUDOCS 8212270294
Download: ML20070H972 (7)
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Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:82:159 DEC 2 2 M2 i

Mr. Paul S. Check, Director CRBR Program Office i

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatorj Commission Washington, D.C.

20555

Dear lir. Check:

ADDITIONAL INFORMATION REGARDING EMERGENCY PLANNING, PRELIMINARY SAFETY ANALYSIS REPORT (PSAR) SECTION 13.3 Enclosed are the responses to requests for additional information regarding emergency planning of the Clinch River Breeder Reactor Plant.

contains information on the location of plant emerger.cy personnel and plant data transmissions. This information should be considered preliminary, as discussed with Mr. Williams of the Emergency Preparedness Licensing Brcoch, I

and will be updated for the Final Safety Analysis Report. Enclosure 2 contains information on the control room locations in Figure 13.3-2, a description of the Technical Support Center (TSC), habitability features of the TSC, and the plant data acquisition system. Thi.; information will be incorporated into Amendment 75 to the PSAR scheduled for submittal in January 1983.

Questions regarding this submittal may be directed to W. Hibbitts' (FTS 626-6455) of the Oak Ridge Project Office staff.

Sincerely,

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t Unt L Jo n R. Longenecker Acting Director, Office of Breeder Demonstration Projects Office of Nuclear Energy 2 Enclosures cc: Service List Standard Distribution Licensing Distribution gol f 8212270294 821222

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PDR ADOCK 05000537

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EN0tOSURE 1 O

Finding:

Provide a matrix showing the location of key plant emergerey personnel during: (1) a site alert, (2) a site area emergency, (3) a general emergency.

Response

WA staffs the plant TSC and OSC from alert to all higher ercergency classifications.

Therefore, the attached matrix will be the same for all three emergency classificatiors.

Finding:

URC requeste information or, now data transmission is to be established to the CECC, DNPEC, ar.d, MSEC.

Response

TVA will handle data transmission for LRBRP in the same tranner it is currently handling data transmission for its operating nuclear power plants.

More specifically, hard copy data transmission will be accomplished by Panarax from CRBRP to the DNPEC, the CECC, and the HSEC.

The ha-dcopy transmission is then followed up and verified by redundant telephone con:::unications.

By redundant telephone communications it is implied that there will be a, dedicated WA line, (i.e., Dimension System), and as a backup, the standard Bell system can be used.

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A t tactment I (Contiraed) c, l

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CI:ltRT Ft1EIM;fNCY lifflT orM;AfilZATION s

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thergerrv Directoe

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PM e Beartor flanuf acturer T5C 1echnical Seg scwt Center WC: Ogeratingel Supiert Center Fut;lic 1-chnical llcalth flairiterorre Userations Safety Asses: rant Ihysicit.L Harsger Manager (TSC)

Manager l

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(TSC)

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Shift, F.nni:eer (Control Rons)

Electrical Heactor Hadio.. _..

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Test E rg.ireer Ery.,1reer Chemelat ical Engineer l ey.ireer (TSC)

(TSC) hy.irect Frtireer (TSC)

(1S0)

I ShiIt lectwitcal (T'Ci (100)

Advisor (Control Room)

(GC Coordinator rower Systms.....

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(% tar.c l ftgerviror TVA/NRC Ogerations fr.r I.tv.t reer l (100) try,t reer fl~ k'G (150) j (T3C)

(1TC )

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- c-ENCLOSURE 2 j

The responsibilities o' the minimum staff under fethnical FM eifications.

Under emergency conditions normal oper.tions will be an outlinec; in the P3AR.

The site the responsibilities of the minimum staff will be unchanged.

' emergency organization vill augment the shif t operations crew in accordance I

If members of the site secrgency with NUREG-0654-R1-1980, Table B-1.

organization are not pres".at when an emergency occurs, the shif t engineer on duty will be designated the Site Emergency Director until relieved by the 8

The duties and responsibilities of the I

Mant msnager or his alternate.

various plant supervisors concerning plant emergencies will be outlined in the CRM P-REP.

An on-site Technical Support Center (17C) will be provided in accordance with 10 CFR 50 Appendix E-1982 and NUREG-06%-1981, " Functional Criterie for The TSC will perform the followirg functions,:

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Emergency Response Facilities".

Monitor plant operations and provide technical advice and overall o

plant management from a non-control room location Supply sufficient plant information for analysis of pirnt status and o

extent of any plant damage Record sufficient information to allow for a thorough revaew of plant o

incidents and to aid in plant recovery Provide communications with off-site personnel and provide for other peripheral functions not directly felated to reactor coeratietse 8 5/ l o c./ of O o

02 Relieve control room congestion bw.'lc/,'og S ee, /~ p re r t..a -9 4 45./

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o In order to provide these functions, the TSC will be locatedAccess to the TSC du proximity to the control room.

The TSC will provide adequate limited to those persons identified in the REP.

working, space for the 13entified support personnel and required support The TSC will be capable of being staffed cnd functional within equipment.

Radiological protection from approximately 30 minutes of kn emergency.

airborne radioactivity and plant sources will be provided.

. I%6cef An on-si te Operational Support Cente- (OSC) will provide a location where 4

support personnel can assemble and where support can be coordinated and will The location of the provide com=unication with the contrr1 room and the TSC.The OSC will have tecess n-: l eting 1-e? "" +*r

l;nt.

OSC will benecessary to support the plant emergency \\es gr.se, j*h (See,y gpg g g /,,,

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la s c h r eo m a.r e s of t h e. P The on-site emergency organization will be supported by the staffs of four the Central Emergency Control Center (CECC) Staff and the emergency centers:

Division of Nuclear Power Em<.rgency Center (DNPEC) Staff in Chattanooga, Tennessee; the Muscle Shoals Emergency Control Center (HSECC) Staff in Muscle Shoals, Alabama; and the Knoxville Emergency Control Center (K':CC) Starf in The CECC will function and provide all services as a Knoxville., Tennessee.

In addition, the offsite emergency

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'near-site' Emergency Operations Facility.

organization will be supported by other TVA organizations as may be required 7*), e T'>C., > :s eIn)ed w % N f h c. G., fro l bom de b. k 4. I. l zone y

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I, cations of Technical Support Center, Operational

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Support Center, Medical Facilitics and Personnel Page 13.3-12 Figure 13.3-2 LS00-Decontamination Pacilities, g

July 19u2

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