IR 05000261/1980022
| ML14175B190 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/11/1980 |
| From: | Brooks E, Quick D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B189 | List: |
| References | |
| 50-261-80-22, NUDOCS 8010270068 | |
| Download: ML14175B190 (5) | |
Text
REG&,
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION il 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report No. 50-261/80-22 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina Facility Name:
H. B. Robinson Docket No. 50-261 License No. DPR-23 Inspection at H. B. Robinson site near Hartsville, South Carolina Inspector:_______________________
E. H. Brooks Date Signed Approved by:
D. R.- Quick, Section Chief, RONS Branch date Signed SUMMARY Inspection on August 5-14, 1980 Areas Inspected This routine, announced inspection involved 92 (resident) inspector-hours on site in the areas of witnessing general plant operations, followup inspection of outstanding items, inspection of hydraulic supports and restraints, and witnessing portions of the safety injection test Results Of the 4 areas inspected, no items of noncompliance or deviations were identifie.o
DETAILS Persons Contacted Licensee Employees
- R. B. Starkey, Jr., General Manager
- G. W. Crawford, Manager, 0 & M
- H. S. Zimmerman, Manager, T & A
- J. M. Curley, Engineering Supervisor
- R. T. Connolly, Director, Nuclear Safety & QA
- F. L. Lowery, Operating Supervisor - Unit 2 R. Dayton, Engineer D. Baur, QA W. Garrison, QA M. Watford, Eng. Tec R. Chambers, Maintenance Supervisor Other licensee employees contacted included shift supervisors, reactor operators and health physics personne NRC Resident Inspector
- E. H. Brooks, Acting Resident Inspector
- Attended exit interview Exit Interview The inspection scope and findings were summarized on August 14, 1980 with those persons indicated in Paragraph 1 abov The inspection activities presented in these details were discusse.
Licensee Action on Previous Inspection Findings Not Inspecte.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviation New unresolved items identified during this inspection are discussed in paragraph.
Areas Inspected In the period August 5 to August 14, 1980, the inspector acted in the capacity of NRC Resident Inspecto Areas inspected are discussed in the following paragraph.
General Operations The inspector witnessed plant operations prior to and during plant shutdown for refuelin The plant was brought to zero percent power on August 8, 198 The type of activities performed included: Observation of control room activities and discussion with operating
, personne Review of shift supervisor logs and equipment-out-of service log c. Daily tour of auxiliary building during normal and backshift period Inspection activities in this area included observations of instrumentation operation and calibration, adherence to radiation controls, housekeeping, maintenance activities and securit No problems were identified within these area.
Review of Outstanding Open Items The inspector reviewed outstanding open items with licensee personnel. The following were reviewed: Evaluate audibility of evacuation alarms in high noise area Corrective action and testing performed and documented by licensee. This item was close Establish a cleanliness control program by 8-1-8 The licensee advised NRC by telephone on 8-25-80 that the clean liness control program was established on 8-18-8 This item will remain open subject to inspector followu Establish a program of trend evaluation by 8-1-8 The licensee advised NRC by telephone on 8-25-80 that the trend evaluation program was established on 8-18-8 This item will remain open subject to inspector followu Evaluation of torque switch settings (auxiliary feedwater motor operated valves LER 32, 33, 34) Evaluation not complete This item remains ope Drawing control progra The licensee's Quality Assurance representatives consider this item to be close However, the licensee was advised at the exit interview that conver sations with licensee personnel indicate that outdated drawings may still be in circulation within the plant and
-3 that the drawing control program is not effectively admin istered. The licensee-agreed to investigate and advise the NRC accordingly by Nov. 1, 1980. This item is considered to be unresolve (80-22-01) Safety Injection Tests The inspector witnessed safety injection testing with diesel generator startup on August 11, 198 Details of these tests are covered in inspection report 50-261/80-1.
Inspection of Pipe Support and Restraint Systems The inspector reviewed the licensee's surveillance activity for safety related piping supports and restraint This included a review of procedures for technical adequacy; examination of various installed dynamic and fixed supports and restraints; and review of recent surveillance record Following is a tabulation of the 29 safety-related hydraulic snubbers installed in the H. B. Robinson plant:
12 - Anker Holth (Steam Generators)
11 -
Grinnell 5 -
Blaw Knox or Power Piping 2 - Basic Engineers The inspector reviewed the latest Periodic Test Procedure CPL-PT-31.0, Revision 9, dated and approved on 1-16-80, entitled Inspection of Hydraulic Shock Suppressors Refueling Interval and as Required by Technical Specifi cation The status of the licensees program for inspection and testing of hydraulic snubbers as required by Technical Specifications is as follows: Inacessible Snubbers Inspected 7-11-79 (none inoperable)
Next Inspection due -
18 months Accessible Snubbers Inspected May, 1979 (none inoperable)
Next Inspection due 12 months Functional Testing Completed May, 1979 (one snubber failed test)
During functional testing snubber number 30 experienced a broken shaft during the compression test. This snubber was replaced with a spare and 3 additional snubbers were tested as required by the technical specification The additional snubbers were successfully teste S It was decided by the licensee to visually inspect all snubbers during the current outage even though inspection 'of the inaccessible snubbers was not
--due.
Two snubbers were found to be empty of fluid during this inspection and were declared inoperabl Accordingly, the licensee stated that a 30 day report would be submitted to the NRC and the next snubber inspection will be changed in accordance with the schedule dictated by the technical specification The inspector accompanied by licensee personnel performed an inspection of the safety related snubbers installed inside the reactor containment, and on feedwater and steam supply lines outside containment. Following are the results of this inspection: Snubber number 38, installed on the pressurizer relief line was found to have a loose lock nut and could possibly permit the snubber to become detached from its support bracke The licensee was advised that a positive locking device is required for all snubbers similarly affecte Snubber number 39, installed on the pressurizer relief line could not be checked for lockup since the snubber alignment was such that there was no end play and the snubber cylinder could not be rotate The licensee was advised that realignment of the snubber appeared to be necessary to assure snubber operabilit Five safety-related Blaw Knox snubbers installed in the H. B. Robinson plant are equipped with control valve adjustable "handwheels".
These
"handwheels" are easily rotated and can conceivably cause a change in the lockup and bleed settings of the control valves due to such causes as vibration, maintenance activities, and transporting during installa tion or functional testin The licensee was advised that this condition is unacceptable and that corrective action is required to assure that the control valve settings cannot be disturbed subsequent to snubber functional testin The licensee agreed to provide corrective action for the three conditions stated above prior to plant startu These items were identified as open pending licensee corrective action and inspector followup (80-22-02).