IR 05000261/1990007
| ML14176A858 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/19/1990 |
| From: | Jape F, Matt Thomas NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14176A857 | List: |
| References | |
| 50-261-90-07, 50-261-90-7, NUDOCS 9005030081 | |
| Download: ML14176A858 (5) | |
Text
ak R E G UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
c 101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report No.: 50-261/90-07 Licensee: Carolina Power and Light Company P. 0. Box 1551 Raleigh, NC 27602 Docket No.:
50-261 License No.:
DPR-23 Facility Name: H. B. Robinson Inspection Conducted:
April 2 - 6, 1990 Inspector:
-/ - ()
M. Thomas Date Signed Approved by:
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.
.
F. Jape, Section Chief Date Signed Quality Performance Section Operations Branch Division of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of Design Changes and Modification Results:
In the areas inspected, violations or deviations were not identifie The Nuclear Engineering Department is involved in all phases of the modification package development. This includes preparation of the implementing procedures and post modification test procedure The level of involvement by design engineering in the modification package development is considered a strength in the licensee's design change progra PEIjrC pric)./~
REPORT DETAILS 1. Persons Contacted Licensee Employees
- R. Barnett, Shift Outage Manager W. Biggs, Manager, NED Site Engineering Support R. Clark, Senior Specialist, Mods/Projects
- S. Clark, Procurement Engineering Supervisor
- S. Griggs, Technical Aide, Regulatory Compliance E. Harris, Jr., Manager, Onsite Nuclear Safety
- M. Heath, Engineering Supervisor, Mods/Projects C. Kelly, Engineering Technician, Planning & Scheduling
- T. Kinnaman, Engineering Supervisor, Technical Support L. Kirkland, Senior Specialist, Mods/Projects
- J. Kloosterman, Director Regulatory Compliance/Acting Plant Manager
- A. McCauley, Principle Engineer, Onsite Nuclear Safety M. Page, Manager, Technical Support D. Smith, Senior Specialist, Mods/Projects R. Smith, Manager, Maintenance A. Wallace, Operations Coordinator
- H. Young, Manager, QA/QC Other licensee employees contacted during this inspection included engineers, operators, technicians, and administrative personne *NRC Resident Inspectors
- L. Garner, Senior Resident Inspector K. Jury, Resident Inspector
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragrap. Design, Design Changes and Modifications (37700)
a. The inspector reviewed the modification packages listed below to determine the adequacy of the 10 CFR 50.59 evaluations; verify that the design changes were prepared and installed in accordance with licensee administrative procedures and applicable industry codes and standards; field changes were reviewed and approved in accordance with administrative controls; and post modification test requirements were specified. The following modification packages were reviewe M-955, Emergency Diesel Generators A&B Upgrad This modification consisted of rerouting of the fuel oil drain piping to eliminate leaking of fuel oil onto the exhaust manifold; addition of air line
The inspector reviewed the DCNs and verified that they had been initiated, reviewed, and approved in accordance with the licensee's administrative controls and the changes were addressed in the 10 CFR 50.59 safety evaluatio There were no violations or deviations identified in the areas inspecte b. PIRs One of the mechanisms used by the licensee for personnel to identiy problems and concerns requiring technical and/or engineering assistance is a PI PIRs are generally initiated in situations where work requests cannot handle the scope of the work or evaluations desire The inspector reviewed open and closed PIRs which were initiated by licensee personnel from various department All PIRs are reviewed by the immediate supervisor and unit supervisor of the individual who initiated the PIR. The PIR is then assigned to the appropriate department for revie These reviews provide a mechanism for assessing the need of the request and the priority that should be assigned to the PI For those PIRs reviewed by the inspector, adequate reviews were performed by licensee personne PIRs deemed necessary are then assigned a PCN number by the Long Range Planning Grou PCNs provide a mechanism for tracking PIR Some PIRs resulted in modifications being generate For those PIRs which resulted in modifications, the PIRs are not closed until the modifications have been completed. There were appriximately 400 open PIRs at the time of this inspectio The number of open PIRs includes approved modifications which were in various stages of completio There were no violations or deviations identified in the areas inspecte. Exit Interview The inspection scope and results were summarized on April 6, 1990, with those persons indicated in paragraph The inspector described the areas inspected and discussed in detail the inspection results. Proprietary information is not contained in this report. Dissenting comments were not received from the license. Acronyms and Initialisms CFR Code of Federal Regulations DCN Design Change Notice EDG Emergency Diesel Generator LER Licensee Event Report NED Nuclear Engineering Department (Corporate)
PCN Project Control Number PIR Plant Improvement Request
isolation valves on lines to the oil boosters to allow barring of the EDGs using the air start system; new lube oil sample taps to permit better control and monitoring of lube oil quality; changes to the lube oil keep warm system to ensure proper temperatures will be maintained in the oil sump; additon of permanent lifting beams in the EDG rooms to make EDG maintenance easier and faster; addition of strainers to the fuel oil supply lines to provide additional fuel oil filtration capabilities between the EDG fuel oil transfer pumps and the inlet solenoid valves upstream of the EDG fuel oil day tanks; starting air compressor low air alarm switch replacement to provide more accurate indication of low starting pressure; EDG breaker indication modification to allow for breaker trip indication at the RTGB and position indication on both the RTGB and local control panel; and installation of new. supports for the exhaust ducts for both EDG M-966, RHR Cold Leg Recirculation Pressure Interlock. This modifica tion consisted of installing new safety related, environmentally qualified pressure switches in the RHR/SI cross-tie pipin This modification corrected a plant condition which created a potential violation of the single failure criterion. This problem was reported and discussed in LER 87-030-00 dated December 17, 1987. The LER was closed in NRC Inspection Report 50-261/89-0 M-981, RHR 744B Valve Reorientatio This modification involved reorientation of valve RHR 744B and its operator by rotating the valve around the valve/pipe centerline, and by rotating the operator around the valve stem centerline. This reorientation was necessary to avoid interferences with existing plant components during installation of the new larger valve operator on valve RHR 744 The valve internals were also replace The valve internals replacement and the operator replacement were performed under Engineering Evaluation 88-14 During review of the above modifications, the inspector noted that the cognizant engineers in NED responsible for the modification packages reviewed were involved in all phases of the modification developmen This included development of the implementing procedures and the PMT procedure The inspector considers this level of involvement by NED to be a strength in the licensee's modification progra The safety evaluations and PMT requirements for the applicable modifications were adequat While reviewing modification package M-955, the inspector noticed that there were several DCNs written which involved construction interferences associated with installation activitie The inspector questioned licensee personnel concerning these DCNs because they were generated after the modification package appeared to have been complete Licensee personnel stated that the DCNs were written for the installation of new supports on the exhaust ducts of both EDG The decision was made to add the supports via DCNs to modification package M-955 in lieu of developing a separate modification package because of the time and costs involved in developing a new modification packag PMT Post Modification Testing QA Quality Assurance QC Quality Control RHR Residual Heat Removal RTGB Reactor Turbine Generator Board SI Safety Injection