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Results
Other: ML17328B057, ML19249A376, ML19249A382, ML19317H481, ML19340D243, ML19343B503, ML19343B506, ML19350E266, ML20003D588, ML20009C888, ML20024E960, ML20069N118, ML20076H115, ML20080G331, ML20086C757, ML20132F461, ML20151H856, ML20206M021
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MONTHYEARML19261C5191979-02-27027 February 1979 Forwards Safety Evaluation Rept for Fire Protection Program. Concludes Program,W/Scheduled Mods,Meets General Design Criterion 3 & Is Therefore Acceptable Project stage: Approval ML19261C5211979-02-27027 February 1979 Fire Protection Safety Evaluation Rept. Until Scheduled Improvements Are Made,Present Fire Protection Tech Specs Provide Sufficient Protection Against Fire Threatening Safe Shutdown Project stage: Approval ML19249A3761979-07-26026 July 1979 Amend 18 to License NPF-3,adding License Condition Re Completion of Facility Mod for Fire Protection & Modifying Tech Specs to Require Five Individuals W/Fire Protection Training on Site Project stage: Other ML19249A3781979-07-26026 July 1979 Fire Protection Safety Evaluation Supporting Amend 18 to License NPF-3 Project stage: Approval ML19249A3821979-07-26026 July 1979 Notice of Issuance & Availability of Amend 18 to License NPF-3 Project stage: Other ML19249A3721979-07-26026 July 1979 Forwards Amend 18 to License NPF-3,safety Evaluation & Notice of Issuance & Availability Project stage: Approval ML19317H4811980-05-19019 May 1980 Forwards Proposed Rule Entitled, Fire Protection Program for Nuclear Power Plants Operating Prior to 790101. Rule Adds New Section 50.48 & App R to 10CFR50 & Is Expected to Be Published in Fr by End of May Project stage: Other ML19351D6201980-10-0707 October 1980 Application for Amend to License NPF-3,providing Tech Specs for Fire Detection Sys Per License Condition 2.c(4) Project stage: Request IR 05000346/19800161980-11-18018 November 1980 IE Insp Rept 50-346/80-16 on 800609-11 & 1020-24.No Noncompliance Noted.Major Areas Inspected:Refueling Outage Maint,Plant Operations Review & Equipment Calibr Project stage: Request ML19343B5061980-11-18018 November 1980 Notice of Issuance & Availability of Amend 34 to License NPF-3 Project stage: Other ML19343B5031980-11-18018 November 1980 Amend 34 to License NPF-3,modifying Tech Specs to Include Fire Detection Instrumentation Mods Project stage: Other ML19340D2431980-11-24024 November 1980 Forwards Revised 10CFR50.48 & App R to 10CFR50 Re Five Protection Features of Nuclear Power Plants.Rules Take Effect 810217.Summary Listing of Open Items Re Fire Protection Features of Facility Encl Project stage: Other ML17328B0571980-11-24024 November 1980 Ltr to All Power Reactor Licensees W/Plants Licensed Prior to 790101.Forwards Revised Section 10CFR50.48 & App R Re Fire Protection Features in Nuclear Power Plants & List of Requirements for Resolution of Open Issues.W/O Encl Project stage: Other ML20151B3601980-12-26026 December 1980 Application for Amend of License NPF-3 Changing Tech Specs Re Fire Detection Sys,Decay Heat Removal Capabilities,Low Temp RCS Overpressure Event,Axial Power Shaping Rod Insertion Limits & Util Reorganization Project stage: Request ML20003D5881981-03-19019 March 1981 Responds to Re Submittal of Plans,Schedules & Design Descriptions of 10CFR 50,App R,Mod for Fire Protection.Forwards Design Description of Alternate Svc Water Capability Project stage: Other ML19350E2661981-06-10010 June 1981 Requests re-evaluation of Class III Fees Assessed for 810319 Proposal for Alternate Svc Water Capability.Review of Amend 18,Item B Requirements Stated No License Amend Fee Required for Response to Proposal.Class III Fee Encl Project stage: Other ML20009C8881981-07-10010 July 1981 Marked-up Revised Tech Specs 3.4.2,4.4.2,3.4.3,4.4.3, 3.8.1.2,4.8.1.2,4.8.1.1.2,4.8.1.1.2.C.2,3.1.3.6,3/4.2,3.2.1, 4.2.1,3.2.5,6.5.2.2,6.5.2.3,6.5.2.4,6.5.2.5,6.5.2.6, 3/4.7.10,3.7.10,4.7.10,Pages 3/4.7-5,B 3/4.4-19 & 3.8.1.2 Project stage: Other ML20009C8871981-07-10010 July 1981 Application for Amend of License NPF-3,revising Tech Specs for Auxiliary Feedwater Pump Turbine Speed Switches,Setpoint Index for Pressurizer Electromatic Relief & Code Safety Valves,Emergency Diesel Generator & Administrative Errors Project stage: Request ML20009C8841981-07-10010 July 1981 Forwards Application for Amend of License NPF-3,requesting Revisions to Tech Specs Project stage: Request ML20054C9511982-04-0808 April 1982 Submits List of Drawings Needed for Consideration Re Proposed Facility Mods for App R,Per 820323 Meeting Project stage: Meeting ML20053E5221982-06-0202 June 1982 Forwards Safety Evaluation of Util Requested Mods to Comply w/10CFR50 App R Sections Iii.G,Iii.J & Iii.O Re Alternate Svc Water Capability.Proposed Mods Acceptable Project stage: Approval ML20053E5241982-06-0202 June 1982 Safety Evaluation Supporting Requested Mods to 10CFR50 & 10CFR50.48 App R Project stage: Approval ML20067C1711982-11-23023 November 1982 Safety Evaluation Supporting Exemption from Certain Requirements of App R to 10CFR50 Project stage: Approval ML20069N1181982-11-23023 November 1982 Notifies That Alternate Dedicated Svc Water Sys Will Be Installed within 30 Months of NRC 820602 Acceptance Date,Per 10CFR50.48(c)(4) Project stage: Other ML20076H1151983-08-26026 August 1983 Forwards Plans & Evaluation Addressing Understanding Findings Identified by NRC Following 830725-29 Fire Protection Audit,Per 830816,18 & 22 Requests.Adequate Fire Protection Features in Place to Return to Cycle 4 Operation Project stage: Other ML20024E9601983-08-31031 August 1983 Forwards Revised Action Summary Table to Util 830826 Evaluation of NRC 830725-29 App R Audit Findings & Corrective Action Plan Project stage: Other ML20080G3311983-09-13013 September 1983 Forwards Revised Evaluation of NRC 830725-29 App R Audit Findings & Corrective Action Plan,Superseding Info Submitted w/830826 & 31 Ltrs.Findings & Plan Justify Continued Operation Project stage: Other ML20151H8561983-09-19019 September 1983 Reviews Licensee short-term & long-term Compensatory Actions on Insp Findings Re 10CFR50,App R Shutdown/Fire Protection deficiencies.Short-term Actions Acceptable Project stage: Other ML20086C7571983-11-23023 November 1983 Forwards Revised Schedule for Plan to Address Findings of NRC 10CFR50,App R Audit.Schedule Updates 830913 Commitment. Extension Needed to Incorporate Concerns of IE Info Notice 83-69, Improperly Installed Fire Dampers.. Project stage: Other ML20155C9641984-08-0606 August 1984 Summary of 840612 Meeting W/Util in Bethesda,Md Re Program to Correct Fire Protection Deficiencies in Facility Fire Protection Features & non-compliance W/Respect to Requirements of App R to 10CFR50.Related Info Encl Project stage: Meeting ML20132F4611985-09-26026 September 1985 Forwards List of Facility Change Requests Re Fire Protection Scheduled for Completion at End of Fifth Refueling Outage to Begin in Sept/Oct 1986.List Prioritized 25 Most Important to Nuclear Safety Project stage: Other ML20212P2741987-01-21021 January 1987 Responds to Stolz 861217 Request for Addl Info Re Fire Protection & Meeting to Discuss Issues.Fire Protection Program in Conformance W/App a to BTP Apcsb 9.5-1 as Accepted by 790726 Ser.Meeting Schedule to Be Established Project stage: Meeting ML20206M0211987-04-0909 April 1987 Advises That Fire Protection & Alternate Shutdown Sys Mods Required to Meet 10CFR50.48 Scheduled to Be Completed by End of Sixth Refueling Outage,Per Generic Ltr 86-10, Implementation of Fire Protection Requirements Project stage: Other 1982-11-23
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O U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No. 50-346/80-16 Docket No. 50-346 License No. NPF-3
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Licensee: Toledo Edison Company Edison Plaza, 300 Madison Avenue
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Toledo, Ohio 43652 Facility Name: Davis-Besse 1 Inspection At: Oak Harbor, Ohio Inspection Conducted: June 9-11, 1980 October 20-24, 1980 Rrto W i
Inspectors:
E. R. Swanson Nov /S, /9c o R ru) Fw M. L. Gildner p,., f,g, / <;f c>
I? FLoamwk frr-Approved By:
K. R. Baker, Chief 4 ffp Nuclear Support Section 2 Inspection Summary Inspection on June 9-11, 1980 and October 20-24, 1980 (Report No.
50-346/80-16)
Areas Inspected: Routine unannounced inspection of maintenance during refueling outage, review of plant operations, Crystal River III lessons learned and equipment calibrations. The inspection involved a total of
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74 inspector-hours onsite by two NRC inspectors including six inspector-hours onsite during off-shifts.
Results: Of the areas inspected no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted T. Murray, Station Superintendent D. Huffman, Admistrative Coordinator
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J. Greer, Quality Assurance Supervisor P. Carr, Maintenance Engineer T. Powers, Instrumentation and Control Engineer 2.
Maintenance The inspector reviewed planned maintenance to assure that administrative approvals were required for removal and return to service, hold points for quality inspections were utilized when necessary, system restoration and operational testing was required following maintenance, ignition sources and fire protection requirements were met, material certification was provided when needed, and that deficiencies noted were reported as required.
In addition to review of the controlling procedures and administrative controls the inspector reviewed the design change packages for the Containment Air Coolers (FCR 79-280 Solenoid replacement) and the installation of the Saturation Meters (FCR-0439).
3.
Review of Plant Operations Administrative Controls and check lists for returning safety related systems and components which underwent maintenance to an operating status were-reviewed. Plant Startup Procedure PP 1102.02 and Pre-Startup Checklist PP 1102.01 were found to adequately address routine system restoration and Technical Specification requirements for return to power.
It was noted that there were no provisions for integrating Special Startup Tests into the existing procedure and checklist.
4.
Crystal River III Lessons Learned The inspector inspected instrument and control system modifications pursuant to the Confirmatory Order for Davis-Besse Nuclear Power Station Unit No. 1 issued April 21, 1980. FCR 79-0410 (Provide positive indication of all three relief valves on the pressurizer)
and FCR 80-058 (PORV and spray valve closure on N.N.I. power failure)
were reviewed with no deficiencies identified. Further inspection is needed to verify proper physical installation and to review system test results, operating procedures and surveillance test revisions.
5.
Equpment Calibration The inspector reviewed selected records and procedures relating to the calibration of equipment associated with safety related functions i
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to determine if calibrations were in conformance with Technical Specification requirements and other requirements as set forth by the licensee.
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The selected records were reviewed for proper calibration frequency; limiting conditions for operations were observed; and proper reviews were conducted test results data.
The selected procedures were reviewed to determine that the technical content results in proper accuracy and time response, traceability of results to National Bureau of Standards, and settings will be in compliance with the Technical Specification.
The inspector observed the calibration of RPS Channel 3 linear Flux Channel and resetting of the Hi Flux Trip Set point to 20% as required for low power physics testing. Current procedures were utilized and adhered to.
During the inspector's review of controls for test equipment used for calibrations, the Calibration Due Date Log was examined and found to be out of date for several pieces of test equipment.
Backup controls prevent use of out of calibration test equipment for equipment calibrations. The Due Date Log is being evaluated by the licensee for possible format revision and update review.
6.
The inspectors met with the licensee representatives denoted in Paragraph 1 at the conclusion of the inspections and summarized the scope and findings of the inspection activities.
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