Letter Sequence Other |
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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
[Table View] |
Text
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UNITID STATES
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NUCLEAR REGULATORY COMMISSION
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a WASHINGTON, c. C. 20565
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THE TOLEDO EDISON COMPANY-
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a 4
AND_
THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1 I
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.18 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A. The filings by The Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated December 12, 1977, January 11, April 11, May 3, June 22, July 27, September 7 and 25, 12, 1978, January 10, February 28 and November 25, December comply with the standards and requirements of the April 12,1979, Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in confonnity with the licensees' filings, 8.
the provisions of the Act, and the rules and regulations of the Comission; There is reasonable assurance (i) that the activities authorized C.
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; The issuance of this amendment will not be inimical to the comon D.
defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part E.
51 of the Comission's regulations and cll applicable requirements have been satisfied.
847 127 790822 h
. Accordingly, Facility Operating License No. NPF-3 is hereby amende 2.
as follows:
Amend paragraph 2.C(2) to read as follows:
A.
2.C(2) Technical Scecifications The Technical Specifications contained in Appendices
, are A and B, as revised through Amendment No.The licensee hereby incorporated in the license.shall operate the facili Technical Specifications.
Add paragraph 2.C(4) as follows:
B.
2.C(4) Fire Protection The licensee may proceed with and is required to complete the modifications identified in Section 1 of the NRC's Fire Protection Safety Evaluation 26, 1979 and sup-(SE) on the facility dated JulyThese modifications shall be plements thereto.
completed as specified in Table 1 of the SE or supplements thereto.
15, 1979.*
This license amendment is effective as of August 3.
FOR THE NUCLEAR REGULATORY C0fEISSION 4./fm Y Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: July 26, 1979
- Provided no hearing is requested under 10 CFR Part 2 paragraph 2.204.
847 128~
ATTACHMENT TO LICENSE AMENDMENT NO. 18 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Remove page 6-1 of the Appendix A Technical Specifications and replace with enclosed page 6-1.
847 i29'
6.0 ADMINISTRATIVE CONTROLS 6 1 RESPONSIBILITY eration and shall delegate in writing the success i i 1.1 6.
op l ity during his absence.
6.2 ORGANIZATION _
0FFSITE The offsite e-nanization for facility management and technical
.2.1 6upport shall be as shown on Figure 6.2-1.
s FACILITY STAFF The Facility organization shall be as shown on Figure 6.2-2 and:
6.2.2 Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
a.
At least one licensed Operator shall be in the control room when b.
fuel is in the reactor, At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and c.
during recovery from reactor trips.
An individual qualified in radiation protection procedures shall d.
be on site when fuel is in the reactor.
All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator e.
Limited to Fuel Handling who has no other concurrent respon-sibilities during this operation.
A site Fire Brigade of at least 5 members shall be maintained The Fire Brigade shall not include 3
members of the minimum Shift crew necess onsita at all times #.
during a fire emergency.
s47 130
- Fire Brigade Composition may be less than the minimum requirements d
period of time not to exceed 2 hcurs in order to acc restore the Fire Brigade to within the minimum requirements.,
- This change from 3 to 5 individuals will be implemented by start up after the first refueling outage.
Amendment No. 9, 18 6-1 DAVIS-BESSE, UNIT 1
-w-
