IR 05000335/1982021
| ML20058C028 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/30/1982 |
| From: | Bibb H, Elrod S, Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058C020 | List: |
| References | |
| 50-335-82-21, 50-389-82-26, NUDOCS 8207260233 | |
| Download: ML20058C028 (4) | |
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UNITED STATES p-NUCLEAR REGULATORY COMMISSION
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E REGION 11 101 MA RIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 30303
Report Nos. 50-335/82-21 and 50-389/82-26 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33152 Facility Name:
St. Lucie Unit 1 and 2 Docket Nos. 50-335 and 50-389 License Nos. DPR-67 and CPPR-144 Inspection at St. Lucie site year Ft. Pierce, Florida (,!Ja/gL Inspectors:
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T) ate Signed S. A. Elrod i
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/!86 H. E. Bibb f
Date Signed C 'W'M b/3#[P
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Approved by:
C. A. Juliin, Section Chief, Division of Date Signed Project and Resident Programs SUMMARY Inspection on May 15 - June 10, 1982 Areas Inspected This routine, inspection involved 252 resident inspector-hours on site in the areas of Maintenance observation, Surveillance Observation, Safety Verification, IE Information Notices and Circulars, Preoperational testing.
Results Of the five areas inspected, no violations or deviations were identified.
8207260233 820630 PDR ADOCK 05000335 G
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DETAILS 1.
Persons Contacted Licensee Employees
- C. M. Wethy, Plant Manager
- J. H. Barrow, Operations Superintendent J. E. Bowers, Maintenance Superintendent D. A. Sager, Operations Supervisor
- N. G. Roos, Quality Control Supervisor 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 J. Barrow, Fire Prevention Coordinator
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O. D. Hayes, Nuclear Plant Supervisor L. W. Pearce, Nuclear Plant Supervisor N. D. West, Nuclear Plant Supervisor C. L. Burton, Nuclear Plant Supervisor M. B. Vincent, Assistant Plant Superintendent - Electrical T. A. Dillard, Assistant Plant Superintendent - Mechanical A. W. Bailey, Quality Assurance Supervisor Other licensee employees contacted included construction craftsmen, technicians, operators, shift technical advisors, security force members, and office personnel.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 10, 1982, with those persons indicated in paragraph 1 above.
3.
Maintenance Observation Station maintenance activities of safety-related systems and components listed below were observed / reviewed to ascertain that they were conducted in accordance with requirements. The following items were considered during this review: that the limiting conditions for operation were met; that activities were accomplished using approved procedures; that functional testing and/or calibrations were performed prior to returning components or systems to service; that quality control records were maintained; that activities were accomplished by qualified personnel; that parts and materials used were properly certified; and that 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
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equipment maintenance which may affect system performance. The following maintenance activities were observed / reviewed:
a.
Plant Work Order 7297 - Repair valve position indication component cooling water to 1A1 reactor coolant pump seal, b.
Check nozzle ring settings on pressurizer code safety valves.
c.
Repair leak on pressurizer spray line flow control valve.
d.
The inspector reviewed licensee actions taken to investigate the operability of steam generator blowdown line B-1 (2 inch).
The review included interviews with maintenance supervisors, quality control inspectors, and engineers that were involved. Documents reviewed included:
Plant work orders 3964, 3972, and 3922 of May 1982 Quality control reports 11044 and 11049 Plant change / modification 68-82 EBASCO services letter SL-BF-82-191 of May 25,1982 Facility Review group minutes 82-47 (PCM 68-82)
e.
During a licensee surveillance, the licensee determined that two mechanical snubbers numbered 143 and 186, were immovable. These snubbers are on the 1A steam generator blowdown line.
During subsequent operability evaluation by the Architect / Engineer, restraints B1-H3, B1-H4, B2-H2, B2-H8, and B2-H7 were also found to need repair.
Licensee records and interviews with the licensee's staff show that repairs and formal analysis of system operability were accomplished prior to startup on May 24, 1982.
f.
The inspector observed that many restraints incorporate a finned clamp, usually forming a cross. This clamp is installed on the pipe with a close fit inside an opening fabricated as part of the restraint.
If the finned clamp loosens on the pipe, the clamp may rotate.
This is not viewed as a problem if the restraint opening is round, however some restraint openings are fabricated with one or more flat sides.
Clamp rotation then disables the restraining function.
Such rotation was reported to have occurred on restraints B1-H3 and B2-H2 which have flat surfaces. Considering the reported actual occurrences above, the licensee was requested to evaluate the adequacy of the existing restraint design. This will be followed up during a future inspection.
335/82-21-01.
No violations or deviations were identified in this are.
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4.
Surveillance Observation During the inspection period, the inspector verified plant operations compliance with at least sixteen different technical specification require-ments. Typical of these was confirmation of compliance with the Technical Specification for reactor coolant system leakage, reactor coolant chemistry, refueling water tank, containment pressure, control room ventilation and AC and DC electrical sources. The inspector verified that testing was performed in accordance with adequate procedures, test instrumentation was-calibrated, limiting conditions for operation were met, removal and restora-tion 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.
5.
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. The tours also verified that maintenance 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 component cooling water system to verify operability. The inspector also witnessed portions of the radio-active waste system controls associated with radwaste shipments.
No violations or deviations were identified in this area.
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8.
IE Information Notices s
a.
(Unit 1) The following IE Information Notices were reviewed to ensure their receipt and review by appropriate management.
IE Information Notices are considered closed upon receipt and review.
Information Notice No.
Subject 82-12 Surveillance of Hydraulic Snubbers
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82-11 Potential inaccuracies in wide range pressure instruments used in Westinghouse designed plants 82-10 Following up symptomatic repairs to assure resolution of the problem 82-09 Cracking in Piping of Makeup Coolant lines at B&W Plants 82-08 Check Valve Failures on Diesel Generator engine cooling system 82-07 Inadequate Security Screening Programs 82-06 Failure of Steam Generator Primary side Manway Closure studs 82-05 Increasing frequency of drug-related incidents 82-04 Potential deficiency of certain AGASTAT E-7000 series time-delay relays 82-03 Environmental tests of electrical terminals blocks 82-01 Auxiliary feedwater pump lockout resulting from Rev. 1 Westinghouse W-2 switch circuitry modification 80-32 Clarification of certain requirements for exlusive Rev. 1 use shipments of radioactive materials b.
(Closed Unit 2) Information Notice 80-29 - Broken studs on Terry Turbine Steam Inlet Flanges. Closed based on applicant review that shows the studs to be ASTM A-193 Grade B7 as specified by the manu-facturer.
7.
IE Circulars (Closed - Units 2) IEC 78-02 -_ Proper Lubricating oil for Terry Turbines.
Closed based on inspector review of letter of Instruction MSU-3, Revision 3, which specifies mobil vapor tec light oil for Unit 2.
The Unit 1 Terry Turbine also uses this oil per Instruction PSL MSA 072-32.
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