IR 05000261/1979018
| ML14175B092 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/12/1979 |
| From: | Messitt B, Moon B, Ruhlman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B091 | List: |
| References | |
| 50-261-79-18, NUDOCS 7910250032 | |
| Download: ML14175B092 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report No. 50-261/79-18 Licensee: Carolina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 Facility Name: H. B. Robinson Unit 2 Docket No. 50-261 License No. DPR-23 Inspection at H. B. obin n site near Hartsville, South Carolina 29550 Inspectors:
.4 B. R. M ssit Date Signed Aproedby T. moon IDate Signed Approved by:
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,(..Ruh an, A tin Section Chief Date Signed fRONS Branch SUMMARY Inspection on August 27-28, 1979 Areas Inspected:
This routine, uannnounced inspection involved 24 inspector-hours onsite in the areas of surveillance of in-plant, technical specification required systems (equipments).
Results Of the one area inspected, no apparent items of noncompliance or deviations were identifie DETAILS Persons Contacted Licensee Employees R. B. Starkey, Plant Manager
- C. W. Crawford, Operating Supervisor
- J. M. Curley, Engineering Supervisor
+*B. W. Garrison, Quality Assurance Supervisor W. T. Traylor, Administrative Supervisor C. Wright, Engineering Technician
- H. S. Zimmerman, Maintenance Supervisor Other licensee employees contacted included technicians, operators and office personne *Attended exit intervie +Acted for Plant Manager at exit intervie.
Exit Interview The inspection scope and findings were summarized on August 28, 1979 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 Test Procedure and Results Verification Review Conducted The inspectors conducted a review of the following surveillance procedures and results:
PT 1.7, Power Range Calculation During Power Operations PT 1.4, Nuclear Instrumentation Comparator Channel PT 1.8, NIS Power Range Axial Offset Calibration PT 2.1, Safety Injection Test
-2 PT 2.5, Accumulator Check Valve Operability PT 5.1, T Average and Delta T Protection Channel Testing PT 2.7A, Safety Injection System Component Test PT 2.8A, Residual Heat Removal System Component Test PT 5.4, Reactor Coolant Flow Protection Channel Testing PT 6.1, Under Frequency Test on 4KV Busses PT 8.0, Reactor Coolant System Leakage Evaluation PT 9.0, Fire Protection Pump and Power Supply PT 10.1A, Containment Fan Coolers PT 11.1, Containment Pressure Protection Channel Testing PT 23.2, Emergency Diesel Auto Start on Loss of Power and Safety Injection Emergency Diesel Trips Defeat PT 33.0, Axial Power Distribution Monitoring System The inspectors monitored the Performance of portions of the following surveillance tests conducted on August 28, 1979:
PT 19 A/B, Reactor Protection Logic Train "A" and "B" PT 23.1, Emergency Diesels The inspectors also conducted a review of training records for five reactor operators and technician The test procedures and test results were reviewed to verify:
That test prerequisites and plant conditions were specified and reviews and approvals had been performed; That contents of the procedures were correct and the tests were performed on schedule; That test instruments were listed in the procedures and instruments used were identified in the results; That test results were recorded and compared with acceptance criteria and the return of the system/equipment to service and removal of test equipment was verified upon cbmpletion
of the tes The inspectors used one or more of the following acceptance criteria for the above items:
ANSI N18.7 (1972)
ANSI N1 H. B. Robinson, Plant-Operating Manual Vol. 11, "Continuing Quality Assurance Program" H. B. Robinson, Plant Operating Manual Vol. 10, "Periodic Tests" Technical Specifications ANSI N45.2 (1971) Inadequate Data Review The inspectors found that the plant reviews conducted on the following procedure data sheets were not adequate in terms of identifying incor rect data recording and timeliness of the revie A signature by the performing individual is missing on Form 1.8-4 of PT 1.8, Calorimetric Data, which was completed on 4/6/7 Performing individual's initials are recorded at the places where flow rates are required to be entered (GPM).
These were found in Step 7.1.3 of PT 2.8A performed on 5/23/79 and in Step 7.1.1 of PT 2.7A performed on 5/24/79 respectivel The first level review and approval was not done expeditiously on PT 1.8 (Step 5.5) which was completed on 4/10/79. The review was done 36 days later 5/16/7 These items are similar to an item of noncompliance 261/79-10-01 dealing with inadequate review Since these items all occured prior to the licensee response to 261/79-10-01 they will be considered further examples of inadequate review of completed dat Procedure Housekeeping During the above review the inspectors noted that PT 33.0, "Axial Power Distribution Monitoring System" was written such that the acceptance criteria did not recognize the presence of an insignificant computer round off error. This deficiency was brought to the licensee attentio The licensee initiated an immediate procedure change to include this ropoof e~of T4i s j4ejp ir jp