IR 05000261/1978021
| ML14175A984 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/26/1978 |
| From: | Mchenry T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175A983 | List: |
| References | |
| 50-261-78-21, NUDOCS 7811080289 | |
| Download: ML14175A984 (6) | |
Text
SER REG&
UNITED STATES NUCLEAR REGULATORY COMMISSION C'
REGION 11
< j 230 PEACHTREE STREET, N. W. SUITE 1217-t
~,ATLANT GEORGIA 30303 Report No.:
50-261/78-21 Docket No.:
50-261 License No.: DPR-23 Licensee: CaroLina Power and Light Company 366 FayetteviLLe Street RaLeigh, North CaroLina 27602 FaciLity Name:
H. B. Robinson 2 Inspection at: H. B. Robinson site, HartsviLLe, S. Inspection conducted:
August 22-25, 1978 Inspector: T. J. McHenry Approved by:
If C L
H. Dance, Chief Date Reactor Projects Section No. 1 Reactor Operations and NucLear Support Branch Inspection on August 22-25, 1978 (Report No. 50-261/78-21)
Areas Inspected:
Routine unannounced inspection of plant cleanLiness; Licensee event foLLowup; spent fueL shipment activities; inservice inspection program for pumps and vaLves; and independent inspection effort. The inspection invoLved 32 inspector-hours onsite by one NRC inspecto Results:
Of the five areas inspected no items of noncompliance or deviations were identifie (III1)
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RII Rpt. No. 50-261/78-21 I-1 DETAILS I Prepared by:
1 ce/r ecto r
T. J. Mclienry eactor Inspect Date Reactor Projects Section N Reactor Operations and Nuclear Support Branch Dates of Inspection:
August Z2-25, 1978 Reviewed by: 4 C
C- /7 H. C. Dance, Chief Date Reactor Projects Section No. 1 Reactor Operations and Nuclear Support Branch Persons Contacted
- R. B. Starkey, Jr., Plant Manager
- R. E. Morgan, Operations Supervisor
- H. S. Zimmerman, Engineering Supervisor
- B. W. Garrison, Quality Assurance Supervisor W. T. Traylor, Administrative Supervisor R. McGirt, Senior Generation Specialist
- M. Page, Engineering Technician Several control room shift foreman and operator *Denotes those present at exit intervie.
Licensee Action on Previous Inspection Findings No previous items of noncompliance or deviations were reviewed during this inspectio.
Unresolved Items No new unresolved items were identified during this inspectio.
Exit Interview A meeting was held on August 25, 1978, with Mr. R. B. Starkey, Plant Manager, and staff members denoted in paragraph The scope and findings of the inspection were discusse RII Rpt. No. 50-261/78-21 1-2 Inservice Inspection Program for Pumps and Valves The inspector reviewed the licensee's inservice inspection (ISI)
program for pumps and valves to determine the status of the ISI program implementation and to establish criteria and guidelines for the development of a formalized NRC inspection procedur The licensee's ISI program for pumps and valves has been conditionally approved by NRC Licensing for implementation but has not had final NRC Licensing approva The final approval of the licensees 1SI program is pending the ongoing review by NRC Licensing and the license The inspector reviewed the implementation of the conditionally approved ISI pump and valve program against the requirements of the 1974 Edition of Section XI of the ASIME Boiler and Pressure Vessel Code through Summer 1975 Addend The inspector noted that the licensee's program did not provide for testing of pumps and valves per all requirements of Section XI Code and that current conditionally approved 1SI program did not provide relief from these requirement Specifically, the following Section XI Code requirements were not included in the licensee ISI testing program:
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requirement to establish reference values for measured pump parameters, IWP-311 requirement to establish inservice test plan, IWP-623 requirement on the scope of test, IWP-330 requirement to verify valve position indicator, IWV-330 The inspector discussed the apparent uncertainty of the licensee's commitment in the areas listed above with licensee personne The licensee indicated that the requirement to establish relief in the areas discussed would be evaluated and relief would be requested if necessary. The inspector stated that additional inspection of the ISI pump and valve program would occur following final approval of the licensee's ISI program by NRC Licensin (78-21-01) Spent Fuel and Shipping Cask Handling The inspector observed fuel movement, shipping cask movement and shipping cask decontamination on all three operating shifts. Fuel and cask handling were observed to insure compliance with the following procedures:
RII Rpt. No. 50-261/78-21 1-3
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FT-15.1 Administrative Procedure for Transporting Spent Fuel
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FT-15.2 Loading and Shipping of PWR Fuel During the inspection of the fuel and cask loading several radiological control items were noted and identified to the licensee: Existing radiological access control to the spent fuel pool and cask wash areas did not require or provide for frisking of hands, feet and face prior to exiting of these areas. Current controls would not detect contamination of an individual until the auxiliary building is exite The donning of protective clothing was not standard in that some personnel tapped ankles and wrists while others did no Further some personnel wore rubber boots on the outside of paper boots while others wore paper boots on the outside of rubber boot Exiting procedures appeared to be silent on prescribing a
standard method of donning protective clothin c. Efforts to prevent contamination of a hand radio used to direct crane operator in the fuel storage and cask wash areas resulted in frequent removal and replacement of protective gloves which could result in contamination of both the radio and the operato An excessive amount of protective clothing was located in the spent fuel are This clothing was not labeled clean or contaminated and the purpose for this clothing was not known and this location was not designated as a clean are The hook and cables of the cask crane are submerged in the spent fuel pool during cask movement, but the status of the contamination (if any) of the crane hook, cables and drum was unknown. Further, the crane is located outside and possible contamination by rainfall washing contamination (if any) to areas below had not been considere The licensee acknowledged the inspectors comments on radiological control The inspector indicated that these items would be considered on a future inspection (78-21-02). Review of Licensee Event Reports (LER's)
The inspector reviewed selected LER's for consistency with the requirements of the Technical Specification The inspector examined
RII Rpt. No. 50-261/78-21 1-4 the licensee's analysis of the event, the corrective action taken and discussed the LER's with licensee representative The following LER's were reviewed: LER 78-18, Station Battery Fire The inspector discussed the LER with several licensee personnel including the plant engineer assigned to the repair and evaluation of this occurrenc Discussion with the licensee's representatives confirmed the designation of the cause and corrective action take However, the battery vendor has also conducted an investigation into this occurrence and the licensee has not received the vendor's written repor This LER will remain open pending the licensee's receipt of the vendor written report and subsequent review during a future inspectio LER 78-09 "B" Auxiliary Feedwater Pump Failed to Start This LER was reviewed during inspection 78-12 and required a supplemental report to accurately report the corrective actio The inspector reviewed supplemental report with licensee personnel and confirmed corrective actio This LER is close LER 78-10 "B" Auxiliary Feedwater Pump Breaker Trip Coil Setting Low This LER was also reviewed during inspection 78-12 and required a supplemental report to accurately report the cause of the occurrence. The inspector reviewed the supplemental report with licensee personnel and confirmed the cause of the occurrenc This LER is close.
Thirty-day Written Report Requirements The inspector discussed unresolved item (78-16-02), concerning requirements for thirty-day written reports for Limiting Conditions for Operation (LCO's)
created by corrective maintenance, with the plant manager. The inspector stated that the licensee could continue to report under exiting NRC guidelines for reporting which do not require thirty-day report for LCO's created by maintenance provided that the LCO does not exist or is determined to have existed prior to the maintenanc This unresolved item is close RH Rpt. No. 50-261/78-21 1-5 Plant Cleanliness The inspector toured the facility, including the turbine area, auxiliary building, spent fuel, and control room to ascertain the status of housekeepin The inspector reviewed the following instructions and procedures to assure appropriate controls to minimize potential fire and safety hazards:
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Administrative Instruction, Section 11
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QAP-2, General Cleaning and Flushing Requirements
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Fire Protection Manual No problems were identified.