ML20216E987

Notification of 970910 Meeting W/Util in Rockville,Md to Discuss Potential Dose Consequences from Postulated Steam Line Break & Postulated Accident Sys Leakage Limits

ML20216E987
Person / Time
Site:	Three Mile Island
Issue date:	09/08/1997
From:	Buckley B NRC (Affiliation Not Assigned)
To:	Eaton R NRC (Affiliation Not Assigned)
References
NUDOCS 9709110126
Download: ML20216E987 (3)

Text

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l tlEMORANDUMT0: Ronald B. Eaton, Acting Dirsctor

. Project Directorate I-3 Divisien of Reactor Projects - I/II Office of Nuclear Reactor Regulation FROM: Bart C. Buckley, Senior Project Manager Original signed by Project Directorate I-3 Division.of Reactor Projects - I/II Office of Nuclear Reactor Regulation

SUBJECT:

MEETING WITH REPRESENTATIVES OF GPU NUCLEAR CORPORATION -

THREE MILE ISLAND NUCLEAR GENERATING STATION, UNIT 1 (TMI-1)

DATE & TIME: September 10, 1997 9:30 a.m. - 12:30 p.m.

LOCATION: U.S. Nuclear Regulatory Commission One White Flint North 11555 R6ckville Pike Room 0-4 B6 Rockville, Maryland PURPOSE: To discuss potential dose consequences from postulated steam line break and postulated accident systems leakages limits.

See enclosed discussion items.

PARTICIPANTS:* NRC Participants are from the Office of Nuclear Reactor Regulation (NRR).

lig UTILITY C. Miller, NRR D. Distel, R. Emch, NRR et al.

J. Lee, NRR B. Buckley, NRR Docket No. 50-289 l

cc: See next page CONTACT: Bart C. Buckley, NRR 415-1483

-- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to " Commission Policy Statement on Staff  ;

Meetings Open to the Public" 59 Egderal Reaister 48340,9/20/94.

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9709110126 970908 0FFICIAL RECORD COPY PDR ADOCK 05000289 '

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Three Mlle Island Nuclear Station, Unit No. I cc:

Michael Ross Robert B. Borsum Director, O&M, TMI B&W Nuclear Technologies GPU Nuclear Corporation Suite 525 P.O. Box 480 1700 Rockville Pike Middletown, PA 17057 Rockville, MD 20852 John C. Fornicola William Dornsife, Acting Director Director, Planning and Bureau of Radiation Protection Regulatory Affairs Pennsylvania Department <,f GPU Nuclear Corporation Environmental Resources 100 Interpace Parkway P.O. Box 2063 Parsippany, NJ 07054 Harrisburg, PA 17120 Jack S. Wetmore Dr. Judith Johnsrud Manager, THI Regulatory Affairs National Energy Committee GPU Nuclear Corporation Sierra Club P.O.-Box 480 433 Orlando Avenue Middletown, PA 17057 State College, PA 16803 Ernest L. Blake, Jr., Esquire Mr. James W. Langenbach Shaw, Pittman, Potts & Trowbridge Vice President and Director TMI 2300 N Street, NW. GPU Nuclear Corporation Washington, DC 20037 P.O. Box 480 Middletown, PA 17057 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 Chairman Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 Wayne L. Schmidt Senior Resident Inspector (TMI-1)

U.S. Nuclear Regulatory Commission P.O. Box 311 Middletown, PA 17057 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 l

DISCUSSION ITEMS WITH GPU License Amendment Request No. 266 (1) Spray Removal Coefficients for Particulate and Elementallodines (2) Mixing Rate between Sprayed and Unsprayed Regions (3) ECCS Water Flashing Factors (4) Methodologies Used for determining X/O Values for EAB and LPZ (5)

ECCS leakage Pathway to BWST and Mixing Efficiency in the BWST (6) ECCS Leakage Pathway in Aux Bldg and Sump Water Volume Used License Amendment Request No. 269 (1) Break Flow Rate (2) Feulted SG Steam Release Rate (3) Intact SG Steam Release Rate (4) Integrated Flashed Break Flow (Flashing Factors)

(5) Total Activity Released (Pre-accident lodine Spike)

(6) Total Activity Released (Accident initiatM lodine Spike)

(7) lodine Release Rate Calculation (B) ' Accident Duration Assumed N e ENCLOSURE

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