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| {{Adams | | {{Adams |
| | number = ML20148D963 | | | number = ML20197B824 |
| | issue date = 09/12/1978 | | | issue date = 10/25/1978 |
| | title = IE Inspec Rept#50-298/78-15 on 780828-30 During Which 1 Item of Noncompliance Was Noted:Failure to Maintain 2 Fire Doors in an Operable Status as Req by Natl Fire Code | | | title = Ack Receipt of 781003 Ltr Informing NRC of Steps Taken to Correct Deviations Noted in Inspec Rept#50-298/78-15 |
| | author name = Johnson E, Madsen G, Verduzco G | | | author name = Madsen G |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Pilant J |
| | addressee affiliation = | | | addressee affiliation = NEBRASKA PUBLIC POWER DISTRICT |
| | docket = 05000298 | | | docket = 05000298 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-298-78-15, NUDOCS 7811060055 | | | document report number = NUDOCS 7811080106 |
| | package number = ML20148D944 | | | package number = ML20197B829 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 6 | | | page count = 1 |
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| {{#Wiki_filter:- ___ ___ ___. | | {{#Wiki_filter:. . _ . . _ _ |
| | gR $Ec ue UNITED STAT ES |
| | [ 'o NUCLEAR REGULATORY COMMISSnON |
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| | REciON iv 611 RYAN PLA"'A DRIVE, SUITE 1000 |
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| | G ,MA |
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| | o [ ARLINGTON, TEXAS 76011 |
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| | ***** October 25, 1978 In Reply Refer To: |
| | g Docket No. 50-298/78-15 Nebraska Public Power District ATTN: Mr. J. M. Pilant, Director Licensing and Quality Assurance P. O. Box 499 Columbus, Nebraska 68601 Gentlemen: |
| | Thank you for your letter of October 3,1978 in response to our letter and Notice of Deviation aated September 12, 1978. We have no further questions at this time and we will review the actions you have taken to satisfy the NFPA Code requirements during a future inspectio |
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| | Sincerely, f"7?/x.4 v-- |
| U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENF0FCEMENT
| | G. L. Madsen, Chief, Reactor Operaticns and Nuclear Support Branch cc: |
| | | L. C. Lessor, Superintendent Cooper Nuclear Station P. O. Box 98 Brownville, Nebraska 68321 781108 o/ 0 C, |
| ==REGION IV==
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| Report No. 50-298/78-15 Docket No. 50-298 License No. DPR-46 Licensee: Nebraska Public Power District i
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| P. O. Box 499 Columbus, NeSraska 68601 Facility Name: Cooper Nuclear Station ,
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| Inspection At: Cooper Nuclear Station, Nemaha County, Nebraska Inspection Condt . _ ,. : August 28-30, 1978 I Principal Inspector: A 9Itt f,8 E. H. Johrson, Reactor Inspector Date
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| "T.N.de.I% 'l/o.l,a Ffo G. H. Verduzco, Reactor Inspector (Training) Date Approved By: 7[v& 8,. cv 9/a/W ;
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| 'G. L. Madsen, Chief, Reactor Operations and Date
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| Nuclear Support Branch l Insoection Summary Inspection on fugust _28-30.1978 (Report No. 50-298/78-15) | |
| Areas Inspected Routine, Unannounced inspection of plant operation 3; and safety reiltWmaintenance activities. The inspection involved twenty 'five (25)
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| inspector-hours on-site by one inspecto Results: 0' the two areas inspected no items of noncompliance or deviations were noted in one area. One deviation (failure to maintain a fire door in an operable ste:us as required by National Fire Code - Details, paragraph 2) was noted in one area.
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| 'CETAILS Persons Contacted P. Borer, Technical Assistant to the Station Superintendent B. Brungardt, Shift Supervisor R. Creason, Shift Supervisor
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| *L. Lessor, Station Superintendent R. Peterson, Reactor Engineer P. Thomason. Assistant to the Station Superintendent
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| M. Williams, Operations Supervisor V. Wolstenholm, Quality Assurance Specialist
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| *Present at the exit interive In addition to the above technical and supervisory personnel, the inspector held discussions with various maintenance, operations, technical support and administrative members of the plant staf . Plant Status Curing the period of this inspection, the plant was conductne; > P,ine power operations at approximately 95% powe . Review of Plant Operations The inspector reviewed the below listed plant logs and records, tid discussions with shift personnel, observed control room and plant process instrumentation, toured accessible areas of the plant and observed routine operations, including routine radiological controls to determine that no abnormal conditions were in existence and that oper'ations were being ccnducted in accordance with license conditions and other NRC requirement Night Order Book, May 23, 1978 through August 28, 1978 Shif t Supervisor's Log, May 23, 1978 through August 28, 1978 Control Room Operator's Log, July 24, 1978 through August 5, 1978 Jumper Log - all outstanding entries s Clearance t.og - all outstanding clearances Ccntrol Room Log Sheets, July 11, 1978 through July 31, 1978 Auxiliary Patrol Log Sheets, July 11, 1978 through July 31, 1978 Special Instruction Log and Special Order Log - all outstanding entries Nonconformance Reports, May 14, 1978 through August 20, 1978
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| en a-On August 28, 1978, following the end of normal working hours, tF~
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| inspector conducted a .our of accessible areas of the station. It was noted that one fire door in tne reactor building 903 foot level leading to the southwest quadrant was blocked open by a water hos The inspector noted that the hose was connected to an instrument tap at one end but disconnected at the other end. No work was in progress in the vicinity of the hose, nor was a watchstander present at the fire doo The National Fire Code NFPA 80-1977, " Fire Doors and Windows," Section 14 .12, requires m pect that doors shall be operable at all times and they shall be kept losed and latched or arranged for automatic closin Cemrary to thn Code requirement, the blocking open of the southwest qui.drant reactor building fire door rendered this fire door inoperabl This constitutes e deviation from an industry approved cod No other items of noncompliance or deviations were noted in this are During the tour of the facility, the following minor discrepancies were noted and brought to the attention of the licensee for review and correction. The air start piping for number 1 diesel generator was noted to be vibrating while the air start flasks were rechargin Although this vibration was not excessive, it might be indicative of a loose piping hanger or support. The inspector noted that the grout sealer in one pipe chase in the vicinity of the CRD pressure control station had spalled, indicrlive of deterioration of the grout or possible piping vibration in this area. These items were discussed with the Station Superintendent during the exit interview who indicated that they would be reviewed and appropriate corrective action initiate . Safety Related Maintenance Activities The objective of this inspection effort was to determine that maintenance activities on safety related equipment were scheduled and controlled in the manner required by the licensee's Quality Assurance Program. This effort also verified that maintenance activities were properly performed and inspected and that Technical Specification Limiting Conditions for Operation were met while the equipment was out of servic The inspector reviewed the below listed maintenance activities:
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| 78-6-177 Source Range D Reading Erratic l 78-6-135 Reactor Recirculation Pump Seal Pressure Instrument )
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| 78-4-89 Drywell to Torus Vacuum Breakers I
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| 4-MWR # Subject 78-4-219 Control Rod Drive 30-35 - Align and Renew Gaskets and 0-Rings 78-4-173 HPCI-M0-15 Seal Ring Leak 78-4-205 Overhaul Control Rod Drive #1620 78-7-11 250 VDC Battery Charger Fails to Charge 78-169 Instrument Sensing Line Plugged 78-8-75 Diesel Generator #2A Air Receiver Relief Valve Within the area of this inspection, no iters of noncompliance or deviations were noted; hovver, the following additional findi.ngs were mad For six of the nine maintenance activities reviewed, the inspector noted that block 4 of the Malfunction / Work Request fonns (MWR) a quality control inspection was required. However, the type of inspection specified was indicated to be " Job Completion" or " Review Completion." The inspector was unable to determine what constituted this type of QC inspectio The licensee had no quality control procedures which specify what is to constitute a job completion QC inspection. Section 4.1.1 of the licensee's Quality Assurance Manual describes Quality Control Inspections and requires that safety related niaintenance shall include appropriate quality control checkpoints, were applicable. Quality Assurance Manual states,
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| "The QC checkpoint shall identify specific work which is to be subjected to inspection or verification and shall provide, in detail, the elements of work to be inspected which include: . . 2. Type of Inspection or Observation . . . ."
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| During inspection 78-13, the inspector reviewed the licensee's quality control activities for safety related maintenance (Reference IE Inspection Report 50-298/78-13, Details, paragraph 4) and noted that the licensee had failed to record the type of observations and the results of quality control inspections for several safety related maintenance activitie This item was identified as an item of noncompliance. In the corrective action for this item of noncompliance, it will be necessary for the licensee to establish definitive requirements for quality control inspection of maintenance activities. This corrective action will adequately resolve the questions raised above regarding the " type of inspection or observation." This item is designated as an unresolved item pending completion of licensee's corrective action on the item of noncompliance described in Inspection Report 78-13 (Unresolved Iten
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| ! 7815-1).
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| In reviewing the overhaul of control rod drive #1620 (MWR 78-4-205)
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| the inspector noted that upon disassembly of the drive, the licensee determined that a sei;al number was not present on the rod and tub .
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| . Maintenance on this drive was conducted in accordance with Maintenance l Procedure 7.2.39, " Control Rod Drive Inspection." Attachment B to '
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| this procedure governs the reassembly of the drive and provides check- '
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| points and signoff block:; for recording specific data regarding the drive. Step 6A of attc:cirent B to the maintenance procedure requires a dimensional check of the rod and tube be performed unless: The serial number on the coupling rod is identical with the serial number on the CRD flange; i If no CRD parts have becn replaud, other than seals, bushings and 0-Rings; and If no difficulty has been reported in uncoupling the CRD during service in the reacto l The inspector noted that these dimensions were not verified for the rod and tube in contral drive #1620 when the serial number on the :
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| coupling rod could not be verified. The inspector discussed this item with the licensee representative who indicated that the leak test of this drive had not yet been conducted and that it was normal practice to perform the dimensional checks on the rod and tube at the time the ,
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| leak test is performed. This item will remain unresolved pending completion of the leak test and dimensional checks on this rod (Unresolved Item 7815-2).
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| In reviewing MWR #78-4-173, covering the repair of a seal ring leak on valve HPCI-M0-15, the inspector noted that the repair was accomplished by tightening down the cap screws on the seal ring. The inspector reviewed the instruction manual and manufacturer's drawing for this valve and determined that the allowable torque for the seal ring retainer cap screws was not specified. The inspector discussed this !
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| with a licensee representative and expressed his concern that this apparent deficiency in the manufacturer's instruction manual had not been identified during the performance of maintenance on this valv !
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| , The adequacy of the licensee S maintenance procedures and the l manufacturer's instruction manuals will receive continued followup during future inspection . In-Office Review of Licensee Event Reports Licensee event reports are issued in accordance with the requirements of Technical Specification 6.7.2.A and 6.7.2.B to report certain events to the NRC. When received at the regional office these reports are reviewed for their safety significance and completeness by the inspecto Certain reports are selected for a detailed review at the site. The i status of these reports is indicated in the report for the inspection '
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| -6-The below listed reoorts have been reviewed by the inspector in-offic Based on the 100 percent review by the inspector of all licensee internal nonconformance reports, discussions with licensee personnel during the course of inspections, and periodic review of station logs, these reports were closed with no further on-site followu LER # Subject 78-8 HPCI Isolation on Hi Indicated Steam Flow From Air in Sensing Line 78-21 Crud Buildup in Excess From Check Valve
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| *78-23 Recirculation Riser /CS Piping Indicati1ns
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| +78-27 REC System Weld Leak Unresolved Items Unresolved Items are matters about which more information is required to ascertain whether they are acceptable items, items of noncom,nliance or deviations. The following unresolved items were identified during this inspectio Type of Quality Control Inspection Performed (paragraph 3)
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| 7815-2 - Dimeiiional Check of Uncoupling Rod on CRD #1620 (paragraph 3) Exit Interview The inspector met with the Station Superintendent at the conclusion of ,
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| the inspection. The scope of the inspection and the findings above
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| . ore discussed. The Station Superintendent acknowledged the findings relative to the deviation detailed in paragraph 2 above, and indicated the item would be reviewed and correcte *Followed up on in IE Report 50-298/78-06, Details, paragraphs 7 and +Followed up on in IE Report 50-298/78-10, Details, paragraph 3.
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