IR 05000335/1989022
| ML17223A356 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/28/1989 |
| From: | Crlenjak R, Elrod S, Michael Scott NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17223A355 | List: |
| References | |
| 50-335-89-22, 50-389-89-22, NUDOCS 8910190043 | |
| Download: ML17223A356 (18) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report Nos:
50-335/89-22 AND 50-389/89-22 Licensee:
Florida Power 8 Light Co 9250 West Flagler Street Miami, FL 33102 Docket Nos.:
50-335 and 50-389 License Nos.:
DPR-67 and NPF-16 Facility Name:
St.
Lucie 1 and
'nspection Conducted~August 15 'eptember 10, 1989 Inspector-s-.,
S.
A.
E d', Senio'e dent Inspector M. A.
Sc
,
esi ent ns ector Approved By:
R.
Cr enjak, S
on Chi Di sion of Reac or Projects g SF'.~'g Date Signed Date Signed ate ign d SUMMARY Scope:
This routine resident inspection was conducted onsite in the areas of plant operations review, maintenance observations, surveillance observations, review of nonroutine events, and followup of previous inspection findings and regional office requests.
Re'suits:
Licensee activities during this period were typical of a site with both units at power and involved reviews of site operations and detection of equipment degradation and subsequent repairs.
The licensee has recently increased the frequency of contacts with equipment vendors to resolve problems with vendor technical manual informatio REPORT DETAILS Persons Contacted Licensee Employees
"D. Sager, St.
Lucie Site Vice President
"G. Boissy, Plant Manager
- J. Barrow, Operations Superintendent J.
Barrow, Fire Prevention Coordinator, S. Brain, Independent Safety Evaluation Group H. Buchanan, Health Physics Supervisor C. Burton, Operations Supervisor C, Crider, Outage Supervisor D. Culpepper, Site Juno Engineering Manager
- R. Dawson,'aintenance Superintendent R. Frechette, Chemistry Supervisor J. Harper, Quality Assurance Superintendent C. Leppla, IKC Supervisor
"L. McLaughlin, Plant licensing Supervisor L. Rogers, Electrical Maintenance Supervisor
"N. Roos, Quality Control Supervisor B. Sculthorpe, Reliability and Support Supervisor R. 'Sipos, Services Manager D. West, Technical Staff Supervisor W. White, Security Supervisor C. Wilson, Mechanical Maintenance Supervisor E. Wunderlich, Reactor Engineering Supervisor Other licensee employees contacted included engineers, technicians, operator's,'echanics, security force members and office personnel.
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragraph.
2.
Review of Plant Operations (71707)
Unit
began the inspection period at -power and, after period of operation, ended the inspection period in day operation'.
Unit
began the inspection period at power and, after period of operation, ended the inspection period in day operation.
an uneventful 56 of power an uneventful 75 of power On September 5,
1989, an enforcement conference was held at the NRC Region II office in Atlanta, Georgia to discuss concerns identified in IR 335,389/89-2 Plant Tours (Units 1 and 2)
The inspectors periodically conducted plant tours to verify that monitoring equipment w'as 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 materials 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,'omponent positions, adequacy of fire fighting equipment, and instrument calibration dates.
Some tours were conducted on backshifts.
The frequency of plant tours and control room visits by site management was noted to be adequate.
The inspectors routinely conducted partial walkdowns of ECCS 'systems.
Valve, breaker, and switch lineups and equipment conditions were randomly verified both locally and in the control room.
The following accessible-area ECCS system walkdowns were made to verify that system lineups were in accordance with licensee requirements for operability and that equipment material conditions were satisfactory:
Unit 2 HPSI piping.
EDG.
Unit
CCW pump area.
Emergency ventilation.
No violations or deviations were identified in these areas.
Plant Operations Review (Units 1 and 2)
The inspectors periodically reviewed shift logs and operations records, including data sheets, instrument traces, and records of equipment malfunctions.
This review included control room logs and auxiliary logs, operating orders, standing orders, jumper logs and equipment tagout records.
The inspectors routinely observed operator alertness and demeanor during plant tours.
During routine operations, control room staffing, control room access and operator performance and response actions were observed and evaluated.
The
- inspectors conducted random off-hours inspections 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.
Control room annunciator status was verifie The following safety-related tagouts (clearances)
were reviewed in depth:
2-6-33, Breaker 2-41516 - fuel pool transfer machine (tag 1).
2-6-33, Breaker 2-41517 - fuel pool monorail hoist (tag 2).
2-3-375, CVCS radiation monitor outlet drain valve (tag 134);
2-3-375, Primary water to spent fuel pool isolation valve V 15538 (tag 116).
2-8-75, Repair containment spray flow control valve FCV 07-1B (all tags).
2-8-128, Replace rubber plugs on 2A CCMHN (all tags).
The following quality assurance activities and findings concerning control room operations were reviewed to determine if the objectives were being met:
Audit Number
'
"
Date Issued
{}SL-OPS-89-682 QSL-OPS-89-687 August 31, 1989 August 24, 1989 QSL-OPS-89-688 August 16, 1989 The posting of required notices to workers was reviewed.
The postings were in accordance with 10 CFR 19. 11, which was implemented on site by procedure AP 0010721, Rev 15, NRC Required Non-routine Notifications and Reports.
The required material was posted as specified in the procedure.
No violations or deviations were identified in these areas.
Technical Specification Compliance (Units 1 and 2)
Licensee compliance with selected TS LCOs was verified. This included the review of selected surveillance test results.
These verifications were accomplished by direct observation of monitoring instrumentation, valve positions, and switch positions, and by review of completed logs and records.
The licensee's compliance with LCO action statements was reviewed on selected occurrences as they happened.
The inspectors verified that plant procedures involved were adequate, complete, and the correct revision.
Instrumentation and recorder traces were observed for abnormalities.
No violations or deviations were identified in this are d.
Physical Protection (Units I and 2)
The inspectors 'verified by observation during routine activities that security p'rogram plans were being implemented as evidenced by:
proper display of picture badges; searching of packages and personnel at the plant entrance; and vital area portals being locked and alarmed.
No violations or deviations. were identified in,this area.
3.
Surveillance Observations (61726)
= Various plant operations were verified to comply with selected TS requirements.
Typical of these were confirmation of TS compliance for reactor coolant chemistry, RWT conditions, containment pressure, control room ventilation and AC and OC 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 properly, test results met requirements and were reviewed by personnel other than the individual'irecting the test, and that any deficiencies identified during the testing were properly reviewed
'and resolved by appropriate management personnel.
The following surveillance tests were observed:
Performance of IEC procedure 1-1400064F, Rev 8,
Installed Plant Instrumentation Calibration (Flow),
tab 4,
was observed.
This procedure control 1 ed the AFW f1 ow channel checks.
PWO 6579/62, accomplished in conjunction with the surveillance, replaced the Barton transmitter case 0-rings for the AFW flow instruments.
FT 09-2C2 for the 2C pump was found to be slightly out of calibration and a repair PWO was submitted.
No problems were identified.
Performance of Unit 2 monthly surveillance OP 2-1400054, Rev I, Reactor Protection System - Loss of Turbine - Hydraulic Pressure Low, was observed at the turbine stand.
Four pressure switches located at the turbine stand sense turbine control oil pressur e
and send trip signals to the reactor protection system if the pressure decreases sufficiently.
This test verifies the function of the switches and circuits.
The test was satisfactory.
Each pressure switch had an isolation valve and a 'test'leedoff valve.
These valves were not labeled at the time of the test, however the operator was able to discern the correct valves for each test section.
Isolation valve label tags were located among the large quantity of tags recently received under the ongoing relabeling program and were promptly installed.
The test valves were not numbered, therefore not included in the program.
'Label deficiency'ags were hung on the test valves.
The label deficiency process has been similarly used to gather other unnumbered valves into the label program.
The licensee's prompt response satisfactorily resolved this situatio *
Performance of Unit
weekly surveil lances prescribed by AP 1-0010125A, Rev ll, Data Sheet ¹36, Appendices D
(CCW)
and E (ICW),
Weekly Valve Status Checks, were observed at the CCWHX area.
The SNPO-found an ICW strainer bypass valve open, informed the control room operator, and closed it when directed.
This valve was not a
vital flowpath valve.
Subsequently, the ca'use of the, valve being open was determined to be a personnel error and corrective action was taken by the licensee.
Performance of Unit
weekly containment fan cooler CCW flow surveillance per AP 1-0010125, Rev 78, Schedule of Periodic Tests, Checks, and Calibrations, Check Sheet ¹7, Survei llances Performed on Friday,-was observed.
The surveillance was satisfactory.
Performance of AP '2-0010125A, Rev 14, Data Sheet
¹17, Monthly Pump Code Run,
'2C ICW pump, was observed.
Thi s survei l lance required operators at the pump and two flow meter stations in addition to the control room.
The various operators'ctions were well coordinated.
The recorded data reflected the observed smooth pump operation.
The surveillance was satisfactory.
4.
No violations or deviations were identified in this area.
Maintenance Observation (62703)
Station maintenance activities involving selected safety-related systems and components were observed/reviewed, to ascertain that they were conducted in accordance with requirements.
The following items were considered during this review:
LCOs were met; activities were accomplished using approved procedures; functional tests and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accompli shed 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.
Portions of the following maintenance activities were observed:
PWOs 2711/62 (stroke timing and trouble shooting)
and 2734/62 (disassembly and repair)
. controlled the repair of FCV 07-.1B, the containment spray system flow control valve.,
The valve had degraded over a
p'eriod of time and was exhibiting excessive valve closing time.
The valve's gate and seats were removed for decontamination and inspection.
The gate was hand honed to remove gall indications and new seats and seals were installed in the valve body.
The inspector examined the valve gate and observed post-repair valve stroking.
No problems were identified.
This repair put Unit 2 into a
72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO for the 2B Containment Spray system.
The licensee exited the LCO with approximately
hours remaining'
The 2A heater drain cooler developed a heat exchanger shell expansion joint leak.
The joint was repaired under PWO 0437/62 and PCM 242-2890, which replaced the joint with a belly band and backing rings.
The leak and the subsequent repair required a power reduction from 100 percent power to approximately
percent.
The power reduction began on August 13th and ended on the 20th.
No problems were identified.
PWO 2765/61 controlled a repai r of ECCS sump drain isolation valve HCV 25-6A.
The valve failed to operate by hand wheel though the air operator was operable.
Health physics interaction in the work was adequate.
No problems were identified.
The 2A ICW pump was rebuilt per PWO 0446/62.
The pump flow had degraded such that the pump was placed in the alert status established by the site's interpretation o'f ASME Code Section
The aluminum bronze impeller was badly eroded and was replaced with a stainless steel impeller.
The PWO reverified the pump internal clearances.
No problems were identified during the work observation.
PWO 2661/62 controlled the repair of transfer canal isolation valve V
4111.
The valve was being repaired in the canal with the canal drained.
Appropriate health physics controls were in place and the area was being treated as a hot particle area.
No problems were identified during the work observation.
The repai r continues past the end of the inspection period.
No violations or deviations were identified in this area.
5.
Onsite Followup of Written Nonroutine Event Reports (Units
and 2)
(92700)
An LER was reviewed for potential generic impact, to detect trends, and to determine whether corrective actions appeared appropriate.
The Event was reported immediately and was reviewed as it occurred to determine if the TS was satisfied.
This LER was reviewed in accordance with the current NRC Enforcement Policy.
(Closed)
LER 335/85-012, ISI Snubb'er Inspection Failures.
This LER resulted from the first formal inspection of the installed mechanical snubbers during the fall of 1985.
Revision
was submitted on November 24, 1987.
The failures were evaluated and found to be concentrated in the smallest size mechanical snubber.
The failed ones were generally'eplaced with more substantial snubbers.
Retesting and analysis over several years have shown that system vibration has been an important contributor to failure and that replacement of the failed snubbers with a different brand has been effective in reducing the failure rate.
Failures were analyzed for system operability with no adverse impact found'
No violations or deviations were found in this area.
\\
6.
Followup (Units 1 and 2) (92701)
Followup of Unresolved Items (Closed)
URI 335,389/89-18-02, Control of CCWHX Tube Plugging.
This item concerned the prior use of rubber plugs not described in the vendor manual and the controls placed on the installation process.
At that time, the 'Unit
CCWHX rubber plugs had been recently replaced by brass plugs but the Unit 2 status was not determined.
Subsequent to inspection 89-18, the licensee's engineering staff assessed the operability of the Unit
CCWHXs, recognizing hydrostatic tests conducted in the Spring of 1989.
They also conducted laboratory tests of the plugs used.
These tests included heat aging and pressure retention, and utilized water of the same chemistry as the CCW system.
The tests concluded that the rubber plugs were suited for the service, with substantial margin, provided that the expansion screws were torqued to
inch pounds.
Replacement with brass plugs was a recognized alternative.
The licensee had previously decided to replace the Unit 2 rubber plugs during the next CCWHX cleaning.
2A CCWHX was cleaned on August 30-31.
Inspection of the worksite found adequate preparation, procedures in use, and active supervision.
An engineering representative inspected the HX during the worksite inspection.
There were about 32 tubes plugged by double rubber plugs.
Three plugs were found missing, however those tubes were not leaking.
Expansion screw torque for some of the plugs was checked by the licensee.
Thirteen of the 32 plugs checked were torqued greater then
inch-pounds.
Though eight plugs were torqued less than
inch-pounds, none leaked.
Engineering testing showed that leakage was not a problem above 3 inch-pounds torque.
Brass plugs that had been receipt inspected were used to replug the HX.
Two vendor manual problems were found and resolved during this repair.
CCWHX 2B is scheduled for cleaning the week of September 11.
The inspector had no further questions concerning the operability of the CCWHXs.
The other problems were identified by and corrected by the licensee.
This item is closed.
Followup of Headquarters and Regional Requests (Closed Units
and 2) TI 2515/100, Proper Receipt, Storage, and Handling of EDG Fuel Oil.
TI 2515/100 inspection activities consisted of completion of a brief questionnaire involving the licensee's programs to purchase and store
EDG fuel oil.
This information has been collected and the results forwarded as directed.
No additional inspection activities are requi red.'
No violations or deviations were found.
This item is closed.
(Closed Units
and 2) TI 2500/22, Collection of Collocated TLD Yea surement Re sul t s.
TI2500/22 inspection activities consisted of cataloguing data from the Licensee/state environmental TLDs that were collocated with NRC environmental TLDs to compare readings.
The data was collected and catalogued in the fall of 1987 and forwarded as directed by the TI.
This entry is to document closure.
No violations or deviations were found.
This item is closed.
c.
Other Followups (Closed - Units" 1 and 2)
P2189-01, Rebound Springs for Slow Close Levers on ABB Power Distribution, Inc., K-line Circuit Breakers.
This 10CFR-21 report concerned a
necessary field modification to seismically-qualified K-line circuit breakers manufactured prior to mid-1974.
The modification added a spring to the slow close lever to stabilize it during a
seismic event.
The licensee addressed this issue under internal CAR 020789.
The field modification to Unit
circuit b~eakers was completed under PWOs.5941 and 5964 in July 1989.
A portion of the field work was witnessed by the inspector and discussed in IR 335,389/89-18.
The completed PWOs were reviewed and found to be satisfactory.
The Unit 2 circuit breakers were found to not need the field modification.
No violations or deviations were found.
This item is closed.
7.
Exit Interview (30703)
The inspection scope and findings were summarized on September 12, 1989 with those persons indicated in paragraph
above.
The inspector described the areas inspected and discussed in detail the inspection findings listed below.
Proprietary material is not contained in this report.
Dissenting comments were not received from the licensee.
Item Number Status Descri tion and Reference 335,389/89-18-02 closed URI Control of CCWHX tube plugging, paragraph 6.a.
335,389/TI 2515/100 closed IFI - Proper receipt, storage, and handling of EDG fuel oil, paragraph Item Number Status Descri tion and Reference
~ 335,389/TI2500/22 closed IFI - Collection of collocated TLD measurement results, paragraph 6.b.
h 335,389/P2189-01 closed Abbre ABB AC AFW; ALARA ANPO ANSI AP ASME Auxiliary Feed Water (system)
As Low as Reasonably Achievable (radiation exposure)
Auxiliary Nuclear Plant [unlicensed]
Operator American National Standards 'Institute Administrative Procedure American Society of Mechanical Engineers Boiler and Pressure
'ode IFI - Rebound springs for slow close levers on ABB Power Distribution, ines K-line circuit breakers, paragraph 6.c.
viations, Acronyms, and Initialisms ASEA Brown Boveri (company)
Alternating Current ATWS BQAP CAR CCW CEA CFR CIS CST CVCS DC DDPS DEV ECCS EDG FCV FIS FPL FSAR FT GDC GL HCV HP HPSI HVE HX IFI IN 18(C ICW INPO IR Vessel Code Anticipated Transient Without Scram Backfit Quality Assurance Procedure (EBASCO Services Inc.)
Corrective Action Request (a local form).
Component Cooling Water Control Element Assembly Code of Federal Regulations Containment Isolation System Condensate Storage Tank Chemical and Volume Control System Direct Current Digital Data Processing System Deviation (from Codes, Standards, Commitments, etc.)
Emergency Core Cooling System Emergency Diesel Generator Flow Control Valve Flow Indication Sensor The Florida Power 8 Light Company Final Safety Analysis Rep'ort Flow Transmitter General Design Criteria (from 10 CFR 50, Appendix A)
NRC Generic Letter Hydraulic Control Valve Health Physics High Pressure Safety Injection (system)
Heating and Ventilating Exhaust (fan, system, etc.)
Heat Exchanger NRC Inspector Follow-up Item NRC Information Notice Instrumentation and Control Intake Cooling Water Institute for Nuclear Power Operations Inspection Report (NRC)
ISI JPE JPN LTOP LCO LER LPSI MFIV MFP MSIV MV MW NCV NPO NPS NRC ONOP
'P PCM
, PIS PORV pslg PPQ PT PWO QA QC QI RAB RCB RCO RCP RCPB RCS Rev RG RO RWT SALP SAS SDC SDCS'G-SIT
.
SNPO SRO Tavg TCW TE TI InService Inspection (program)
E (Juno Beach)
Power Plant Engineering
'Juno Beach)
Nuclear Engineering Low Temperature Overpressure Protection (system)
TS Limiting Condition for Operation Licensee Event Report Low Pressur e Safety Injecti on (system)
Main Feed Isolation Valve Main Feed Pump Main Steam Isolation Valve Motorized Valve Megawatt(s)
Non-Cited Violation (of NRC requirements)
Nuclear Plant Operator Nuclear Plant Supervisor Nuclear Regulatory Commission Off Normal Operating Procedure Operating Procedure
,
Plant Change/Modification Pressure Indicator/Switch Power Operated, Relief Valve Pounds per square inch (gage)
Part( s)
per Million Pressure Transmitter Plant Work Order Quality Assurance Quality Control Quality Instruction Reactor Auxiliary Building Reactor Containment Building Reactor Control Operator Reactor Coolant Pump Reactor Coolant Pressure Boundary Reactor Coolant System Revision
[NRC] Regulato'ry Guide Reactor [licensed] Operator Refueling Water Tank Systematic Assessment of Licensee Performance Safety Assessment System Shut Down Cooling Shut Down Cooling System Steam Generator Safety Injection Tank Senior Nuclear Plant [unlicensed] Operator Senior Reactor [licensed] Operator Reactor average temperature Turbine Cooling Water Temperature Element C
Temporary Instruction (an NRC document)
TLD TMI TR TS URI VIO ThermoLuminescent Dosimeter Three Mile Island Temperature Recorder Technical Specification(s)
NRC Unresolved Item Violation (of NRC requirements)