ML20128H632
| ML20128H632 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/20/1996 |
| From: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| To: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 9610100013 | |
| Download: ML20128H632 (3) | |
Text
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J Curut Es 11. Cm E Baltimore Gas and Electric Company Vice President Calven Cliffs Nuclear Power Plant Nuclear Energy 1650 Calven Cliffs Parkway Lusby, Maryland 20657 410 495 4455 September 20,1996 U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 ATTENTION:
Mr. II. J. Miller, Regional Administrator
SUBJECT:
Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation; Docket No. 72-8(50-317/318)
Annual Report of Changes. Tests. and Exneriments -- 10 CFR 72.48 In accordance with 10 CFR 72.48(b)(2), Baltimore Gas and Electric Company hereby submits this report containing brief descriptions of changes, tests, and experiments made under the provisions of 10 CFR 72.48. Paragraph 72.48(b)(2) requires annual submittal of such a report to the Regional Office with a copy to the Director, Office of Nuclear Material Safety and Safeguards. The attached report covers the period from September 20,1995 through September 20,1996.
Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours,
/
.A N'
/
for J
C.11. Cruse Vice President - Nuclear Energy CllC/GT/bjd
Attachment:
Calvert Cliffs Independent Spent Fuel Storage Installation Annual Report of Changes, Tests, and Experiments [10 CFR 72.48(b)(2)]
cc:
E. Y. Shum, NRC (Without Attachment)
Document Control Desk, NRC A. W. Dromerick, NRC R. M. Bernero, NRC Resident inspector, NRC D. A. Brune, Esquire R.1. McLean, DNR pgg, l J. E. Silberg, Esquire J.11. Walter, PSC
~
Director, Project Directorate I-1, NRC 9610100013 960920 PDR ADOCK 05000317 R
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b ATTACIIMENT (1)
Calvert Cliffs Independent Spent-Fuel Storage; Installation Annual Report-of Changes, Tests,. andIExperiments
- [10 CFR 72.48(b)(2)];
Baltimore Gas and Electric Company Docket No. 72-8(50-317/318)
September 20, 1996
ATTACIIME.NT (1)
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CALVERT CLIFFS NUCLEAR POWER PLANT INDEPENDENT SPENT FUEL STORAGE INSTALLATION l
10 CFR 72.48 SAFETY EVALUATION SUMMARIES SEPTEMBER 20,1995 TO SEFTEMBER 20,1996 SAFETY EVALUATION
SUMMARY
LOG NO.
SE00002 The location of the Transportation Facility was changed during construction of the new Nuclear Office Facility to a location east of the Independent Spent Fuel Storage Installation spent fuel transfer route. The new location is closer to the transfer route than stated in the Updated Safety Analysis Report (Appendix A, Q&A, Question 8.0-6), but still outside the NFPA 30-1987 specified setback of 25 feet. In addition, the size and number of underground storage tanks was i.Mreased from two 3000 gallon tanks to two 4000 gallon tanks and one 550 gallon tank for diesel fuel, gasoline, and waste oil, respectively. This change does not represent an Unreviewed Safety Question, a significant increase in occupational exposure or a significant unreviewed environmental impact because the underg und storage tanks are still outside the NFPA setback requirements. In addition, the new location is such that the 100m tanker truck exclusion zone will preclude fuel deliveries during the time of spent fuel transfer operations from the Calvert Cliffs Nuclear Power Plant Auxiliary Building to the Independent Spent Fuel Storage Installation.
SE00003 Changed the description of the dry shielded canisters (DSCs) insertion as described in Updated Safety Analysis Report, Section 4.2.3.2, to reflect the deletion of dry lubricant from the DSC shell and the addition of Nitronic hard sliding rails to the Transfer Cask and Horizontal Storage Module. The DSC is designed to slide from the Transfer Cask into the Horizontal Storage Module and back without undue galling, scratching, gouging, or other damage to the sliding surfaces. Substantial galling had been observed in a similar application of the dry lubricant to the DSC shell. The addition of the Nitronic rails was made as a design improvement, and testing in similar applications was found to perform substantially better than the previous design. After a thorough review, it has been concluded that the design change does not constitute an Unreviewed Safety Question, a significant increase in occupational exposure or a significant unreviewed environmental impact.
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