IR 05000298/1987024

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Insp Rept 50-298/87-24 on 870901-1010.No Violations or Deviations Noted.Major Areas Inspected:Actions on Previous Insp Findings,Ie Bulletins,Ie Info Notices,Allegations,Esf Walkdown,Secutity,Spent Fuel Shipments & Operational Safety
ML20236K797
Person / Time
Site: Cooper Entergy icon.png
Issue date: 11/02/1987
From: Conway J, Jaudon J, Mullikin R, Plettner E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20236K769 List:
References
50-298-87-24, IEB-87-001, IEB-87-1, IEIN-86-106, NUDOCS 8711090361
Download: ML20236K797 (12)


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APPENDIX  ! U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-298/87-24 License: DPR-4C Docket: 50-298 Licensee: . Nebraska Public Power District (NPPD) P. O. Box 499 Columbus, NE 68601 i

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Facility Name: Cooper Nuclear Station (CNS)' Inspectinn At: Cooper Nuclea r Station, tiemaha County, Nebraska

Inspection Conducted: September 1-October 10, 1987 Inspectors: I.4, Ms /O - / 3 - 8 7 . E.A. Plettner, Resident Inspector, (RI)- Date -

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R. P. Mullikin, Project Inspector ulzin Date '{

 , 4.( nM J. T. Conway, SPIS Vendor Inspection Branch nizin Dat j Approved: _
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P. daudon, Chief, P'roject Section A,

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Reactor Projec' Branch l j

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8711090361 071106 i PDR ADOCK 05000298 ' G PDR .

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i 2 ) i Inspection Summary  !

Inspection Conducted September 1 through October 10, 1987 (Report 50-298/87-24)  !

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Areas Inspected: Routine, unannounced. inspection of licensee action o previous inspection findings, IE Bulletins, IE Information Notices, allegation, I engineered safety feature (ESF) walkdown, spent fuel shipments, operatior,al

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safety verification, security. radiological protection, monthly surveillance, j maintenance activities, and the annual emergency preparedness exercis j i Results: Within the areas inspected, no violations or deviations were i Ilienti fie q

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OETAILS Persons Contacted Principal Licensee Employees < l

* R. Horn, Division Manager of Nuclear Operations  -I
*L. E. Bray, Regulatory Compliance Specialist
*J. C. Ditto, Senior Quality Assurance Specialist
* D.' Black, Supervisor, Operations
* D. Hamm, Supervisor,' Security    l
* M. Peterson, Manager, Acting Plant Services   i
* Brungardt, Manager, Operations    l
* V. Sayer, Radiological Manager    1
* Norvell, Manager, Maintenance    1 TheNRCinspectorsalsointerviewedotherlicenseeemhloyeesduringthe  )

course of the inspectio * Denotes those present~during exit interview October 13, 198 )l Licensee' Action on Previous' Inspection Finding l The following violations, open, and unresolved items were reviewed by the NRC inspector-to verify that the licensee's response to the items identified in previous inspection reports are now,in conformance with regulatory requirements and that corrective measures were comp!

' timely manne ? ted in;a j (Closed) Violation 298/8606-02: Failure to Follow the Requalification Training Plan - This violation' wasudue to a difference of interpretation o of requirements in the approved Operator and Senior Operator?

Requalification program. Corrective action taken by the licensee was to submit a change to the Operator and Senior Operator Requalificatio program to clarify the requirement j i The licensee submitted a revision to the licensed operator requalification j program to the Institute of Nuclear Power Operations'(INP0) for j accreditation. Under the INP0 program with NRC approval', NPPD was allowed the option of substituting the INP0 accredited trair,ing program for the current operator initial:and requalification training program approved by the NRC. Accreditation for the newly developed operator ' initial and , requalification was received from the National Academy for Nuclear Training on August 5, 1987, and NPPD_ exercised the option. The NRC-inspector reviewed the newly approved NRC licensed personnel initial.and : requalification program and determined that~ corrective actions were: completed and' adequat This item is close '(Closed) Violation 298/8636-02:- ' Failure to have Documented Procedure Evaluation -'This violation,was'due to procedural inadequacies in that/the- , a> ' l

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test results were meant to be reviewed after the test procedure was ; completed. The licensee's corrective actions were as follows: 1

. .To perform a review of the procedures identified in the violatio <
. To revise all Instrumentation and Control (I&C) procedures requiring i review to have the existing " reviewed by" signoff space changed to j
" test complete and reviewed."   l The RI reviewed the above licensee action and determined that those 'd actions were completed and adequat j
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This item is close l (Closed) Violation 298/8703-01: Failure to Provide' Adequate Procedures - l This violation was due to procedural deficiencies to the failure of-various personnel involved to fully comprehend the synergistic effect of .. Design Change 86-36. Corrective actions included the following: i

. Revisions were made to System Operating Procedure '(SOP) 2.2.59, -i 50P 2.2.60, and Alarm Procedure 2.3.2.21A, to address drywel ')

pneumatic header pressure concerns during inertin j

. Nitrogen system pressure regulators were reset to higher values (140 psig and 145 psig).    .,
. The event was reviewed by the operations supervisor during regular monthly meetings conducted with each shift cre . The event was reviewed by qualified Shift Technical Advisor The RI reviewed the above licensee actions and deteni.ined that those actions were completed and adequat (Closed) Unresolved 298/8705-01: Failure to Perform All the Required Control Manipulations - This potential violation was considered to be an .

unresolved item in accordance with the commission policy statement on 4 training qualification of nuclear power plant personnel (50 FR 11147, dated March 30, 1985.) The licensee submitted a ravision to the licensed operator requalification program to INP0 for accreditation. .Under the INP0 program with NRC approval, NPPD was allowed the option of substituting the INP0 accredited training program for the current operator initial and requalification training program approved by the NR ' Accreditation for the' newly developed operator, initial and requalification training was received from.the National Academy for Nuclear Training on August 5, 1987, and NPPD exercised the option. .The NRC inspector reviewed the newly approved NRC licensed personnel', initial and requalification program and determined that corrective actions were completed and adequat This item is closed.

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(Closed) Open Item 298/8706-03: This iteui involved examples.in an I&C procedure that were similar to the violation 298/8636-02 which is closed in this paragraph. The RI reviewed the documents identified in ,

this open item and determined that the corrective actions were' completed 1 and adequat This item is close (Closed) Violation 298/8706-04: Failure to Follow a Maintenance and Test ! Equipment Procedure # This violation was due to personnel error in j completing and reviewing the data sheet in accordance with procedure :J The licensee's corrective actions were as follows:

. The two instruments identified in the violation were to be recalibrates and properly documented.-
. All I&C procedures requiring review would be revised to change'the existing " reviewed by " signoff space to " test' completed.and -

reviewed."

The RI reviewed the'above licensee actions and determined that those ! actions were completed and adequat This item is close a IE Bulletins J (Closed) IE Bulletin 87-01: " Thinning of Pipewall in' Nuclear Power Plants," dated July 9, 1987. The bulletin requested the licensee to 'j provide information concerning their program for monitoring the wall thickness of pipes in condensate, feedwater, stean, andl connecting hig .l l l energy piping systems, including all safety-related and nonsafety-related piping systems fabricated of carbon steel. IE Bulletin 87-01 requires that the licensee: (a) identify.the code or standards to which the piping j! was designed and fabricated; (b.)' describe the scope and' extent of their program for ensuring that pipe wall . thickness was not reduced below' the minimum allowable thickness; (c) for liquid phase systems, state specifically whether the following factors have been considered'in establishing the criteria for selecting points at which to monitor pipe;

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thickness: (1) piping material, (2) piping configuration, (3) pH of water in Lhe system, (4) system temperature, (5) fluid bulk velocity,'and (6) oxygen content in the system; (d) chronologically list and summarize the results of all inspections that have been performed which were ' specifically conducted for'the purpose'of. identifying pipe wall. thinning ; whether or not pipe wall thinning was discovered. ' Also, any other . . j inspections where pipe wall thinning was discovered, even.though that was'- l not the purpose of that specific inspection. -Describe any plans,- either-l for revising the present, or for developing new or additional programs for

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monitoring pipe wall thickness. To. provide a written report within 60 days of receipt of the bulletin providing the information requested above. The licensee responded to the NRC in a letter dated September 1, 1987, reference letter No. CNSS878246. The letter contained the information requested abov This item is close . IE Information Notice (Closed) Information Notice 86-106: "Feedwater Line Break," dated

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December 16, 198 (Closed) Information' Notice 86-106, Supplement 1: "feedwater Line Break," dated February 13, 189 (Closed) Information Notice 86-106, Supplement 2: "Feedwat'er Line Break,"- dated March 18, 1987. .This notice, with supplements, was provided to alert licensees of a potential generic problem with'feedwater pipe-thinning'and other problems related to the event that, occurred at the

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i Surry Power Station. The aboverinformation notice with supplements became IE Bulletin 87-01 which was closed in paragraph 3 of this report.

' l These items are close . Allegation (Closed) Allegation 4-87-A-071: This item involved the Fluke Model 8842A Multimeter and RFL Model 829 Voltage Standard used by EM Corporation l (Electrometrics) to calibrate test instruments at Cooper Nuclear Station (CNS).

The NRC inspectors visited on September 2, 1987, the NPPD corporate of fice, and the EM Corporation office on September 3,1987, to investigate the following allegations: l . The Fluke multimeter was being used as a standard.

I . The RFL voltage standard had not recently been calibrated and that-its accuracy was +/-1 percent when the test. instruments at CNS' ' required a +/ .01 percent accurac . There were no temperature and humidity controls in the EM calibration lab.

l i The NRC inspectors reviewed the Instrument Calibration Data Sheets.(ICOS) for all CNS instruments calibrated by EM for 1986 and 1987. The NR inspectors found that EM used approximately 20 different pieces of equipment to calibrate CNS test instruments. All of the EM equipment.used . were found to' have a certificate of calibration. Records also'showed that l they are scheduled to be recalibrates when the current calibration period expires. An. inspection of the EM equipment showed the current calibration

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l sticker attached to each piece of equipment.

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.F [7 b iThe Fluke Model 8842A Multimeter (SN 4092159) was purchased new by EM _i Corporation with a. September 26,1986,- Certificate ~of. Calibration, I traceable to the National Bureau of.-Standards. The Fluke instruction-
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Dj manual recommends a calibration frequency of 2 years for the ' accuracy 1 desired by'EM. Thus, this' meter does_not require _recalibration'until- H September 1988. The NRC inspectors found that the Fluke multimeter was J being used as.a standard to' calibrate.'other instruments, but this was acceptable to the NRC inspectors-as long.as.the required' calibration frequency of the Fluke multimeter is maintaine R A review of records found that the RFL Model 829 Voltage: Standard- ;i (SN FL 212) had not been calibrated,in 1986 or 1987. However, discussions' I with-EM personnel revealed that the voltage standard is not required;to be l calibrated. The actual v'ltage o output of the standard is regulated using- - other calibrated instruments (example: Fluke multimeter). This results 1 in EM using,a calibrated' input voltage?for.CN5 instruments. This-was l found to be acceptable to the NRC. inspector , j ! l The NRC-inspectors also discovered that EM did no't have' humidity controls-in their calibration laboratory. .There was a calibrated thermometer in-the laboratory. The Technical Services Manager stated that he had a-barometer in his office but did not read it on a regular basis. .EM j representatives stated that they mainly depend on physical. indications.of i a humiriity problem. The NRC inspectors noted that at.the time of the inspection the temperature in the lab was within the Fluke instruction ' d i manual-required temperature range'of 64 F-82 F, and the humidity;did not appear hig ! ' In conclusion, with,the exception'of the temperature' controls, thel l allegations were substantiated. However, based upon the recommended us ~ ! of the two piecesof equipment and thel stated calibration requirements,:it

  . appears that a safety significant~ problem ~does not exis ~

l Engineered Safety Feature (ESF) Walkdown The inspection was performed to independently verify the status of.an ESF.

l system. 'The NRC. inspector performed a walkdown~of selected ESF, systems to'. l verify operability ~, to confirm that licensee system lineup procedures  : L match plant drawings and the as-built configuration, and to . identify equipment conditions or items that might degradetsystem performance., The .

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NRC inspector reviewed the following systems: '

   . 120/240 V AC Instrument Power System 250 V DC Electrical' System
   . 125 V DC Electrical. System

! . 24 V DC Electrical System L In preparation for performing the system' walkdown of;the aboveEsystens,- the NRC inspector' conducted a review of and compar,ison'between'.the-

  .following licensee system checklistsLand' applicable as-built drawingsi
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. System Operating Procedure (S0P) 2.2.23, "120 V/240 V AC Instrument l Power System," Revision 14, dated December 28, 1986, Appendix "B" l
 . Breaker and Fuse Index, Revision 12   ;
. S0P 2.2.24, "250 V DC Electrical System,"' Revision 13, detid j February 6, 1986, Appendix "B" Breaker and Fuse Index, Revision 10 !
. S0P 2.2.25, "125 V DC Electrical System," Revision 16, dated f February 23, 1987, Appendix "B" Breaker and Fuse Index, Revision 10
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. S0P 2.2.26, "24 V DC Electrical System," Revision 7, dated March 5, j 1987, Appendix "B" Breaker and Fuse Index, Revision 4
. As-Built Drawing Burns and Roe 3010 for 120/240 V System
. As-Built Drawing Burns and Roe 3058 for 125 V DC System, 24 V DC !

System, and 250 V DC System

. As-Built Drawing Burns and Roe 3059 for 125 V DC System
. As-Built Drawing Burns and Roe 3401 for 125 V DC System  j The review identified labeling deficiencies between the above SOPS Appendix "B" Breaker and Fuse Index', the associated Burns and Roe drawing, and the label on the breaker box. The deficiencies exist because several design changes were implemente When notified, the licensee' initiated prompt action to correct the deficiencies in labeling between breaker box and the associated $0P Appendix "B" Breaker and Fuse Index. Drawing change notices were initiated as part of.the design changes to update the associated Burns and Roe Drawings. Because this deficiency appeared to fall into the scope of an ongoing licensee corrective action resulting from a violation cited in NRC Inspection Report 50-298/86-14, it is not made a violation herein, but will be tracked as an open ite (298/8724-01)

7. Spent Fuel Shipment The NRC inspector reviewed the licensee's activities associated with shipment of spent fuel from CNS. The observations, reviews, and independent measurements were conducted to verify that spent fuel handling and shipment operations were in conformance with the requirements established in the CNS Operating License, Technical Specification, Parts 71 and 73 of 10 CFR, and Parts 171-178 of 49 CF The spent fuel shipment left CNS on September 17, 1987. The shipment consisted of 2 spent. fuel shipping casks, each of which contained 18 s' pent fuel bundles. The shipment was transported to.the'G.E. Morris 0peration Complex, Morris, Illinoi The spent fuel casks identification numbers - were IF301 and IF30 No violations or deviations were identified in.this are _,

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9 , Operational Safety Verification The NRC inspector observed control room operations, instrumentation, .. controls, reviewed applicable plant logs, tagout' records, and conducted discussions with' control room personnel. Maintenance requests were reviewed to verify that appropriate priority was assigned and the maintenance was performed in'.a timely manne Tours of accessible areas'at the facility were conducted to confirm operability of plant equipment including the fire suppression syctems and other emergency equipment. Controls were adequate to ensure a safe working environment. Facility operations were performed in accordance with the requirements established in the CNS Operating License and Technical Specification (TS).

.The NRC inspector conducted a review of the Updated Safety Analysis Report (USAR) Section VIII, Electrical Power Systems. During review of Table 5-5 in Section VIII under the conditions required for continuous i operation,'the USAR states "for the Diesel Generators to be considered operable, there shall be a minimum of 45,400 gallons _of diesel fuel in the main diesel generator fuel tanks." CNS TS 3.9.A.18 states, "Both diesel generators shall be operable and there shall be a_ minimum of 45,000 gallons of diesel fuel in the' diesel fuel storage tanks." The NRC inspector inquired of the licensee to determine which of the two numbers was correct. The licensee stated that 45,400 gallons was correct. The licensee has agreed to submit a TS change to bring the TS limit into agreement with the USAR limit. This item will be tracked as an open item pending TS change. (298/8724-02) During a refueling outage at another nuclear power facility, a problem was

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identified with storage tanks manufactured by Eaton Tank Corporatio Faulty welds were discovered in several of the tanks. manufactured by the company located at the nuclear power facility. The NRC inspector inquired of CNS to determine if they had any tanks manufactured by Eaton Tank Corporation. A review of licensee records revealed that CNS had 13 tanks manufactured by Eaton Tank Corporation. Nine of those' tanks were classified as Class I Seismic. The licensee' reviewed the contract under which the tanks were purchased and noted that radiographic examinations were required prior to acceptance of the tanks at CNS. The licensee continued to retrieve and review the data sheets generated from the radiographic examinations conducted on the tank Review of those records

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indicated that all tank welds had receiud a satisfactory 100 percent radiograph. It was concluded that CNS does not have a problem with tanks _ manufactured by Eaton Tank Corporatio No violations or deviations were identified in this are . Security i I The NRC inspector verified that the physical security plan was being L implemented by selected observation of the following items.

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. Minimum manning requirements for the security organization were met'.
. Personnel within the. protected area (PA) displayed their identification badge . Vehicles were properly authorized, searched, and escorted or controlled within the P . Persons and packages were properly cleared and checked before entry into the PA was permitte '
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. Effectiveness of the security program was maintained when security ]i equipment failure or impairment required compensatory measures to be 5 employed.

l . PA barrier was maintained and the isolation zone kept free of transient materia . Vital area barriers were maintained and not compromised by. breaches 4 or weaknesse !

. Illumination of the PA was adequat ']

, . Security monitors at the secondary and central alarm stations were l performing their intended functions, j

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The NRC inspector during review of licensee nonconformance report-(NCR) i No. 87117 dated August 24, 1987, noted that on August 20, 1987, 1 day- i after a current fuel shipment, a compromise of safeguards information I occurre Part 73.21(B)(2)(II) of 10 CFR states ". . . schedules for fuel .l shipments may be released 10 days after the last shipment of a 1 current series." This is an apparent violation of failure to adhere to l Part 73.21(B)(2)(II) of 10 CFR. A notice of violation will not be issued since the violation was self-identified by the licensee and~it meets the remaining four criteria stated in Appendix C, Section V.A~of 10 CFR Part ' No violations or deviations were identifie . Radiological Protection Observations , The NRC inspector verified that selected activities of the licensee's radiological protection program were implemented in conformance with the facility policios and procedures and in compliance with regulatory requirement The NRC inspector observed and/or-' reviewed the following-activities:

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Health physics (HP) supervisory personnel conducted plant tours to check on activities in progres _j

l . Radiation work permits contained the appropriate;information to ensure work was performed in.a safe and controlled manne i l

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  . Personnel in radiation controlled areas:(RCA) were' wearing the - i required personnel monitoring equipment and protective clothin l
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  . Radiation and/or contaminated areas =were properly. posted and j controlled based on theractivity.. levels within the are ,)
  . Adequate frisking was performed by ' personnel: prior to exiting anLRCA'.
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No violations or deviations were identifie < R

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I 11. Monthly Surveillance Observations The NRC inspector observed portions.-of TS required surveillance testing 'to'- ; , verify that testing was performed by qualified personnel in accordance i l with approved test procedures. Removal and restoration of the affected i components were accomplished while meeting limiting conditions for . 1 operations. The test instruments used in performing the test were i calibration. Discrepancies. identified'during theitesting were corrected

  'in a timely manner. . Test results met the requirements established in the CNS Operating. License-and TS.'

The NRC. inspector observe'd the licensee's performance of the following . surveillance tests on the indicated dates:

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i September 2, 1987: Surveillance Procedure-(SP) 6.2.1.4.2,."PCIS Mainsteam Line High Flow Calibration and Functional / Functional Test," Revision-19,;

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dated October 23, 198 September 20, 1987: ;SP 6.1.7, " Main Turbine Stop Valve Closure and Steam-Valves Functional Test," Revision 14, dated February 12, 1987;- _ September 20,.1987: SP 6.4.8.2.3,.'" Main Turbine Trip Functional. Test," Revision 8, dated June 11,.198 "

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September 20, 1987: SP 6.4.8.2.5, " Main Turbine'EH High.-Pressure' Fluid ! System Functional Test," Revision 6,; dated May 22,.198 September 20, 1987: SP 6.4.8.4.2, "RFPT Backup 011 Pumps and Filter / Cooler Differential Pressure. Alarm Test," Revision .6, dated '.- March 13, 1986.

I No violations or' deviations were identified in'this are ' 12. Monthly Maintenance: Activities The NRC inspector observed' preventive and corrective ma'intenanc activities.of safety-related systems and components--toderify that

 ' maintenance ~' activities were conducted.by qualified personnel u' sing approved procedures.- Removal and restoration of theiaffected'compo'nents were accomplished;while meeting limiting conditions for. operations;
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i i 12 j l , Appropriate industrial codes and standards including-quality control- , i radiological controls, fire controls, and ' safety controls were met, j Applicable postmaintenance/ surveillance tests.were performed as required prior to returning the equipment to service. Maintenance operations met the requirements established in the CNS Operating License and T ; The NRC inspector observed the licensee's performance of the following l maintenance activities on the indicated date:

 . September 8 and 11, 1987: Work Item 86-2939 Turbine Equipment Cooling (TEC) Pump C using Maintenance Procedure (MP)-7.2.19,
  " Turbine-Building Equipment Cooling Water Pump Assembly Removal And -

Replacement," Revision 4, dated February -12,198 . September 16, 1987: Preventative Maintenance (PM) 03249, " Diesel Generator No. 2 Crankcase Oil Sample," using MP 7.2.0.9, " Lube Oil Sampling," Revision 0, dated July 5, 198 . September 29 and 30, 1987: Work Item 87-3031, " Diesel Generator i Engine No. 1," dated September 28, 198 '

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No violations or deviations _were identified in this are ) l 13. Annual Emergency Preparedness Exercis ,

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The CNS annual emergency exercise occurred on October 7, 198 The NRC , inspector acted as an NRC participant in the Control Room.and Technical i Support Center areas. Specific comments were provided,to the NRC exercise team leader and included in NRC Inspection Report 50-298/87-25, 14. Exit Interviews Exit interviews were conducted at the conclusion of each portion of the inspection. The NRC inspectors summarized the scope and findings of each inspection segment at those meetings and at a summary exit interview on i October 13, 198 I

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