IR 05000261/1981021
| ML14176A666 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 08/28/1981 |
| From: | Bemis P, Upright C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14176A665 | List: |
| References | |
| 50-261-81-21, NUDOCS 8109240440 | |
| Download: ML14176A666 (5) | |
Text
REQ (IUNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report No. 50-261/81-21 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Facility Name:
H. B. Robinson Docket No. 50-261 License No. DPR-23 InspectionAt Robinso site near Hartsville, SC Inspe tgr y
P. R. Bem'
Date Signed Approved by:
- 6
'i C. M. Upright ecti4 Chief D e Sfgned Engineering I spect n Branch Engineering and Technical Inspection Division SUMMARY Inspection.on July 27-31, 1981 Areas Inspected This routine, unannounced inspection involved 44 inspector-hours on site in the areas of surveillance, calibration, and surveillance testing and calibration control program Results Of the three areas inspected, no items of noncompliance or deviations were identifie '8109240440 819 PDR ADOCK 050002 1
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REPORT DETAILS 1. Persons Contacted Licensee Employees
- F. Bishop, Unit 2, Senior Engineer, Maintenance
- R. Chambers, Unit 2, Maintenance Supervisor
- F. Gilman, Senior Specialist, Regulatory Compliance F. Lowry, Unit 2 Operations Supervisor
- R. Starkey, Plant General Manager
- C. Wright, Specialist, Regulatory Compliance J. Young, Director, Corporate QA/QC H. Zimmerman, Director Planning and Scheduling Other licensee employees contacted included shift foremen and maintenance planners-analyst NRC Resident Inspector
- S. Weise
- Attended exit interview 2. Exit Interview The inspection scope and findings were summarized on July 31, 1981 with those persons indicated in paragraph 1 abov.
Licensee Action on Previous Inspection Findings Not inspecte. Unresolved Items Unresolved items were not identified during this inspectio.
Surveillance (61700)
References:
a Technical Specifications Section 4 b
ANSI N18.7-1972, Administrative Controls and Quality Assurance for the Operating Phase of Nuclear Power Plants c
ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel d
PT21.2, Rod Control Cluster Exercise and Rod Position Indication, Revision 2, 6/75 e
PT33, Axial Power Distribution Monitoring System, Revision 2, 1/76 0)
f PT1.8, Nuclear Instrumentation System Power Range Axial Offset Calibration, Revision 2, 9/76 g
PT55, Steam Generator Water Level Protection Channel Testing, Revision 1, 4/75 h
PT8, Reactor Coolant System Leakage Evaluation, Revision 3, 10/78 i
PT5.1, T ave and Delta T Protection Channel Test, Revision 3, 7/76 j
PT2.11, Safety Injection System Integrity, Revision 0, 12/79 k
PT2.5, Accumulator Isolation and Check Valve Operability, Revision 4, 5/81 PT11.1, Containment Pressure Protection Channel Test, Revision 3, 4/75 m
PT3.1, Containment Spray System, Revision 3, 3/79 n
PT6.1, Underfrequency Test on 4KV Busses, Revision 4, 4/79 o
PT23.1, Emergency Diesels, Revision 6, 2/80 p
PT9.3A, Inspection of Fire Protection System, Revision 0, 2/81 q
PT9.4A, Unit 2 Portable Fire Extinguishers, Fire Hose, and Houses, Revision 0, 1/81 Using references d-q the inspector verified the following:
a. Properly approved surveillance procedures exist for the following systems:
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Reactivity Control and Power Distribution
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Instrumentation
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-
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Containment Systems
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Plant and Electrical Power Systems
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Fire Protection/Prevention System b. The procedures include the following:
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Prerequisites and preparations for each test
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Acceptance criteria
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Instruction to insure systems and/or components are restored to operation folloing testin C. The technical content assures compliance with the requirements of reference a. The inspector witnessed the test in reference 1 to verify the test procedure was in use, special test equipment was in service and calibrated., prerequisites were met and system restoration was correct. For completed tests in references d-q the inspector reviewed the tests for Technical Specifiction compliance, for appropriate action on any item failing acceptance criteria, and that tests were performed by qualified individual Based on this review and observation, no violations or deviations were identifie. Calibration (56700)
References:
a Technical Specifications Section 4 b
ANSI N18.1-1971, Selection and Training of Power Plant Personnel c
ANSI N45.2.4-1972, Installation, Inspection and Test Requirements for Instrumentation and Electrical Equipment During Construction of a Nuclear Power Plant d
PT1.8, Nuclear Instrumentation System Power Range Axial Offset Calibration, Revision 2, 9/76 e
PT5.6, Turbine First Stage Pressure Channel Testing, Revision 1, 4/75 f
PT5.1, T ave and Delta T Protection Channel Test, Revision 3, 7/76 g
PT5.7, Steam Generator Pressure Protection Channel Test, Revision 1, 4/75 h
PT11.1, Containment Pressure Protection Channel Test, Revision 3, 4/75 i
PT23.2, Emergency Diesel Auto Start on Loss of Power, Revision 3, 9/75 j
PT1.2A, Nuclear Instrumentation Power Range, Revision 1, 6/75 k
PT2.1, Safety Injection Test, Revision 1, 9/75
LP4-4, Calibration Procedure for Reactor Coolant Flow, Revision 0, 5/81 m
LP4-24, Calibration Procedure for Containment Pressure n
o PT2.8, RHR Component Test, Revision 5, 10/80 p
LP4-30, Turbine First Stage Pressure Calibration Procedure, Revision 0, 5/81 q
LP4-28, Steam Generator Pressure Calibration Procedure, Revision 0, 5/81 Using References d-k the 'inspector verified that the frequency of calibration specified in reference a has been met for the following systems:
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Reactivity control and power distribution
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Plant auxiliary. systems
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-
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Containment systems
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Plant and electrical power system In addition, the inspector reviewed completed test documentation for completeness, acceptance criteria met, use of properly approved revision, and verified qualifications of individuals performing calibration The inspector examined the technical content of reference j to determine if the procedures were reviewed and approved as required by Technical Specifications; if procedures contain controls to insure limiting conditions for operations were met; if procedures will result in satisfactory calibration; if as-found and as-left conditions were recorded; if calibration equipment was traceable; if instrument was properly returned to service; and, if calibration sheets were initialed to identify the instrument technician performing the claibration. The inspector witnessed the performance of reference Based on the review and observation, no violations or deviations were identifie. Surveillance Testing and Calibration Control Program (61725)
References a) Technical Specifications Section 4 and Section 6 b)
ANSI N18.7-1972, Administrative Controls for Nuclear Power Plants c) Regulatory Guide 1.33 Appendix A, Typical Procedures for Pressurized Water Reactors The inspector verified that a master schedule for surveillance testing/calibration/inservice inspections required by Technical Specifications and 10 CFR 50.55a had been established which included frequency of tests, group responsible for test, and test statu The inspector reviewed the licensee's program to determine if formal requirements had been established for conducting tests and calibration with approved procedures and if formal methods have been defined for review and evaluation of tests and calibration The inspector also reviewed the licensee's program, which is under development, for calibration of safety related components not identified in Technical Specification Even though the program is not complete, it appears to be moving in an acceptable directio Based on this review, no violations or deviations were identified.