Letter Sequence Request |
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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
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Omaha Public Power District 1623 HARNEY E O M AH A. NEARASKA 68102 a TELEPHONE S36 4000 AREA CODE 402 January 26, 1983 LIC-83-015 Mr. Robert A. Clark, Chief U. S. Nucleat Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Brunch No. 3 Washington, D.C.
20555
Reference:
Docket No. 50-285
Dear Mr. Clark:
Fort Calhoun Station Containment Leakage Tipting Program The Commission's letter dated July 23, 1982 transmitted a Safety Evalu-ation Report (SER) regarding the District's proposed Technical Speci-fication changes to incorporate the subject Appendix J requirements.
This SER identified three open items that were subsequently addressed in
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the District's letters dated September 3 and November 5,1982. The District stated in the November 5, 1982 letter, in response to SER open item #3, that our previous Appendix J amendment application (i.e.,
March 30, 1977) would be revised to incorporate Type C testing of penetration M-44.
Accordingly, forty (40) copies of a revised amendment application which incorporate this change, as well as several other changes, are attached.
All of the cht.nges to our March 30, 1977 appli-cation are identified in the discussion section to the attached amend-ment application. The more significant changes are detailed below:
1)
The maximum allowable leakage rate (La) will be calcult.ted using 0.2% by weight of the containment atmosphere per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 60 psig, instead of the previous 0.1% value. This is consistent with the allowable leakage rate utilized in the District's original Final Safety Analysis Report for the maximum hypothetical accident at the Fort Calhoun Station.
Further justification is provided in the discussion section of the attached application.
2)
Reduced pressure testing of the personnel access lock (PAL) doors will be at a test pressure of 5 psig, with an acceptance criterion of less than or equal to 0.01 La, as agreed upon per a telephone conference call between the District and Commission on November 24, 1982.
8302100296 830126 gh PDR ADOCK 05000285 P
PDR
e.
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Mr. Robert A. Clark LIC-83-015 Page Two Additionally, the District is requesting an exemption from the Appendix J requirement applicable to the PAL that requires testing at Pa_(if the PAL has been opened) prior to reaching a containment integrity required condition when coming out of a cold or refueling shutdown operating mode. The District proposes to leak test the PAL door seals at 5 psig prior to achieving the containment inte-grity required condition and within two weeks test the entire PAL assembly at Pa (60 psig). The District's justification for this exemption is provided in the attached.
Communications with the Commission's staff have indicated that this approach would be acceptable.
3)
Present Technical Specification (TS) Section 3.5(6) has been moved to a new TS section, Section 3.16.
TS Sections 3.5(8), 3.5(9), and 3.5(10) have.been removed from the TS because these tests were only applicable during the initial years of plant operation.
4)
Penetration M-44 has been added to the Type C testing list.
Sincerely, W. C. Jones Divis.on Manager Production Operations WCJ/TLP:jmm I
Attachment cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036 Mr. E. G. Tourigny, NRC Project Manager l.
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