ML20003D494
| ML20003D494 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/23/1981 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20003D495 | List: |
| References | |
| NUDOCS 8103270428 | |
| Download: ML20003D494 (2) | |
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B ALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 1475 B A LTIM O R E. M A R YL A N D 2120 3 Antwum E. LUNQVALL,Ja.
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March 23, 1981 Sv nt a
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Office of Nuclear Reactor Regulation
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U. S. Nuclear Regulatory Commission p
Washington, D. C. 20555 ff[
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A14 [ g O IS8 1am.
ATTENTION: Mr. R. A. Clark, Chief Operating Reactors Branch #3 Division of Licensing G u.a. k g g 11 b
SUBJECT:
Calvert Cliffs Nuclear Power Plant g
Units No. I and 2, Docket Nos. 50-317 v
y and 50-318 Core Barrel Movement Technical Specification Gentlemen:
We propose to reduce the monitoring and reporting requirements now specified in Technical Specification 3.4.11 (Core Barrel Movement).
BACKGROUND A core barrel movement monitoring iequirement was included in the Technical Specifications of several nuclear units including Calvert Cliffs Units 1 and 2 af ter the Palisades Plant experienced excessive barrel motion several years ago. The vendor, Combustion Engineering, Inc. (CE), devised a generic (esign modification to prevent such motion. That modification was made to the Calvert Clifis units. About ten (10) reactor-years of monitoring experience on the Calvert Cliffs units has not revealed any excessive core barrel motion. Visual inspection has not revealed any unexpected wear in the flange area of the core barrel to reactor vesselinterface.
Technical Specification 3.4.11 in its present form has served its purpose and has become an unnecessary burden.
TECHNICAL SPECIFICATION CHANGE Although it would appear that sufficient evidence exists to support abolishing Technical Specification 3.4.11 altogether, we only request relief from some of its more burdensome monitoring and reporting requirments. Proposed modifications to Technical Specification pages 3/4 4-29,4-30, and B 3/4 4-12 are attached. The modified Technical Specifica' ion is similar to those of other licensees.
SAFETY ANALYSIS Technical Specification 3.4.11 was devised to confirm the adequacy of a design modification to preclude excessive core barrel movement. Significant successful 810827 0 84N 9
Office of Nuclear Reactor Regulation Page two operating experience of the Calvert Cliffs and other licensee units has confirmed the adequacy of that modification. In addition, excessive core barrel movement is a slowly developing phenomenon.
The proposed modifications to the monitoring program are consistent with the reduced probability of excessive movement and with the speed with which it develops.
The Plant Operations and Safety Review Committee (POSRC) and Offsite Safety Review Committee (OSSRC) have concluded that the proposed modification does
't constitute an unreviewed safety question and that the proposed action does not present an undue risk to the health and safety of the public.
BALITMORE GAS AND ECTRIC COMP ANY
/
BY hM
- A. E. Lungdent - Supply
/
all, Jr.
Vice Pres.
STATE OF MARYLAND, CITY OF BALTIMORE, TO WIT:
Arthur E. Lundvall, Jr.. being duly sworn states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he executed the foregoing Amendment for the purposes therein set forth; that the statements made in said Amenoment are true and correct to the best of his knowledge, information,and belief; and that he was authorized to execute the Amendment on behalf of said Corooration.
1 WITNESS My Hand and Notarial Seal thisM/2 sday of
/ yg 1981.
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- )
l 4 r) v lAAjs Notary Public /
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My Commission Exprires:
Attachment cc:
- 3. A. Biddison, Esquire G. F. Trowbridge, Esquire Messrs. E. L. Conner, Jr., NRC P. W. Kruse, CE