IR 05000346/1997014
| ML20199A853 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/10/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20199A842 | List: |
| References | |
| 50-346-97-14, NUDOCS 9711180130 | |
| Download: ML20199A853 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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REGIONlil-
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i Docket No:
50-346-License No:
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Report No:
50-346/97014(DRS)-
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' Licensee:
Toledo Edison Company -
Facility: -
Davis-Besse Nuclear Power Station
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5503 N. State Route 2
Oak Harbor, OH 43449 ~
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Dates:
October 21 - 23,1997 Inspector:
Martin J. Farber, Reactor Ins pector Approved by:
James A. Gavula, Chief, Engineering Specialists Bianch 1 Division of Reactor Safety
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9711180130 9711to-F PDR ADOCK 0$000346
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EXECUTIVE SUMMARY
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Davis-Besse Nuclear Power Station NRC Inspection Report 50-346/97014(DRS)
This inspection was a follow-up to the Maintenance Rule Baseline inspection conducted January 13 - 17,1997, which examined the licensee's implementation of 10 CFR 50.65,
" Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," The
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report covers a three-day on-site inspection by one regional inspector, Maintenance Two findings involving reliability performance criteria and the structure monitoring
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program were closed.
An NRO concem involving lack of formal, specific guidance for prograrn activities was
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appropriately addressed by the issuance of a maintenance rule administrative procedure.
The licensee's corrective actions were acceptable and were properly implemented,
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Report Details Introduction This inspection was a follow-up to the Maintenance Rule Baseline inspection conducted January 13 - 17,1997, which examined the licensee's implementation of 10 CFR 50.65,
" Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." The report covers a three-day on-site inspection by one regional inspector.
II. Maintenance M8 Miscellaneous Maintenance issues (92902)
M8.1 (Closed) Violation 50-346/97002-01(DRS): Reliability Performance Criteria The inspector reviewed a sensitivity study (Calculation No. C-NSA-99.16-20,
" Maintenance Unavailability and Reliability Sensitivity Analysis"), that was conducted to determine the correlation between established reliability criteria and the reliability assumptions in the Individual Plant Examination. The study required replacing the reliability and availability assumptions in the Individual Plant Examination with the performance criteria. Unavailability performance criteria were used directly and reliability performance criteria were used to develop failure rates. Two failure rate methodologies were evaluated. The first was to replace the assumed failure rate with a simple ratio of the number of allowable failures to the expected number of demands or to the expected run times. The second method was the more standard Bayesian updating of known failure rates. The first method was extremely conservative and resulted in a core damage frequency of 1.26E-4, a 92 percent increase from the baseline of 6.57E-5. This was the bounding case and was not a realistic change in core damage frequency. The standard Bayesian update method was used to generate a more accurate assessment of the change in core damage frequency. Bayesian updating resulted in a core damage frequency of 7.66E-5, a 17 percent increase over the base case. This was considered acceptable. This item is closed.
M8.2 LC]osed) Unresolved item 50-346/97002-02(DRS): Structure Monitoring Program The inspector reviewed M/S DG-26, " Design Guidelines for Maintenance Rule
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Evaluation of Structures.* The structures within the scope of the program were listed as well as those structures that were excluded. The guideline also established an organization, walkdown criteria, documentation requirements, evaluation guidance, and deficiency resolution guidance. Programs already in place to evaluate structures were also identified. The inspector noted that the five attributes for an acceptable structure monitoring program, as stated in Regulatory Guide 1.160, Revision 2, were incorporated into the licensee's program. The inspector reviewed a sample of the Maintenance Rule Evaluation Worksheets generated during structure walkdowns and concluded that they l
provided a useful way to collect and evaluate data on structural conditions. This item is (
closed.
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M8.3 - Procedure CDDCMD.
During the inspection, the team was concemed by the lack of formal, specific guidance for program activit_ies; this concem was expressed in the letter transmitting the Maintenance Rule Baseline inspection report (50-346/97002(DRS)). In response to this concem, the licensee issued administrative procedure DB-FF-00003, " Maintenance Rule." The inspector reviewed this procedure and determined that it adequately addressed the necessary aspects of the station's maintenance rule program.
V. Management Meetinas
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X1 Exit Meeting Summary On October 23,1997, the inspector presented the inspection results to licensee management.
The licensee acknowledged the findings presented.
' The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
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PARTIAL LIST OF PERSONS CONTACTED -
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Licensee
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'l R. Rishel, Maintenance Rule Coordinator-l
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E A. McCallister. Test / Performance Supervisor
- G. Wolfe, Licensing D. Eshelman, Operations Manager
- J. ~ Rogers, Plant Engineering Manager.
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S.' Stasek, Senior Resident inspector
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LIST OF INSPECTION PROCEDURES USED IP 62002 inspection of Structures, Passive Components, and Civil Engineering Features at
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Nuclear Power Plants IP 62706 Maintenance Rule IP 92902 Maintenance Follow-up LIST OF ITEMS CLOSED 50-346/97002-01(DRS)
- Reliability Performance Criteria" 50-346/97002-02(DRS)
" Structure Monitoring Criteria" LIST OF ACRONYMS USED DRS Division of Reactor Safety NRC Nuclear Regulatory Commission CFR Code of Federal Regulations PARTIAL LIST OF DOCUMENTS REVIEWED
.PJopeqires DB-PF-00003, Revision 00, August 22,1997,"Mairitenance Rule"
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MRPM 03, October 13,1997, " Maintenance Rule Program Manual"
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M/S DG-26, Revision 2, October 10,1997, " Design Guidelines for Maintenance
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f Rule Evaluation of Structures" WPG-1, Revision 6, October 20,1997," Work Scheduling Guideline"
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PE-02, Revision 2, July, 28,1997, " Plant Engineering Policy - System Walkdown
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Checklist" Calculations C-NSA 99.16-20, Revision 0, May 13,1997," Maintenance Unava'laoility and
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Reliability Sensitivity Analysis" C NSA-99.16-20, Attachment 1, Revision 0, May 12,1997, " Demand and
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Run Time per 24-Month Cycle" C-NSA-99.16-20, Attachment 2 Revision 0, May 12,1997, " Bayesian
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Updatc Calculation" C-NSA-99.16-20, Attachment 3 Revision 0, May 12,1997, "Cutset
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Report T6 - Luss of Makeup to the RCS" C-NSA-99.16-20, Attachment 4 Revision 0, fAay 12,1997, "Cutset
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Report, T12 - Loss of All Survice Water" C-NSA-99,16-20, Attachment 5 Revision 0, May 12,1997, "Cutset
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Report, T14 - Loss of Component Cooling Water"
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C-NSA 99.16-20, Attachment 6, Revision 0, May 131997, "CAFTA input
and Output" C-NSA-99.16-20, Attachment 7. Revision 0, May 13,1997, * Failure
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Rates for Maintenance Rule Sensitivity Studies - Feedwater (Motor-Driven Feed Pump)"
C-NSA-99.16-19, Revision 2, May 5,1997, * Maintenance Unavailability Analysis
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(Measured Performance)"
C-NSA-99.16-19, Attachment 1, April 30,1997, "Cutset Report, T6 - Loss
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of Makeup to the RCS" C-NSA-99.16-19, Attachment 2 October 11,1996,"Cutset Report, T14 -
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Loss of Component Cooling Water" C-NSA-99.16-19, Attechment 3, April 30,1997, "Cutset Report, T6 - Loss
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of Makeup to the RCS" C-NSA-99.16-19, Attachment 4, April 30,1997, ~lPE and Revised Event
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Probabilities and CDF" C-NSA-99.16-19, Attachment 5, April 30,1997, " Demand and Run Time
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per 24-Month Cycle" C-NSA-99.16-20, Attachment 6, April 30,1997, "Baycelan Update
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Calculation" Other Documents Intra-company Memorandum NPE-97-00219, July 17,1997, " Auxiliary
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Boiler / Steam Goals"
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Procedure Change Request 97-1737, July 16,1997," Potential Condition
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Adverse to Quality Reporting" Structure Monitoring - Maintenance Rule Evaluation Worksheett
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Structure Monitoring - Maintenance Rule Evaluation
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Intra-company Memorandum NPE-96-00525, December 11,1996, * Maintenance
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Rule implications for Communications and Emergency Lighting" Intra-company Memorandum NPE-97-00250, August 22,1997,"4160 Volt
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System Goals" Maintenance Rule Systems in Category (a)(1)
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