Letter Sequence Other |
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Results
Other: ML19256E032, ML19257A557, ML19257C529, ML19257D427, ML19262C105, ML19305C443, ML19309C376, ML19340E129, ML20207L334, ML20207L340, ML20265C731, ML20265C732, ML20265C735, ML20265C736, ML20265C739, ML20265C740
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MONTHYEARML19256E0321979-10-23023 October 1979
Forwards Response to NRC Re Enhancements in Plant Design,Operations & Emergency Planning
Project stage: Other
IR 05000346/19790321979-12-27027 December 1979
IE Insp Rept 50-346/79-32 on 791015-20,1101-02,15-16 & 20. No Noncompliance Noted.Major Areas Inspected:Reactor Trip & Subsequent Loss of Offsite Power That Occurred on 791015 & Followup on Corrective Action on 791025
Project stage: Request
ML19257A5571979-12-31031 December 1979
Submits Addl Implementation Schedules for short-term TMI Lessons Learned Task Force Requirements Re Safety Valve Position Indication,Reactor Coolant Saturation Meter,Leakage Reduction Program & Design Review of Plant Shielding
Project stage: Other
ML19257C5291980-01-18018 January 1980
Forwards Summary of Methods of Implementing Short-Term Lessons Learned Commitments Actually Implemented by 800101 at Facility, in Response to NRC 800102 Request
Project stage: Other
ML19262C1051980-01-22022 January 1980
Forwards Responses to NRC 800102 Show Cause Order Re Implementation of Lessons Learned Task Force short-term Requirements.Requests Operation of Facility After 800131.All Requirements Met Except Two equipment-related Delays
Project stage: Other
ML19257D4271980-01-31031 January 1980
Forwards Results of Design Review of Plant Shielding for Spaces Outside Containment Which May Be Used in post- Accident Operations.Study on Areas Requiring Infrequent Operator Access Not Completed
Project stage: Other
ML19305C4431980-03-21021 March 1980
Forwards Responses to Requests & Questions Raised During NRC 800225 & 26 Site Visit to Review Util Implementation of Lessons Learned Task Force short-term Recommendations
Project stage: Other
IR 05000346/19800051980-03-31031 March 1980
IE Insp Rept 50-346/80-05 on 800204-08,11,15,19-22,25-28 & 0303-07.No Noncompliance Noted.Major Areas Inspected: Previous Insp Findings,Plant Operations,Physical Protection, Followup on LERs & Reactor Trip on 800205
Project stage: Request
ML19309C3761980-04-0101 April 1980
Forwards Addl Responses to Questions Raised During 800225-26 Site Visit for Review of Implementation of NUREG-0578 Requirements
Project stage: Other
ML20207L3401980-04-0303 April 1980
Documents 800218 & 25 Discussions W/Nrc Re Facilities Proposed to Support Emergency Response Capability.Criteria Used in Developing Key Facilities Enumerated
Project stage: Other
ML20207L3341980-04-0909 April 1980
Evaluation of Licensee Compliance W/Category `A Items of NRC Recommendations Resulting from TMI-2 Lessons Learned, Davis Besse Nuclear Power Station
Project stage: Other
ML19340E1291980-12-30030 December 1980
Responds to NUREG-0737.Util Working W/Oh State Univ on Feasibility Evaluation of long-term Program to Phase Out Need for Shift Technical Advisor.Commitment Supersedes All Previous Commitments
Project stage: Other
ML20265C7361987-01-15015 January 1987
Equipment Locations Containment & Auxiliary Building Plan El 585 Ft. No Rev Date
Project stage: Other
ML20265C7391987-01-15015 January 1987
Equipment Locations Containment & Auxiliary Building Plan El 565 Ft. No Rev Date
Project stage: Other
ML20265C7401987-01-15015 January 1987
Equipment Locations Containment & Auxiliary Building Plan El 545 Ft. No Rev Date
Project stage: Other
ML20265C7351987-01-15015 January 1987
Equipment Locations Containment & Auxiliary Building Plan El 603 Ft. No Rev Date
Project stage: Other
ML20265C7321987-01-15015 January 1987
Equipment Locations Containment & Auxiliary Building Plan El 623 Ft. No Rev Date
Project stage: Other
ML20265C7311987-01-15015 January 1987
Equipment Locations Containment & Auxiliary Building Plan El 643 Ft. No Rev Date
Project stage: Other
1980-12-30
[Table View] |
Text
"
TOLEDO Docket No. 50-346 l3[3]6)()Pd License No. NPF-3 ACHARO P. CAouSE Serial No. 570 Ell!"""*
(4191253-5221 December 31, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
Toledo Edison identified its schedule for complying with your staff's short term lessons learned recommendations for the Three Mile Island, Unit Two,.(IMI-2), incident in our letter of October 23, 1979 (Serial No. 546) and later revised portions of the response in our letter of November 21, 1979 (Serial No. 559). The recommendations, committed to for implementation by January 1, 1980 at the Davis-Besse Nuclear Power Station, Unit #1 are now completed to the extent previously defined.
Since submittal of our November 21, 1979 letter, we have further defined the schedules of four activities. These include:
- 1) Recommendation 2.1.3a - PORV and Safety Valve Position Indication.
The equipment delivery for installation includes cabling, cabinets and,- sensors that we currently project will be available in March of 1980. This would allow installation concurrent with the reactor coolant saturation meter, which will utilize common cabinetry, during the planned spring ou tage.
- 2) Recommendation 2.1.3b - Reactor Coolant Saturation Meter.
The current projected schedule for delivery of equipment cabling and cabinets is April 1, 1980. This would allow installation during the planned spring outage.
- 3) Recommendation 2.1.6a - Leakage ReductioncProgram.
In addition to the summary description of the leakage reduction program an initial system leakage reduction effort will be completed by January 31, 1980.
()bb/
- 4) Recommendation 2.1.6b - Design Review of Plant Shielding.
5 Any proposed modifications and their implementation schedule will be provided by January 21, 1980 instead of February 20, 1980.
THE TOLECO EDISON COMPANY EDISON PLAZA 300 MADISON AVEflUE TOLEDO. CHIO 43652 1689 182 8001040 1
Docket No. 50-346 License No. NPF-3 Serial No. 570 December 31, 1979 Page 2 of 2 It is expected that these activities or revised schedules will provide timely resolution of Toledo Edison's efforts to implement your staff's short term lessons learned recot:mendations. As always, we are avail-able to further discuss any aspect of this submittal.
Very truly yours,
((
,ma; RPC:TJM:sle cc: Mr. Dan Garner 1689 183
._
