ML20002C340
| ML20002C340 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 11/19/1980 |
| From: | Walbridge W SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20002C336 | List: |
| References | |
| 80119, TAC-51696, NUDOCS 8101100083 | |
| Download: ML20002C340 (2) | |
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SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street. Box 15830. Sacramento. Cahfernia 95813; (916) 452 3211 qOE ~
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November 19, 1900 D. '. Q..,q 'Q i.e.
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Mr.
R. H.
Engelken, Director A gr p
Region V Of fice of Inspection r, Enforcement
' %' ' D-, 8 U. S. Nuclear Regulatory Commission 1990 North California Boulevard Walnut Creek Plaza, Sui te 202 Walnut Creek, California 0L936 Re:
J. L. Crews to J. J. Mattimee
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Letter 9ated November 7,1980 Operating License DPR-54 l'ocket No. 50-3IJ.
Dear Mr. Engelken:
In reply to your letter from Mr. J. L. Crews reques ting an addi tional response to i tem C of the Notice of Violation dated September 26, 1980, we of fer the following explanations and corrective actions to assure full compliance with NRC requirements.
Appendix A, item C of the September 26, 1980 letter notes the following inf raction:
10 CFR Part 50, Appendix A, Cri terion 23 states that the protection sys tem shall be designed to fail into a safe s tate or into a s tate demons tra ted to be acceptable on some other defined basis if condi tions such as disconnection of the sys tem, loss of energy (e.g., electric power. Instrument air), or postulated adverse envirorments (e.g. extr ae heat or cold, fi re, pressure, s team, water, and radiation) are ex pe r ienced.
In the FSAD. Appendix 1A, Page I A-26 as part of a discussion on Cri terion 23, the licensee s tates, " Safety features equipment can be manually initiated by the operator at any time even i f power is lost to the actua tion sys tem."
Contrary to the above the reactor building purge inlet line valve SFV 53503, the reactor building ourge outlet line valve SFV 53604, and the reactor building pressure equalizing line valve SFV 53210 will onparently fail open on loss of direct current power to the solenoid operators.
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a Mr. R. H. Engelken November 19, 1980 SMUD Reoly As stated above, the three valves do presently fall in the open position on a loss of direct current power to the controlling solenoid valves.
Since the valves in question are all outside containment valves with a fully redundant inside containment motor-operated valve, containment integrity would not be violated upon loss of direct current power to the solenoid.
However, to further assure containment integrity, it was decided to isolate the air to the three valves in question whenever reactor building containment integri ty is requi red.
Basically, this "f ails" the valves in their respective safety features positions and subsequent loss of direct current power to the solenoid operators will not alter the position of the valve.,
The above ccrrective action has been implemented as an interim solution.
District engineers have designed a modification to the system which will provide a closure signal on loss of direct current power. Upon completion of this modification, the valves in question will fully meet all the requirements of 10 CFR Part 50, Appendix A, Criterion 23 It is the District's intention to make these modifications during the 1981 refueling ou tage.
Sincerely, e
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Wm. C. Walbridge General Manager WCW:HH:jr