IR 05000155/1988019
| ML20151V070 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/08/1988 |
| From: | Harrison J, Huber M, James Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20151V058 | List: |
| References | |
| 50-155-88-19-EC, NUDOCS 8808220089 | |
| Download: ML20151V070 (3) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-155/88019(DRS)
Docket No. 50-155 License No. DPR-06 Licensee: Consumers Power Company 1945 West Parnall Road Jackson,.V.I 49201 Facility Name: Big Rock Point Nuclear Plant Meeting At: Region III office, Glen Ellyn, Illinois Meeting Conducted: July 21, 1988 Type of Meeting:
Enforcement Conference Date of Previous Inspe tion: April through June 6, 1988 l
Inspectors:
. P. Huber f / ff Reactor In ector Date C1 d
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y f ac f J. F. Smith
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Date Approved By:
. J. Harrison, Chief bO b
Engineering Branch Date Meeting Summary Meeting on July 21, 1988 (Report No. 50-155/88019(DRS))
Areas Discussed: Additional information presented by the licensee and deficiencies pertaining to an apparent violation of ASME Code Section XI requirements for full stroke testing of reactor depressurization valves documented in Inspection Report No. 50-155/88011(DRS).
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DETAILS 1.
Persons Contacted a.
Consumers Power Company (CPCo)
F. W. Buckman, President D. P. Hoffman, Vice President, Nuclear Operations T. W. Elward,. Plant Manager, Big Rock Point Plant K. W. Berry, Director, Nuclear Licensing J. L. Bacon, Assistant General Counsel G. C. Withrow, Engineering and Maintenance Superintendent, Big Rock Point Plant D. E. Moeggenberg, Supervisory Engineer, Big Rock Point Plant R. J. Alexander, Technical Engineer, big Rock Point Plant E. M. Evans, Senior Engineer, Big Rock Point Plant
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M W. Acker, ISI Coordinator, Big Rock Point Plant b.
Target Rock Corporation V. Liantanco, Engineer-Consultant c.
Di Benedetto Associates, Inc.
D. A. Di Benedetto, Consultant d.
NUS Corporation V. S. Noonan, Consultant e.
Nuclear Regulatory Commission A. B. Davis, Regional Administrator, Region III H. J. Miller, Director, Division of Reactor Safety W. L. Axelson, Chief, Reactor Projects Branch 2
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J. W. Clifford, Regional Coordinator, DEDRO W. E. Scott, Project Manager, NRR D. H. Danielson, Chief, Materials and Processes Section i
I. N. Jackiw, Chief, Reactor Projects Section 2B E. A. Plettner, Senior Resident Inspector, Big Rock Point Plant M. P. Huber, Reactor Inspector, DRS J. F. Smith, Reactor Inspector, DRS N. R. Williamsen, Resident Inspector, Big Rock Point Plant W. H. Schultz, Enforcement Coordinator B. W. Stapleton, Enforcement Specialist
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C. D. Anderson, Technical Assistant, Division of Reactor Projects
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Enforcement Conference As a result of an apparent violation of NRC requirements an enforcement conference was held in the NRC Region III office on July. 21, 1988.
The preliminary findings which were the basis for this apparent violation of NRC requirements were documented in NRC Inspection Report No. 50-155/88011(DRS) and were transmitted to the licensee by letter dated June 29, 1988. The attendees of this conference are noted in l
Paragraph 1 of this report.
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The purpose of the conference was to:
(1) discuss the apparent violation, the significance, cause, and the licensee's corrective actions; (2) determine whether there were any aggravating or mitigating circumstances; and (3) obtain other information which would help determine the appropriate enforcement action.
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The NRC representatives identified the apparent violation, noting that several other issues were of concern.
The concerns were aging, system importance, and the adequacy of testing practices at the Big Rock Point Plant.
The extreme importance of the system in question to mitigate the consequences of an accident was underlined to stress the concern on the part of the NRC.
The licensee stated that the problem was being addressed; however, additional valve problems took precedence due to imediate concerns of personnel safety and prolonged Reactor Coolant System leakage.
Partial stroke testing, instead of full stroke testing of the RDS valves, was outlined by the licensee in their In-Service Testing Program.
In the Integrated Plant Safety Assessment Report (NUREG-0828) dated May 1984, the staff recognized that the issues of the RDS valve full stroke testing was not resolved and endorsed making the resolution a lower priority than resolving the RDS valve leakage problem.
Corrective actions were taken at the time of the inspection to include:
1) full stroke testing of all valves each refueling outage with an inspection of the internals of one valve, 2) full stroke testing of each valve during the current refueling outage, and 3) modification of the pilot valve assembly to correct the pilot valve leakage problem.
Further analysis of possible valve failure mechanisms is being conducted by the licensee to ascertain the effect or possibility of accelerated corrosion or presence of foreign materials causing degradation of the RDS depressurization valves.
The licensee plans to have a test specification and a schedule for analysis completed by mid August 1988.
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