IR 05000285/1988037

Insp Rept 50-285/88-37 on 881017-21.Violation Noted.Major Areas Inspected:Design Changes & Mods,Receipt,Storage & Handling of Equipment & Matls & Measuring & Test Equipment

ML20206B964
Person / Time
Site:	Fort Calhoun
Issue date:	11/03/1988
From:	Barnes I, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20206B926	List: IR 05000285/1988037 ML20206B924 ML20206B938 ML20206B964
References
50-285-88-37, NUDOCS 8811160061
Preceding documents:	ML20246M849 (11 July 1989)
Download: ML20206B964 (7)

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APPENDIX B U.S. NUCLEAR REGULATORY COWi!SSION

REGION IV

NRC Inspection Report: 50-285/88-37 Operating License: DPR-40 Docket: 50-285 Licensee: Omaha Public Power District (OPPD) 1623 Harney Street Omaha, Nebraska 68102 Facility Name: FortCalhounStation(FCS) Inspection At: FCS, Blair, Nebraska Inspection Conducted: October 17-21, 1988 e // 5 -tr Inspector: [ W..M. McNeill, Reactor Inspector, Materials Date and Quality Programs Section, Division of Reactor Safety Approved: be I. Barnes, Chief. Materials and Quality

               // J -PP Date Programs Section, Division of Reactor Safety Inspection Sumary Inspection Conducted October 17-21, 1988 (Report 50-285/88-37)

Areas Inspected: Routine, unannounced inspection of design changes and modifications; receipt, storage, and handling of equipment and m6terials; and measuring and test equipmen Results: Withinthethreeareasinspected,oneviolation(failuretomaintain traceability of measuring and test equipment usage, paragraph 4) was identifie ! DR ADOCK0500g5 i l

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l DETAILS i i , Persons contacted ! , OPPD l

*J. Bobba, Radiological Protection Supervisor       ;

C. J. Brunnert, Operations Quality Assurance (QA) Supervisor L R. P. Bunz,' Quality Control (QC) Inspector

*A.G.Christensen,FieldHealthPhysicist(HP)       j D. W. Dale, QC Supervisor        .

D. H. Ecklaud, Lead Mechanical Engineer l

*J. J. Fisicaro. Nuclear Licensing Manager       -;
*W. G. Gates, FCS Manager        t
*S. K. Gambhir, Production Engineering Division Manager      r
*L. L. Gundrum, Licensing Engineer        !
*D. Jacobson, Chemical / Radiological Protection Training      ,

J. G. Kucera, Design Engineer D. J. Matthews Supervisor, Nuclear Licensing t

*K. J. Morris, Nuclear Operations Division Manager       '
*J. M. Pilant, Consultant Nuclear Operations       l
*C. F. Simons Onsite Licensing Engineer        l
*K Steele, HP Special Services Coordinator       I
*M. A. Tesar, Technician & General Employee Training Supervisor      l S. T. Tramell, Matorial Consultant        j The NRC inspector also interviewed other licensee errployees during the     !

irspectio }

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* Denotes attendance at exit interview conducted on October 21, 198 )
          ; Design Changet and Modifications Program (37702)       i The objective of this inspection was to ascertain whether the licensee is implementing a QA program for the control of design changes and modifications that is in conformance with regulatory requirements and licensee connitments. This inspection was a continuation of inspection activities began in NRC Inspection Report 50-285/88-31. In this regard, the NRC inspector reviewed the QA program description found in Appendix A     -

of the Updated Safety Analysis Report (USAR), Revision 5. dsted July 1988; f the QA Plan for FCS, Unit 1, Revision 13 dated August 1,1988; and the following implementing procedures:

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 "QA Review of Design Documents," 0DP-18 Revision 5, dated August 1,     !

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 * "Station Modification Control," SO G-21, Revision 32, dated      i August 11, 1989         l l
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 "Preparation of Design Packages," GEG 3, Revision 0, dated      l November 1987         i
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 "Modification Request Development," A-2, dated February 1988
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 "Production of Design Description and Evaluation Nuclear Modifications," B-2, dated December 1987
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 "Independent Design Verification," B-11, dated February 1988     <

The NRC inspector reviewed the following sample of five design packages for modifications to be performed during the current outage;

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FC-86-96, "RPS Power Supplies"

* FC-87-37, "Diesel Generator Electrical Modification"
* FC-87-38, "Diesel Generator Mechanical Modification"      l
* FC-85-135, "Reactor Coolant Loop RTD Indicator Replacement" i
* FC-85-022, "Control Room Identification of Thermal Overload of     l Limitorque Operators" The NRC inspector found that a program has been established to control modification activities which appeared adequat i No violations or deviations were identified in the review of this program     i are ; Receipt, Storage, and Handling of Equipment and Materials (38702)     l The objective of this in3pection wat to detemine whether the licensee is     l implementing a OA program for the control of receipt, storage, and     ;

handling of equipment and naterials that is in conformance with regulatory i

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requirements and licensee comitments. This inspection was a continuation of inspection activities began in NRC Inspection Report 50-285/88-31. In j this regard, the NRC inypector reviewed the QA program description found , in Appendix A of the USAR, Revision 5, dated July 1988; QA Plan for FCS, l Unit 1, Revision 13 dated August 1, 1988; and the following implementing l

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procedures:

* "Material / Service Acceptance and Receipt Inspection," QDP-12,     !
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Revision 6, dated August 1, 1988 i

* "Receiving, Shipping, Store Control and Storage of Critical Equipment and Radioactive Material Packing Fire Protection Material, and     :

Limited CQF," SO G-22. Revision 29, dated July 27, 1988 l The NRC inspector found that the program requirements for receipt, ' storage, and handling appeared to be satisfactory. The NRC inspector

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performed a review of the storage and handling practices for a sample of eight items which were applicable to the modifications referenced in paragraph 2 above. On October 19, 1988, during this review, the NRC inspector observed evidence of soda pop drinking in the storage area of the old warehouse. Two soda cans, one which was empty and one which was partially full, were found on shelving in the mezzanine area. This practice is contrary to Procedure 50 G-22 which requires storage areas for safety-related equipment to be maintained free of food and drinks. The licensee took imediate corrective and preventive actions. The Supervisor. 0)erations QA issued a memorandum on eating and drinking in tie warehouse to all affected personnel. Materials are currently being moved to a new warehouse facility and use of the old warehouse will be discontinued for safety-related items. At the time of this inspection, about 20 percent of the inventory of safety-related items remained in the old warehouse. As the items are moved, they are subject to a soecial inspection which, as a result of the NRC inspector's observation, has been changed in scope to include cleanlines In that the specific observation represents a minor regulatory concern, and corrective action was initiated, completed, and verified prior to the conclusion of the NRC inspection, the noncompliance with Procedure 50 G-22 requirements has not been included as an item in the Notice of Violatio . Measuring and Test Equipment (35750) The objective of this inspection was to ascertain that the licensee has developed and implemented a QA program relating to the control of measuring and test equipment that is in confomance with regulatory requirements, commitments in the application, and industry standards. In this regard, the NRC inspector reviewed the QA program description found in Appendix A of the USAR, Revision 5. dated July 1988; QA Plan for FCS, Unit 1 Revision 13, dated August 1, 1988; and the following implementing procedures:

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   "Calibration of Mechanical Gauging Equipment " 50 H-7 Revision 27, dated July 26, 1988
  * "Calibration Procedures " S0 M-26. Revision 15. dated August 25, 1988
  * "Calibration of Test Equipment," SO H-28 Revision 29 dated August 17, 1988
  * "Calibration Procedures " SO T.27, Revision 4, dated July 18, 1988 The NRC inspector found that adequate programs have been established to control calibration activities for mechanical, I&C, electrical, and health physics equipmen _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ _ _ _ _ _ _ _ _ .
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The calibration records for 23 items were reviewed with respect to equipment identification, calibration status, compliance with calibration i frequency requirements, and evaluation of calibration failures. The NRC i inspector additionally reviewed three licensee audits of calibration

activities. The NRC inspector found the calibration program to be satisfactorily implemented with the exception noted belo A compari;on was made between measuring and test equipment usage logs and identities of equipment recorded in QC inspection logs for seven recent test activitie This comparison identified three omissions in the Instrument

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and Control (I&C) log. On October 3.1988, the QC log (No. 88-1810) noted ~ that a containment local leak detection test type B (ST-CONT-2) was performed using a penetration leak test rig which consists of a pressure , gauge (No. 311) and two flow gauges. On October 17, 1988, the QC q log (No. 88-2396) noted that reactor protection system power supplies were i tested as part of Modification FC-86-96 using a digital voltmeter (No. 372).

! On October 17, 1988, 88-2424) noted that auxiliary building i the tested air filtering units were QC tog ((No.ST-VA-4) using an anemometer (No. 285).

] The I&C shop logs did not identify the usage of such equipment on the i dates in question. The failure to maintain traceability of measuring and . test equipment usage was identified as an apparent violation (285/8837-01).

j 6. Exit Interview

' An exit interview was conducted on October 21, 1988, with the personnel

denoted in paragraph 1. The NRC resident inspectors attended. At the

! exit interview, the NRC inspector sum 3rized the scope and findings of the

inspection. There was no information presented to the NRC inspector that j was identified by the licensee as proprietary.

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