ML19347F072
| ML19347F072 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/11/1981 |
| From: | Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19347F073 | List: |
| References | |
| NUDOCS 8105150191 | |
| Download: ML19347F072 (3) | |
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esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street Box 15830, Sacramento, California 95813; (916) 452-3211 RJR 81-333 May 11, 1981 DIRECTOR OFFICE OF INSPECTION AND ENFORCEMENT U. S. NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 OPERATING PLANT STATUS REPORT DOCKET NO. 50-312 Enclosed is the April Operating Plant Status Report for Rancho co Unit One.
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R. J. Rod i ucz Manager Nuclear Operations Enclosure cc:
ISE Washington (9)
Region V MIPC (2) 8105150/9/..,
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SUMMARY
OF PLANT OPERATION 4-01 to 4-24 Continued surveillance and prevent ive maintenance items associated with the fourth refueling outage.
4-25 Began plant heatup.
4-29 Reduced RCS pressure to work on leaking pressurizer valve.
4-30 Increasing RCS pressure.
PERSONNEL CHANGES REQUIRING REPORTlHG No personnel changes that require reporting in accordance with Technical Specifications Figure 6.9.2 were made in April, 1981.
SUMMARY
OF CHANCES IN ACCORDANCE WITH 10 CFR 50.59(b) 1)
Pevised Rancho Seco Emergency Plan to establish an emergency classification system, description of ten and 50 mile emergency planning zones (piume and ingestion exposure), and expand the scope of the overall Emergency Plan and emergency preparedness as requi red by 10 CFR 50.
2)
Completed modification to add radiation detectors on the reactor building vent, auxiliary building vent, main steam line A, and main steam line B.
These radiation monitors were added to measure releases up to and including those resulting f rom the NRC's hypothetical source term, as requi red by NUREG-0578. This capability provides monitoring dose rates higher than those described in the FSAR.
This provides additional information following a postulated accident, and in no way interferes with the safe operation of the plant. This monitoring capability will nnt affect the existing moni tori ng sys tem, and the power supplies will not affect any existing safety-re lated power suppl i es.
CYCLE 4 PLWER DISTRIBUTION COMPARISON In the District's letter to Mr. Robert W. Reid, dated February 27, 1980, Rancho Seco committed to perform Radial Power Distribution Comparisons during Cycle 4 as a result of this being the first reload core utilizing Lumped Burnable Poisons.
On January 27, 1981, with the reactor at 100% power and 225 EFPD, the RMS deviation on the radial power distribution was 0.022, well within the acceptance limit of 0.073 Cycle 4 ended on January 31, at 229 EFDD.
This completes the commitment for Cycle 4 power dist ribut ion information.
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MAJOR ITEMS OF SAFETY RELATED MAlHTENANCE
- 1) Reset OMR sump pump overload heater compensator.
- 2) Replaced seals and repositioned limit switches on RB purge valves.
- 3) Welded leaking joint on HPlP cooler. Cleaned and epoxy coated cooler.
- 4) Corrected phasing of wiring in boric acid power panel.
- 5) Reversed phasing of boric acid pump.
(Pump was running in reverse.)
- 6) Repaired body-to-bonnet leak in auxiliary feedwater turbinr.
Replaced internals and lapped plug to seat.
- 8) Added balance weights to RCP shafts.
- 9) Replaced RCP seals.
- 10) Replaced defective solenoid on seal return isolation valve.
- 11) Rewi red and tested safety features cont rol panel.
- 12) Replaced defective contact buffer in safety features panel.
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- 13) Repaired defective relay in atmospheric dump valve control.
14)
Replaced defective relay in DC electrical system.