ML20086L176
| ML20086L176 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/17/1974 |
| From: | Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20086L173 | List: |
| References | |
| AO-74-22, NUDOCS 8402070449 | |
| Download: ML20086L176 (2) | |
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April 17, 1974 O
i Xr. James P. O'Reilly, Director
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United States Atc=ic Energy Cc=ission Directorate of Regulatory Operations g3 7 /g 631 Park Av.nue King of Prussia, Pennsylvania 19406
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l Subiect :
Abner al Occurrence 2h. Hour Notification Confir=ing cy conversation with Mr. Ed Greenman, A.E.C. Region I Regulatory Operations Cffice on April 17. 1974
Reference:
1,1 cense Nunber DPR 44. Amend =ent Nu=ber 1 Technical Specification 3 5.C.1 Report No.:
50-277-74-22 Report Date:
April 17, 1974 Occurrence Date: April 16. 1974 Facility:
Peach Bottos Ato:ie Pcwer Station, R.D.1, Delta, Pennsylvania 17314
- Identification of Occurrence:
HPCI tripped during renctor vessel injection test.
Conditiens Prior to Occurrence:
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. Plant shutdown following a p1nnned turbine trip and ocram fro: M power.
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Designation of Occurrence:
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As part of the start-up test progr., an HPCI system test which delivers
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water to the reactor vessel is required. This test was performed on 1
4 April 16, 1974 following a planned turbine trip and reactor scram from the 50% power level.. Upon auto..atic initiation, the EMI turbine isolated.
Icolation was caused by a high steam flow ccndition to the turbine. High I
stea= flow was sensed bv a differential pressure switch connected to an elbow tap flow ele ent in the steam cupply to the HPCI turbine. The isolation was i=ediately reset by the operntor. This per=itted the HPCI to restart and cuccessfully, injected water to the reactor vescel at rated flow. Data taken during this test indicated additional control adjuste=ents are require 3.
g Desi mation of Apparent Cause of Occurrence:
Data tt%en during the EPCI injettic: test shows that turbine acceleration rate during the initial start was significantly g-eater than during the restart. Thie infers that the stea= flow during the initial sta-t was also significantly greater than bring the restart. The precise cauce has not been deter =ined at this time.
Analyeis of Occurrence:
The initial isolation of the HPCI system during the infection test has no '
p safety i=plicatiene in that the system was de=cnstrated i=:ediately to gf q be capable of injecting water to the reactor vessel.
Start-up tecting q
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is perfor=ed for the purpose of identifying and correcting ninor control proble=s with engineered cafegusrd systems prior to achieving reactor 18 power levels where design system response it, required to citigate accidents. O B402070449 740426 PDR ADOCK 05000277
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Corrective Action:
1 Folleving this coeurrence, the EPCI controls were checked. No l
ccnditiens.hi:h would account for the initial high flow g
were identified.
System operability testa chall be perforced during the next start-up at apprcxirstely 400 pcig reactor preerure.
System automatic initiation tests shall be perfor:ed at rated reactor pressure ucing the pu=p test loop flev path.
Vessel injection testa shall be repeated at a nominal 514 power level-Failure Octa:
No previcus ci=ilar EPCI failures have been experienced.
Of' W. T. Ullrich, Superintendent Fench Botto: Atenie Power Station.
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