05000277/LER-1980-001, Forwards LER 80-001/01T-0

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Forwards LER 80-001/01T-0
ML19257C662
Person / Time
Site: Peach Bottom 
Issue date: 01/17/1980
From: Cooney M
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19257C663 List:
References
NUDOCS 8001290563
Download: ML19257C662 (3)


LER-1980-001, Forwards LER 80-001/01T-0
Event date:
Report date:
2771980001R00 - NRC Website

text

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 (215)841 4000 January 17, 1980 Mr. Boyce H.

G rie r, Director Region I Office of Inspection & Enforcement US Nuclear R e gu la t o ry Commissisn 631 Park Avenue King of Prussia, PA 19406 Dea r Mr. Grier:

SUBJECT:

Licensee Event Report Narrative Descriotion The following occu rren ce was reported to Mr. Greenman, Region I, Office of Inspection and Enforcement on January 3, 1980.

Reference:

Docket No. 50-277 Report No.:

LER 2-80-1/lT Report Date:

January 17, 1980 Occurrence Date:

January 3,

1980 Facility:

Peach Botton Atomic Power Station RD 1,

Delta, Pennsylvania 17314 Technical Soecification Reference:

Technical Specification 6.9.2a(6) requires reporting "p ers onnel e rror or p rocedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cop e with accidents analyzed in the SAR."

Descriotion of the Eventt} On 1/3/80 with Unit 2 at 92% power and the drywell being deinerted in p reparation f or a planned outage, two drywell ventilation isolation valves (AO-25 21 A & A0-25213) were found to be fully opened instead of being limited to 37 degrees open which is permitted during reactor operation. The valves were j}{yg[L b 8 oo 129 o f63

Mr. 3oyce H. Grier Page 2 immediately readjusted to less than 37 degrees open. The valves had been in the full open p os iti on f or approxima tely eight h ou rs. Consecuences of Event Reactor operation with the isolation valves at more than a 37 degree opening could have resulted in a closure time greater than the maximum allowable five seconds for the drywell ventilation isolation valves. Cause o' Event The valves were in the full open p os ition because the air supply regulator output pressures to the valves had been incorrectly set. The most probable cause of the event was inadequate procedural control. , Corrective Action: Discussions have taken place between Philadelphia Electric Company (PECO) and NRC personnel concerning the op era ti on of the drywell ventilation isolation system at PBAPS. Also, a meeting between PECO and the NRC was held in Bethesda, Maryland on August 24, 1979 to review operational aspects of this system. Recommendations for long term modifications to the containment ventilation is ola tion valves are being de velop ed by the PECO Engineering Department and the valve manufacturer. The short term solution, as discussed at the referenced meeting with the NRC, has been t o place administrative controls on valve operation t o ensure the five second closure ti=e. In this case, immediately after the valves were f ound full open the corrective action was to reduce the opening to less than 37 degrees. In addition, a cautionary tag stating the correct operating pressure has been placed on the air supply regulator for each drywell ventilation isolation valve on Unit 2 and Unit 3. 1821! 232

Mr. B oy c e H. Grier Page 3 Also, p r oce du ral revisions will be made to include a requirement to maintain the ou tp ut of the air supply regulating valve at zero psig (the is ola ti on valves require air to open) during reactor operation except while inerting or deinerting the drywell. It, therefore, will take two d e li b e r a t e and separate actions to operate the is ola tion valves (s olenoid actuation and regulator adjustment). The procedural changes are being made to ensure the proper operation of the drywell ventilation isolation valves. Very truly yours, ',ll<b // M. ho ney Sug,rintendent Generation Division Nuclear Attachment cc: Director, NRC Office of Inspection and Enforcement Mr. Norman M. Haller, NRC Office of Management & Program Analysis 182FZ 233 }}