IR 05000335/1982012
| ML20053B270 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/22/1982 |
| From: | Bibb H, Elrod S, Hardin A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20053B264 | List: |
| References | |
| 50-335-82-12, 50-389-82-14, IEB-77-03, IEB-77-3, IEB-79-01B, IEB-79-05, IEB-79-05A, IEB-79-05B, IEB-79-05C, IEB-79-1B, IEB-79-5, IEB-79-5A, IEB-79-5B, IEB-79-5C, IEB-81-01, IEB-81-1, NUDOCS 8205280238 | |
| Download: ML20053B270 (6) | |
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UNITED STATES 8'
~'l NUCLEAR REGULATORY COMMISSION E
REGION 11
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101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 30303
Report flos. 50-335/82-12 and 50-389/82-14 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33152 Facility flame:
St. Lucie Unit 1 and 2 Docket flos. 50-335 and 50-389 License fios. DPR-67 and CPPR-144 Inspection at St. Lucie site near Ft. Pierce, Florida Inspectors:
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[22[76 S. A. El rod g
Date Sigaed Yb u r
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H. E. Bibb
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L Date Signed Approved by:
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V// 2 [,7 2 A. K. Hardin, Acting Section Chief, Division of Date Signed Project and Resident Programs SUMilARY Inspection on flarch 11 - April 10,1982 Areas Inspected This routine, inspection involved 204 resident inspector-hours on site in the areas of Followup of IE Bulletins, Plant Operations, Surveillance, Maintenance, Followup of Previously Identified Items, Plant Procedures Review, Licensee Action on Previous Inspection Findings.
Results Of the seven areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees C. M. Wethy, Plant Manager B. J. Escue, Construction Site Manager
- J. H. Barrow, Operations Superintendent
- J. E. Bowers, Maintenance Superintendent D. A. Sager, Operations Supervisor N. G. Roos, Quality Control Supervisor R. J. Frechette, Chemistry Supervisor C. F. Leppla, Instrument and Control Supervisor P. L. Fincher, Training Supervisor R. R. Jennings, Technical Department Supervisor C. A. Pell, Reactor Engineering Supervisor H. F. Buchanan, Health Physics Supervisor J. G. West, Security Supervisor J. Barrow, Fire Prevention Coordinator 0. 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 A. W. Bailey, Quality Assurance Supervisor
- J. Walls, Quality Control Engineer P. Carrier, Licensing Engineer R. Gritz, Licensing Engineer R. Colthorpe, Startup Engineer E. Sherman, QA Engineer Other licensee employees contacted included construction craftsmen, technicians, operators, shift technical advisors, security force members and
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office personnel.
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- Attended exit interview i
2.
Exit Interview The inspection scope and findings were summarized on April 8,1982, with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Violation 335/81-18-02; Open cable penetrations through Switchgear/ Cable Spreading Room Floor. The inspector reviewed FPL I
actions as described in FPL letter L-81-431 responding to the
violation.
Plant Construction Contractor Procedure CFP-E-3, Rev. O,
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" Request to Breach Fire Barrier", has been in use since August 1981 with apparent success.
b.
(Closed) Violation 50-335/81-18-03; Frequent subsequent inspections have confirmed that the licensee has instilled an increased awareness in plant personnel in regard to proper frisking upon exiting the radiation controlled area.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Ibintenance Observation a.
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:
the limiting conditions for operation were met, activities were accomplished using approved procedures, functional testing and/or calibrations were perfonned 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:
PWO-2707
"C" Charging Pump Discharge Relief Valve - Replaced.
PW0's-5019, 0108
"1C" Intake Cooling Water Pump high vibration readings PWO-6017 - Check alarm setpoints on CCW flow to Letdown Heat Exchanger 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 High Pressure Safety Injection System, Safety Injection Tanks, Auxiliary Feed-water System, and Plant Chemistry.
The inspector observed portions of the following surveillance tests:
OP1400054 - Reactor Protection System - Loss of Turbine-Hydraulic Fluid Pressure
AP0010125, Check Sheet 7 - Rotate Containment Fan Coolers
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The inspector ver.ified 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 maintenance requests had been initiated for equipment in need of main-tenance.
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 auxiliary feedwater system to verify operability.
The inspector also witressed portions of the radio-active waste system controls associated with radwaste shipments.
No violations or deviations were identified in this area.
8.
IE Bulletins The following IE Bulletins were reviewed to determina whether they had been received and reviewed by appropriate management, responses, where necessary, were accurate and complete, and that action taken, if required, was complete.
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a.
(Closed - Unit 2) IE Bulletin 79-01B - Environmental Qualification of Class 1E Equipment. This IE Bulletin was sent to operatir.g plants only.
For St. Lucie Unit 2, the safety concerns included in the IEB are addressed in NUREG 0588, " Interim Staff Position on Environmental
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Qualification of Safety-Related Electrical Equipment" and in section 3.11 of the Final Safety Analysis Report.
For this reason, IEB 79-01B is administratively closed for St. Lucie Unit 2.
b.
(Closed - Unit 2) IE Bulletins 79-05,79-05A, 79-05B, 79-_05C - Nuclear Incident at Three !!ile Island.
These IE Bulletins are cl'osed for St.
Lucie Unit 2 as "not applicable to reactor plants other than those supplied by B&W".
The safety concerns raised in these IE Bulletins are
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addressed to licensees with other reactor designs via IE Bulletin 79-06 series and via NUREG 0737.
c.
(Closed - Unit 2) IE Bulletin 77-03 - On-line Te ting of the Westing-s house Solid State Protection System. This IE Ulletin is closed based on review of FPL letter L-77-301 and other internal correspondence indicating that this equipment is not used at St. Lucie Unit 2.
d.
(Closed - Unit 2) IEB 81-01 Surveillance of Mechanical Snubbers - This
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IE Bulletin is administratively closed based on inclusion in the Final
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Sifety Analysis Report, at Question 640.18 and in Chap'.er 14, detailed
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-commitments to conduct preoperational testing of snubers.
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commitments also respond to an NRR letter (Tedesco-Unrig of liarch 27,
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1981) and the associated response L-81-189 of May 1, 1981.
9.
Plant Pr6r.ed res Review l
a.
On fiarch 26, the inspector reviewed new revision 4 to I&C Procedure l
3400021.
This procedure was then identified to the plant manager as apparently containing safeguards information but not being under the controls required for such information. On March 29, the inspector was notified that the licensee concurred with the inspectors assessment, however NRC had verbally deferred until May 1982 implementation of the new requirements at FPL Plants. The inspector confirmed this with Region II office. The licensee took immediate action to add this procedure to the list of procedures containing safeguards information.
b.
During a routine check of technical specification surveillance compliance' the inspector noted a surveillance requirement for which implementation was in question. The requirement is contained in technical specification 4.7.7.1.e.2 and reads as follows:
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At least once per 18 months by:
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. Verifying that on a containment isolation signal or chlorine accident detection signal, the system automatically isolates the control roan within 35 seconds and switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.
The problem involved here is that while the chlorine detectors are calibrated (chemistry procedure C-74) every 18 months during a refueling outage, the automatic operation of the control room venti-lation system is not. verified. Automatic operation of the control room ventilation system is verified during the 18 month engineered safeguards test for the containment isolation signal.
l There does exist a procedure describing automatic and operator action l
required upon receipt of a control room high chlorine alarm, E0P-1900030, Auxiliary and Control Building Ventilation Off-normal Operation, but this procedure is not implemented at the time of l
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chlorine detector calibration, nor does it call for verification of the 35 second time requirement called for in the technical specification.
Inasmuch as the chlorine detection system will become unnecessary when the chlorine is removed from the site in the near future, this will not i
require any procedural action at the time. The inspector had no further comment in this area.
10.
Followup of Previously Identified Items a.
(Closed) Inspector Followup Item 335/79-13-03.
This item identified 15 discrepancies found during operating procedure and drawing review. A subsequent inspection reported in IE Report 50-335/81-14 found all but one item corrected.
This report finds that last item corrected.
b.
(Closed) Inspector Followup Item 335/79-FI-06-Health Physics Followup
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That IE Circular had previously been closed in Inspection Report 335/79-32. A recent health physics inspection confirmed that previous closure.
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