ML20004F931
| ML20004F931 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/18/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8106260236 | |
| Download: ML20004F931 (3) | |
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UNITED STATES
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E W ASHINGTON, D. C. 20555 k,.....,,f.
- JUN 181981
., g\\ g Docket No. 50-317
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Mr. A. E. Lundvall, Jr.
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Vice President - Supply Baltimore Gas & Electric Company L-osts588 8'" p EN 8
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P. O. Box 1475 WJ Baltimore, Maryland 21203 g,
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Dear Mr. Lundvall:
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We are currently reviewing your February 4,1981 submittal of "Calvert Cliffs Unit No.1 Nuclear Plant Reactor Pressure Vessel Surveillance Program: Capsule 263".
We find that additional information as delineated in the enclosure is necessary to complete our review.
Please provide the requested additional information at your earliest co'venience.
Sincerely, C/aab>/?C Nap Robert A. Clark. Chief l.
4 Operating Reactors Branch #3 l
Division of Licensing l
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Enclosure:
As stated cc: See next page l
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8106260236
Baltimore Gas and Electric Company cc:
.. James A. Biddison, Jr.
Ms. Mary Harrison, President Calvert County Board of County Commissioners General Counsel Baltimore Gas and Electric Company Prince Frederick, MD 20768 P. O. Box 1475 Baltimore, MD 21203 U. S. Environmental Protection Agency Region III Office George F. Trowbridge, Esquire Attn: EIS Coordinator Shaw, Pittman, Potts and Trowbridge Curtis Building (Sixth Floor) 1800 M Street, N. W.
Sixth and Walnut. Streets Washington, D. C.
20036 Philadelphia, PA 19106 Mr. R. C. L. Olson, Principal Engineer Mr. Ralph E. Architzel Nuclear Licensing Analysis Unit Resident Reactor Inspector Baltimore Las and Electric Company NRC Inspection and Enforcement Room 922 - G&E Building P. O. Bos 437 P. O. Box 1475 Lusby, MD 20657 Baltimore, MD 21203 Mr. Charles S. Brinkman Manager - Washington Nuclear Operations Mr. Leon B. Russell 4
Plant Superintendent Combustion Engineering, Inc.
Calvert Cliffs Nociedar Power Plant 4853 Cordell Avenue, Suite A-1 Maryland Routes 2 & 4 Bethesda, MD 20014 Lusby, MD 20657 Mr. J. A. Tiennan, Manager Bechtel Power Corporation Nuclear Power Department Attn: Mr. J. C. Judd Calvert Cliffs Nuclear Power Plant Chief Nuclear Engineer Maryland Routes 2 & 4 15740 Shady Grove Road Lusby..h!D 20657 Gaithersburg, MD 20760 Director, Criteria and Standards Division Combustion Engineering, Inc.
Office of Radiation Programs ( ANR-460)
Attn: Mr. P. W. Kruse, Manager U. S. Environmental Protection Agency Engineering Services Washington, D. C.
20460 P. O. Box 500 Windsor, CT 06095' Mr. W. J. Lippold, Supervisor Nuclear Fuel Management Public Document Room Baltimore Gas and Electric Company Calvert County Library Calvert Cliffs Nuclear.Porer Plant Prince Frederick, MD 20678 P. O. Box 1475 Baltimore, Maryland 21203 Director, Department of State Planning 301 West Preston Street Mr. R. E. Denton, General Supervisor Baltimore, MD 21201 Training & Technical Services '
Calvert Cliffs Nuclear Power Plant Mr. R. M. Douglass, Manager Maryland Routes 2 & 4 Quality Assurance Department..
Lusby, MD 20657 Fort Smallwood Road Complex P. O. Box 1475 Baltimore, ftD 21203 Mr. T. L. Syndor, General Supervisor Administrator, Power Plant Siting Program Operations Quality Assurance Energy and Coastal Zone Administration Calvert Cliffs :!uclear Power Plant Department of Natural Resources Maryland Routes-2 & 4 Tawes State Office Building Lusby, MD 20657 Annapolis, MD 21204
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Enclosure CALVERT CLIFFS NUCLEAR PO'.lER PLANT UNIT 1 REVIEW OF PRESSURE TEMPERATURE LIMITS REQUEST FOR ADDITIONAL INFORMATION BALTIMORE GAS AND ELECTRIC
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DOCKET NO. 50-317 1.
Provide a map of the end-of-life isofluence at the internal surface of th'e beltline region of the reactor vessel, showing a) the location of the longitudinal and girth welds in relation to the core configuration, and b) the location of the materials surveillance capsules.
2.
Identify the computer code used for calculating the fluence.
3.
In the event that other materials surveillance capsules have been removed from the reactor, a) compare the predicted with the actual fluence values as determined by dosimetry, b) identify the published surveillance reports, and c) state when the next surveillance capsule is scheduled to be removed from the reactor.
4.
Provide a transverse operational cross-section of the reactor vessel in the beltline region showing the reactor internal components and the location of the surveillance capsules.
Indicate the dimensions of the materials inter-posed at full power density between the core and the walls of the reactor vessel.
5.
Explain wgy the capsule.at 263 was pulled and tested instead of the one at 97. What is the future planned removal,s,equence? Justify briefly.
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