ML17206A618
| ML17206A618 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie |
| Issue date: | 11/20/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17206A611 | List: |
| References | |
| 50-389-78-10, NUDOCS 7901180323 | |
| Download: ML17206A618 (4) | |
Text
APPENDIX A NOTICE OF VIOLATION Florida Power and Light Company License No.:
CPPR-144 Based on the results of the NRC inspection conducted on October 24-27,
- 1978, it appears that certain of your activities were not conducted in full compliance with NRC requirements as indicated below.
These items have been categorized as described in our correspondence to you dated December 31, 1974.
10 CFR, Part 50.55, paragraph (e)(1), "Conditions of Const, ruction Permit," as implemented by FPL's Quality Assurance Manual Procedure QP 16.6, Rev. 0, states in part, ".....
The holder of the permit. shall notify the commission of each deficiency found in design and construc-tion, which, were it to have remained uncorrected, could have affected adversely the safety of operations of the nuclear plant at anytime throughout the expected lifetime of the plant, and which represents:
.....(ii) a significant deficiency in final design as approved and released for const. ruction such that the design does not conform to the criteria and bases stated in the safety analysis report or construction permi t; Contrary to the above requirement,s, the licensee failed to notify the commission of the below listed examples of significant deficiencies in final design:
FPL documentation examined at the site on October 24-27, 1978 revealed the licensee was advised by its nuclear steam supplier (NSS) by letter (L-CE-3826, dated July 28, 1978) of a significant.
flow problem experienced in the high pressure safety injection (HPSI) system of a similar designed facility.
This flow problem was at. tributed to excessive pressure drop through specifically identified control valves thereby preventing initiation of a
safety injection signal.
The licensee was advised by its NSS that Plant St.
Lucie - Unit 2 (PSL-2)
HPSI system would be utilizing the same type control valves and by a subsequent letter dated August.
1, 1978 (L-CE-3830) that this item was considered report,-
able under 10 CFR 50.55(e) requirements.
The subject control valves were shipped back to the vendor for change in valve trim.
~
g
Appendix A Notice of Violation CPPR-144 2.
FPL documentation examined at the site on October 24-27, 1978 revealed that the licensee had previously experienced potential impeller locking device assembly design problems as early as November 21,
- 1975, and although alerted by RII on August 23, 1978 of the possibility that this generic problem may effect PSL-2 the licensee failed to report this matter to the NRC in accordance with 10 CFR 50.55(e) reporting criteria.
This is a deficiency.