ML19263E942

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Summary of 790508 Meeting W/Util & Bechtel in Bethesda,Md Re Licensee Design of Hard Wire control-grade Reactor Trip Caused by Loss of Feedwater &/Or Turbine Trip & Other Matters Related to NRC Shutdown Order
ML19263E942
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 05/15/1979
From: Zwetzig G
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-11649, NUDOCS 7906290028
Download: ML19263E942 (4)


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WASHINGTON, D. C. 20555

,o May.5,1979 Docket No.: 50-346 LICENSEE: TOLEDO EDISCN COMPANY, ET AL.

FACILITY: DAVIS-BESSE NUCLEAR GENERATING STATION, LNIT 1 -(Davis-Besse 1)

SUBJECT:

SUMMARY

OF MEETING HELD ON MAY 8, 1979 TO DISCUSS LICENSEE'S DESIGN OF HARD WIRE CONTROL GRADE REACTOR TRIP CAUSED BY LOSS OF FEEDWATER AND/0R TURBINE TRIP, AND OTHER MATTERS RELATED TO CONFIRMATORY ORDER TO SHUT DOWN The meeting was held at the Commission's offices in Bethesda, Maryland. A list of attendees is given in Attachment 1.

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SUMMARY

1.

NRC Organization for Review.

In response to a question from the licensee the organization for review of the responses to the forthcoming order,tas described. It was noted that for matters pertaining to the order, the NRC contact was G. Zwetzig but that for other matters pertaining to Davis-Besse 1, the NRC contact remained G. Vissing.

2.

Hard-Wired Control Grade Reactor Trip Caused by loss of Feedwater and/or Turbine Trip.,

F. Mills of TECO presented the details of the trips that are currently being installed. The loss of feedwater trip is initiated by a reverse pressure of 170 psi across the chek valves in both main feedwater discharge lines; and turbine trip is initiated through operation of auxiliary relay contacts in the Electrohydraulic Control System when the turbine trips. Provision is made for manual block of the Turbine Trip below 15% power. Mr. Miller described how the trip signals produced reactor trip and what alarms and annuciator messages would be produced. He also outlined the design criteria for the system. Following staff questioning, the staff concluded that it had no further questions at that time and that the design appeared generally comparable to those proposed by other licensees with B&W reactors.

3.

Need for NRC Conclusion as to Acceptability. The licensee was advised tnat the wording of the forthcoming order would be such that it would be necessary for the NRC to confirm that the actions ordered had been completed and to conclude that the analyses submitted were acceptable and that the implementing procedures were appropriate. Accordingly, he was further advised that any submittals required by the order shocid be made sufficiently in aavance of the desired startup date to permit staff review.

It was also noted that the needed information could be submitted to the NRC as soon as it was ready and did not need to be held up for inclusion in a single submittal.

2303 258 79062900R$

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Meeting Summary for 08-1 Held on 5/8/79 4.

Additional Infomation Needed. Two draft lists of questions were given to the licensee to provide a preliminary indication of the information needed by the staff to complete its review. The licensee expressed objections to some of the information requested - Stating that it did not pertain to the scope of the order. The staff explained why it considered some of the information fell within the scope of the order.

It also acknowledged that while other portions of the information did not fall within the scope of the order, it was needed because of deficiencies in the Davis-Besse 1 responses to IE Bulletin 79-05A.

The licensee also expressed strong objections to planned request for sub-mission of detailed operating procedures. The basis for the objection was that such submission would result in highly detailed plant operation infor-mation being placed in the docket file and therefore subject to unrestricted public inspection. The licensee believed this was extremely unwise relative to maintenance of plant security and the prevention of sabotage.

G. Zwetzig advised the licensee to proceed with assembling the infomation requested by the draft lists and to submit it as soon as possible. He also stated that he would advise the licensee as to clarification obtained relative to how procedures would be reviewed and if any of the information requested by the draft lists could be deleted.

4 CyuR p-n Gerald B. Zwetzig, Project Manager Operating Reactors Branch #4 Division of Operating Reactors

Attachment:

List of Attendees 2303 359 e,g-e we e

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LIST OF ATTENDEES MEETING NRC/TECO Davis-Besse 1 RESPONSE TO ORDER NAME AFFILIATION G. B. Zwetzig NRC T. J. Myers TECO F. R. Miller TEC0 J. Ventura Bechtel B. Novich Bechtel F. Ashe NRC D. C. Fischer NRC B. Boger NRC G. Mazetis NRC a

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MEETING SUMitARY DISTRIBUTION ORB #4 Mr. Lowell E. Roe Vice President, Facilities Development Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652 Docket File R. Reid NRC PDR V. Noonan s

L PDR P. Check ORB #4 Rdg G. Lainas i

NRR Rdg G. Knig.. ton H. Denton Project Manager E. G. Case OELD V. Stello 01&E(3)

D. Eisenhut R. Ingram R. Vollmer R. Fraley, ACRS (16)

W. Russell Program Support Branch B. Grimes TERA T. J. Carter J. R. Buchanan A. Schwencer Meeting Summary File D. Ziemann NRC Participants T. Ippolito

n. Ashe D. C. Fischer B. Boger G. Mazetis 2303 361 c

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