ML19340B838
| ML19340B838 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/31/1980 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8011120416 | |
| Download: ML19340B838 (2) | |
Text
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J esuuo SACRAMENTO MUNICIPAL UTILITY olsTRICT O 6201 s street. Box 15830, sacramento Califomia 95813; (916) 452-3211 October 31, 1980 I:
Director of Nuclear Reactor Regulation JJ Attention: Mr. Robert W. Reid, Chief Operating Reactors, Branch 4 U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Docket 50-312 b.,I m
Rancho Seco Nuclear Generating Station, Unit No.1
Dear Mr. Reid:
SMUD is participating in the B&W Integrated Reactor Vessel Materials Surveillance Program with the Toledo Edison Company, Davis-Besse Unit I reactor serving as the host reactor for Rancho Seco sur-veillance capsules. Technical Specification 4.2.8.2 for Rancho Seco requires the submittal of a report, or an application for a facility operating license amendment, whenever (starting one year after Davis-Besse begins commercial operation at 100% full power) Davis-Besse does not maintain a cumulative reactor utilization factor of o5% or greater.
Davis-Besse reached 100% full power on July 31, 1978, and as of one year later had not maintained the required utilization factor.
By letter of October 31, 1979, the District provided information to support the continued operation of Rancho Seco.
At the end of the second year of commercial operation - Julv 31, 1980 - the Davis-Besse cumulative reactor utilization factor rema:ned below 65%. However, the current Rancho Seco Technical Specifications related to reactor vessel material irradiation are valid for an accumulated neutron fluence corresponding to five effective full power years (EFPY) of operation. A Rancho Seco surveillance capsule with an exposure equi-valent to greater than eight EFPY was with P twn from Davis-Besse during the second quarter of 1980. The material specimens in this capsule are presently being testod and the data evaluated. As a result, revised Technical Specifications 'or operation beyond five EFPY will be submitted during 1981, prior to Rancho Seco approaching the current license limits.
Therefore, as the present Technical Specifications related to reactor vessel material irradiation remain valid, and the limits will v\\
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o Mr. Robert V Reid October 31, 1980 be modified before expiration to account for ongoing irradiation and to extend the applicability period, continued operation of Rancho Seco is acceptable.
Sincerely, Ob ht4Na John. Mattimoe Assistant General Manager and Chief Engineer l