IR 05000261/1979002
| ML14175B022 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 01/31/1979 |
| From: | Dance H, Mcthenry T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B021 | List: |
| References | |
| 50-261-79-02, 50-261-79-2, NUDOCS 7903130093 | |
| Download: ML14175B022 (6) | |
Text
R REGQ UNITED STATES o0 NUCLEAR REGULATORY COMMISSION Al
REGION II
101 MARIETTA STREET, &
ATLANTA, GEORGIA 30303 Report No.: 50-261/79-2 Docket No.: 50-261 License No.:
DPR-23 Licensee:
Carolina Power and Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 Facility Name:
H. B. Robinson 2 Inspection at:
H. B. Robinson Site, Hartsville, South Carolina Inspector:
T. J. McHenry Approved by:
x H. C. Dance, Chief
/Date Inspection Summary Inspection on January 9-12, 1979 (Report No. 50-261/79-2)
Areas Inspected:
Routine unannounced inspection of licensee event followup; IE Circular followup; Open item followup; independent inspection effort and facility tour The inspection involved 29 inspector-hours onsite by one NRC inspecto Results: Within the five areas inspected, no items of noncompliance or deviations were identifie o3 1300'-3
RII Rpt. No. 50-261/79-02 I-1 DETAILS I Prepared by:
_____________
___
T. J. McHedify, Reactor Inspector Date Reactor Projects Section No. 1 Reactor Operations and Nuclear Support Branch Dates of Inspection: January 9-12, 1979 Reviewed by: f C4-4 ---
/3/t H.'C. Dance, Chief Date Reactor Projects Section No. I Reactor Operations and Nuclear Support Branch Persons Contacted
- R. B. Starkey, Jr., Plant Manager
- R. E. Morgan, Operations Supervisor
- C. W. Crawford, Maintenance Supervisor
- H. S. Zimmerman, Engneering 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. McGirt, Senior Nuclear General Specialist W. T. Traylor, Administrative Supervisor
- J. M. Curley, Senior Engineer F. Bishop, Electrical Engineer F. Lowery, Training Coordinator Several Control Room, Shift Foreman and Plant Operator *Denotes those present at the exit intervie.
Licensee Action on Previous Inspection Findngs No previous items of noncompliance or deviations were reviewed during this inspectio.
Unresolved Items No new unresolved items were identified during this inspectio RII Rpt. No. 50-261/79-02 1-2 Exit Interview A meeting was held on January 12, 1979, with Mr. R. B. Starkey, Plant Manager, and staff members denoted in paragraph 1. The scope and findings of the inspection activities presented in these details were discusse.
Review of Licensee Event Report (LER's)
The inspector reviewed five LER's for consistency with the requirements of Technical Specifications Section The inspector examined the licensee's analysis of the event, corrective action taken, and discussed the LER's with licensee's representatives. The following LER's were reviewed: LER 78-20, Service Water Valve (V6-12D) Failed to Open The information provided in this LER did not describe corrective actions taken to restore the inoperable service water header to operation. The inspector determined that the faulty service water valves were manually opened shortly after failure to restore the service water valves header to an operable status even though the valve actuator was not operable until several hours later. The inspector discussed the information requirements of LER's at the exit interview emphasizing the importance of including corrective actions for all affected components or system This LER is close LER 78-22, Primary to Secondary Leak on S/G A The inspector reviewed control room logs for August 21-22, 1978 to ascertain that plant logs reflected the occurrence as described in the LER. The inspector determined that control room logs confirmed assessment described in the LER. However, control room logs had several entries indicating values of leakage in excess of the limits prior to the final leakage determination upon which action was take It was determined that earlier values of leakage logged were not sufficient for an accurate evaluation. The inspector discussed the review of control room logs at the exit interview and the importance of providing adequate explanation for all values logged out of limits was discussed. This LER is close LER 78-27, Air Supply to RHR Valves Not Isolated The inspector reviewed OP-38C, Residual Heat Removal System operating procedure and determined that the procedure had been revised as stated in the LER. Corrective action to prevent recurrence of this event appears adequate. This LER is close.
RH Rpt. No. 50-261/79-02 1-3 LER 78-28, Broken IVSW Header Flow Indicator The inspector observed that the affected indicator was in opera tion during plant tour. In addition, it was determined that a design modification is being considered to bypass Isolation Valve Seal Water (IVSW) flow indicators such that an inoperable flow device will not render the header inoperable. This LER is close LER 78-29, Generic BFD Relay Problem The inspector reviewed PT-19.0 A/B, Reactor Protection Logic Test and determined that the periodic test had been revised as stated in the LER as the interim corrective action. The inspector stated the NRC is still evaluating the generic aspect and corrective actions required for this problem. Therefore corrective measures taken and proposed by the licensee is acceptable pending possible additional NRC corrective requirements. This LER is close.
Review of IE Circular (IEC)
The inspector reviewed IEC 78-18, UL Fire Test, with licensee personnel to ascertain that the IEC had been received onsite and reviewed by cognizant personnel. The inspector determined that the circular had been received, reviewed and forwarded to the engineering group respon sible for the fire protection design modification to be completed during next refueling. The inspector had no further questions on IE Circular 78-1.
Followup on Inspector Identified Open Items The inspector reviewed the licensee's status on the following open items to determine if corrective measures had been taken and/or if additional corrective measures are required: Item 50-261/78-10-01 This item involved apparent procedural conflicts between GP-1, Plant Startup and PT-R-6.0 Refueling Startup. The inspector reviewed proposed new procedure GP-3A, Plant Startup which contains steps necessary to clarify the use of PT-R-6.0. Since the new GP-3A is scheduled for final approval prior to the next refueling, this item is close Item 50-261/78-21-01 This item is based upon the inspectors committment to inspect implementation of the Inservice Inspection (ISI) program for pumps and valves following final program approval by NRC licensin RII Rpt. No. 50-261/79-02 I-4 Since the licensee is still under the requirements of the tenta tively approved ISI program, this item will remain open pending issuance of the final approval of the ISI progra Item 50-261/78-22-01 This item concerned the adequacy of the licensee's procedural instruction for emergency condition where a loss of site power may follow actuation of safety injection. The inspector reviewed EP-1, Incidents Involving Reactor Coolant System Depressurization and determined that the procedure had been revised to incorporate steps necessary to alert operators of actions required for loss of site power subsequent to safety injection actuation. This item is close Item 50-261/78-22-02 The inspector reviewed plant startup and emergency procedures to ascertain if adequate instruction were provided to recover from an inadvertant safety injection (SI) actuatio In addition, the recovery of the plant from inadvertant SI was discussed with several control room operators who had performed the recovery evaluation. Based upon these reviews and discussions, the inspector determined that exiting procedural guidance and operator training appear to be sufficient in the area of concern. This item is close.
Review of Plant Fire Procedures This item (50-261/78-24-01) was identified as unresolved and concerned whether existing plant procedures were acceptable for meeting the requirements of Regulatory Guide 1.33 which requires a plant fire emergency procedure. The inspector reviewed Plant Notice No. 5, Fire Station Bill and Volume 19, Fire Protection Manua In addition, several plant operators were questioned by the inspector to ascertain their level of familiarity with existing plant requirements for plant fires. Based upon these reviews and discussion it appears that existing procedures meet the requirement of providing approved emergency procedures for a plant fire. This item is close.
Welder Certification The licensee had identified a problem with the certification testing program for plant welders. Specifically, the licensee had determined that the existing welding certification testing program may not have been adequate to substantiate the certification of three welders. The inspector discussed this problem, including corrective actions taken,
RII Rpt. No. 50-261/79-02 I-5 with the QA Supervisor. The licensee's corrective actions and actions to prevent recurrence of this item appear to be adequate. The inspector had no further questions with regard to this ite. Facility Tours The inspector toured portions of the facility including the auxiliary building, turbine are and control room to ascertain the general state of cleanliness and housekeeping. Control room operations, including performance of plant-surveillance testing were observed and discussed with control room personnel to assure compliance with Technical Specifications. No problems were identified.