ML19254B160
| ML19254B160 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/20/1979 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| TAC-08247, TAC-8247, NUDOCS 7909240503 | |
| Download: ML19254B160 (3) | |
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("SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramento, California 95813; (916) 452 3211 September 20, 1979 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Robert W. Reid, Chief Operating Reactors, Branch 4 Division of Opersting Reactors Re: Docket No. 50-312 Proposed Amencment No. 45 Rev. 1 Rancho Seco Nuclear Generating Station, Unit No. 1
Dear Mr. Reid:
In accordance with 10 CFR 50.59, the Sacramento Municipal Utility District hereby proposes to amend its Operating License DPR-54 for Rancho Seco Nuclear Generating Station, Unit No. 1, by submitting forty (40) copies of Proposed Amendment No. 45 Rev. 1 The attached Proposed Amendment No. 45 Rev. 1 is in respons: to your request to Mr. J. J. Mattimoe dated July 23, 1979.
The District previously submitted an application for a license amendment concerning steam generator monitoring requirements prior to March 22, 1979.
The original document for an amendment was forwarded to you on October 20, 1976, and therefore is exempt from Class III fees.
If you have any questions cor.cerning this Proposed Technical Specification change, please contact Mr. R. Colombo at Rancho Seco Unit I.
Respectfully submitted, v.
J. Mattimoe Assistant General Manager and Chief Engineer JJM:RWC: jim
$3'201 7 9 092 4 o IFt13i AN ELECTRIC SYSTE M S E RVIN G MORE THAN 600,000 IN THE HEART OF C All F 0 R N I A
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ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
The provisions of 10 CFR 50.36 (c) (1) (i) shall be complied a.
with immediately.
b.
The Safety Limit violation shall be reported to the Plant Super-Intendent, the Manager of Nuclear Operations, the Chairman of the HSRC and to the Commission immediately.
c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
TheSafetyLimitViolationReportshallbesubmittedtothe Commission, the MSRC, the Manager of Nuclear Operations and the Plant Superintendent within 10 days of the violation.
6.9 000CEnUDFC 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.
b.
Refueling operations.
c.
Surveillance and test act!vities of safety related equipment.
d.
Security Plan implementation, e.
Emergency Plan implementation.
f.
Secondary water chemistry monitoring to include (1) Identifica-tion of a sampling schedule for.the critical parameters and control points for these parameters; (2) identification of the procedures used to quantify parameters that are critical to control points; (3) identification of process sampling points; 45 (4) procedure for the recording and management of data; (5) procedures defining corrective actions for off control point chemistry onditions; and (6) a procedure identifying the authority responsible for the interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action.
6-11 Preposed Amendment io. 45 Rev. l
i ADMINISTRATIVE CONTROLS 6.8.2 Each procedure and administrative policy cf 6.8.1 above, and changes thereto, shall be reviewed by the PRC. Tho e matters pertaining to items 6.8.la, b and c, above shall be approved by the Plant Superin-tendent prior to implementation and reviewed periodically as set forth in each document. The manager of Nuclear Operations shall also approve Security Plan and Emergency Plan implementing procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The Intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the PRC and approved by the Plant Superintendent within seven (7) days of. implementation.
6.9 REPORTING REQUIP.EMENTS 6.9 1 in addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of inspection and Enforcement unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license; (2) amendment to the license involving a planned increase in power level; (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic per-formance of the plant.
The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a co ;srison of these values with design predic-tions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commit-ments shall be included in this report.
6.9.1.2 Startup reports shall be submitted within (1) Minety (90) days following completion of the startup test program; (2) Ninety (90). days following resumption or commencement of commercial power operation; or (3) Nine (9) months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, comoletion of startup test program and resumption or commencement of cor. ercial power operation), supplementary reports shall be submitted at least every three (3) months until all three events have been com-pleted.
6-12 Proposed Amendment No. 45 Rev. l
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