ML20212M567
| ML20212M567 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/21/1986 |
| From: | Mcneil S Office of Nuclear Reactor Regulation |
| To: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8608260390 | |
| Download: ML20212M567 (3) | |
Text
PDL Docket Nos. 50-317 and 50-318 August 21, 1986 jb O/
Mr. J. A. Tiernan Vice President - Nuclear Energy Baltimore Gas & Electric Company P. O. Box 1475 Baltimore, Maryland 21203
Dear Mr. Tiernan:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION-PRESSURIZED THERMAL SH0CK RULE We have received your letter dated January 23, 1986 in response to 10 CFR 50.61, " Fracture Toughness Requirements For Protection Against Pressurized Thermal Shock Events." We have determined that additional information is required to complete our review of your pressurized thermal shock assessment.
The request for additional information is enclosed.
Please provide the information as requested within 30 days following the receipt of this letter or inform us within 15 days of your need for additional time to respond and of your proposed schedule for providing the information requested herein.
This request for additional information affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Scott A. Mc Neil, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B
Enclosure:
Request For Additional Information cc w/ enclosure:
See next page Distribution:
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F Mr. J. A. Tiernan Bsitimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant cc:
Mr. William T. Bowen, President Regional Administrator, Region I Calvert County Board of U.S. Nuclear Regulatory Commission Commissioners Office of Executive Director Prince Frederick, Maryland 20768 for Operations 631 Park Avenue D. A. Brune, Esq.
King of Prussia, Pennyslvania 19406 General Counsel Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Jay E. Silberg, Esq.
Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Washington, DC 20036 Mr. M. E. Bowman, General Supervisor Technical Services Engineering Calvert Cliffs Nuclear Power Plant MD Rts 2 & 4, P. O. Box 1535 Lusby, Maryland 20657-0073 Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box 437 Lusby, Maryland 20657-0073 Bechtel Power Corporation ATTN:
Mr. D. E. Stewart l
Calvert Cliffs Project Engineer 15740 Shady Grove Road Gaithersburg, Maryland 20760 Combustion Engineering, Inc.
ATTN:
Mr. W. R. Horlacher, III Project Manager P. O. Box 500 1000 Prospect Hill, Road Windsor, Connecticut 06095-0500 Department of Natural Resources Energy Administration, Power Plant Siting Program ATTN:
Mr. T. Magette Tawes State Office Building Annapolis, Maryland 21204
REQUEST FOR ADDITIONAL INFORMATION BALTIM0RE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 RESPONSE TO 10 CFR 50.61, " FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS."
1 1.
Provide the copper and nickel contents and the initial RT
- values, andthejustificationforthem,asrequiredbyparagrah5bl(b)(iii) of the PTS rule.
It requires:
(iii) "Cu" and "Ni" mean the best estimate weight percent of copper and nickel in the material. The source of these values must be included in the assessment.
The relationship of the material, on which any measurements were made, to the actual material in the pressure vessel must be described."
For the weld metals, which appear to be controlling for Unit 1, it would be acceptable to describe the weldments on which measurements were made and relate them to the vessel welds by their weld wire heat numbers, giving the individual measurements or the number of measurements, their range and their average.
If the values in the submittals are not averages, their derivation should be justified.
2.
Provide the values of the fast neutron fluence (E 2 1.0 MeV) used in the cubn)t(asofthedateofthesubmittal)fluencevaluesandattheend RT estimates of your submittal dated January 23, 1986.
Provide of license.
State the assumptions for future cycle loadings.
State the code used for the calculation and the assumptions on neutron sources and their representation, cross sections and the computational approximations.
_