IR 05000261/1979009
| ML14175B055 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/21/1979 |
| From: | Martin R, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B054 | List: |
| References | |
| 50-261-79-09, 50-261-79-9, NUDOCS 7908170461 | |
| Download: ML14175B055 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
ATLANTA, GEORGIA 30303 Report No. 50-261/79-09 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. Robinson 2 Site near Hartsville South Carolina Inspectorb ar Approved by:
D. M r
, ection Chi
, RONS Branch Da-teSigned SUMMARY Inspection on May 7-9, 1979 Areas Inspected This routine, announced inspection involved 19.5 inspector-hours onsite in the areas of hydraulic shock suppressors, battery load testing and followup of inspector identified item Results Of the three areas inspected, no apparent items of noncompliance or deviations were identifie ;1
DETAILS Persons Contacted Licensee Employees
- R. Starkey, Jr., Plant Manager
- S. Zimmerman, Maintenance Supervisor
- W. Crawford, Operations Supervisor J. Hopkins, Nuclear Engineer R. McGirt, Nuclear Generation Specialist R. Dayton, Engineer M. Page, Engineer M. Watford, Engineering Technician P. Gerald, Electrician M. Grooms, Electrician
- Attended exit interview Exit Interview The inspection scope and findings were summarized on May 9, 1979, with those persons indicated in Paragraph I above. The inspector also discussed the status of items identified for followup inspections as delineated in paragraphs 3 and 7 of this report as follows: NRC Position: Low voltage alarms on "A" and "B" batteries must be tested to verify proper operation and setpoint Licensee Response: A plant work order has been issued to verify the proper operation and setpoints on "A" and "B" battery low voltage alarm Verification will be complete prior to plant startu NRC Position: Functional test data for snubbers must be compared with the architect engineers analysis to verify correct lockup and bleed velocitie Further, test data must be corrected for temperature to verify snubber performance in the operating environment is acceptable prior to leaving plant mode Licensee Response:
Architect engineer's analysis will be on site in one day. Acceptable performance of snubbers in the operating environment for all snubbers tested during this outage will be confirmed prior to plant heatu Subsequent to the inspection, the licensee's test engineer confirmed by in telephone on June 18, 1979, that the architect engineer has evaluated the snubber performance data and has determined that the snubbers will perform properly under expected operating condition q-2 Licensee Action on Previous Inspection Findings (Open)
Infraction (261/78-08-01):
Failure to Develop and Use a Procedure for Functional Testing of Hydraulic Suppressor The inspector found this item was incomplete during this inspection due to a delay in obtaining the architect engineer input for required lockup and bleed range (Closed) Infraction (261/78-08-02): Failure to Perform Timely QA Review of Plant Work Orders. The inspector found that the handling and QA review of plant work orders had been addressed in a memorandum from the Maintenance Supervisor to all Maintenance Foremen dated May 23, 197 (Closed)
Unresolved Item (261/78-08-03):
Determination of lifetime for non-ethylene propylene seal material used in Hydraulic Shock Suppressor The inspector found that the licensee had evaluated the lifetime of Vitan A seal material used in the steam generator snubber The Basic Engineer snubbers which contain non-ethylene propylene seal material were inspected on a 31 day frequency. The licensee intends to install ethylene propylene seals in the Basic Engineer snubbers during the current outag.
Unresolved Items Unresolved items were not identified during this inspectio.
Hydrualic Shock Suppressors The inspector reviewed the draft procedure CPL-PT-31.0 for inspection of snubbers for conformance with Technical Specification 4.1 The licensee stated that final approval of PT 31 could not be completed until data on the appropriate lockup velocities and bleed rates were obtained from the architect enginee This information was reportedly in the mai The inspector toured the containment and inspected about 30% of the snubbers and found no visable signs of leakage or deterioration. Since the licensee was awaiting final approval of CPL-PT-31.0 prior to performing the visual inspection and functional testing, data were not available for review at this tim The inspector will review the architect engineer's data, PT-31.0 and licensee test results at a future inspection (261/79-09-01) Station Battery Load Test The inspector reviewed the procedure for the station battery load test (CPL-PT-20.3)
observed portions of the test and reviewed the test results to verify that station batteries "A" and "B" meet the load requirements of the FSAR Section 8 and Technical Specification 4.6. The batteries carried the expected shutdown load for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> without terminal voltage falling below 105 volts and were recharged in about 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. One problem
-3 was identified in the test in that the low voltage alarm was not verifie The licensee issued a plant work order to verify operability of this alar This item will be reviewed at a future inspection (261/79-09-02).
7. Follow Up on Previous Inspection Items (Closed) Open Item (261/78-08-04):
Failure to Include Inspection of Snubber Ventholes in Procedure. The inspector's review of the approved final proce dure CPL-PT-31.0 shows that inspection of snubber vent holes is included in the procedur (Closed) Open Item (261/78-08-05):
Failure to Include Resetting of Nozzle Ring in Pressurizer Relief Valve in Test Procedure PT 2 Resetting and independent verification of nozzle ring has been included in PT 25. 1.