IR 05000324/1980035
| ML19340E929 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/04/1980 |
| From: | Kellogg P, Ouzts J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19340E928 | List: |
| References | |
| 50-324-80-35, 50-325-80-38, NUDOCS 8101160268 | |
| Download: ML19340E929 (6) | |
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UNITED STATES 4h t,
NUCLEAR REGULATORY COMMISSION
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101 MARIETTA ST N.W., SulTE 3100
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ATLANTA, GEORGIA 30303 Report Nos. 50-325/80-38 and 50-324/80-35 Licensee:
Carolina Power & Light Company 411 Fayetteville Street Raleigb, NC 27602 Facility Name:
Brunswick Units 1 and 2 Docket Nos. 50-324 and 50-325 License Nos. DPR-71 and DPR-62 Inspection at Brunswick site near Southport, North Carolina Inspector:
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P.p. fe p gg g on Chief, RONS Branch Datd Signed
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SUMMARY Inspection on October 1-31, 1980
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Areas Inspected This routine, announced inspection involved 109 inspector-hours on site in the areas of control room observations, review of plant logs, tours of vital areas, tours of physical security barriers, radiation protection, housekeeping and cleanliness, fire protection, followup on I&E Headquarters and Region II request, review and followup on licensee event reports (LERS), review of Bulletins,
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circulars and notices, discussions with licensee management, independent inspection effort, and review of Unit No. 2 trip.
Unit 1 Areas Inspected This routine inspection by the resident inspector involved 52 man hours of inspection time on site in the first twelve areas identified above.
Unit 1 Findings Of the twelve areas inspected no apparent items of noncompliance or deviations were identified.
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Unit 2 Areas Inspected s
I This routine inspection by the resident inspector involved 57 man-hours of
inspection time on site in thirteen areas identified above.
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Unit 2 Findings
Of the thirteen areas inspected no apparent items of noncompliance or deviations
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were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- A.
C. Tollison, Plant General Manager
- J. M. Brown, Operations Manager
- G. T. Milligan, Maintenance Manager
- R. E. Morgan, Manager of Operations
- G. Olliver, E&RC Manager AJ. A. Padgett, Director of QA and Safety
- W. M. Brown, Administrative and Technical Manager Other licensee employees contacted included construction craftsmen. two technicians, ten operators, two mechanic, four security force members, and
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four office personnel.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on October 10, and 22, 1980 with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the month of October.
The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of vital areas, diesel and reactor buildings and service water building were conducted to observe plant equipnent condi-tions, including potential fire hazards, fluid leaks, and excessive vibrations to verify that maintecance requeese t33 been initiated for equipment in need of maintenance.
The inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan.
The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls.
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-2-These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications, 10 CFR, and administrative procedures.
As a result of these inspections and reviews no items of noncompliance or
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deviations were identified.
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6.
Licensee Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accemplished, and corrective action to prevent recurrence had been i
accomplished in accordance with technical specifications.
Unit No. 1 Title LER No.
1-80-72 Containment atmosphere recorder 1-CAC-AR-1259 Calibration problem 1-80-78 Control rod position indication system reed switch problem Unit No. 2 Title LER No 2-80-52 Control rod position indication problem 2-80-61 Failure of suppression pool exhaust valve to shut due to failure of torque switch contact 2-80-63 Drywell atmospheric analyzer 2-CAC-AT-1259 instrument drift problem-2-80-64 Reactor low water level annunciator circuit ground problem 2-80-65 Containment atmospheric monitor 2-CAC-AT-1259 air Flow problem 2-80-67 RCIC injection valve 2E51 F0 13 failure to open due to missing jumper around torque switch contact 2-80-78 HPCI System turbine control valve problem resulting from cable connector problem 2-80-69 RCIC flow instrument square root converter module replaced with wrong module 2-80-70 ADS valve 2-B21-F013F failure to actuate due-to damaged actuator solenoid coil l
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-3-2-80-71 Suppression pool level instrument calibration problem 2-80-72 Long scram time for rod 38-15 of 13 seconds The corrective action inddicated for each of the above events was determined to be adequate. No items of noncompliance or deviations were identified.
7.
IE Bulletin Followup For the IE Bulletins listed below the inspector verified that the written reponse was within the time period stated in the bulletin, that the written response included the information required to be reported, that the written response included adequate corrective action commitments based on information presentation in the bulletin and the licensee's response, that licensee management forwarded copies of the written response to the appropriate onsite management representatives, that information discussed in the licensee's written response was accurate, and that corrective action taken by the licensee was as described in the written response.
IEB No.
Title IEB 80-17 and supplements Failure of control rods to insert during 1, 2, and 3 a scram at a BWR
, The action taken on this Bulletin was verified to be as' described in corre-spondence to NRC. No items of noncompliance or deviations were identified in the review of action taken by the licensee.
8.
IE Circular Followup
I For the IE Circulars listed below, the inspector verified that the Circular was received by the licensee management, that a review for applicability was performed, and that if the circular were applicable to the facility, appropriate corrective actions were taken or were scheduled to be taken.
IEC. No Title IEC 80-22 Confirmation of employee qualifications The licensee action to the above circular was determined to be adequate. No
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items of noncompliance or deviations were identified.
9.
Inspection of TMI Task action Plan Category "A" Requirements.
The inspector verified licensee action on category "A" requirements as l
covered in the TMI Task Action Plan (NUREG 0660) and requirements clarified
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in NRR's letter of September 5,1980, entitled " Preliminary Clarification of TMI Action Plan requirements".
The licensees actions were verified to be as described in correspondence to NRC. No item's of noncompliance or deviations were identified in the review of actions taken by the licensee.
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Plant Trips Following the Unit 2 plant trip at 0759 on October 28, 1980 the inspector ascertained the status of the reactor and safety systems by observation of control room indicators and discussions with licensee personnel concerning plant parameters, emergency system status and reactor coolant chemistry.
The inspector verified the establishment of proper communications and
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reviewed the corrective actions taken by the licensee.
All systems responded as expected, and the plant was returned to operation on October 29, 1980.
11.
Acceptance Criteria The inspector used one or more of the following sources,.of acceptance criteria for evaluating the above areas inspected.
a.
10 CFR 50, Appendix "B" b.
10 CFR 20 c.
Technical Specifications
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ANSI N45.2.3 (1971)
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ANSI N18.7 (1972)
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Regulatory Guides g.
Site Security Plan h.
Quality Assurance Program l
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