Letter Sequence Request |
|---|
|
|
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
'
(
Omaha Public Power Distritt 1623 Harney Omaha Nebraska 68102-2247 402/536-4000 November 27, 1985 LIC-85-536 l
l Mr. A. Thadani, Project Director l
PWR - Directorate #8 Division of PWR - Licensing - B Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
References:
(1) Docket No. 50-285 (2) Application for Amendment dated March 30, 1977 (3) Letter OPPD (W. C. Jones) to NRC (R. A. Clark) dated January 26, 1983 (LIC-83-015)
(4) Letter OPPD (W. C. Jones) to NRC (R. A. Clark) dated September 2, 1983 (LIC-83-221)
Dear Mr. Thadani:
10 CFR 50 Appendix J Amendment Application In Reference (3), the Omaha Public Power District submitted changes to Reference (2), concerning 10CFR50 Appendix J. In Reference (3), OPPD provided justification for additional Technical Specification changes, including a change of the allowable containment design base accident leak rate from 0.1% to 0.2% by weight per day.
Since that time, it has been determined that the results of the Fort Calhoun Control Room Habitability study will not support an allowable contaiment leak rate of 0.2% by weight.
Consequently, OPPD hereby resubmits Section 3.5, to maintain the maximum allowable containment leak rate at 0.1% by weight per day.
i Additionally, OPPD submitted Reference (4), which contained changes to Section 3.2, Equipment and Sampling Tests. These changes were necessi-tated by the requested chpnge to the allowable containment leak rate.
Since we are withdrawing 'Q1e requested change to the containment leak rate, we also wish to wit h w the Reference (4) request.
Su28suBihajhs P
1
\\
40
\\
J5 5124 Employmen h ual opporturuty
v-Mr. A. Thadani Page 2 LIC-85-536 Accordingly, forty (40) copies of the revised Section 3.5 are provided
-here as amendment to Reference (2).
If you should have any questions, please do not hesitate to call.
Sincerely,
$ //h R. L. Andrews Division Manager Nuclear Production
-RLA/AND/me cc:
LeBoeuf, Lamb, Leiby E MacRae 1333 New Hampshire Ave., N.W.
Washington, D.C. 20036 Mr.- E. G. Tourigny, NRC Project Manager Mr. P. H. Harrell, NRC Senior Resident Inspector
.
