IR 05000261/1978017
| ML14175A973 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/08/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175A969 | List: |
| References | |
| 50-261-78-17, NUDOCS 7810230027 | |
| Download: ML14175A973 (5) | |
Text
kR UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report No.:
50-261/78-17 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, Inspection conducted:
August 1-4, 1978
.
Inspector: T. J. McHenry Reviewed by: 4 L-H. C. Dance, Chief Da e Reactor Projects Section No. 1 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on August 1-4, 1978 (Report No. 50-261/78-17)
Areas Inspected:
Routine, unannounced inspection of procedure administra tive controls; followup on reportable occurrences; followup on IE Bulletins and Circulars; independent inspection effort and facility tours. The inspection involved 32 inspector-hours on site by one NRC inspecto Results: Of the five areas inspected, no items of noncompliance or devia tions were identified in four areas; one apparent item of noncompliance was identified in one area (Infraction: Failure to distribute and/or use current revisions of plant procedures (78-17-01)).
RII Report No. 50-261/78-17 I-1 DETAILS I Prepared by:
2-7-7n T. J. McHe y, Reactor In ector Date Reactor P ojects Section No. I Reactor Operations and Nuclear Support Branch Dates of Inspection:
Au ust 1-4, 1978 Reviewed by:
4 C Ib&i.-fc 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 C. W. Crawford, Maintenance Supervisor H. S. Zimmerman, Engineering Supervisor
- B. W. Garrison, Quality Assurance Supervisor D. S. Crocker, Environmental and Radiation ControlbSupervisor C. Wright, Engineering Technician
- M. Page, Engineering Technician Several control room shift foreman and operators
- 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 4, 1978, with Mr. R. B. Starkey, Plant Manager, and staff members denoted in paragraph 1. Items covered by this inspection were discussed, including a new noncompliance concerning distribution and use of plant procedure.
Plant Procedures The inspector reviewed selected copies of the licensee's procedure Procedures were reviewed for compliance with Technical Specification
RIl Report No. 50-261/78-17 1-2 6.8 and Administrative Instruction, Section 5.0 (Operating Manual).
Selected procedures included Operating, Abnormal, Emergency, Maintenance, Periodic Test and Administrative procedure During the review of plant administrative procedures for controlling issuance of revisions and changes to plant procedures, the inspector noted that no written administrative system existed for controlling the distribution and use of procedures contained in working file Several working files containing selected procedures of the type that are written on such as periodic tests, check sheets, etc. are maintained in various plant location The inspector reviewed selected copies of procedures in the control room file for revision status as compared with the current revision contained in the operating manua The following discrepancies were identified in implementing the requirements of ANSI-N18.7 Section as required by Technical Specification 6. PT-40.0 (Inservice Quarterly Valve Test) was revised to revision 1.1 on April 18, 1978. However, the control room working files contained only copies of the superceded revision zero. In addition this procedure had been performed on June 28, Q978, using the superceded revision zer PT-2.7C (Safety Injection System Component Test) was revised to revision 1.4 on June 30, 1978. The control room file had only copies of the superceded revision This procedure had not been performed using the superceded revision. This procedure had been revised to prevent inadvertant dilution of the Boron Injection Tank which had resulted in two previous reportable occurrence The above two items have been identified as an infraction in the Notice of Violation (78-17-01). Review of Licensee Event Reports (LER's)
The inspector reviewed two LER's for consistency with the requirements of Technical Specification Section 6.9. The inspector examined the licensee's analysis of the event, the corrective action taken, and discussed the LER's with licensee representatives. The following LER's were reviewe LER 78-15, Engine Driven Fire Pump Failure to Start This LER closed without commen RII Report No. 50-261/78-17 1-3 LER 78-03, Overpressurization During SI Periodic Test The inspector reviewed this LER with the licensee and determined that plant design modification had been performed as specified as part of the LER corrective action. However, revision of PT- (Safety Injection Test-Refueling) had not been performed as specified as part of the LER corrective action. This LER will remain open pending revision of PT-.
Review of IE Circulars and Bulletins The inspector reviewed applicable IE Circulars with licensee personnel to ascertain that they have been received on site and reviewed by cognizant supervisory personnel. The licensee's actions on the following IE circulars were reviewed:
Circular N Subject 78-05 Inadvertent SI During Plant Cooldown 78-06 Common Mode Flooding of Equipment Rooms 78-07 Damaged Components of Bergen-Patterson Series 25000 Hydraulic Test Stand 78-09 Arcing of General Electric NEMA Size 2 Contactors The inspector has no further questions on the above IE Circulars since they have been received and reviewed by cognizant supervisory personne The inspector reviewed IE Bulletin 77-08 (Assurance of Safety and Safeguards During an Emergency-Locking Systems) to ascertain the status of design modifications specified in the licensee's response to this bulletin. The inspector reviewed this bulletin with plant personnel and determined that part of the required modification was in progress but entire modifications would not be completed until approximately April of 197 This bulletin will remain open pending completion of design modification.
Facility Tours The inspector toured portions of the facility, including the auxiliary building, spent fuel pool and control room on both day and evening shifts to ascertain the general state of cleanliness and housekeepin Control room operations and indicated parameters were observed and discussed with control room personnel to assure compliance with Technical Specifications. No problems were identifie RII Report No. 50-261/78-17 1-4 Plant Startup Following Reactor Trip The reactor tripped at 3:06 PM on August 1, 1978, due to a main turbine trip caused by high steam generator level. The inspector observed control room operations following the reactor trip to assure compliance with applicable procedures and Technical Specification requirement The cause of the reactor trip was attributed to a temporary erroneous low level in a steam generator (caused by a personnel door modification near the instrumentation cabinets) which caused excessive feeding of the affected steam generator resulting in a high level turbine trip-reactor trip. The plant was stabilized in hot shutdown. No problems were identifie The inspector return to the site during evening shift to observe the plant startup to ascertain compliance with applicable procedures and Technical Specifications. The inspector observed performance of periodic surveillance testing required prior to startup, verification of various pre-startup checklists and procedure adherence during the reactor startup. No problems were identifie e.