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Other: A840006, Forwards Three Repts Re Facility Safety Parameter Display Sys (Spds),Per Requirements of Suppl 1 to NUREG-0737. SPDS Will Be Installed During Upcoming Recirculation Piping Replacement Outage, ML20087A949, ML20087A964, ML20087A998, ML20099D468, ML20099D484, ML20155G453, ML20155G463, ML20199C843, ML20199C854, ML20212E169, NLS8400254, Forwards Schedule for Submittal of Addl Safety Parameter Display Sys Info,Per 840803 Request, NLS8500045, Forwards Addl Info Re Spds,Per 841005 Commitment.Finalized List of SPDS Parameters,Isolation Test Procedure for Fiber Optics & Description of Displays for SPDS Encl, NLS8500319, Advises That Addl SPDS Info Will Not Be Submitted by Date Specified in Re Verification & Validation Testing.Start of 1,000 H Test Scheduled for 860115.Info Will Be Submitted by 860501, NLS8600153, Forwards Results of 1,000 H Test After SPDS Implementation for Confirmatory Review, Documentation That Info Displayed on SPDS Readily Perceived & Does Not Mislead Operators.Validation Test Plans & Results Also Encl, NLS8600212, Forwards Rev C to Failure Mode & Effects Analyses & Rev 0 to Final Verification & Validation Rept for Nebraska Public Power District Plant Mgt Info Sys
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MONTHYEARML20087A9641984-03-0101 March 1984 Procedure 503-8500000-51, Verification & Validation Plan Project stage: Other ML20087A9981984-03-0101 March 1984 Procedure 503-8500000-27, Safety Parameter Display Sys Implementation Plan Project stage: Other ML20087A9491984-03-0101 March 1984 Safety Parameter Display Sys Safety Analysis Project stage: Other A840006, Forwards Three Repts Re Facility Safety Parameter Display Sys (Spds),Per Requirements of Suppl 1 to NUREG-0737. SPDS Will Be Installed During Upcoming Recirculation Piping Replacement Outage1984-03-0101 March 1984 Forwards Three Repts Re Facility Safety Parameter Display Sys (Spds),Per Requirements of Suppl 1 to NUREG-0737. SPDS Will Be Installed During Upcoming Recirculation Piping Replacement Outage Project stage: Other NLS8400254, Forwards Schedule for Submittal of Addl Safety Parameter Display Sys Info,Per 840803 Request1984-10-0505 October 1984 Forwards Schedule for Submittal of Addl Safety Parameter Display Sys Info,Per 840803 Request Project stage: Other ML20099D4681984-12-13013 December 1984 Isolation Test Procedure for Fiber Optics Project stage: Other ML20099D4841985-02-0101 February 1985 Rev 2 to Detailed Descriptions of Displays for Cooper Nuclear Station Spds Project stage: Other NLS8500045, Forwards Addl Info Re Spds,Per 841005 Commitment.Finalized List of SPDS Parameters,Isolation Test Procedure for Fiber Optics & Description of Displays for SPDS Encl1985-02-28028 February 1985 Forwards Addl Info Re Spds,Per 841005 Commitment.Finalized List of SPDS Parameters,Isolation Test Procedure for Fiber Optics & Description of Displays for SPDS Encl Project stage: Other NLS8500319, Advises That Addl SPDS Info Will Not Be Submitted by Date Specified in Re Verification & Validation Testing.Start of 1,000 H Test Scheduled for 860115.Info Will Be Submitted by 8605011985-11-15015 November 1985 Advises That Addl SPDS Info Will Not Be Submitted by Date Specified in Re Verification & Validation Testing.Start of 1,000 H Test Scheduled for 860115.Info Will Be Submitted by 860501 Project stage: Other ML20155G4631986-03-12012 March 1986 Validation/Field Installation Verification Test Rept for Plant Mgt Info Sys Project stage: Other ML20155G4531986-04-0707 April 1986 Results of 1,000 H Test After SPDS Implementation for Confirmatory Review Project stage: Other NLS8600153, Forwards Results of 1,000 H Test After SPDS Implementation for Confirmatory Review, Documentation That Info Displayed on SPDS Readily Perceived & Does Not Mislead Operators.Validation Test Plans & Results Also Encl1986-04-28028 April 1986 Forwards Results of 1,000 H Test After SPDS Implementation for Confirmatory Review, Documentation That Info Displayed on SPDS Readily Perceived & Does Not Mislead Operators.Validation Test Plans & Results Also Encl Project stage: Other ML20199C8541986-05-30030 May 1986 Final Verification & Validation Rept for Nebraska Public Power District Plant Mgt Info Sys Project stage: Other ML20199C8431986-06-12012 June 1986 Rev C to Failure Mode & Effects Analyses Project stage: Other NLS8600212, Forwards Rev C to Failure Mode & Effects Analyses & Rev 0 to Final Verification & Validation Rept for Nebraska Public Power District Plant Mgt Info Sys1986-06-13013 June 1986 Forwards Rev C to Failure Mode & Effects Analyses & Rev 0 to Final Verification & Validation Rept for Nebraska Public Power District Plant Mgt Info Sys Project stage: Other NLS8600254, Informs That SPDS Declared Operable on 860731,meeting 850829 Confirmatory Order Requirement.Sys Reliability Demonstrated by Results of 1,000 H Run Test1986-08-0101 August 1986 Informs That SPDS Declared Operable on 860731,meeting 850829 Confirmatory Order Requirement.Sys Reliability Demonstrated by Results of 1,000 H Run Test Project stage: Meeting ML20212E1691986-12-30030 December 1986 Notice of Violation from Insp on 861001-1130 Project stage: Other NLS8800365, Forwards Responses to 880422 Request for Addl Info Re Spds. W/One Oversize Drawing1988-07-21021 July 1988 Forwards Responses to 880422 Request for Addl Info Re Spds. W/One Oversize Drawing Project stage: Request 1986-03-12
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APPENDIX A' NOTICE OF VIOLATION Nebraska _Public Power District Docket:
50-298 Cooper Nuclear Station License:
DPR-46 During an NRC inspection conducted during the period October 1 through November.30, 1986, four violations of NRC requirements were identified.
The violations involved failure to have an adequate refueling procedure, failure to have adequate procedure controls, failure to have a procedure for conducting maintenance activities, and a lack of cleanliness controls.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1986), the violations are listed below:
A.
Failure to Have an Adequate Refueling Procedure Appendix B, Criterion V, of 10 CFR Part 50, and the licensee's Quality Assurance Plan require that activities affecting quality shall be prescribed by documented instructions and procedures.
These instructions and procedures shall include appropriate qualitative acceptance criteria for determining that important activities have been satisfactory accomplished.
Contrary to the above, Nuclear Performance Procedure 10.25, " Refueling,"
Revision 6, dated August 7, 1986, was inadequate, in that the procedure failed to specify the need to ensure that the refueling mast was fully retracted before moving the refueling bridge from the fuel pool to the reactor cavity.
This is a Severity Level IV violation.
(Supplement I.D)(298/8627-02)
B.
Inadequate Cleanliness Controls Appendix B, Criterion II, of 10 CFR Part 50, and the licensee's Quality l
Assurance Program establish the requirements that activities affecting quality shall be accomplished under suitably controlled conditions.
Controlled conditions include the use of appropriate equipment; suitable environmental conditions for accomplishing the activity, such as adequate cleanliness; and assurance that all prerequisites for the given activity have been satisfied.
Contrary to the above, suitable cleanliness controls were not maintained in the high pressure coolant injection (HPCI) pump room during pneumatic wire brush cleaning operations.
As a result, the area immediately adjacent to the cleaning activity, which included components ev h as the HPCI turbine and auxiliary lube oil pump and motor, were cc,aed with j
particulate material and residual aged lubricant.
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This is a Severity Level V violation.
(Supplement I.E)(2SS/8627-05) 8701050267 861230 PDR ADOCK 05000298
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2 C.
Failure to Provide Adequate Controls in a Special Test Procedure Appendix B, Criterion V, of 10 CFR Part 50, and the licensee's Quality Assurance Plan require activities affecting quality shall be prescribed by documented instructions and procedures.
These instructions and procedures shall include appropriate qualitative acceptance criteria for determining that important activities have been satisfactory accomplished.
Contrary to the above, Special Test Procedure 86-08, " Inspect 1E Floor Mounted Switchgear," dated October 18, 1986, was inadequate, in that it failed to identify the removal of an insulating device called a boot from a set of relay contacts on an under voltage relay.
The boot, when installed, would have prevented the automatic starting of emergency diesel generator No.1 upon a loss of Emergency Transformer Voltage.
This is a Severity Level IV violation.
(Supplement 11.0)(298/8627-06)
D.
Failure to Have a Procedure for Controlling Maintenance Activities CNS Technical Specifications 6.3.1 requires that station personnel shall be provided detailed written procedures to be used for operation and maintenance of system components and systems that could have an effect on nuclear safety.
Contrary to the above, maintenance was performed on the refueling bridge on Octooer 16, 1986, without a procedure while the bridge was located above the spent fuel pool, which at the time contained both spent and new fuel.
This is a Severity Level IV violation.
(Supplement I.D)(298/8627-07)
Pursuant to the provisions of 10 CFR 2.201, Nebraska Public Power District is l
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, l
including for each violation:
(1) the reason for the violations if admitted, (2) the corrective steps which have been taken and the results achieved, (3) the corrective steps which will be taken to avoid further violations, and
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(4) the date when full compliance will be achieved. Where good cause is shown,
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consideration will be given to extending the response time.
l Datedatprlington, Texas this 30t dayof{yggtht. 1986 L