Letter Sequence Other |
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Results
Other: ML13333B918, ML17328B057, ML19256A614, ML19256A618, ML19319D898, ML19319D903, ML19340B388, ML19343C515, ML20010E308, ML20038A915, ML20039D540, ML20040C821, ML20041A980, ML20126F962, ML20147H137, ML20263M630
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MONTHYEARML19319D8981978-02-28028 February 1978 Amend 19 to License DPR-54,adding License Conditions to Completion of Fire Protection Mods Project stage: Other ML19319D9031978-02-28028 February 1978 Notice of Issuance & Availability of Amend 19 to License DPR-54 Project stage: Other ML19319D9021978-02-28028 February 1978 Safety Evaluation for Fire Protection Sys Supporting Amend 19 to License DPR-54 Project stage: Approval ML19319D8961978-02-28028 February 1978 Forwards Amend 19 to License DPR-54,safety Evaluation & Notice of Issuance & Availability.Requests Addl Info by 780301 Project stage: Approval ML19309B0561978-08-28028 August 1978 Submits Proposed Mod Design Details Re Fire Protection in Response to NRC 780228 Request for Addl Info Per Fire Protection Safety Evaluation.Revision of OL Amend 19 Requested to Delete Ref to Fire Area 50 Project stage: Request ML19256A6141978-12-14014 December 1978 Amend 25 to License DPR-54 Revising Completion Date for Mods Intended to Improve Level of Fire Protection at Facility Project stage: Other ML19256A6151978-12-14014 December 1978 Safety Evaluation Supporting Amend 25 to License DPR-54 Project stage: Approval ML19256A6181978-12-14014 December 1978 Notice of Issuance & Availability of Amend 25 to License DPR-54 Project stage: Other ML20147H1371978-12-14014 December 1978 Approves Supplemental Info Re Section 3 of Fire Protection Ser,Including Installation of Thermal Insulation on Channel A,C & D Conduits,Mod of Lube Oil Pump Control Circuits Associated W/Hpis & Procedures for Diesel Generators Project stage: Other ML19256A6111978-12-14014 December 1978 Forwards Amend 25 to License DPR-54 in Response to 781201 Application.Revises Completion Date for Mods Intended to Improve Fire Protection at Facility.Also Forwards Suppl 1 to Fire Protection Safety Evaluation Supporting Amend Project stage: Approval ML19261C5191979-02-27027 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 ML19257D6631980-01-17017 January 1980 Advises of Acceptability of Designs Proposed for Implementing Mods Re NRC Fire Protection Safety Evaluation Sections 3.1.30(2) & 3.1.31(2).Makeup Pump Room & Penetration Valve Area Altered to Assure Safe Shutdown 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 ML19340B3881980-09-25025 September 1980 Forwards Questions Re Proposed Amend 68 to Tech Specs 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 ML19343B5031980-11-18018 November 1980 Amend 34 to License NPF-3,modifying Tech Specs to Include Fire Detection Instrumentation Mods Project stage: Other ML19343B5061980-11-18018 November 1980 Notice of Issuance & Availability of Amend 34 to License NPF-3 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 ML19343C5151981-03-17017 March 1981 Discusses Util Plans for Implementing App R Requirements to 10CFR50 Re Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101,in Response to NRC 810220 Request.Reassessment of Each Fire Area Encl Project stage: Other ML20126F9621981-03-17017 March 1981 Ceramic Fiber Blanket Wrap for Fire Protection of Cable Trays & Conduits Project stage: Other 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 ML20009C8841981-07-10010 July 1981 Forwards Application for Amend of License NPF-3,requesting Revisions to Tech Specs Project stage: Request 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 ML20010E3051981-08-20020 August 1981 Forwards Amend 35 to License DPR-54,safety Evaluation & Notice of Issuance.Amend Revises Tech Specs to Incorporate Newly Installed Fire Protection Sys Project stage: Approval ML20010E3111981-08-20020 August 1981 Notice of Issuance of Amend 35 to License DPR-54 Project stage: Approval ML20010E3081981-08-20020 August 1981 Amend 35 to License DPR-54 Revising Tech Specs to Incorporate Newly Installed Fire Protection Sys Project stage: Other ML20010E3091981-08-20020 August 1981 Safety Evaluation Supporting Amend 35 to License DPR-54 Project stage: Approval ML20038A9151981-11-19019 November 1981 Forwards Sketches of Raceway Layout in Fire Area 47 of Facility,In Response to Gage-Babcock Associates,Inc Request. Trays M39A1,M39AG1 & M39AD8 Have Been Insulated W/Kaowool Blankets.Table Re Function of Raceway Cables Encl Project stage: Other ML20039D5401981-12-14014 December 1981 Advises of Postponement Until 820122,for Installation of Control Room Emergency Lights Required by 10CFR50.48. Installation of Lights Requiring Outage for Placement Will Begin Sept 1982.Delays Due to Late Deliveries Project stage: Other ML20040C8211982-01-0707 January 1982 Special Rept:Due to TMI-related Mods,Several Fire Barrier Penetrations Have Been non-functional for Periods Greater than 7 Days Project stage: Other ML20040E2041982-01-12012 January 1982 Forwards Safety Evaluation of Westinghouse Basic Safety Rept.Transient Analysis for Startup of Inactive Reactor Coolant Pump,Excess Load & Loss of Normal Feedwater Acceptable Project stage: Approval ML20041A9801982-02-12012 February 1982 Advises That NRC Will Conduct Fire Protection Review on 820208 to Evaluate Util 810317 Request for Exemptions from Section III.G.2 & Iii.J of App R to 10CFR50.Social Security Info Withheld Per Privacy Act Project stage: Other 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 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 ML20067C1711982-11-23023 November 1982 Safety Evaluation Supporting Exemption from Certain Requirements of App R to 10CFR50 Project stage: Approval ML20263M6301983-03-0909 March 1983 Tray Lay-out Fire Area 34. No Drawing Date Project stage: Other ML13333B9181983-08-0404 August 1983 Advises That Only Rancho Seco & San Onofre 1 in Region V Remain to Be Inspected Per 10CFR50,App R,Section Ii.G Re Fire Protection.Rancho Seco to Be Inspected Between Mar & Sept 1984.San Onofre 1 to Be Inspected in Late FY85 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 1981-12-14
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Text
~'JI>>'ITL0 sTA.T f.s MUCLEAI~K"G ULAT0 I>> 7 CO>Vib/IISSIOI>>I
'I'" SHINGTON, o C:s05&b November 24, 1980 Docket NG.
50-31 5/316 Plant Name:
D.
C. Cook, Unit Nos.
1 and 2
'I TO ALL POWER RE'ACTOR LICENSEES WITH PLANTS LICENSED PRIOR. TO JANUARY 1, 1979 The CoImission published on November 19, 1980 (45 FR 76602),
a revised Section 10 CFR 50.48 and a
new Appendi x R to 10 CFR 50 regarding fire protection features of nuclear power pla'nts.
The. revised Section 50.48 and Appendix R will become effective February 17,
- 1981, which is 90 days after publication.
A>>copy of the Federal Receister Notice is enclosed (Enclosure 1).
The provisions of 'Appendix R that are applicable to the fire protection features of your facility'an be divided into two categories.
The first category consists of those provisions of the Appendix that are required to be backfit 'in their entirety by the new rule, regardless of whether or not alternatives to the specific requirements of these Sections have been previously approved by the NRC staff.
These requirements are set forth in Sections III.G, Fire Protection of Safe Shutdown Capability; III-J; Emergency Lighting; and III-O, Oil Collection Systems for Reactor CooTant Pimp.
The fire protection, features of your facility must satisfy the specific require'ments of these three Sections by the dates established by Paragraph 50.48(c),
unless an exemption from the Appendix.R requirements is approved by the Commission'ou should note the provisions for tolling the time'for completing the modifications required by these three Sections of Appendix R set forth in Paragraph 50.48(c)(6).
The second category of Appendix R provisions applicable to the fire protection features of your facility'.consists of requireInonts concerning the "open" items of previous NRC staff fire protection reviews of your facility.
An open iten is defined as a fire protection feature that has not been previously approved by the NRC staff as satisfying the provisions of Appendix A to Branch Technical Position BTP'PCSB 9.5-1, as reflected in a staff fire protect'ion safety evaluation report.
The fire protection features of your facility that are in this category must satisfy the'specific requirements of Appendix R by the dates. established by Paragraph 50.48(c),
unless an exemp-tion from the Appendix R requirements on those features is approved by the.
Conmi ssion.
Enclosure 2 is a summary listing of. the open items concerning the fire protec'tion features of your facility based on a review of our records.
Also included is our position on the specific requirements that IIUst be satisfied in order to resolve these open items.
If you have any questions or disagree-men's with this enclosure, please advise us within 30 days af your receipt of this letter.
n(PO
. cgP
g
~
'Ritn regard to the fire-protection modifications that have been previously approved by the NRC staff, Paragraph 50.48(d) specifies a.new schedule for their completion.
This paragraph, when it becomes effective, will supersede the currently effective section of the regulations that temporarily suspends corpletion dates for previously approved fire protection modifications that are given.in facility license conditions (45 FR 71569, October 29, 1980).
The Cormiss'ion expects that all such modifications will be completed in accordance with this new schedule, unless an extension has been requested and granted by the Director of the Office of Nuclear Reactor Regulation
[see Paragraph 50-48(d)3, or an exemption has been requested and granted by the Commission pursuant. to Section 50.12 of the Comnission's regulations.
If you have previously requested extensions of 'dates for completion of modifications that are req'uired by license conditions for your facility which were not approved, and you have determined that these extensions are still necessary and justifiable, it will be necessary for you t'o reapply for any such. extensions in accordance with the provisions of Paragraph
,50.48(d).
I
.A11 requests for Commission action resulting from'this rule are subject to the schedule of fees specified in 10 CFR 170.21.:If you have any questions concerning the subject matters of this letter, please contact the NRC Project Pianager for your facility.
Si ncerely, ll C~"'~<'~
.'arrell G. Eisenhut, Director J,
Division of Licensing Office of Nuclear Reactor Regulation
Enclosures:
Notice - Fire Protection Rul'e 2.
Summary of Staff Require-
'ents to Resolve Open' tems cc w/enclosures:
See next pag'e
0 Enclosure 2
SUMMARY
OF STAFF RE(UIREHENTS-TO RESOLVE OPEN ITEMS D.
C.
- COOK, UNITS 1
A 2 There are no open items for this facility.