IR 05000335/1982005
| ML20054D811 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/25/1982 |
| From: | Bibb H, Dance H, Elrod S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20054D796 | List: |
| References | |
| 50-335-82-05, 50-335-82-5, 50-389-82-04, 50-389-82-4, IEB-78-03, IEB-78-09, IEB-78-11, IEB-78-13, IEB-78-3, IEB-78-9, IEB-79-08, IEB-79-10, IEB-79-12, IEB-79-18, IEB-79-20, IEB-79-22, IEB-79-26, IEB-79-8, IEB-80-01, IEB-80-07, IEB-80-1, IEB-80-13, IEB-80-14, IEB-80-22, IEB-80-25, IEB-80-7, NUDOCS 8204230405 | |
| Download: ML20054D811 (8) | |
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UNITED STATES
3, NUCLEAR REGULATORY COMMISSION G
z REGION 11 0,
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101 MARIETTA ST., N.W., SUITE 3100 b
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o ATLANTA, GEORGIA 30303 Report Nos. 50-335/82-05 and 50-389/82-04 Licensee: Florida Power and Light Company 9250 tiest Flagler Street liiami, FL 33152 Facility Name:
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 License Nos. DPR-67 and CPPR-144 Inspection at St. Lucie site nea Ft. Pierce, Florida Inspectors:
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S.A.'Elrod)
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Date Signed 5l75 (2-sci
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Date Signed A,nproved by:
O/2JIA H. C. Dance, Section Chf'ef, Division of Date Signed Project and Resident Programs Sullf1ARY Inspection on February 13, 1982 - flarch 10, 1982 Areas Inspected This routine, inspection involved 225 resident inspector-hours onsite in the areas of Followup of IE Bulletins, Plant Operations, Surveillance, Maintenance and Instrument Calibration.
Results Of the five areas inspected, no apparent item of noncompliance was identified.
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DETAILS 1.
Persons Contacted
Licensee Dnployees
- C. fl. Wethy, Plant Manager
- B. J. Escue, Site Manager, Unit 2 J. H. Barrow, Operations Superintendent
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J. E. Bowers, Maintenance Superintendent D. A. Sager, Operations Supervisor N. G. Roos, Quality Control Supervisor
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C. F. Leppla, Instrument and Control Supervisor P. L. Fincher, Training Supervisor R. R. Jennings, Technical Department Supervisor H. F. Buchanan, Health Physics Supervisor J. G. West, Security Supervisor
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J. Barrow, Fire Prevention Coordinator i
0. D. Hayes, Nuclear Plant Supervisor L. W. Pearce, Nuclear Plant Supervisor
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N. D. West, Nuclear Plant Supervisor
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C. L. Burton, Nuclear Plant Supervisor
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M. B. Vincent, Assistant Plant Superintendent - Electrical
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- T. A. Dillard, Assistant Plant Superintendent - ikchanical
- A. W. Bailey, Quality Assurance Supervisor
- P. Carrier, Licensing Engineer Other licensee employees contacted included construction craftsmen,
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technicians, operators, shift technicians advisors, security force members, j
and office personnel.
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- Attended exit interview
2.
Exit Interview
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The inspection scope and findings were summarized on liarch 12, 1982, with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings
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Not inspected.
4.
Unresolved Items i
Unresolved items were not identified during this inspection.
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Maintenance Observation a.
Station maintenance activities of safety-related systems and components listed below were observed / reviewed to ascertain that they were
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conducted in accordance with requirements.
The following items were considered during this review:
the limiting conditions for operation were met, activities were accomplished using approved procedures, functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; and radiological controls were implemented as required. Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety-related equipment maintenance which may affect system performance. The following maintenance activities were observed / reviewed:
(1)
Plant Work Order #2666 - Pump / Motor Shaft Re-alignment on lA High Pressure Safety Injection Pump.
(2) Plant Work Order #6714 - Troubleshot and Vented Pressurizer Pressure D/P Cells.
(3)
Plant Work Order #2656 - Repaired Leak on Gas Decay Tank Isolation Valve.
No violations or deviations were identified in this area.
b.
Instrument Calibration During a routine inspection of the boric acid makeup tanks, the inspector noted that the temperature controllers for the tanks had last been calibrated on the following dates:
Instrument No.
Calibration Date TIC-2206 12-6-73 TIC-2207 6-24-74 TIC-2208 6-24-74 TIC-2209 3-11-75 Further investigation showed that these instruments were not included in the Instrument and Control Departments Periodic Calibration Program even though a detailed plant calibration procedure existed - I&C Procedure 1400064, Rev.11., Installed Plant Instrument Calibration.
The manufacturer of the equipment, Foxboro Corporation, was contacted and stated that the instruments only needed recalibration after initial installation if significant physical damage was sustained.
The licensee, however, has since added these instruments to the calibration program on a once per 18 months frequency.
No violations or deviations were identified in this are,
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Plant liodification Activities
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The inspector observed activities under Plant Change 20-81.
This change replaced the springs in the ultimate heat sink valves with improved springs with a greater pre-load.
The purpose was to insure that the valves completely open in the future.
The inspector observed portions of the testing of the valves after modification.
No violations or deviations were identified in this area.
6.
Surveillance Observation During the inspection period, the inspector verified plant operations compliance with at least sixteen different technical specification requirements. Typical of these was confirmation of operability of the Auxiliary Feedwater Systen per Operating Procedure 0700050, Rev. 13, Auxiliary Feedwater Periodic Test; DNB Parameters, Accident tionitoring Instrumentation, Reactor Coolant System Chemistry and others.
l The inspector verified that testing was performed in accordance with adequate procedures, test instrumentation was calibrated, limiting conditions for operation were met, removal and restoration of the affected components were accomplished, test results met requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
No violations or deviations were identified in this area.
7.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the report period.
The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of the reactor, auxiliary and turbine buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that main-tenance requests had 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. The inspector walked down the accessible portions of the safety injection tank systems to verify operability. The inspector also witnessed portions of the radio-active waste system controls associated with radwaste shipments, and reviewed a liquid release made on 12/21/81 under liquid release Permit No. 81-43 to assure canpliance with 10 CFR 20 limits.
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The inspector conducted an in-depth review of Operating Procedure 0410021, Rev.17, Safety Injection Tank Normal Operation for accuracy, technical content and compatibility with the technical specifications. No dis-crepancies were identified.
It was noted, however, that four valves that were identified as " locked closed" (V-3830, 3881, 3908 and 3887 - SI Tank Drain Valves) were not included in Administrative Procedure 0010123, Rev. 28, Administrative Control of Valves, Locks and Switches. This was discussed with the Nuclear Plant Supervisor and he indicated that a procedure change would be forthcoming.
This will be verified during a future inspection and will be carried as Inspector Followup Iten 335/82-05-01. No violations or deviations were identified in this area.
8.
IE Bulletins The following IE Bulletin was reviewed to detendine whether it had been received and reviewed by appropriate management, responses, where necessary, were accurate and complete, and that action taken, if required, was complete.
(Closed - Unit 1) IE Bulletin 79-18 - Audibility Problems Encountered on Evacuation of Personnel from High-Noise Areas.
This IE Bulletin is closed based on modifications to the Unit 1 announcing system made by the licensee during the fall of 1981 and repairs made to several loudspeakers following the February 1982 General Emergency Drill.
The inspector has also witnessed tests in high-noise areas such as the Unit 1 feed pump area and CEA-drive motor-generator area. Open item 335/79-23-04 is closed also.
9.
IE Bulletins, Circulars and Information Notices - Unit 2 a.
The licensee has commenced a program to determine the functional applicability and present status of IE Bulletins, Circulars and Infomation Notices issued subsequent to the issuance of a construction permit for Unit 2.
Interviews with the Project Engineer for this effort show that the program is to include formal resolution of applicability, formal determination of actions required to comply with the requirements of suggestions, and formal documentation of completion of actions. The inspector reviewed the present records maintained by the project engineer and had no further questions at this time, b.
The following IE Bulletins and Circulars have not previously been addressed in inspection reports for St. Lucie Unit 2.
They have been reviewed by the licensee under the program discussed above.
(Closed - Unit 2) IE Bulletin 78-03 - Potential Explosive Itixture
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- BWR Offgas Operations. This IE Bulletin is closed as not applicable to pressurized water reactors.
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(Closed - Unit 2) IE Bulletin 78-09 BWR Drywell Leakage Paths -
Inadequate Closures. This IE Bulletin is closed as not applicable to pressurized water reactars such as St. Lucie Unit 2.
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(Closed - Unit 2) IE Bulletin 78-11 Examination of flark I
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Containment Torus Welds. This IE Bulletin is closed as not applicable to pressurized water reactors such at St. Lucie Unit 2.
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(Closed - Unit 2) IE Bulletin 78-13 Failures in source heads of KAY-RAY Inc. Guages. This IE Bulletin is closed as not applicable to St. Lucie.
(Closed - Unit 2) IE Bulletin 79-10 Requalification Training
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Program Statistics - This Bulletin requested one-time infonnation from operating plants.
It is not applicable to St. Lucie Unit 2.
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(Closed - Unit 2) IE Bulletin 79-12 Short Period Scrams at BWR Facilities - This IE Bulletin is not applicable to Pressurized
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Water Reactors such as St. Lucie Unit 2.
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(Closed - Unit 2) IE Bulletin 79-20 - Packaging, Transport and Burial of Low Level Radioactive Waste.
This IE Bulletin applies to materials licensees only.
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(Closed - Unit 2) IE Bulletin 79-22 - Possible Leakage of Tubes,f
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Tritium Gas used in timepieces for Luminosity.
This Bulletin is
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not applicable to power reactors.
(Closed - Unit 2) IE Bulletin 79-26 - Boron Loss from BWR Control
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Blades - This IE Bulletin is closed as not applicable to St. Lucie 2 which uses a different control configuration.
(Closed - Unit 2) IE Bulletin 80-01 - Operability of ADS Valve
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Pnuematic Supply (BWR). This IE Bulletin is not applicable f
because St. Lucie uses a different control configuration.
(Closed - Unit 2) IE Bulletin 80-07 - BWR' Jet Pump Assembly
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Failure - This IE Bulletin does not apply to PWRs.
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(Closed - Unit 2) IE Bulletin 80-13 Cracking In Core Spray
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Spargers - This IE Bulletin does not apply to PWRs.
(Closed Unit 2) IE Bulletin 80-14 Degradation of BWR Scram
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Discharge Volume Capability - This IE Bulletin does not apply to PWRs since they use a functionally different scram system.
(Closed - Unit 2) IE Bulletin 80-22 - Automation Industries sealed
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source connectors.
This IE Bulletin is closed as no applicable.
It applies only to Radiography licensees.
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(Closed - Unit 2) IE Bulletin 79-08 Events Related to Boiling
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Water Reactors Identified During the Three Mile Island Incident.
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This IE Bulletin is not applicable to Pressurized Water Reactor Plants.
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(Closed - Unit 2) IE Bulletin 80-25 - Operating Problems with Target-Rock Safety Relief Valves at BWRs. This IE Bulletin is not applicable to St. Lucie.
It refers to a special style valve used on BWRs.
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(Closed - Unit 2) IEC 77-02 and 77-02A Potential Heavy Spring Flooding. This IE Circular was not applicable to Plants in the Southeastern United States.
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(Closed - Unit 2) IEC 77-09 - Improper Fuse Coordination in BWR Standby Liquid Control Systems.
This IE Circular is not applic-able to pressurized water reactors.
(Closed - Unit 2) IEC 77-07 - Short Period During Reactor Startup.
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This IE Circular applies to Boiling Water Reactors.
It is not applicable to pressurized water reactors since they use a different control scheme.
(Closed - Unit 2) IEC 77-12 - Dropped Fuel Assemblies at BWR
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Facili ties. This IE Circular is not applicable to St. Lucie.
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(Closed - Unit 2) IEC 78-01 - Loss of Well-Logging Source. This IE Circular is not applicable to reactor plants.
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(Closed - Unit 2) IEC 78-10 - Control of Sealed Sources used in Radiation Therapy. This IE Circular is not applicable to power plants such as St. Lucie 2.
(Closed - Unit 2) IEC 78-11 - Recirculation ti-G set overspeed
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stops (BWR). This IE Circular is not applicable to pressurized water reactors. They have no such M-G set.
(Closed - Unit 2) IEC 78-13 - Inoperability of multiple service
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water pumps. This IE Circular is closed as not aplicable to power plants in the Southeastern United States.
(Closed - Unit 2) IEC 79-01 - Administration of Unauthorized
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Byproduct Material to Humans. This IE Circular applies to meoical licensees only.
(Closed - Unit 2) IEC 79-06 - Failure to use Syringe and Bottle
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shields in Nuclear itedicine - applies to medical licensees only.
(Closed - Unit 2) IEC 79-07 Unexpected Speed Increase of Reactor
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Recirculation MG set Resulted in Reactor Power Increase. This IE Circular is closed as not applicable to pressurized water'
reactors.
PWRs use a different system for control of power.
(Closed - Unit 2) IEC 79-14 Unauthorized Procurement / Distribution
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of Xe-133 - applies to medical 1icensees only, e
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(Closed - Unit 2) IEC 79-16 - Excessive Radiation Exposures to
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members of the General Public and a Radiographer.
This IE
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Circular is not applicable to power reactors.
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(Closed - Unit 2) IEC 80-06 - Control and Accountability systems for Implant therapy sources - applies to medical licensee only.
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(Closed - Unit 2) IEC 80-08 - Boiling Water Reactor Technical Specification Inconsistency - Not applicable to Pressurized Water
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Reactors.
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(Closed - Unit 2) IEC 80-19 - Noncanpliance with licensee requirements for medical licensees - not applicable to power plants.
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(Closed - Unit 2) IEC 80-20 - Changes in SAFE Slab Dimensions.
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This IE Circular applies to fuel facilities not to power plants.
(Closed - Unit 2) IEC 80-24 - AECL Teletherapy Unit Malfunction -
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This IE Circular is not applicable to power plants.
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- (Closed - Unit 2) IEC 80-25 - Case History of Radiography Events.
This IE Circular is not applicable to St. Lucie 2 - FPL is not a radiography licensee.
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