ML19208A062
| ML19208A062 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/27/1979 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML19208A063 | List: |
| References | |
| NUDOCS 7909120482 | |
| Download: ML19208A062 (2) | |
Text
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SACRAMENTO MUNICIPAL UTruTY olsTRICT C C1 s street. Box 15830. sacramento. Califemia 95813; (916) 452 4211
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August 27, 1979 U.S. Nuclear Regulatory Ccmission Attention: Mr. R. H. Engelken Director, Region V Office of Inspection and Enforcement 1990 North California Boulevard Walnut Creek Plaza, Suite 202 O. f88 Qf. a Walnut Creek, California 94596
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d Occket No. 50-312 Rancho Seco Nuclear Generating Station, Unit No. 1 Cear Mr. Engelka, The Sacramento Municipal Utility District has mceived IE Bulletin No.79-05C and has taken the following actions in response to the items in that bulletin:
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1.
Instructions have been issued to all licensed operators to trip all operating reactor coolant pcmps upon a reactor trip and initiation of high pressure injection caused by Icw reactor coolant system pressure.
In addition, two licensed operators am in the Rancho Seco Unit 1 control room at all times during operation to accomplish this action.
These actions will remain in effect until a system has been designed and installed at Rancho Seco Unit I which will assure automatic tripping of the reactor coolant pumas as required by the long term action item in this bulletin.
2.
The Babcock & Wilcox Company has cerformed an analysis to support the early reactor coclant pumo trip.
The District has determined this analysis to be applicable to Rancho Seco Unit 1 and the report, " Analysis Summary and Support of an Early RC Pump Trip" is enclosed. This report also contains a Section 3, "I:: pact Assessment of a RC Pump Trip on Non-LOCA Events' which is included and allcws the development of non-LOCA guidelines as re-quired in Item 3 belcw.
The Section 3 analysis is being reviewed by the District and its applicability will be determined after this review is comoleted.
Further analysis covering a range of time laoses between reactor trip and pump trip will be submitted by September 11, 1979.
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AN ELECitt; SY TEM I!1vl1G 40t! THAM $ 0 0. J 0 3 IN isE HEART OF O A LI F O R N I A
Mr. Engelken August 27, 1979
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Guidelints for operator actions for both LOCA and non-LOCA transients have been developed that take into account the impact of reactor coolant pump trip require-men ts.
These guidelines are presently being reviewed for use to develop emergency procedures as required by Item 4.
All licensed reactor cperators and senior reactor operators will be trained on tnese procedures within the 45 day schedule required by this bulletin.
5.
The B&W Owners Group has instructed the Babcock &
Wilcox Company to perform an analysis and develop guidelines related to inadequate core cooling as requested.
The District will submit a design whiuh will assure automatic tripping of the operating reactor coolant pumps under all circumstances in which this action may be needed by October 31, 1979, as required as a long term action by this bulletin.
Please advise if any further information is necessary.
Sincerely yours,
.Y J. J. Mattimoe Assistant General Manager and Chief Engineer Enclosure
.cc: Director, Office of Inspection and Enforcement Director, Office of Nuclear Reactor Regulation -
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