IR 05000261/1978024
| ML14175B009 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 11/07/1978 |
| From: | Belisle G, Dance H, Mchenry T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B008 | List: |
| References | |
| 50-261-78-24, NUDOCS 7812150063 | |
| Download: ML14175B009 (5) | |
Text
t REcGIq, UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report No.:
50-261/78-24 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, SC Inspection conducted:
October 3-6, 1978 Inspectors: T. J. McHenry G. A. BeLisLe Approved by:
/ 7 7F H. C. Dance, Chief Date Reactor Projects Section No. 1 Reactor Operations and NucLear Support Branch Inspection Summary Inspection on October 3-6, 1978 (Report No. 50-261/78-24)
Areas Inspected:
Routine, unannounced inspection of reviews and audits, IE BuLLetin followup, Licensee event followup, Licensee action on previous inspection findings, pLant tour and independent inspection effor The inspection invoLved 60 inspector-hours on site by two NRC inspector Results:
Of the six areas inspected, no items of noncompliance or deviations were identifie '7812 15 0 ob
SRII Rpt. No. 50-261/78-24 I-1 DETAILS I Prepared by:
T. J. McHenr, Reactor Inspector a t Reactor Pro ects Section No. 1 Reactor Operations and Nuclear Support Branch Dates of Inspectio Octobe 3-6, 1978 Reviewed by:
n Q I--
/ / 7/ 7 H. 9. Dance, Chief at Reactor Projects Section No. 1 Reactor Operations and Nuclear Support Branch Persons Contacted
- R. B. Starkey, Jr., Plant Manager
- R. E. Morgan, Operations Supervisor B. W. Garrison, Quality Assurance Supervisor
- D. S. Crocker, Environmental and Radiation Control Supervisor C. Wright, Engineering Technician M. Page, Engineer R. H. Chambers, Senior Engineer R. S. McGrit, Senior Nuclear General Specialist
- W. T. Traylor, Administrative Supervisor
- J. M. Curley, Senior Engineer F. Bishop, Electrical Engineer Several Control Room, Shift Foreman and Plant Operator *Denotes those present at the exit intervie.
Licensee Action on Previous Inspection Findings (Closed) Deficiency (50-261/78-16)
Quarterly reviews of plant proce dures and weekly management facility tour Corrective actions stated in CP&L letter of September 8, 1978, were verified to have been completed. (Paragraph 6) Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviation An unresolved item (78-24-01) disclosed during the inspection is discussed in Paragraph RII Rpt. No. 50-261/78-24 1-2 Plant Fire On October 4, 1978 at approximately 9:00 a.m.,
a fire started in a ventilation duct in the clothing change area of the auxiliary buildin The inspector observed licensee actions during the fire emergency condition. The fire was extinguished within a few minutes by directing water from a fire hose into the affected ventilation duc No major problems were encountered in controlling the fire and only light smoke existed in the area of the fir The affected ventilation duct connected to the main auxiliary building system; however, it was quickly verified that no fire or smoke had spread to any auxiliary building safety related equipment areas. The fire emergency condition was terminated at approximately 10:15 A post analysis of the fire indicated that the fire had started when lint, which had accumulated in the duct from the plant laundry dryer exhaust, was ignited when a cutting torch cut through the duc The cut through the duct was inadvertently made by a workman who was removing a steel wall frame from around the duct. The close proximity of the frame to the duct resulted in cutting through the duct and subsequent ignition of the lint inside the duc The inspector reviewed the licensee's procedural controls for handling the fire emergency to verify that applicable procedures existed and that appropriate actions specified were taken by the licensee. During this review it was noted that the licensee did not have a fire emergency procedure as part of the Plant Operating Manua Technical Specifiction, Section 6. requires that written procedures and administrative policies shall be established that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix A of Regulatory Guide 1.33 dated November 3, 197 Instructions for response to a plant fire were contained in Plant Notice N, Fire Station Bill. In addition, Volume 19, Fire Protection Manual, provides information on fire brigade organization and training but excludes specific emergency instructions for plant operatio The inspector discussed the Technical Specification requirement with the plant manager who stated that the Fire Protection manual and the Plant Notice had been considered adequate to meet the Technical Speci fication requirements to establish administrative policie The inspector noted that Plant Notice N did not appear to contain all topics required by ANSI-18.7, Section 5.3.8.1 and further Plant Notice N is not subject to administrative controls for approval, distribution, review, training and revision as specified in administrative
instruction RII Rpt. No. 50-261/78-24 1-3 The licensee indicated that the need for incorporating a plant fire procedure in the operating manual would be reviewe The inspector stated that this matter would remain unresolved pending a determination of the acceptability of Plant Notice N to meet requirements of Technical Specification 6.8.1. (78-24-01)
M G. R. Jenkins, NRC Radiation Specialist, was also on-site and observed radiological controls utilized during the fir Comments on the radiological controls utilized are documented in IE Inspection Report 50-261/78-2.
Quarterly Reviews of Plant Procedures and Weekly Management Facility This item was originally discussed in IE Report N /78-16, Details I, Sections 11 and 12,and dealt with a deficiency where the licensee had not documented quarterly procedure reviews and weekly facility inspections by plant management. CP&L letter GD-78-2422 dated September 8, 1978 stated the corrective actions to be taken on this item and that full compliance would be achieved on August 4, 197 The inspector reviewed quarterly procedure review records for the second quarter 1978 and weekly facility inspection reports for period of January -
June 1978. These records were found to be in conformance to the requirements of Administrative Instructions, Volume 1, Sections 4.1.6 and 4. In addition, the format of the weekly facility inspection form had been changed as stated in the licensee's corrective actions respons This matter is close.
Review of Licensee Event Report (LER)
The inspector reviewed LER 78-19, RTD Failure, for consistency with the requirements of the Technical Specification Section 6.9. The inspector examined the licensee's analysis of the event, the corrective action taken and the LER was discussed with the licensee representatives. The inspector reviewed control room logs to verify corrective action stated in the LER. In addition, it was determined that the failed RTD had been replaced and returned to service during the last outage. The LER is close.
Review of IE Bulletins (IEB's) The inspector reviewed IEB 78-06, Defective Cutler-Hammer, Type M Relay with DC Coil The inspector had no further questions on the Bulletin, since discussion with cognizant licensee personnel indicated that the licensee's actions and reply to this Bulletin were satisfactory.Bulletin 78-06 is close RII Rpt. No. 50-261/78-24 1-4 The inspector reviewed IEB 78-10, Bergen-Paterson Hydraulic Shock Suppressor Accumulator Spring Coil The inspector discussed licensee actions on this Bulletin with licensee representatives, no problems were identifie Bulletin 78-10 is close.
Emergency Diesel Generator Start/Stop Design The inspector reviewed the control schematics for the emergency diesel generators to determine if any problems existed with manual diesel starting following engine trip under emergency start conditio The inspector determined that all diesel generator trips (except 86 lock out) are normally defeated, therefore no problems would be encounted due to engine trip under emergency condition This matter was reviewed to investigate a possible generic problem with starting the emergency diesel generator following an engine trip under emergency start conditon No problems were identified in the area of concer.
Review and Audits The inspector reviewed the Plant Nuclear Safety Committee (PNSC)
minutes from December 1, 1977 to July 28, 1978 to verify that the meeting frequency, membership, selection of alternates and consultant involvement was in accordance with the Technical Specification, Section Selected plant records were reviewed to verify that; proposed test and experiments which affect nuclear safety, proposed changes to Technical Specifications, violations to Technical Specifications, reportable occurrences and facility operations were reviewed as required by the Technical Specification No discrepancies were identifie isI