ML19345E807
| ML19345E807 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/29/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19345E800 | List: |
| References | |
| 50-277-80-24, 50-278-80-18, NUDOCS 8102060174 | |
| Download: ML19345E807 (3) | |
Text
{{#Wiki_filter:. . 'O APPENDIX A NOTICE OF VIOLATION Philadelphia Electric Company Docket Nos. 50-277 50-278 Based on the results of an NRC inspection conducted on July 1-31, 1980. It appears that certain of your activities were not conducted in full compliance with conditions of your NRC Facility License Nos. DPR-44 and DPR-56 as indicated below. Item A is an infraction and Item B is a deficiency. A. Technical Specification 3.11.D requires in part, "... Snubbers listed in Table 3.11.D.1 shall be operable except... Fmm and after the time that a snubber is detennined to be inoperable, continued reactor operation is permissible only during the succeeding 72 hours..." Contrary to the above, Philadelphia Electric Company was advised by the architect-engineer on June 5,1980 that Snubber 10-G8-S-44 listed in Table 3.11.D.1 was inoperable. Plant operation then continued for a period of 43 days with this snubber inoperable and no shutdown being initiated. B. Technical Specification 6.9.2.9, " Prompt notification with written followup," states in part, "The types of events listed below shall be reported...within 24 hours...with a written followup report within ten working days... Perfonnance of structures, systems or components that requires remedial action or corrective measures to prevent operation in a manner less con-servative than assumed in the accident analyses in the safety analysis report..." Contrary to the above, on nine occasions as listed below, no report 'was made to the NRC when the licensee was informed by its architect-engineer of seismic restraint inadequacies which required corrective action to prevent operation in a manner less conservative than assumed in the accident analysis in the safety analysis report. The pipe supports involved and the dates of architect-engineer notifications were: Component System Date Infonaed M-295-61 Main Steam Sample June 16, 1980 6-HF-54 Feedwater Long PatP July 2, 1980 Recirculation M-295-76, PG-11 Reactor Pressure Vessel July 2, 1980 and PS-104 Drain 8102 0 60 f~/k ww =
4 Appendix A 2 Components System Date Informed Drawing Detail High Pressure Service July 9,1980 No. X System M-295-77 Reactor Pressure Vessei July 2,1980 CSP-H901 Drain 27HC-S6 Condensate Transfer System June 30,1980 27HC-S56 Condensate Transfer System June 30,1980 Reactor Pressure Reactor Pressure Vessel June 30,1980 Vessel Column B Level Instrumentation l t 1 .-3 m
APPENDIX B NOTICE OF VIOLATION Philadelphia Electric Company Docket Nos. 50-277 50-278 Based on the results of an NRC inspection conducted on July 1-31, 1980, it appears that one of your activities was not conducted in full compliance with conditions of your NRC License Nos. DPR-44 and DPR-56 as indicated belcw. This item is an infraction. These paragraphs, containing 2.790 Information, not for public disclosure are intentionally left blank. S =.}}