Letter Sequence Other |
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Results
Other: 05000369/LER-1986-013-02, :on 860626,discovered Loose Fuel Pellets from Fuel Assembly D-03 on Reactor Core Baffle Plate Near Core Location P-3.Caused by Baffle Jetting.Assembly Removed from Core & Core Redesigned, ML20100H434, ML20100H458, ML20202B388, ML20204H649, ML20204H655, ML20205C934, ML20206M289, ML20211G106, ML20214M662
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MONTHYEARML20100H4581985-02-28028 February 1985
Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program
Project stage: Other
ML20100H4341985-04-0505 April 1985
Forwards WCAP-10786, Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program, Per App H to 10CFR50.Based on Rept,Rev to Tech Specs May Be Necessary.Nrc Will Be Advised If Rev Needed
Project stage: Other
ML20155J5671986-05-15015 May 1986
Application for Amends to Licenses NPF-9 & NPF-17,changing Tech Specs to Ensure Plant Operation Consistent W/Design & Statements in Unit 1 Cycle 4 Reload Safety Evaluation.Fee Paid
Project stage: Request
ML20195E2591986-05-23023 May 1986
Forwards Peaking Factor Limit Rept for Unit 1,Cycle 4 in Support of 841116 Application for Amends to Licenses NPF-9 & NPF-17.Conclusions in Reload Safety Evaluation Remain Valid
Project stage: Request
ML20211G1061986-06-0606 June 1986
Informs That Correct Date for Submittal of Proposed License Amends Re Cycle 4 Optimized Fuel Assembly Reload Is 860515, Not 841116 as Ref in Transmitting Peaking Factor Limit Rept
Project stage: Other
ML20202B3881986-06-30030 June 1986
Proposed Tech Specs Re Specific Criteria & Predicted Values of Safety Analyses & Evaluations Performed for Transients Sensitive to Positive Moderator Coefficient
Project stage: Other
ML20204H6551986-07-31031 July 1986
Rev 1 to Reload Safety Evaluation,Mcguire Nuclear Station, Unit 1 Cycle 4
Project stage: Other
ML20204H6491986-08-0404 August 1986
Proposed Tech Specs,Reflecting Revised Design Features to Generally Allow Use of Modified Fuel Assemblies in Core
Project stage: Other
ML20204H6241986-08-0404 August 1986
Revised Application for Amends to License NPF-9 & NPF-17, Changing Design Features Tech Spec Section to Generally Allow Use of Modified Fuel Assemblies in Core.Cycle Specific Reload SER Revised to Reflect Core Redesign
Project stage: Request
ML20205C9341986-08-0404 August 1986
Notice of Consideration of Issuance of Amends to Licenses NPF-9 & NPF-17 & Proposed NSHC Determination & Opportunity for Hearing Re Supplemental Request Concerning Optimized Fuel Assemblies
Project stage: Other
ML20206M2891986-08-12012 August 1986
Advises That Rev to Peaking Factor Limit Rept Unnecessary. End of Cycle 3 Refueling Outage Schedule Provided in 860804 Submittal Revised to Reflect Unit 1 860823 Cycle 4 Startup
Project stage: Other
ML20214M6621986-08-28028 August 1986
Notice of Violation from Insp on 860707-11
Project stage: Other
05000369/LER-1986-013-02, :on 860626,discovered Loose Fuel Pellets from Fuel Assembly D-03 on Reactor Core Baffle Plate Near Core Location P-3.Caused by Baffle Jetting.Assembly Removed from Core & Core Redesigned1986-08-28028 August 1986
- on 860626,discovered Loose Fuel Pellets from Fuel Assembly D-03 on Reactor Core Baffle Plate Near Core Location P-3.Caused by Baffle Jetting.Assembly Removed from Core & Core Redesigned
Project stage: Other
1986-06-30
[Table View] |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Docket No. 50-369 Duke Power Company License No. NPF-9 McGuire Unit 1 During the Nuclear Regulatory Commission (NRC) inspection conducted on July 7-11, 1986, a violation of NRC requirements was identified.
The violation involved inadequate control of materials entering the primary system.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1985), the violation is listed below:
10 CFR 50, Appendix B, Criterion II is implemented by the accepted quality assurance program documented in Duke Power Company Topical Report, Quality Assurance Program (Duke-1-A, Amendment 9), which in turn is implemented by Station Directive 3.11.0.
Collectively, these documents require that activities affecting quality be accomplished under suitably controlled conditions.
Controlled conditions include suitable environmental conditions such as adequate cleanness.
Contrary to the above, in July 1986 two towels were discovered beneath the reactor lower core plate.
The undetected entry of the objects into the reactor coolant system demonstrates a failure to accomplish activities affecting quality under suitably controlled conditions such as adequate cleanness.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including:
(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the correc-tive steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed by Roger D. Walker Roger D. Walker, Director Division of Reactor Projects j
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Dated at Atlanta, Georgia this @h day of August 1986
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