ML20086H020
| ML20086H020 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/24/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20086H024 | List: |
| References | |
| AO-75-11, NUDOCS 8401130338 | |
| Download: ML20086H020 (2) | |
Text
{{#Wiki_filter:. D O PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET PHILADELPHIA. PA.19101 (215)841-4000 Febmary 2h,1975 (4i@ '.,~ N' Mr. A. Giambusso, Director /~?'. .\\ Division of Reactor Licensing -{/ /.g@. Office of Nuclear Reactor Regulations (- j , f) 4 United States Nuclear Regulaton Comission ly Ir ' c Washington, D.C. 20555 J .s p: 'El l 1% '( h, N -/0/
Dear Mr. Giambusso:
( lt* }iN
Subject:
Abnomal Occurrence f, The following occurrence was reported to Mr. Walt Baunack, Office of Inspcetion and Mforecnent, Region 1, United States Fuclear Regulatory Comission on Fcbmary 1h,1975. Written notification can modu i.u -:c. mm, T. C %111.y, Cfflus uf Lwya,.t1w. un.: l'ufcrc=.=.t, Region 1, United States Uuclear Regulatory Coptission on Febmary 1h, 1975 In accordance with Section 6.7 2.A of the Technical Specifications, Appendix A of DPR-56 for Unit 3 Peach Botton Atcmic Power Station, the following report is being submitted to the Directorate of Reactor Liunsing as an Abnomal Occurrence. Referenec: License Nunber DPR-56 Technical Specification Refercnce: h.7.D.1.b(1) and Table 3.7.h Report No.: 50-278-75-11 Report Date: February 2h,1975 Occurrence Date: Febmary 1h,1975 Facility: Peach Bottem Atomic Power Station R.D.1, Delta, Pennsylvania 1731h Identification of Occarrence: Fxcessive leakage drywell 02 Analyzer Sa ple Systen Inner Isolation Valve (SV-3671C). Q>[ Conditions Prior to Occurrence: 9 'I Unit 3 at 99 9% power. 8401130330 750224 N;! O-PDR ADOCK 05000278 S PDR COPY SENT REGION 1
Mr. A. Gimbusso Febmary 2h,1975 -Paga 2 Description of Occ'irrence: hhile perfoming Surveillance Test 6.2 PCIS nomally open valves, this valve failed to seat. Measured leakage was in excess of acceptable values. Designntion of Anparent Cause of Occurrence: Disnsse.bly of the valve indicated dirt on the seat and a small amount of dirt in the body of the valve preventing tight seating. Analysis of Occurrence: The safety implications of this occurrence are minimal since the outer isolation valve SV-3978C did close and seat. Corrective Action: The valve was taken spart, the intemals and seat were cleaned, end the valve was reasseloled. Subsequent leak testing of the valve was successful. Fed "lu m Dn +.n ? A previous failure was reported as an Abnomal Occurrence on 11/9/73 Very tmly yours, M. .. Cooney Ass't Genil Sup -rintendent Genorction Divisicn ec: Mr. J. P. O' Reilly Director Office of Inspection and Enfome.ent Region 1 United States Nuclear Regulatory Connission 631 Park Avenue King of Pmssia, PA 19h06 -. ~ W w- -,}}