ML20127K671
| ML20127K671 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/19/1985 |
| From: | Denton R BALTIMORE GAS & ELECTRIC CO. |
| To: | Butcher E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8506270530 | |
| Download: ML20127K671 (2) | |
Text
I a
BALTIMORE G AS AND ELECTRIC COMPANY P.O. Bo x 14 7 5 B ALTIM OR E. M A R YL AN D 212o3 NUCLEAR POWER DEPARTMENT CALVERT CLIFFS NUCLEAR POWER PLANT LUSeY M ARYLAND 20657 June 19,1985 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 ATTENTION:
Mr. Edward J. Butcher, Jr., Chief Operating Reactors Branch #3 Division of Licensing
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Request for Amendment
REFERENCES:
(a)
Letter from A. E. Lundvall, Jr., BG&E, to 3. R. Miller, NRC, dated April 26,1985, Request for Amendment Gentlemen:
Reference (a), Change No. 3, proposed a change to our Technical Specifications to provide clarification of the Surveillance Requirements for containment tendon end anchorages and adjacent concrete surfaces. This letter provides additional information in response to a verbal request by Mr. D. H. Jaffe, NRC Project Manager.
Calvert Cliffs' concrete crack observation program examines eleven locations on each containment structure. Unit 1 observation areas are located at six positions around the vertical tendon anchors on the ring girder and at five horizontal tendon anchors on the 90 buttress. The Unit 2 inspection covers similar areas, with the exception that one base slab-wall intersection area is substituted for a horizontal tendon location. The surface area of each location ranges from approximately 50 to 100 square feet. The concrete adjacent to over 50 end anchorages per containment is thereby inspected each surveillance.
The location numbers for the observation areas correspond to those used in the Structural Integrity Test. This preservice test, performed by Calvert Cliffs' Architect / Engineer Bechtel Power Corporation, consisted of: (1) an evaluation of the containment structure's ability to withstand 115 percent of design pressure, and (2) the measurement of structural response to changes in internal pressure. Calvert Cliffs continues to monitor the above selected, safely accessible areas during the Type A containment leakage rate tests.
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e Mr. E. 3. Butcher, Jr.
June 19,1985 Page 2 Should you have further questions regarding this reply, we will be pleased to discuss them with you.
Very truly yours e
aw-R. E. Denton General Supervisor -
Training & Technical Services RED /BEH/sjb NRC 85-27 cc:
D. A. Brune, Esquire G. F. Trowbridge, Esquire D. H. Jaffe, NRC T. Foley, NRC T. Magette, DNR k
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