ML20042G411
| ML20042G411 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 05/08/1990 |
| From: | Bores R, Roth J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20042G408 | List: |
| References | |
| 70-1100-90-04, 70-1100-90-4, NUDOCS 9005140206 | |
| Download: ML20042G411 (15) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION I Report No. 70-1100/90-04 Docket No. 70-1100 License No.
SNM-1067 Licensee:
Combustion Engineering. Incorporated 100 prospect Hill Road Windsor, Connecticut 06095-0500 Facility Name: Windsor Nuclear Fuel Fabrication Facility Type of Meeting: Management Meeting Meeting Date: April 27, 1990 Inspectors:
@o J.(floth,ProjectEngineer, Effluents I date~
Radiation Protection Section, Facilities Radiological Safety and Safeguards Branch, Division of Radiation Safety and Safeguards Dj -
Approved by: [#r'-
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R. J. Bores 6 Chief. Ef fluents Radiation date Protection Section, Facilities Radiological Safety and Safeguards Branch Meeting Summary: A management meeting was held at Region I, King of Prussia, Pennsylvania, on April 27, 1990, to discuss the results of the' licensee's self-assessment of performance, which was conducted at the. request of the NRC following completion of the Nuclear Fuel Integrated Improvement Program (NFIIP). The licensee representatives also discussed the preliminary results of their rcot cause analysis conducted to determine the reasons for six violations of regulatory requirements identified by the NRC during Inspection No. 70-100/90-03. That inspection was conducted following completion of the NFIIP. The NRC provided the licensee with information concerning the status and time schedule for completion of the current NRC Systemmatic Assessment of Licensee Performance (SALP) report for the tin's period July 1,1988 to March'31, 1990.
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DETAILS 1.0 Meeting Attendees 1.1 Combustion Engineering, Incorporated S. T. Brewer, President, ABB-CE Nuclear C. R. Waterman, Acting Vice President, Nuclear Fuel A. E. Scherer, Vice President, Nuclear Quality R. Vaughn, Plant Manager W. D. Mawhinney, Chairman, Independent Assessment Task Force 1.2 Nuclear Regulatory Commission T. T. Martin, Regional Administrator M. R. Knapp, Director, Division of Radiation Safety and Safeguards (DRSS)
J. Joyner, Division Project Manager, DRSS R. Bores, Chief, Effluents Radiation Protection Section (ERPS), DRSS W. J. Pasciak, Chief, Facilities Radiation Protection Section (FRPS) DRSS G. H. Bidinger, Section Leader, Fuel Cycle Safety Branch, Nuclear Material Safety and Safeguards P. N. O'Connell, Radiation Specialist, FRPS, DRSS J. Roth, Project Engineer, ERPS, DRSS 2.0 Summary of Discussion-The meeting agenda is Attachment I to this report. Mr. Martin opened the meeting and thanked the licensee's representatives for attending.
Mr. Joyner provided information on the sources of information to be used by the NRC for input to the Systematic Assessment of Licensee Performance (SALP) report and the projected schedule for completion of NRC actions leading to the June 1990 Senior Management Meeting. He also provided the licensee with an overview of the results of the NRC review of the licensee's " Internal Systematic Assessment of Licensee Performance" report issued by the licensee on February 28, 1990. A copy of the slides used by Mr. Joyner is Attachment 2 to this report.
1 Mr. Hawhinney provided information on the methodology used by the independent self-assessment task force during conduct of the internal SALP and summarized the results of the assessment.
In general, it was found that(1) significant progress was made in the improvement of safety programs at the Nuclear Fuel Manufacturing facility, (2) that some improvements remained to be implemented, and (3) that facility management was in control and was effective. A copy of the slides used by licensee representatives is Attachment 3 to this report.
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Mr. Waterman discussed the results of the licensee's preliminary review of the violations of regulatory requirements identified during a recent inspection (Inspection No. 70-1100/90-03).
He stated that, based on reviews conducted since the inspection, four of the six violations identified may not be violations, but may have resulted because the individuals questioned by the inspectors were apparently.not aware of the availability of the information needed to demonstrate compliance.
The licensee's rationale will be provided for consideration by the NRC in the licensee's response to the Notice of Violation issued with the inspection report.
Dr. Brewer provided a discussion of his perspective on the facility two year performance improvement program, and stated that CE had (1) a worn out facility that has been upgraded (2) a facility staff that has been revitalized, and (3) a facility management that has been reinvig-e orated. With regard to the self-assessment, Dr. Brewer indicated that much progress had been made but there was more to do, that documentation of actions taken was not all in place, and that performance in the licensing area (i.e., preparation of license amendment submittals) was better, but needed further improvement.
In response to questions from Mr. Martin, Dr. Brewer stated that he believed he knew where the program was headed, and believed that the licensee's goals were entirely consistent with the NRC's goals relative to protection of the health and safety of the plant workers and the public.
3.0 Conclusions Mr. Martin thanked the licensee representatives for providing the NRC with a review of the actions taken during the self-assessment.
Mr. Joyner concluded the meeting by stating that the NRC will evaluate the information provided during this meeting and in the self-assessment report.
This information will be used, as appropriate, as input to the NRC SALP report. After it meets, the SALP Board will make a recommenda-tion to Mr. Martin with regard to the status of the facility on the NRC Problem Plant List. Mr. Martin will then make a recommendation at the NRC Senior Management Meeting on June 12-13, 1990. Mr. Joyner noted that nothing said-during the meeting (with CE) should be construed to predict what that recommendation might be. The SALP Board will make that recommendation.
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I MANAGEMENT MEETING WITH COMBUSTION ENGINEERING APRIL 27, 1990 AGENDA t
f OPENING REMARKS Tim Martin, Regional Administrator Shelby Brewer, President.
Nuclear Power Businesses REGION I ACTIONS Jim Joyner, Division Project Manager LEADING TO SALP SELF ASSESSMENT TASK FORCE Walt Mawhinney, Chairman, SATF AND METHODOLOGY ONGOING ACTIONS TO CONTINVE Chuck Waterman, Acting Vice President.
THE IMPROVEMENT PROCESS Nuclear Fuel Manufacturing
SUMMARY
-STATE OF THE FACILITY Shelby Brewer CLOSE Tim Martin F
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INPUT TO SALP AND WATCH LIST RECOMMENDATION NRC INSPECTIONS SINCE 1988 (TOTAL OF 17)
CE SELF ASSESSMENT TASK FORCE REPORT i
INFORMATION FROM APRIL.
27, Y990 AND PREVIOUS MANAGEMENT MEETINGS 4
NRC REGION I SALP BOARD MEETING -
MAY 15,1990 SENIOR MANAGEMENT MEETING -
JUNE 12-13,1990 SALP MANAGEMENT MEETING - DATE TO BE DETERMINED p
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j RECOGNIZE AGGRESSIVE EFFORTS TO:
i IMPROVE EQUIPMENT OPERATION AND IMPLEMENT PREVENTIVE MAINTENANCE PROGRAM IMPROVE WORKPLACE CULTURE DEVELOP PROGRAMS SUPPORTED BY CURRENT, DETAILED l
PROCEDURES.
NONETHELESS, AMONG OUR CONCERNS ARE:
STAFFING AND TRAINING OF RADIATION CONTROL GROUP k
ONGOING INDEPENDENT AUDITS TECHNICAL SUPPORT FOR LICENSING GROUPS I
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Aktechment3 WINDSOR NFM FACILITY SELF-ASSESSMENT
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SELF-ASSESSMENT FORMALLY CHARTERED BY PRESIDENT, ABB COMBUSTION ENGINEERING NUCLEAR POWER E
U S
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l SELF-ASSESSMENT OF WINDSOR
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NFM FACILITY
.s CHARTER FOR AN !NDEPENDENT SELT. ASSESSMENT Of V!NDSOR NUCLEAR EvtL OPERAT20NS The Vice President, Nuclear Qualley Systens shsil prepare, conduct and report the results of an independent Cookustion Engineering self assesseent of our Vindsor Nuclear fuel operations. The results of this sesesseent shall be a determination of Windsor Nuclest Tuol's perfocuance in the ten (10) functional stees, and to the saae format and content, as the Nuclest Requistory Cosmission's Systematic Assessment of Licensee Performance Report No.
10 1100/06 99.
In
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acteeplishing this assessernt, the Vice President, Nuclear Qus! Ley Systees, may pursue any issue he deens relevant and significant to this assessment and/or in his capacLcy as Chakraan of the Nuclear $stery Consictee.
To assist him in this assignment, the Vice President, Nuclear Quality Systems, shall estab21sh a
Task force of individuals Andependent of the Vindsor Nuclest Tael operation being assessed and i
any utilise the services of independent outside consultants to the extent necessary to accomplish this antosseent.
In addition, he any esti upon Nuclear fuel for adelnistrative support.
1 The Vice President. Nuclest Qus11ty Systems, shall initiste this
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l sonesseent on or about January 1,1990 with a gost of completing the effort no later than February to,1990.
The Vice President, Nuclear Qus11ty Systees, shall, from cine to time, report his findings as j
spproprLace.
He shall, however, bring to my Lanedisce setention any significant deficiencies he any determine to exist.
The findings of t
I his assesseent should be documented in his signed report to me, and l
copies. provided to the Vice President. Nuclear fuel; Vice President and l
Cenerst
- Manager, Nuclest fuel Manutaccuring;
- Director, Product Development; and the Director, Nuclear Licensing.
An auditable documentation trail shall be svallable for review by the Nuclear Requistory Comeission and others. Vithin thirty (20) calendar days of the finsi report, the Vice President, Nuclest Tuel, shall provide no with his response 'and/or an action plan which addresses the resolution of. any identifLed obsesvacions, findings and/or deficiencies.
S. T. Brewer President Nuclest Power Businesses December 1,1989
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3 SELF-ASSESSMENT OF WINDSOR NFM FACILITY 10 AREAS OF SALP EEPORT N0. 70-1100/86-99 o
o FACILITY OPERATIONS o
NUCLEAR CRITICALITY SAFETY o
SAFEGUARDS 1
o EQUIPMENT MAINTENANCE i
o RADIOLOGICAL PROTECTION o
VENDOR QUALITY ASSURANCE PROGRAM o
MANAGEMENT CONTROLS o
FIRE PROTECTION AND INDUSTRIAL SAFETY 5
o LICENSING ISSUES P
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4 SELF-ASSESSMENT OF WINDSOR NFM FACILITY j
z ELEMENTS OF SELF-ASSESSMENT TASK FORCE CHARTER o
DETERMINE PERFORMANCE IN SAME 10 AREAS AS NRC SALP REPORT NO. 70-1100/86-09 i
o PURSUE ANY ISSUE DEEMED RELEVANT AND SIGNIFICANT o
USE INDIVIDUALS INDEPENDENT OF OPERATION BEING ASSESSED o
USE OUTSIDE CONSULTANTS, IF NECESSARY o
REPORT SIGNIFICANT DEFICIENCIES IMMEDIATELY t'
o DOCUMENT FINDINGS IN SIGNED REPORT l
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SELF-ASSESSMENT OF WINDSOR NFM FACILITY ELDIENTS OF SELF-ASSESSMENT PROGRAM o
CONDUCTED ASSESSMENT AS CHARTERED BY PRESIDENT, NUCLEAR POWER BUSINESSES o
GENERALLY FOLLOWED NRC MANUAL VOLUME 0000: GENERAL ADMINISTRATION CHAPTER 0516
" SYSTEMATIC ASSESSMENT OF LICENSEEPERF0kMANCE"ANDCRITERIA0FTABLE10FPART 0500, " HEALTH AND SAFETY" o
ASSESSED THE FOLLOWING:
- CORRECTIVE ACTIONS FOR SALP REPORT AND MID-SALP REVIEW ITEMS
- CORRECTIVE ACTIONS FOR NRC INSPECTION REPORTS SINCE i
AUGUST 1988
- STATUS 0F NRC OPEN ISSUE LISTS
- STATUS OF INDEFENDENT TASK FORCE ITEMS
- PERFORMANCE IN ALL 10 AREAS COVERED BY NRC SALP REPORT NO. 70-1100/86-99 o
USED PERSONNEL INDEPENDENT OF NUCLEAR FUELS o
USED OUTSIDE CONSULTANT FOR RADIOLOGICAL PROTECTION REVIEW o
DOCUMENTED FINDINGS IN REPORT TO PRESIDENT, NUCLEAR POWER BUSINESSES l-9 w
.4 SELF-ASSESSMENT OF WINDSOR l
NFM FACILITY EVALUATION CRITERIA o
MANAGEMENT INVOLVEMENT AND CONTROL IN ASSURING i
QUALITY
- n. APPROACH TO RESOLUTION OF TECHNICAL ISSUES FROM A SAFETY STANDPOINT o
AUDITS AND FEEDBACK MECHANISMS o
ENFORCEMENT HISTORY o
REPORTING AND ANALYSIS OF REPORTABLE EVENTS o
STAFFING (INCLUDING MANAGEMENT) o TRAINING AND QUALIFICATION EFFECTIVENESS o
QUALITY OF PROCEDURES AND OPERATIONS l
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SELF-ASSESSMENT OF WINDSOR NFM FACILITY SlpMARYOFRESULTS o
SIGNIFICANT PROGRESS IS EVIDENT IN ALL AREAS o
SOME IMPROVEMENTS REMAIN TO BE~ IMPLEMENTED o
MANAGEMENT IS IN CONTROL AND IS EFFECTIVE P
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LICENSE $UBMITTALS o
SYMPTOM:
LICENSE AMENDMENT REQUESTS HAVE REQUIRED NRC STAFF CHANGES TO CRITICAllTY ANALYSES BEFORE APPROVAL o
ROOT CAUSE:
- 1) CE WAS NOT AGGRESSIVE ENOUGH IN IDENTIFYING ALL CREDIBLE ABNORMAL CONDITIONS TO EVALVATE
- 2) CE WAS INADEQUATELY STAFFED WITH EXPERIENCED CRITICALITY PROFESSIONALS
FIX:
- 1) NEW CRITICALITY EVALVATIONS WILL REFLECT GUIDANCE PROVIDED IN AN ASTM DRAFT DOCUMENT "NEW STANDARD ENGINEERING DESIGN FOR NUCLEAR CRITICALITY SAFETY"
- 2) MORE EXHAUSTIVE REVIEW AND EXPOSITION OF ALL CREDIBLE ABNORMAL CRITICALITY CONDITIONS WILL BE PART OF THE CE EVALVATION PROCESS
- 3) CE WILL HIRE / TRAIN ADDITIONAL CRITICALITY PROFESSIONALS 4)
CRITICALITY PROFESSIONALS WILL BE MORE INVOLVED IN THE PLANT DESIGN PROCESS S) ADDITIONAL COMMUNICATIONS WITH THE NRC REVIEW STAFF BOTH BEFORE AND AFTER SUBMITTALS SHOULD FACILITATE MVTVAL UNDERSTANDING OF THE EVALVATION PROCESS AND ITS ACCEPTABILITY l
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