IR 05000261/1979021
| ML14175B106 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/16/1979 |
| From: | Kellogg P, Mchenry T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B105 | List: |
| References | |
| 50-261-79-21, NUDOCS 7912050119 | |
| Download: ML14175B106 (7) | |
Text
oi CUNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report No. 50-261/79-21 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 Facility Name: Robinson Docket No. 50-261 License No. DPR-23 Inspection at Robinson & te Har eville South Carolina Inspected by:
T. J Dat Si ned Approved by: ogg, Se on ief, RONS Branch Da e S gned SUMMARY Inspected on September 18-21, 197 Areas Inspected This routine, unannounced inspection involved 30 inspector-hours onsite in the areas of plant operations, periodic and special reports, licensee event reports, IE Bulletins and Circulars, previous enforcement matters, and outstanding item Results Within the six areas inspected, no apparent items of noncompliance or deviations were identifie /1
DETAILS Persons Contacted Licensee Employees R. B. Starkey, Jr., Plant Manager
- 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 F. Bishop, Electrical Engineer F. Lowery, Training Coordinator Other licensee employees contacted included operators, security force members, and office personne *Attended exit intervie.
Exit Interview The inspection scope and findings were summarized on September 21, 1979 with those persons indicated in Paragraph 1 above. The inspection activities presented in these details were discusse.
Licensee Action on Previous Inspection Findings (Closed) Infraction (78-17-01): Failure to distribute and use revisions to plant procedures. The inspector reviewed selected copies of procedures in the control room working copy file and verified that only current revisions existed in the file. A similar audit of the control room working file was also performed during inspection 50-261/ 79-0 Based upon these audits it appears that the licensee's corrective actions in regard to this item are satisfactor (Closed) Infraction (79-11-01):
Procedure changes without Plant Nuclear Safety Committee review and plant manager approval. The inspector verified that OP-7A valve checklist had been revised to require diesel day tank drain valves to be locked. The inspector also verified that OP-14 had been revisied to assure proper alignment of the motor-driven auxiliary feedwater pump discharge valves. This item was also reviewed during inspection 50-261/79-17. The inspector determined that appropriate locking devices and procedual controls had been established for the turbine-driven auxiliary feedwater pump discharge valv (Closed) Deficiency (79-11-03): Failure of maintenance procedures to restore systems to an operable alignment. The inspector reviewed selected Operating Work Procedures (OWP's) and verified that they had been reviewed and revised as required to assure that component restor ation to an operable alignment following maintenanc (Closed) Unresolved Item (79-11-08): Missing valve identification tag This item was identified during the 1979 refueling outag Subsequent inspection of valve tagging indicated that equipment was tagged and properly identified consistent with plant requirement The missing tags noted during inspection 50-261/79-11 had apparently resulted from losses caused by the extensive refueling maintenance and design modification activitie Since tags had been replaced, it appears that the licensee's existing tagging program meets the require ments of 10 CFR 50, Appendix B, Criterion XI.
Unresolved Items Unresolved items were not identified during this inspectio.
Review of Plant Operations The inspector reviewed the following areas of plant operation to ascertain whether facility operation was in conformance with applicable regulatory requirements and licensee commitments: Operating Logs and Records The inspector reviewed the following operating logs and records to ascertain whether plant operation was in conformance with Technical Specifications and administrative licensee requirements:
-Shift Foremen logbook July 25 - September 9, 1979-Control Room Operator logbook August 25-September 20, 197-Control Room Hot Operation Data log August 1-31, 1979-Auxiliary Operator-Outside Data log August 1-31, 1979-Auxiliary Operator-Inside Data log August 1-31, 1979-Equipment Inoperable Report Forms July 1-September 20, 1979 The inspector reviewed operating logs to insure that logged data was recorded in sufficient detail to communicate equipment status and properly reviewed by supervisory personnel. In addition, logs were reviewed to insure that logged information did not conflict with Technical Specification requirements. The inspector reviewed plant Trouble Tickets and Equipment Inoperable Report Forms to insure that applicable Technical Specifications including reporting requiremens were adhered to for inoperable equipmen No problems were identified in this are * Facility Tours The inspector conducted several facility tours during normal and backshifts. Inspection activities in this area included observation to insure that; instrumentation was operating and calibrated as re quired, radiation controls were established and properly adhered to, fire protection equipment was located as specified and appeared oper able. In addition, selected valves, breakers and control switches were verified to be properly aligned as required by Technical Speci fications and plant procedure No problems were identified within this are Control Room Operations Control room operations were observed and discussed with control room personnel to assure compliance with Technical Specifications and plant administrative requirements. Inspection activities in the control room included observation of selected instrumentation to assure plant operation within required limits, observation of surveillance testing and shift turnover, verification of control room manning in conformance with the requirements of 10 CFR 50.54(k), IE Bulletin 79-06C and discussions with control room operators pertaining to selected parame ters and annunciator No problems in this area were identifie.
Review of Licensee Event Report (LER's)
The inspector reviewed five LER's for consistency with the requirements of Technical Specification Section 6.9. The inspector examined the licensee's analysis of the event, corrective action taken, and discussed the LER's with licensee representatives. The following LER's were reviewed: LER 79-24 and 79-25, Failure to Perform Fire Patrols The current implementation and controls to assure completion of re quired fire patrols was reviewed. The fire patrols are being conducted in accordance prescribed check lists and hourly reports to be shift foreman made to assure completion of the required inspections. This LER is close LER 79-26, Snubber Failure During Functional Test This event was discussed by telephone with the licensee staff on September 20, 1979, in order to ascertain the status of investigation regarding generic concerns identified. Licensee representative stated that a supplemental response would be submitted as soon as the affected snubbers could be rebuilt and tested. During the onsite inspection it was determined that the snubber failure had been caused by the test method. Licensee representatives stated that the details of the
-4 failure mechanism involved in testing would be addressed in the sup plemental response. This LER will remain open pending a review and inspection to followup on the supplemental respons LER 79-28, Nitrogen to Accumulators Fill Valve Stuck The nitrogen to accumalators valve was still in an inoperable statu The inspector verified that required manual valves were locked closed as required by the Technical Specifications. Several plant operators were questioned by the inspector to insure that they were aware of the valve inoperability and associated requirements. The inoperable valve was scheduled for repair when plant conditions permit. This LER is close LER 79-30, Service Water Booster Pumps Inoperable Review of plant logs indicated that a calibration check was performed on the low suction pressure trip switches on both pumps subsequent to loss of both pumps. A review of as-found calibration data indicated that no calibration of the pressure switches was required. In addition, evaluation of possible design or procedure change were still under consideration. This LER is close. Review of Monthly Operating Reports The inspector reviewed monthly operating reports from September, 1978 through August, 1979 for consistency with the requirements of Technical Specification 6.9.1.c. The reports were discussed with a licensee repre sentative. The inspector reviewed selected logs and records to verify the accuracy of information provided in the reports and selected computations were checked to verify their accuracy. No problems were identifie In addition, a review of unplanned reactor trips was performed to determine the cause and to evaluate the licenee's corrective actions to prevent recurrence. During the one year period reviewed, the plant had experienced eight unplanned reactor trips. The inspector catagorized the cause of the eight reactor trip as follows: Four trips due to equipment malfunctio Two trips due to design problem Two trips due to personnel erro A review of Unit Outage Reports for the above events was conducted to ascertain corrective actions taken. In addition, the inspector discussed corrective actions described in the Unit Outage Reports to verify that corrective actions had been completed. Based upon the review of reactor trips, Outage Reports and discussions with plant personnel it appear that plant management is responsive in taking corrective action to prevent recurrence of unplanned reactor trip *
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8. Review of Special Report A Special Report dated August 27, 1979 required by Technical Specification 3.14, Fire Protection System, was reviewed and discussed with a licensee representative to ascertain the current status of the fire protection system. The inoperable systems described in paragraphs 1, 2 and 3 of the special report had been returned to operable status as required by the Technical Specifications. However, two items in the special report re mained incomplete. In order to insure that all items required would be completed, the following items were identified as open (50-261/79-21-01). Installation of heat detectors in the drumming room in lieu of smoke detector Evaluation and upgrading of Halon system to provide an accepable concentration following actuatio.
Review of IE Bulletins (IEB's) IEB 77-08, Assurance Locking System Safety and Safeguards during an emergenc The licensee's response to this IEB was reviewed during inspection 50-261/78-17. However, this item remained open pending installation and testing of additional locking systems during the 1979 refueling outage. The inspector determined that actions required by IEB 77-08, items 1.a.(1), 1.a.(2), 1.b, 2, 3, and 4 had been completed. However 1.a(3) - provision for periodic testing of locking system capability to switch to auxiliary power was still under evaluation. The ability to transfer locking systems to auxiliary power had been demonstrated during pre-operational testing. Further the licensee had originally intended to test this feature monthly; however, system design was determined to make monthly testing impractical. In order to simplify closure this item, IEB 77-08 was closed and the establishement of a periodic testing program for the auxiliary power to locking systems was identified as an open item (50-261/79-21-02). IEB 79-05,79-05A, 79-05B, 79-08 and 79-12 These IEB's were issued to the licensee for information only. The inspector verified that each bulletin had been received and reviewe Since no actions were required by the licensee, these IEB's were close. Review of Outstanding Open Items Item 79-08-01, Reactor Vessel 900F Limitation The inspector reviewed FT-9.4 (Reactor Vessel Stud Removal and Replacement) and verified that a procedure change had been implemented requiring direct verification of reactor vessel head and closure stud
~1-6 temperatures prior to full tensioning. In addition, a revision to GP-6 (Plant cooldown) was under consideration to caution operators to not cooldown below 900 F with closure studs fully tensioned. This item is close Item 79-11-06, Electrical Distribution Manaul A review was performed to ascertain the use of the Electrical Distribution Manual for plant activities and to ascertain the type of document controls established. It was determined that the Electrical Distribution Manual was routinely utilized by operating personnel to identify power supplies to plant loads. Further, the inspector deter mined that no formal administrative controls existed to insure periodic review or revision. In addition, control of the number and holders of copies did not exis This item was discussed with the Plant Manager and at the exit interview. The licensee committed to perform a timely review of the use and distribution of the Electrical Distribution Manual and to implement appropriate document control measures. This item remains open pending a review of licensee actions with regard to this ite Petroleum Jelly In Certain Relays The item was reviewed due to NRC concern of a potential problem as sociated with the use of petroleum jelly to lubricate certain General Electric induction relay The inspector discussed this item with the plant engineer responsible for electrical equipment. It was deter mined that no relays of the type described were utilized. Further, petroleum jelly was not used as a lubricant for any plant electrical equipment. This item is close.
Observation of Plant Fire Drill The inspector observed an unannounced fire drill that was conducted on September 20, 197 The drill consisted of a actual fire in a 55 gallon drum in an open area inside the Unit 2 protected area. The inspector observed the plant response and actions with regard to the fire and veri fied that actions were in accordance with the requirements of the Plant Fire Protection Manual. Two hose stations were utilized and the fire was extinguished. No problems were identified.