ML20064G753
| ML20064G753 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/11/1994 |
| From: | Denton R BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M86437, TAC-M86438, NUDOCS 9403160340 | |
| Download: ML20064G753 (2) | |
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Mouxr E. Dtsum Bahimore Gas and Electric Company Calvert Clifs Nuclear Power Plant Vice President 1650 Calvert Chfs Parkway Nuclear Energ*v Imby. Maryland 20657 410 586-2200 EAI 4455 IDcal 4to 260-4455 Baltimore March 11,1994 U. S. Nuclear Regulatory Commission Washington, DC 20555 A'lTENTION:
Document Control Desk SUIUECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Supplement to License Amendment Request; Personnel Airlock Open During Core Alterations I
REFERENCES:
(a) letter from Mr. R. E. Denton (BG&E) to NRC Document Control Desk, dated November 5,1993, " License Amendment Request; Personnel Airlock Open During Core Alterations" l
(b)
Letter from Mr. R. E. Denton (BG&E) to NRC Document Control Desk, dated May 6,1993, " Control Room Habitability - Interim Engineering Analysis For Thyroid Dose" (TAC Nos. M86437; M86438)
Reference (a) submitted a license amendment request to allow the containment personnel airk)ck (PAL) doors to remain open during core alterations and movement of irradiated fuel in the containment. This letter provides information on the compliance of Calvert Cliffs Nuclear Power l
Plant with General Design Criteria (GDC) 19 following a fuel handling accident under the proposed changc. This informatior, does not affect the content or conclusions of the Determination of Significant llazards contained in Reference (a).
I General Design Criteria 19 requires that a Control Room must be provided from which the plant can be operated safely under accident conditions. Adequate radiation protection shall be provided to l
permit access and occupancy of the Control Room under accident conditions without personnel receiving radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident. For a fuel handling accident, the hmiting radiation exposure is 30 rem to the thyroid. NUREG-0737 defined the " duration of an accident" for continuously occupied areas such as the Control Room as 30 days.
Reference (b) provided the Nuclear Regulatory Commission with information on Baltimore Gas and Electric Company's current compliance with GDC 19. We curren'ly meet GDC 19 following a Loss of Coolant Accident (LOCA) by providing operators with protective measures, such as self-contained breathing apparatus or potassium iodide tablets within 45 minutes following the accident.
Those protective measures are staged in the Control Room and in other areas.
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9403160340 94031g DR ADDCK 05000317
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Mafch 11,1994 Page 2,
Daltimore Gas and Electric Company currently meets the GDC 19 limits following a fuel handling accident with the containment PAL doors closed and without additional protective actions (i.e.; 30 day thyroid dose of 6.2 rem). Following a fuel handling accident with the containtnent PAL doors open and without additional protective measures, using our current analytical methods and assumptions for equipment performance, we would exceed the GDC 19 limits (i.e.,30-day thyroid dose of 50 rem). Operator thyroid dose can be reduced to meet the GDC 19 limits following a fuel handling accident while the containment PAL doors are open as long as the additional protective measures described above are taken within approximately three hours. These protective measures are staged in the affected areas and personnel are trained in their use. Training and procedures will be expanded to include fuel handling conditiom is part of the implementation of this amendment.
As described in Reference (b), BG&E has committed to bring operator dose within GDC 19 limits without additional protective measures. We are pursuing' revised analytical methods, equipment modifications, or other necessary measures. These evaluations include the effects of open PAL doors during fuel handling in their scope.
Should you have any questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, n
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RED /BDM/ dim ec:
.D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., N RC T, T. Martin, NRC P. R. Wilson, NRC R. I. McLean, DNR J. II. Walter, PSC i
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