IR 05000261/1987023
| ML14191A845 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/16/1987 |
| From: | Fredrickson P, Vias S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14191A844 | List: |
| References | |
| 50-261-87-23-EC, NUDOCS 8707310022 | |
| Download: ML14191A845 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report No.:
50-261/87-23 Licensee:
Carolina Power and Light Company ATTN: Mr.. E. E. Utley Senior Executive Vice.President Power Supply and Engineering and Construction P. 0. Box 1551 Raleigh, NRC 27602 Docket No.:
50-261 License No.:
DPR-23 Facility Name: H. B. Robinson 2 Meeting Conducted:
June 26, 1987 Project Enginee (.
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Date Signf Approved by:
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P.F redrickson, Section Chief ate igned Division of Reactor Projects SUMMARY An Enforcement Conference was held at Region II on June 26, 1987, at 10:00 a.m., to review items pertaining to valve lineups and independent verifi cation requirements as they relate to isolation. of both the Residual Heat Removal (RHR)
and Safety Injection (SI)
Systems; and items identified during the Safety System Functional Inspection (SSFI).
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3 0 00 )A B-0 DCIV
REPORT DETAILS 1. Attendance NRC J. N. Grace, Regional Administrator R. J. Goddard, Regional Counsel L. A. Reyes, Director, Division of Reactor Projects (DRP)
D. M. Verrelli, Branch Chief, Project Branch 1, DRP H. E. Krug, Senior Resident Inspector, H. B. Robinson, DRP S. J. Vias, Project Engineer, Projects Section 1A, DRP G. F. Maxwell, Senior Resident-Inspector, Shearon Harris, DRP A..':. Gibson, Director, Division of Reactor.Safety (DRS)
A. R. Herdt, Branch Chief, Engineering Branch, DRS M. B. Shymlock, Section Chief, Operational Programs Section, DRS T. E. Conlon, Section Chief, Plant Systems Section, DRS P. J. Fillion, Reactor Inspector, DRS T.. O'Connor, Reactor Inspector, DRS C. L. Vanderniet, Reactor Engineer, DRS G. R. Jenkins, Director, Enforcement and Investigation Coordination Staff L. Trocine, Enforcement Specialist K. T. Eccleston, Senior Project Manager, Robinson, NRR
- Carolina Power and Light Company E. E. Utley, Executive Senior Vice President M. A. McDuffie, Senior Vice President -
Nuclear Generation H. R. Banks, Manager, Corporate QA A. B. Cutter, Vice President, Nuclear Engineering G. P. Beatty, Vice President, Robinson Nuclear Project R. E. Morgan, General Plant Manager W. J. Planagan, Manager, Design Engineering G. M. Curley, Director, Regulatory Compliance L. J. Sheppard, Manager, Planning and Scheduling D. R. Quick, Manager, Maintenance Event Discussions The Regional Administrator opened the meeting by reviewing the NRC concerns involving independent verification requirements, valve lineups, and the isolations of the SI and RHR Systems. The Regional Administrator also briefly described the overall deficiencies identified during the SSFI team inspectio Mr. Utley then gave a brief opening statement for CP&L. Mr. Sheppard gave a detailed overview of the specific failures to follow plant procedures involving independent verification and the mispositioning of the RHR and SI valves which resulted in the isolation of the RHR and SI System CP& stated that they had a good record up to the 1987 outage and that the decrease in attention to detail began during the startup after the 1987 outage. The corrective actions stated were thorough and promptly insti tute CP&L stated that Quality Assurance (QA)
and the PNSC would increase their review and surveillance efforts in the areas of equipment contro.CP&L stated that, for the foreseeable future, only licensed operators will sign for the independent verification requirement The NRC was impressed with the depth and promptness of these corrective action CP&L stated that they would be forwarding the above concerns to their other two plants for revie Mr. Sheppard continued with the SSPI items, beginning with details in the area of Appendix The NRC stated a concern with respect to. the CP&L staff doubling up on responsibilities for various key positions in order to meet the requirements of Appendix R. A question was raised as to whether or not CP&L routine procedure reviews would have caught any of the concerns discussed in the SSPI inspection repor CP&L stated that they believe they were in full compliance with the requirements of Appendix R at the time of the SSPI inspection. The NRC stated that further inspec tions will be conducted in this are Mr. Quick provided a detailed review of the Emergency Diesel Generator (EDG) failures. CP&L stated that the failure of the "B" EDG was due to foreign object intrusion (which is contrary to the SSFI findings, whereby the failure was due to overheating of the blower).
On the topic of EDG fuel oil testing, CP&L gave addi tional information to the NRC for review and stated that CP&L did not believe a violation of their commitments exists as outlined in the SSFI report. The NRC will review this matter further. Mr. Flanagan addressed the design control issues. The NRC had a concern as to whether CP&L had a program to assure that when modifications are made, they do not compromise the plants design basi In the area of electrical switchgear coordina tion, Mr. Flannagan presented the CP&L review details. The NRC continued to express. concern.over the interchangeability of the molded case breakers and the interrupt capacity of the DB50 breaker Mr. Reyes began the summation stating that, with respect to the RHR and SI System isolations, he is very concerned with the failure of the operators to perform proper independent verification and procedural adherence. CP&L stated that they will submit., within two weeks of the enforcement meeting, a report to address all the issues with respect to the SSPI report. The NRC thanked CP&L for their presentation and closed the meeting.