Letter Sequence Approval |
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MONTHYEARIR 05000285/19800031980-04-0404 April 1980
IE Insp Rept 50-285/80-03 on 800211-14,25-28 & 0310-14. Noncompliance Noted:Failure to Use Correct Maint Procedures & Improper Certification of Respirator Qualification. Employee Wore Contact Lenses While Wearing Face Respirator
Project stage: Request
ML19323F2091980-05-15015 May 1980
Forwards Addl Info Re Containment Leakage Testing,Per NRC 800404 Request.Info Supports Application to Amend Tech Specs to Authorize Exemption from App J Requirements
Project stage: Request
ML20062B7271982-07-23023 July 1982
Forwards Safety Evaluation Identifying Three Open Items Re App J Containment Leak Testing Review.Nrc Review Put on Hold Pending Receipt of Licensee Info.Response Due in 30 Days. Supplemental SER Will Be Issued Upon Review Completion
Project stage: Approval
ML20062B7301982-07-23023 July 1982
Safety Evaluation Re App J Review.Three Open Items Identified
Project stage: Approval
ML20064N4571982-09-0303 September 1982
Responds to Open Items Identified in NRC 820723 Safety Evaluation Re Containment Leakage Testing Program.Resolution of Areas of Containment Personnel Access Door Seal & Isolation Valve Testing to Be Provided by 821101
Project stage: Other
ML20066B9531982-11-0505 November 1982
Forwards Electrical Equipment Qualification Manual Per IE Bulletin 79-01B, Environ Qualification of Safety-Related Electrical Equipment
Project stage: Request
ML20066E5771982-11-0505 November 1982
Forwards Addl Info Re Containment Leakage Testing Program, in Response to Open Items Identified in NRC . Penetration M-44 Will Be Tested Per 10CFR50 App J.Util Amend Application Will Be Revised
Project stage: Other
ML20070U2791983-01-26026 January 1983
Application to Amend OL Revising App J Tech Specs to Incorporate Type C Testing of Penetration M-44 & Calculate Max Allowable Leakage Rate Using 0.2% by Weight of Containment Atmosphere Per 24 H at 60 Psig
Project stage: Request
ML20070U2931983-01-26026 January 1983
Proposed Tech Spec Rev Incorporating Type C Testing of Penetration M-44 & Calculating Max Allowable Leakage Rate Using 0.2% by Weight of Containment Atmosphere Per 24 H at 60 Psig
Project stage: Other
ML20137D8141985-08-0101 August 1985
Notice of Environ Assessment & Finding of No Significant Impact Re Util 830126 Request for Exemptions from Section III of 10CFR50,App J
Project stage: Other
ML20137D8001985-08-0101 August 1985
Forwards Notice of Environ Assessment & Finding of No Significant Impact Re 830126 Request for Exemption from 10CFR50,App J
Project stage: Approval
ML20137V9551985-11-27027 November 1985
Withdraws 830126 & 0902 Applications for Amends to License DPR-40,changing Allowable Containment DBA Leak Rate to 0.2% by Weight Per Day.Tech Spec Section 3.5 Resubmitted,Per 770330 Application for Amend
Project stage: Request
ML20137V9881985-11-27027 November 1985
Tech Spec Section 3.5, Containment Test, Maintaining Max Allowable Containment Leak Rate at 0.2% by Weight Per Day
Project stage: Other
ML20137H5361986-01-10010 January 1986
Forwards Exemption from Certain Requirements of App J to 10CFR50 & SER Re Primary Reactor Containment Leakage Testing for water-cooled Power Reactors.Review of Proposed Tech Spec Changes Continuing
Project stage: Approval
ML20137H5531986-01-10010 January 1986
Exemption from Requirements of 10CFR50,App J Re Primary Reactor Containment Leakage Testing for water-cooled Power Reactors
Project stage: Approval
ML20151Y6671986-02-0303 February 1986
Forwards Amend 95 to License DPR-40 & Safety Evaluation. Amend Revises Surveillance Tech Specs to Ensure That Reactor Containment Bldg Leak Rate Testing Performed Per 10CFR50,App J
Project stage: Approval
ML20151Y6781986-02-0303 February 1986
Amend 95 to License DPR-40,revising Surveillance Tech Specs to Ensure That Reactor Containment Bldg Leak Rate Testing Performed Per 10CFR50,App J
Project stage: Other
ML20151Y6941986-02-0303 February 1986
Safety Evaluation Supporting Amend 95 to License DPR-40
Project stage: Approval
ML20211B1351986-06-0303 June 1986
Safety Evaluation Supporting Amend 97 to License DPR-40
Project stage: Approval
ML20211B1231986-06-0303 June 1986
Amend 97 to License DPR-40,transferring Recirculation Heat Removal Sys Surveillance Requirements from Containment Test Part of Tech Specs to New Tech Spec Section
Project stage: Other
ML20211B0951986-06-0303 June 1986
Forwards Amend 97 to License DPR-40 & Safety Evaluation. Amend Transfers Recirculation Heat Removal Sys Surveillance Requirements from Containment Test Part of Tech Specs to New Tech Spec Section
Project stage: Approval
1983-01-26
[Table View] |
Text
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b OIb February 3, 1986 Docket No. 50-285 DISTRIBUTION:
Docket File JPartlow NRC & L PDRs TBarnhart +4 WJones WRegan PD#8 Rh ACRS+10 Mr. R. L. Andrews FJMiraglia OPA Division Manager, Nuclear Production PMKreutzer LFMB Omaha Public Power District EGTourigny Gray File 1623 Harney Street OELD Omaha, Nebraska 68102 LHarmon EJordan
Dear Mr. Andrews:
BGrimes The Comission has issued the enclosed Amendment No. 95 to Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1.
This amendment consists of chances to the Technical Specifications in partial response to your application dated March 30, 1977, as supplemented by letters dated May 15, 1980, September 3, 1982, November 5, 1982, January 26, 1983 and November 27, 1985.
The amendment revises the surveillance technical specifications to ensure that the reactor containment building leak rate testing (Types A, B, and C) is performed in accordance with and as specified by 10 CFR Part 50, Appendix J.
" Primary Containment Leakage Testing for Water-Cooled Power Reactors."
It should be noted that we made one change to your proposed technical specifications.
The change was discussed with and agreed to by your staff. The change keeps in-place the surveillance requirements for the Containment air purge isolation valves.
It is our understanding that your omitting the current requirements was an oversight.
As you know, we acted on your two exemption requests by letter dated January 10, 1986. The enclosed technical specifications reflect our disposition of that matter.
Our review of your proposed technical specification changes dealing with (1) moving the recirculation heat removal system surveillance requirements to a separate part of the technical specifications, and (2) deletion of surveillance requirements in effect during early plant life, is continuing.
These changes will be the subject of a separate evaluation.
A copy of the Safety Evaluation is also enclosed.
The notice of issuance will be included in the Cormission's next regular bi-weekly Federal Register notice.
Sincerely, g 82 G gg y $$ fd y f37 P'
E. G. Tourigny, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B
Enclosures:
1.
Amendment No. 95 to DPR-40 2.
Safety Evaluation cc w/ enclosure:
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Mr. R. L. Andrews Fort Calhoun Station Omaha Public Power District Unit No. I cc:
Harry H. Voigt 'Esq.
LeBoeuf Lamb. Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D.C.
20036 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68023 MetropolitanblanningAgency ATTN: Dagnia Prieditis 7000 West Center Road
' Omaha, Nebraska 68107 Mr. Phillip Harrell, Resident Inspector
~
U.S. Nuclear Regulatory Commission P. O. Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operatins C-E Power Systems 7910 Woodmont Avenue Bethesda, Maryland 20814 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas. 76011 i
