IR 05000335/1985030
| ML17308A172 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/20/1985 |
| From: | Bibb H, Crlenjak R, Elrod S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17308A171 | List: |
| References | |
| 50-335-85-30, 50-389-85-30, IEB-85-002, IEB-85-2, NUDOCS 8512310401 | |
| Download: ML17308A172 (11) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report Nos.:
50-335/85-30 and 50-389/85-30 Licensee:
Florida Power and Light Company 9250 West Flagler'treet Miami, FL 33102 Docket Nos.:
50-335 and 50-389 License Nos.:
OPR-67 and NPF-16 Facility Name:
St.
Lucie 1 and
Inspection Conducted:
November
Oecember 9,
1985 Inspectors:
~
~(.
ts'c.-
R.
V. Crlenjak, Senior Resident Inspector (
H.
. Bibb, esi ent Inspector Approved by:
S.
. Elrod, Section Chief Oivi sion of Reactor Projects Oate Signed n
Is'ate Signed
)c.c Zo SS'ate Signed SUMMARY
'I Scope:
- This inspection involved 183 inspector hours on site in the areas of Iechnical Specification (TS)
compliance, operator performance, overall plant operations, quality assurance practices, station and corporate management practices, corrective and preventive maintenance activities, site securi ty procedures, radiation control activities, surveillance activities, Inspection and Enforcement ( IE) Bulletins and refueling (Unit 1).
Results:
In the areas inspected, no violations or deviations were identified.
8512310401 851223 PDR ADOCK 05000335 PDR
REPORT DETAILS Persons Contacted Licensee Employees
"K. Harris, St.
Lucie Site Vice President D. A. Sager, Plant Manager
"J.
H. Barrow, Operations Superintendent
- T. A. Diliard, Maintenance Superintendent
"L. W. Pearce, Operations Supervisor
"R. J. Frechette, Chemistry Sup'ervisor C.
F. Leppla, Instrumentation and Control ( I&C) Supervisor P.
L. Fincher, Training Supervisor C. A. Pell, Technical Staff Supervisor (Acting)
E. J. Wunderlich, Reactor Engineering Supervisor (Acting)
H.
F. Buchanan, Health Physics Supervisor G.
Longhouser, Security Supervisor J.
Barrow, Fire PreVention Coordinator
"J. Scarola, Assistant Plant Superintendent
- Electrical C. Wilson, Assistant Plant Superintendent
- Mechanical
"N. G.
Roos, Quality Control Supervisor
"P.
W. Heycock, Inservice Inspection Coordinator
"L. L. McLaughlin, Plant Licensing
- R. Sipos, Services Supervisor
"N. T. Weems, Quality Assurance Superintendent
- W. G. White, Security Coordinator Other licensee employees contacted
.included, technicians, operators, mechanics, security force members, and office personnel.
"Attended exit interview Exit Interview The inspection scope and findings were summarized on December 13, 1985, with those persons indicated in paragraph 1 above.,
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
Licensee Action on Previous Inspection Findings This subject was not addressed in the inspection.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions.
One unresolved item is identified in paragraph Plant Tours (Units 1 and 2)
The inspectors conducted plant tours periodically during the inspection interval to verify that monitoring equipment was recording as required, equipment was properly tagged, operations personnel were aware of plant conditions, and plant housekeeping efforts were adequate.
The inspectors also determined that appropriate radiation controls were properly established, critical clean areas were being controlled in accordance with procedures, excess equipment or material was stored properly and combustible material and debris were disposed of expeditiously.
During tours the inspectors looked for the existence of unusual fluid leaks, piping vibrations, pipe hanger and seismic restraint settings, various valve and breaker positions, equipment caution and danger tags, component positions, adequacy of fire fighting equipment, and instrument calibration dates.
Some tours were conducted on backshifts.
The inspectors routinely conducted partial walkdowns of emergency core cooling systems (ECCS).
Valve, breaker/switch lineups and equipment condi-tions were randomly verified both locally and in the control room.
During the inspection period the inspectors conducted a complete walkdown in the accessible areas of the DC electrical distribution system to verify that the lineups were in accordance with licensee requirements for operability a'nd equipment material conditions were satisfactory.
Additionally, weekly flowpath verifications were performed on the following systems:
letdown and charging, low pressure safety injection and component cooling water.
On November 15, 1985, while performing a walkthrough of the Ui.it 2 reactor auxiliary building (RAB) the inspector noted that several doors to the outside were open.
Additionally, door number 247 could not close fully due to a damaged door jamb.
The inspector also, noted that, through the openings to the outside, there existed a flow of air from inside to outside (i.e.,
building pressure was positive).
The RAB ventilation is normally operated much that air flow would be from outside to inside (i.e., building pressure negative).
The inspector immediately notified the Unit 2 Assistant Nuclear Plant Supervisor (ANPS) of the improper ventilation lineup and the open doors.
The problem of the open RAB doors was also discussed with plant management.
In an initial review of plant procedures and TS, the inspector has been unable to find explicit guidelines/requirements for control of RAB openings and ventilation lineups.
Unit 2 Final Safety Analysis Report paragraphs 9.4 and 9.4.3.
1 discuss design criteria and objectives of the RAB ventilation system.
These criteria/objectives include:
a.
provide air flow from areas of low potential radioactivity to areas of progressively higher potential radioactivity (with exterior doors closed),
b.
assure that the ventilation system operation during normal operation does not cause an annual offsite release of gaseous radioactivity from the plant to exceed limits allowed by
CFR 50, Appendix I,
e c.
ventilation air exhausted from potentially contaminated areas is filtered for the removal of particulates as required to satisfy Appendix I of 10 CFR 50, and d.
air exhausted from the Shield Building'nnulus, Fuel Handling Building and Reactor Auxiliary Building (mai n ventilation system)
is first filtered, and then discharged to the environment through vent stacks in order to facilitate an overall measurement of gaseous releases and to prevent potential contamination of'entilation air intakes.
It is the inspector's position that these criteria/objectives cannot be met or maintained with RAB exterior doors open and, in the case of November 15, 1985, RAB building pressure positive, i.e., air flow through open doors to outside.
Until the inspector has completed a review of these conditions and the appropriate industry guidelines, this item is Unresolved Item 389/85-30-01:
RAB Ventilation and Exterior Door Status.
6.
Plant Operations Review (Units 1 and 2)
The inspector s periodically during the inspection interval reviewed shift logs and operations records, including data sheets, instrument traces,
- .nd records of equipment malfunctions'his review included control room logs and aux liary logs, operating orders, standing orders, jumpe>
logs and equipment tagout records.
The inspectors routinely observed operator alertness and demeanor during plant tours.
During normal'events, operator performance and response actions were observed and evaluated.
The inspectors conducted random off-hours inspections durint the reporting interval to assure that operations and security remained at an acceptable level.
Shift turnovers were observed to verify that they were conducted in accordance with approved licensee procedures.
The inspectors conducted an in-depth review of the following safety-related equipment tagouts:
Unit
~Ta out No.
1-12-4 1-12-5 1-12-8 Unit 2
~Eui ment lA Low Pressure Safety Injection Pump Vressurizer Steam Space Sample Valve MV-09-10 "B" Auxiliary Feedwater Pump Di scharge Val ve Reason Meter Inspection Local Leak Rate Test
'emove Valve Internals and Inspect 2-12-2 FCV-22104 Boric Acid Flow Control Valve Replace Flange Gasket
2-12-3 Reactor Trip Circuit Breakers 758 Preventive Mainten-ance 2-12-13 2A Battery Charger Preventive Mainten-ance Technical Specification Compliance (Units 1 and 2)
During this reporting interval, the inspectors verified compliance with limiting conditions for operation ( LCO) and results of selected surveillance tests.
These verifications were accomplished by direct observation of monitoring instrumentation, valve positions, switch positions, and review of completed logs and records.
The licensee's compliance with LCO action statements was reviewed on selected occurrences as they happened.
Maintenance Observation 9.
Station maintenance activities concerning selected safety-related systems and components were observed/reviewed to ascertain that hey were conducted in accordance with requirements.
The following items were considered during this review; limiting conditions for operation were me
,
activi". es were accomplished using approved procedures, functional testing and/or cali-brations were performed prior to returning components or systems to service; quality control records were maintained; activities were
<<ccomplished by qualified personnel; parts and materials used were properly certified; and radiological controls were implemented as required.
Work requests were reviewed to determine the status of outstanding jobs and to assure that priority was assigned to safety-related equipment.
Physical Protection (Units 1 and 2)
The inspectors verified by observation and interviews during the reporting interval that measures taken to assure the physical protection of the facility met current requirements.
Areas inspected included the organiza-tion of the security force, the establishment and maintenance of gates, doors and isolation zones in the proper conditions, that access control and badging was proper, and procedures were followed.
At the time of this inspection report writing the licensee was making preparations in anticipation of a strike by the security guard force.
The inspectors began implementing inspection procedures 92709, Licensee Plans for Coping With Strikes, and 92710, Licensee's Initial Implementation of Strike Plans.
Next month's report will provide details.
10.
Surveillance Observations During the inspection period, the inspectors verified plant operations in compliance with selected TS requirements.
Typical of these were confirma-tion of compliance with the TS for reactor coolant chemistry, refueling water tank, containment pressure, control room ventilation and AC and DC electrical sources.
The. inspectors verified that testing was performed in accordance with adequate procedures, test instrumentation was calibrated, LCOs were met, removal and restoration of the affected components
were accomplished,'est 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.
Specific surveillances reviewed included reactor trip breaker logic sequence testing, local leak rate testing, coolant charging pump flow rate and reactor protection system monthly functional tests.
11.
IE Bulletins The following IE Bulletin was reviewed to ensure receipt, evaluation and appropriate implementation:
(Closed)Bulletin 85-02, Undervoltage Trip Attachments of Westinghouse DB-50 Type Reactor Trip Breakers.
This IE Bulletin was reviewed and found to be inapplicable to St. Lucie.
However, comparable measures called for in the Bulletin were implemented for the trip circuit breakers and these actions were reviewed by an NRC Anticipated Transient Without Scram (ATWS)
inspection tea It h