IR 05000285/1985023
| ML20137Z031 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/29/1985 |
| From: | Boardman J, Hunnicutt D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20137Z029 | List: |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR 50-285-85-23, NUDOCS 8512110207 | |
| Download: ML20137Z031 (6) | |
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APPENDIX
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I U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
i NRC Inspection Report:
50-285/85-23'
License: CPR-40 i
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Docket:
50-285 i
j Licensee:
Omaha Public Power District
1623 Harney Street Omaha, Nebraska 68102
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Facility Name:
FortCalhounStation(FCS)
j Inspection At:
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Inspection Conducted: October 21-25, 1985 Inspector:
o Mw MA14 1986
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J. J.' Bo~ardman, Reactor Inspector Operations Date Stction
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Approved:
h O fA l b e w 7
///29/9'5 A D. M. Hunnicutt, Chief Cperations Section, Date
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Reactor Safety Branch Inspection Summary j
Inspection Conducted October 21-25,1985,(Report 50-285/85-23)
Areas Inspected:
Routine, unannounced inspection of the licensee's quality assurance program, procurement program, material receipt handling and storage program, document control, and the Fort Calhoun Station plant review committee.
The inspection involved 34 inspector-hours onsite by one NRC inspector.
Results: Within the areas inspected, no violations or deviations were identified.
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DETAILS
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1.
Persons Contacted Omaha Public Power District
- R. L..Andrews, Division Manager, Nuclear Production
- W. G. Gates, Plant Manager FCS
- J. K. Gasper, Manager, Administration Services
- K. J. Morris, Manager, Quality Assurance
- M. R. Core, Supervisor, Maintenance FCS
- L. P. Walling, Supervisor, Administrative Services FCS F. Thurtell, Division Manager, QARA J. Fisicaro, Supervisor, Nuclear Regulatory and Industry Affair P. M. Surber, Section Manager, Generating Station Engineering
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C. Brunnert, Supervisor, Operations Quality Assurance D. R. Podell, Manager, Office Systems The NRC inspector also contacted other licensee employees including engineering, quality assurance, maintenance, and administrative.
- Denotes presence at the exit interview conducted October 25, 1985.
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2.
Follow-up On Previously Identified Items (Closed) (50-285/8133-02) Qualification of Subcontractor Quality Control (OC) and Nondestructive Examination (NDE) Personnel. This concern was that the licensee did not review qualifications of contracted QC and NDE personnel performing safety-related work. The NRC inspector had reviewed several records of training and had noted several apparent anomalies. The licensee QC and QA personnel now review and approve the qualifications of subscontract QC and NDE personnel. All contracts for such personnel performing safety-related activities are now controlled by the licensee as safety-related ("CQE").
3.
Annual Review of Licensee Quality Assurance Program The NRC inspector reviewed changes to the below listed Quality Assurance Program procedures.
Implemented revisions did not lessen licensee commitments.
PROCEDURE REVISION DATE QADP-1 Control of the QA Department Manual
11/30/84 QADP-2 Quality Assurance Department Training
11/30/84
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QADP-3 Training and Certification of Audit Personnel
11/30/84
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QADP-4 Training and Certification of Inspectors
11/30/84 QADP-5 Internal Audit and QA Surveillance Program
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Scheduling
11/30/84
QADP-6 Conduct of Audits
11/30/84 QADP-7 Conduct of QA Surveillances
07/12/85 QADP-8 Conduct of QA Inspections
11/30/84 QADP-10 Review of Procurement Documents
11/30/84 QADP-11 Approval and Audit of Vendors
05/17/85 QADP-12 Material Acceptance and Receipt Inspection
11/30/84
QADP-13 Control of Nonconforming Items and Materials
11/30/84 QADP-14 Deficiency Tracking and Trending
11/30/84 QADP-15 Control of QA Department Documents and Records
07/12/85 i
QADP-17 Control of Deficiencies and Corrective Action
11/30/84 QADP-18 Review of Design Documents
11/30/84 QADP-19 10 CFR 21, Reporting of Defects and Noncompliances
04/12/85 The NRC inspector identified no deviations or violations in the procedures reviewed.
4.
Licensee Onsite Review Committee The NRC inspector attended the Licensee Plant Review Committee (PRC)
meeting on October 23, 1985, and reviewed the minutes of 19 PRC meetings,
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randomly selected from July 3,1984, to the time of this NRC inspection.
All minutes appeared acceptable with respect to Technical Specification requirements, such as attendance.
No violations or deviations were noted in this management area.
5.
Licensee ~ Document Control The NRC inspector reviewed the licensee's document control program as described in the following procedures:
a.'
FortCalhounStation(FCS)StandingOrderNo.C-5,"FortCalhoun Print Files,"' Revision 6, dated September 26, 1985.
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b.
FCS Standing Order No.G-47, " Control Room Drawings," Revision 3, dated September '.0, 1985.
c.
FCS Standing Order No.G-30, "Setpoint/ Procedure Changes,"
i Revision 17, da:ed Septe.iber 26, 1985.
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d.
FCS Standing Order No.G-21, " Station Modification Control,"
j Revision 24, dated September 26, 1985.
e.
FCS Standing Order No.0-27, " Technical Data Book," Revision 4, dated i
May 17, 1985.
f.
FCS Standing Order No.0-19, " Systems Descriptions," Revision 3, dated July 5, 1984.
g.
Generating Station Engineering (GSE) Administrative Procedure A-1,
" Correspondence Control," Revision of August 1985.
h.
GSE Administrative Procedure A-2, " Modification Request Development,"
Revision of August 1985.
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GSE Administrative Procedure A-9, " Document Control," Revision of August 1985.
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GSE Design Procedure B-3, " Drawing Production," Revision of August 1985.
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Engineering Services Department Instruction (ESDI)-04, "P&ID and EM Drawing Update Instruction," Revision 1, approved October 3,1985.
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1.
ESDI-08, " Engineering Design File Closecut Instruction," Revision 0,
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approved October 14, 1985.
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N-TSAP-1, " Preparation and Approval of Technical Services Administrative Procedures," Revision 0, February 1985.
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Records Management Procedure 1.0, " Procedure Control " Revision 0, April 1984.
The NRC inspector discussed with licensee GSE personnel the apparent lack of document controls to assure that calculations of seismic loads for
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safety-related conduit supports reflected station modifications accomplished after the initial design calculations were performed.
GSE personnel stated that they had recently identified this concern as
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part of their overall scoping of Unresolved Safety Issue (VSI) A-46 relating to plant seismic qualifications.
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OPPD Internal Memorandum GSE-FC-85-778, Subject: "NRC Unresolved Safety Issue (USI) A-46 Concerning Seismic Safety of Equipment," dated August 27, 1985, discusses the OPPD program for addressing USI A-46.
This
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i will remain an unresolved item (50-285/8523-01) pending the OPPD response i
to USI A-46.
No violations or deviations were noted in this management area.
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6.
Procurement Control Program The NRC inspector reviewed Licensee Nuclear Purchasing Procedure NPP-1,
" Nuclear Procurement Control," Revision 1, dated April 2, 1984. No violations or deviations were noted in this management area. QADP-10 and 11, which are identified in paragraph 3, also address this area.
j 7.
Licensee Program For Receipt, Handling, and Storage of Material The NRC inspector reviewed the following licensee procedures covering their program for receipt handling and storage of safety-related material:
FCS Standing Order No.G-24, " Receiving and Shipping Control of CQE, a.
Limited CQE, Fire Protection Material and Radioactive Material I
Packaging Materials (Quality Material)," Revision 17, dated December 20, 1984.
b.
FCS Standing Order No. G-22, " Storage of Critical Element and Radioactive Material Packaging, Fire Protection Material, and
Calibrating Equipment," Revision 13, dated October 11, 1985.
FCS Standing Order No. G-25, " Stores Control," Revision 14 dated c.
June 25, 1985. QAPD's-12 and 13, which are discussed in paragraph 3,
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also address this management area.
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.The NRC inspector identified no deviations or violations in the licensee's
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progran for receipt, handling, and storage of material.
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8.
Licensee Control of Limited Life Electrolytic Capacitors for Safety
Related Activities
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Aluminum electrolytic capacitors have a design life of from 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> of
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operation to a total shelf and service life of 15 years depending upon s
1, design, size and application.
Extension of design life may not be possible because secondary failure modes may preclude prediction of capacitor life.
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Licensee maintenance personnel stated that capacitor failure to date had, i
for some applications, resulted in preventive maintenance replacement to prevent future failures. No overall analysis had been done of
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safety-related capacitor applications.
This will remain an open item (50-285/8523-02) pending detennination of the generic aspects of this concern.
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9.
Unresolved Item An unresolved item is a matter about which more information is required in order to determine whether it is acceptable, a violation, or a deviation.
One new unresolved item is discussed in this report in paragraph 5.
10. Exit Interview An exit interview was conducted on October 25, 1985, with personnel in paragraph 1 of this report. At this meeting, the scope of the inspection and the findings were summarized.
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