ML20002C344
| ML20002C344 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/25/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20002C336 | List: |
| References | |
| 50-312-80-26, NUDOCS 8101100097 | |
| Download: ML20002C344 (2) | |
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O APPE!! DIX A Sacramento t'unicipal Utility District P. 0. Box 15330 Sacramento, California 95813 Occket flo. 50-312 License flo. CPR-54 10TICE OF VIOLATI0tl Based on the results of the NRC insoection conducted between August 1 and 29, 1980, it accears that certain of your activities were not in full comoliance with acolicable NRC regulations and conditions of your license, as indicated below:
A.
Technical Specification Table 2.3-1 specifies that the t!uclear Power trip setting is 5, of rated maximum when tne plant is in the shutdown bypass mode.
Contrary to the above, at 1353 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.148165e-4 months <br /> on August 13, 1980, the plant was placed in the shutdown bypass mode, but the fluclear Power trip setting of 5% of ratec maximum was not instituted until 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br /> on August 20, 1980.
This is an apparent repeat infraction.
B.
Technical specification 6.8.1 states in part that written procedures shall be established, implemented, and maintained covering the activities referenced in the applicable procedures reccrrmended in Appendix "A" of Regulatory Guide 1.33, t!ovember 1972.
Appendix "A" of Pegulatory Guide 1.33, tlovember 1972 states in part that instructions for energizing, filling, venting, draining, startup, shutdown, and changing modes of operation should be prepared, as appropriate, for twenty-nine separate systems including the reactor control and protection system.
Step 5.16 of Station Procedure B.4, Diant Shutdown and Cooldown states that one is to " Initiate Reactor protection system shutdown bypass and reset the hign flux trip to 5% as per OP A.69, Section 5.2."
Contrary to the recuirements stated above, on August 20, 1980, Step 5.16 of Station Procedure B.4 was not implemented which resulted in the high flux trip not being reset.
This item is an infraction.
C.
10 CFR Part 50, Appendix A, Criterien 23 states that the protection system shall be designed to fail into a safe state or into a state demonstrated to be acceptable on some other defined basis if conditions such as disconnection of the system, loss of energy (e.g., electric power, instrument air), or postulated adverse environments (e.g.) extreme heat or cold, fire, pressure, steam, water, and radiation) are experienced.
8101 20009];
In the FSAR Apcendix 1A, Page 1A-26 as part of a discussion on Criterion 23, the licensee statbs," Safety features equipment can be manually initiated by the operator at any time even if power is lost to the actuation system."
Contrary t6 the above the reactor building purge inlet line valve, SFV 53503, the reactor buiiding puri.te outlet line valve SFV 53604, and the reactor building pressure eaualiaing line valve SFV 53210 will accarently fail open on loss of direct current pov.er to the solenoid operatorc.
This is an infraction.
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