IR 05000482/1980022
| ML19353A366 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/14/1980 |
| From: | Crossman W, Seidle W, Seyfrit K, Vandel T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19353A364 | List: |
| References | |
| 50-482-80-22, NUDOCS 8101080296 | |
| Download: ML19353A366 (9) | |
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O U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. STN 50-482/80-22 Docket No. STN 50-482 Categcry A2 Licensee:
Kansas Gas and Electric Company Post Office Box 208 Wichita, Kansas 67201 Facility Name: Wolf Creek Generating Station, Unit 1 Meeting at: Wichita, Kansas (November 3,1980)
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NRC Participants:
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K. V. Seyfrit, 01rectm7, Region IV Date
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W. C. Seidle, Chief, Reactor Construction and Date Engineering Support Branch w
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hT.E.Vandel,ResidentReactorInspector, Projects Date v
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W. A. Crossman, Chief, Projects Section Date Meeting Summary:
Meeting on November 3,1980 (Recort No. 50-482/80-22)
Meeting Topics: Announced meeting with the Kansas Gas and Electric Company corporate management concerning the evaluation of the licensee's performance.
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DETAILS 1.
Persons Contacted Principal Licensee Emoloyees Glenn L. Koester, Vice President - Nuclear Thomas D. Keenan, Director - Nuclear Operations Gary L. Fouts, Construction Manager Earl W. Creel, Manager Quality Assurance Maurice E. Clark, Manager, Site Quality Assurance William G. Eales, Jr., Project QA Coordinator NRC Particicants K. V. Seyfrit, Director, Region IV W. C. Seidle, Chief, Reactor Construction and Engineering Support Branch W. A. Crossman, Chief, Projects Section T. E. Vandel, Senior Resident Reactor Inspector 2.
Meeting with KG&E Management a.
Purcose of Meeting The purpose of this meeting was to describe the regional evaluation for the systematic appraisal of licensee performance.
This evaluation is an integral part of the Systematic Assessment of Licensee Performance (SALP) program which is to be implemented in accordance with the commit-ments of the " Action Plan for Implementing Recommendations of the President's Commission and Other Stuides of TMI-2 Accident." The attached Appendix B is the performance evaluation for the Wolf Creek Generating Station, Unit 1 facility for the period August 1,1979, through July 31, 1980, compiled by the NRC participants and a Regional Review Board.
To begin the meeting, the Regional Director outlined the following objectives for a systematic appraisal of licensee performance:
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Identify exceptional or unacceptable licensee performance
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Improve licensee performance
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Improve the IE inspection program
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Provide and achieve a means of regional consistency in evaluating licensee performance-2-
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b.
Enforcement History The enforcement history for the Wolf Creek, Unit 1 facility was reviewed.
The following noncompliances were issued during the period August 1,1979, through July 31, 1980, by NRC, Region IV IE inspectors:
Failure to approve qualifications of blasting specialist.
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Failure to provide prompt and adequate corrective action to
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preclude water standing in storage area for reactor closure head and internals.
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Failure to provide proper storage for stainless steel spool pieces (standing in water).
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Failure to identify nonconforming conditions of reactor cavity and fuel transfer canal concrete damage.
Failure to provide adequate test procedures for UH sink dam
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tests.
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Failure to provide a timely written report for a construction deficiency regarding spalling of concrete in reactor cavity.
Failure to specify appropriate acceptance criteria for
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maximum reinforcement of butt welds.
Failure to establish housekeeping zone designations for
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cleanliness.
Failure to provide appropriate procedures for activities
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affecting quality associated with II/I supports and raceways.
The above nine infractions were issued during 881 man-hours of inspection performed during the review period in the following areas:
Ultimate Heat Sink Excavation and Testing
Storage of Materials
QA/ Management
Reporting
The NRC representatives suggested that the licensee may want to review their program control for Appendix B, Criterion V coverage.
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Two deviations were issued during the period August 1,1979, through July 31,1980:
Failure to designate cable tray for use in Class IE and II/I
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as safety-related material.
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Failure to establish fire protection and prevention requirements.
c.
Summary of Noncompliance Items The NRC participants stated that the nine items of noncompliance issued during 881 man-hours of IE inspection effort is typical of an acceptable construction QA program.
Corrective action of these items indicates an effective positive trend in QA program implementation and management control by Kansas Gas and Electric Company.
d.
Construction Deficiency Reports (50.55(e))
The twelve construction deficiencies for the period were reviewed:
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Imperfect Threads, Southern Bolts 3h" Nuts
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Concrete Block Walls - Repair Positioned Wrong Fuel 0001 Liner Plate Over Pressurized
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Ruskin Fire Dampers (Part 21)
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Class 2 & 3 Bolts Incorrectly Marked
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Discrepant Westinghouse Printed Circuits (Part 21)
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Bunker Ramo Amphenol - Sams Penetrations Undetectable Failure in Engineering Safety Features Actuation
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Colt Emergency Diesel Generators (Part 21)
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Bergen Patterson Sway Struts
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Anaconda Cable Jacket Problems
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Industrial Mechanics, Inc. 2-3/4". Nuts & Solts The NRC participants considered the reporting threshold to be adequate.
Also a conservative, conscientious attitude for timely and accurate reporting has been exhibited by. KG&E.
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e.
Escalated Enforcement Actions No escalated enforcement actions occurred during the last year; however, a management meeting (Inspection Report No. STN 50-482/79-18)
was held at the request of the licensee on October 26, 1979, to dis-cuss the following:
50.55(e) reporting requirements
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lower threshold of incident reporting 10 CFR Part 21 requirements
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Resident Reactor Inspection assignment
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f.
Licensee's Responsiveness and Ability to Take Meaningful Corrective Action on Problems Identified by the IE Inspection Program Responses to IE Bulletins / Circulars / Notices The NRC participants stated that responses have been timely, concise and effective, indicating a meaningful management and engineering control system.
Resconses to Enforcement Actions
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The resentatives discussed the licensee's responsiveness to enfm-cut citations. They stated that the licensee's response has be4n prompt and adequate to meet the necessary requirements.
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Effectiveness and Attitudes of Personnel in Complying with NRC Regulatory Requirements,s
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The NRC participants stated that KG&E has demonstrated an excellent attitude towards complying with their commitments and NRC regulatory requirements.
KG&E personnel have been determined to be effective in this area.
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Summary The Regional Director summarized the discussions at the conclusion of the meeting and emphasized that the license holder is the legal responsible.
party and, therefore, they must be sure to cover all phases. 'He also urged continued management awareness through the transitional phase from construction into preoperational testing.
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APPENDIX 3 Region IV LICENSEE PERFORMANCE EVALUATION (CONSTRUCTION)
Facility: Wolf Creek, Unit No.1 (SNUPPS)
Licensee:
Kansas Gas and Electric Company Unit Identification:
Docket No.
CP No./Date of I suance Unit No.
STN 50-482 CPPR-147/May 1977
Reactor Information:
Unit 1 Unit 2 Unit 3 NSSS Westinghouse Electric MWe 1150 Appraisal Period: August 1,1979 - July 31,1980 -
Appraisal Comoletion Date:
October 21, 1980 Review Board Members:
W. C. Seidle, Chief, RC&ES Branen W. A. Crossman, Chief, Projects-Section R. E. Hall, Chief, Engineering Support Section R. C. Stewart, Reactor Inscector, 3rojects Section C. R. Oberg, Reactor Inscector, Projects Section T. E. Vandel, Pesident Reactor Inspector, Projects Section
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APPENDIX B i-2-A.
Numoer and Nature of Noncomoliance Items Noncomoliance Category:
Unit 1 Unit 2 Unit 3 Violations
Infractions
Deficiencies
Areas of Noncomoliance:
Unit 1 Unit 2 Unit 3 (List Areas as Required)
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(Points)
(Points)
Soils Activities (1)
QA Program Control (5)
Materials Storage Protection (2)
Reporting (1)
Ceviations (2)
Total Points 140 3.
Number and Nature of Deficiency Reoorts 1.
Imoerfect Threads, Southern Bolts 3h" Nuts 2.
Concrete Block Walls - Repair Positioned Wrong 3.
Fuel Pool Liner Plate Over Pressurized (Part 21)
Ruskin Fire Dampers 5.
Class 2 & 3 Bolts Incorrectly Marked
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Discrepant Westinghouse Printed Circuits (Part 21)
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Bunker Ramo Amonenol - Sams Penetrations 3.
Undetectable Failure in Engineering Safety Features Actuation 9.
Colt Emergency Diesel Generators (Part 21)
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Bergen Patterson Sway Struts 11.
Anaconda Cable Jacket Problems 12.
Industrial. Mechanics, Inc. 2-3/a" Nuts & Solts
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APPENDIX B
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Escalated Enforcement Actions i
i Civil Penalties
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None Orders None Immediate Action Letters None
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D.
Management Conferences Held During Past Twelve Months At the request of the licensee, a management meeting was held on
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October 26, 1979, to discuss the following:
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50.55(e) reporting requirements
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2, Lcwer Threshold of Incidents Reporting 3.
10 CFR Part 21 requirements
Resident Reactor Inspector Assignment E.
Justification of Evaluations of Functional Areas Categorized as Recuiring an Increase in Inscection Frecuency/Scoce (see evaluation sneet)
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APPENDIX B-a-
i Inscection
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rgauency anc/or Sccce
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FUNCTICNAL AREA INCREASE NO. CHANGE CECREASE
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Quality Assurance, Management & Training x
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Suostructure i Fcundations xl/
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Concrete xl/
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Liner (Containment & Others)
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Safety-Related Structures y
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Picing & Hangers (Reactor Ccolant
& Others)
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Safety-Related Ccmoonents (Vessel,
Internals & HVAC)
y 8.
Electrical Ecuipment x
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Electrical (Tray & Wire)
x 10.
Instrumentation x
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Fire Protection X
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Preservica Ins;:ection x
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Recorting X
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1/ The decrease is due to the site decrease in construction activity.
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