ML15264A629

Forwards Request for Addl Info Re ISFSI

ML15264A629
Person / Time
Site:	Oconee
Issue date:	09/07/1989
From:	Wiens L Office of Nuclear Reactor Regulation
To:	Tucker H DUKE POWER CO.
References
TAC-68026, TAC-68027, TAC-68028, NUDOCS 8909120138
Download: ML15264A629 (3)

Text

September 7, 19890 Docket Nos.

50-269 50-270 50-287 Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlotte, North Carolina 28242

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION -

OCONEE UNITS 1, 2, AND 3, INDEPENDENT SPENT FUEL STORAGE INSTALLATION (TACS 68026, 68027, AND 68028)

Additional information is required to complete our review of your application for a license amendment relating to operation of an independent spent fuel storage installation. The enclosed request for additional information concerns the plant personnel's ability to respond to a spent fuel accident resulting in the release of Kr-85 as the primary isotope in the release. These questions were discussed with members of your staff during telephone conversations held on August 9 and August 17, 1989. We will be able to complete our safety evaluation upon satisfactory response to these questions.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Original signed by:

Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects-I/II

Enclosure:

Office of Nuclear Reactor Regulation Request for Additional Information cc w/encl:

See next page DISTRIBUTION Docket Fi le NRC PDR Local PDR PDII-3 Reading S. Varga 14-E-4 G. Lainas 14-H-3 D. Matthews 14-H-25 M. Rood 14-H-25 L. Wiens 14-H-25 C. Hinson 11-D-23 OGC (For inform. Only) 15-B-18 E. Jordan MNBB-3302 B. Grimes 9-A-2 ACRS (10)

P-315

[Oconee Plant File]

[TUCKER LTR 8/30]

• See previous concurrence PDII-3*

PDII-3*

PDII-3*

8909:120i 69 MRood LWiens:cb DMatthews DFTR ADOCK 05000269 09/01/89 09/01/89 09/07/89 Y

C

Mr. H. B. Tucker Oconee Nuclear Station Duke Power Company Units Nos. 1, 2 and 3 lw cc:

Mr. A. V. Carr, Esq.

Mr. Paul Guill Duke Power Company Duke Power Company P. 0. Box 33189 Post Office Box 33189 422 South Church Street 422 South Church Street Charlotte, North Carolina 28242 Charlotte, North Carolina 28242 J. Michael McGarry, III, Esq.

Bishop, Cook, Purcell & Reynolds Mr. Alan R. Herdt, Chief 1400 L Street, N.W.

Project Branch #3 Washington, D.C. 20005 U.S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Mr. Robert B. Borsum Atlanta, Georgia 30323 Babcock & Wilcox Nuclear Power Division Ms. Karen E. Long Suite 525 Assistant Attorney General 1700 Rockville Pike N. C. Department of Justice Rockville, Maryland 20852 P.O. Box 629 Raleigh, North Carolina 27602 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 34623-1693 Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 County Supervisor of Oconee County Walhalla, South Carolina 29621

ENCLOSURE The following questions pertain to your ability to detect, measure, and respond to a spent fuel accident involving old fuel in which the gaseous release con sists primarily of Kr-85:

1. Describe the types of radiation monitors (portable,.fixed, cart mounted) that will be used to detect a Kr-85 release from a spent fuel accident involving old fuel.

For each type of monitor available:

verify that the monitor is sensitive enough to detect a Kr-85 release from such an accident.

verify that you will have a sufficient number of these monitors available and in working order to monitor for Kr-85 following a spent fuel accident.

verify that the calibration of the monitor is appropriate for the detection of Kr-85.

2. Verify that the TLDs used at Oconee are sensitive enough to accurately measure beta skin dose from Kr-85 following a spent fuel accident in which Kr-85 is the primary gaseous radioisotope released.

3. The worker training program should include precautions (i.e., skin dose hazards, sheltering, use of.special detectors and dosimetry) to be taken in the event of a spent fuel accident resulting in the release of Kr-85.

Describe to what extent Oconee plant personnel receive such training.

4. Verify that Oconee has procedures which address actions and precautions to be taken in the event of a spent fuel accident in which the gaseous release consists primarily of Kr-85.