ML17229A767
| ML17229A767 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/05/1998 |
| From: | Schin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Plunkett T FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 9806160474 | |
| Download: ML17229A767 (26) | |
Text
CATEGORY 2 REGULATORY INFORMATION DISTRIBUTZON SYSTEM (RIDS)
ACCESSION NBR:9806160474 DOC.DATE:'98/06/05 NOTARIZED: NO FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power
& Light Co.
50-389 St. Lucie Plant, Unit 2, Florida Power
& Light Co.
AUTH.NAME AUTHOR AFFILIATION SCHIN,R.P.
Region 2
(Post 820201)
RECIP. NAME RECIPIENT AFFILIATION PLUNKETT,T.F.
Florida Power
& Light Co.
DOCKET 05000335 05000389
SUBJECT:
Advises of planned insp effort resulting from St Lucie Units 1
& 2 PPR review. Historical listing of plant issues details. of NRC insp plan for next 8 months encl.
DISTRIBUTION CODE:
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SIZE: 2 TITLE: Systematic Assessment of Licensee Performance (SALP) Report NOTES:
E RECIPIENT'D CODE/NAME PD2-3 LA GLEAVES,W INTERNAL: ACRS DEDRO NRR/DRCH/HHFB NRR/DRPM/PECB NUDOCS-ABSTRACT OGC/HDS3 EXTERNAL: L ST LOBBY WARD NOAC COPIES LTTR ENCL 1
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,ID CODE/NAME PD2-3 PD MbK8&XQN FILE CENTE RCH/HOLB NRR/DRPM/PERB OE DIR RGN2 FILE 01 LITCO BRYCE,J H NRC PDR COPIES LTTR. ENCL 1
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NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP.US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR
.23 ENCL 23
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June 5,
1998 Florida Power and Light Company ATT.: Hr. T.
F. Plunkett President
- Nuclear Division P. 0.
Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
PLANT PERFORMANCE REVIEW (PPR)
- ST.
LUCIE UNITS 1 AND 2
Dear Hr. Plunkett:
On Hay 6, 1998. the NRC staff completed the Semiannual Plant Performance Review (PPR) of the St. Lucie Units 3 and 4.
The staff conducts these reviews f'r all operating nuclear power plants to develop an integrated understanding of safety performance.
The results are used by NRC management to facilitate planning ahd allocation of inspection resources.
The PPR for St. Lucie Units 1 and 2 involved the participation of all technical divisions in evaluating inspection results and safety performance information for the period ot October 1997 through April 1998.
PPRs provide NRC management with a current summary of licensee performance and serve as inputs to,the NRC Systematic Assessment of Licensee Performance (SALP) and senior management meeting (SHM) reviews.
Enclosure 1 contains a historical listing of plant issues, referred to as the Plant Issues Matrix (PIH), that were considered during this PPR process to arrive at an integrated view 'of licensee performance trends.
The PIH includes only items from inspection reports or other docketed correspondence between the NRC and Florida Power and Light Corporation.
The PPR may also have considered some predecisional and draft material that does not appear in the attached PIH, including observations from events and inspections that hade occurred since the last NRC inspection report was issued, but had not yet received full review and consideration.
This material will be placed in the PDR as part of the normal issuance of NRC inspection reports and other correspondence.
This letter advises you of'ur planned inspection effort resulting from the St. Lucie Units 1 and 2
PPR review.
It is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personriel availability to be resolved in advance of inspector arrival onsite.
Enclosure 2 details our inspection plan for the next 8 months.
.The rationale or basis for each inspection outside the core inspection program is provided so that you are aware of the reason for emphasis in these program areas.
Resident inspections are not listed due to their ongoing and continuous nature:
9806%60474 980605 PDR ADOCK 05000335 8
PDR OFFICIAL COPY
FPKL During this scheduling cycle, we will be focusing some of our discretionary inspection effort on the resolution of open inspection items.
Therefore, additional inspections may be conducted, which are not listed on Enclosure 2,
to close open inspection items that are ready to be resolved.
You will be notified at least 3 weeks prior to the start of these inspections.
The NRC's general policy for reactor inspections is that each inspection shall be announced, except when announcing the inspection could reasonably compromise the objectives of the inspectors.
Therefore, some specific
'nspections, such as in the security and radiological protection areas, are not included on Enclosure 2 and may not be announced.
We will inform you of any changes to the enclosed inspection plan.
If you have any questions, please contact me at 404-562-4560.
Sincerely, Orig signed by Robert P. Scbin Docket Nos.
50-335 and 50-389 License Nos.
DPR-67, NPF-16 Robert P. Schin, Acting Chief Reactor Projects Branch 3
Division of Reactor Projects
Enclosures:
- 1. Plant Issues Hatrix
- 2. Inspection Plan cc w/encls:
(See page 3)
FPKL cc w/encls:
Mr. J.
A. Stall Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen
- Beach, FL 34957 Hr.
H.
N. Paduano, Manager Licensing and Special Programs Florida Power and Light Company P. 0.
Box 14000 Juno Beach, FL 33408-0420 Hr. J. Scarola Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen
- Beach, FL 34957 Hr.
E. J.
Weinkam Licensing Manage St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen
- Beach, FL 34957 Hr.
M. S.
- Ross, Attorney Florida Power II Light P. 0.
Box 14000 Juno Beach, FL 33408-0420 Mr. John T. Butler, Esq.
- Steel, Hector and Davis 4000 Southeast Financial Center
- Hiami, FL 33131-2398 Mr. Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Ser vices 1317 Winewood Boulevard Tallahassee.
FL 32399-0700 Hr. Joe Hyers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Center view Drive Tallahassee, FL 32399-2100 Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Ft. Pierce, FL 34982 Distribution w/encls:
(See page 4)
FPKL Oistribution w/encls::
L. D. Wert. RII R.
P. Schin, RII S.
B. Rudisail, RII W. C. Gleaves.
NRR G. T. Hopper, RII'UBLIC I
NRC Resident Inspector U.S. Nuclear Regulatory Commission 7585 South Highway A1A Jensen
- Beach, FL 34957-1020 OFFICE SIGNATURE DRP RII DRS/RI DRS/RII TPeebl DRS/R PFr DRS/RII
'Ise DRS/ II KBarr DATE 6
/98 6
/98 6/ ~
/98 6/
/98 6/ k /98 6/
t
/98 6/
/98 OFFI RECORD COPY DOC%EN NANE:
O:iSTLUCIEVPRiSL-I.TR.5
United States Nuclear Regulatory Commission PLANT ISSUES MATRlX by SALP Functional Area ST. LUCIE 05-Jun-98 DATE
-TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES.
4/27/98 NCV 4/27/98 Positive 4/27/98 Negative
.OPERATIONS~~/~~V~VF~~
4/27/98 Positive IR 9843 IR 98-03 IR 98-03 IR 98-03 NRC The inspector identified a weakness in the preparation of the clearance requests. A-large percentage of clearance requests did not comply with the licensee's procedure to propose a detailed boundary. The inspector reviewed 6 safety related clearance requests and found they had inadequate recommended clearance boundaries.
NRC The inspectors found the evolution to take Unit 2 off-line and then restore it to service was accomplished according to procedure in a safe and conscientious manner.
The plant was removed from service to fascilitate repairs to an isophase bus duct that was exhibiting higher than normal temperatures.
NRC Throughout the inspecton period, the inspectors noted generally weak control room conduct.
Examples induded: control room noise level high during turnover, conversations unrelated to the turnover taking place during turnover, general lack of 3-part communication, performance of reactivity manipulations during turnover, operators not understanding the reason for annunciators being in alarm, large number of personnel in the control room during periods other than turnover, and Nuclear Plant Supervisor and Assistant Plant Supervisor involvement in particular activities detracting them away from the overall plant condition.
NRC The inspector verified two safety related ciearances were properly prepared and authorized.
In addition, the inspector walked down the accessible components and found that they were positioned in accordance with the clearance.
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5/4/98
ST. LUCIE 05-Jun-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/19/98 Positive ENG IR 9842 NRC The licensee's response to plant events have been appropriate and conservative.
Noteworthy items include; response to failure of the lower stage of the 182 reactor coolant pump seal, the decision to remove the unit from service to replace an Emergency Safety Features Actuation Systein Power supply and the response to a large turbine hydraulic oil leak which required the unit to be tripped.
1/10/98 'egative MAINT IR 98-02, LER 335/98-003 NRC Response to the manual trip of Unit 1 was complicated by a loss of both main feedwater pumps brought about by a known inability of the feedwater system to recirculate enough feedwater to prevent the feedwater pumps from tripping due to low flowconditions. The licensee's proposed corrective actions for this longstanding equipment problem were similar to those proposed on at least two other occasions.
1/9/98 Positive ENG IR 97-16 1/6/98 Positive IR 98-02 NRC The initial return to service from the Unit 1 steam generator replacement outage was performed in a controlled fashion. Good procedural compliance on the part of operators was noted.
1/3/98 VIO MAINT IR 97-14 LICENSEE Two exar/iptes of a single violation involving failures to properly execute equipment dearance orders were identified. One invovlved a tagiess clearance established to control Reactor Coolant System level and a second involved a personnel error in implementing clearance changes.
1/3/98 VIO ENG IR 97-14 LICENSEE Three examples of violations of Technical Specification limitations for overtime control were identified. Individuals involved included one non-licensed operator and two engineers.
1/3/98 Positive MAINT.
IR 97-14 NRC The licensee's decision to cool down Unit 1 to Mode 5 to repair a low pressure safety injection check valve was considered to be a well thought out and prudent decision.
The valve had failed its local leak rate test and consideration was given to working the valve with the plant pressurized.
Engineering, Maintenance, Operations, and Licensing personnel reviewed the options and concluded that cooling down was the most prudent.
LICENSEE A licensed operator showed a good questioning attitude in identifying a refueling water tank level perturbation during a bistable replacement.
The operator noticed a change in indication when the bistable was replaced and insisted Engineering resolve. This problem ultimately led to the identification of an erroneous recirculation actuation signal setpoint.
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ST. LUCIE 05-Jun-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/3/98 Positive 12/18/97 Positive 12/18/97 Positive 12/18/97 Positive 11/11/97 Positive 11/11/97 VIO 12/18/97 Weakness IR 97-13 MAINT IR 97-13 OPS IR 97-13 IR 97-13 MAINT IR 97-11 IR 97-11 MAINT IR 97-14 NRC The inspector observed an overall increase in the responsibilities and accountabilities of first line supervisors.
Several examples ofwork stoppages by first line supervisors to address issues of housekeeping, procedural adequacy, or safety were noted.
NRC The inspectors concluded the core offioad was completed safely and with an adequate amount of licensee oversight. The inspector noted that activities associated with a misgrappled fuel bundle were completed in a deliberate and a safety-conscious manner.
NRC The inspector concluded that the licensee's response to a lodged Control Element Assembly was extremely well planned and coordinated.
Examples of excellent communication and team work were noted.
NRC The inspector concluded that although the licensed operator requalification program was adequate, several weaknesses were identified in both the training program and operator performance. Examples included written weekly quizzes which were considered minimally discriminating and provided little effective feedback to the program, inattentiveness to control panels and alarms by licensed operators, and evaluators not aggressively implementing management standards.
NRC The licensee performance during the Unit 1 shutdown was professional and in accordance with site procedures.
The pre-brief was attended by necessary personnel and was well organized and informative. Good coordination between the operators was noted.
Extraneous control room activity was minimized.
NRC The inspectors found that the licensee's procedures and methodology for managing overtime improved. The system did not, however, have the capability to be proactive.
It could not identify a person approaching the overtime limits in real time.
-LICENSEE Two examples of operators exceeding the Technical Specifications required overtime limits without approval, were identified by the licensee.
Apparent causes-were inadequate corrective actions from a previous violation combined with the licensee's routine need to fillvacancies with overtime. This was a repeat of VIO 96-09-01.
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ST. LUCIE 05-Jun-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 11/11/97 Negative 11/11/97 Positive 11/1 1/97 Weakness 11/11/97 Positive 11/11/97 Positive 11/11/97 Positive 11/10/97 Strength MAINT SAQV IR 97-11 IR 97-11 IR 97-11 IR 97-11 IR 97-11 IR 97-11 IR 97-15 NRC The inspectors walkdown of the AuxiliaryFeedwater system, Containment Spray system, and Fuel Handling buildings, for both units only revealed only minor discrepancies.
NRC NRC The inspector concluded that guidance provided in the annunciator response procedure associated with the Static Uninterruptible Power Supply (SUPS) was weak in that it referred the operators to the Offnormal Operating Procedure (ONOP) for loss of the system for all SUPS related problems.
However, the ONOP did not provide guidance for resolving misoperation of the SUPS or other problems associated with the system.
The inspector concluded that quick actions by the licensee to extinguish a fire in the static Uninterruptible Power Supply inverter prevented a potential significant challenge to the plant and plant operators.
NRC On September 12, 1997, the operators exhibited good control of Unit 2 during an unscheduled power reduction to repair a feedwater sensing line leak. Briefings held were thorough and involved all of the operators present.
Good control of the plant was exhibited by the Assistant Nuclear Plant Supervisor.
NRC The inspectors'eview of several clearances indicated that they were of good quality and technically adeguatei LICENSEE The questioning attitude by an Assistant Nuclear Plant Supervisor, who identified that the containment cooler fans were not being tested in their emergency configuration, was highly noteworthy.
NRC The inspector identified inadequate Foreign Material Exclusion practices and poor housekeeping around the Unit 2 boron batching tank. The tank lid was found open with no batching operations in progress.
In addition, boric acid covered the floor underneath the tank.
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5/4/98
ST. LUCIE 05-Jun-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 4/27/98 Positive 4/27/98 Negative 4/27/98 Positive 4/27/98 Positive IR 98-03 IR 98-03 IR 98-03 IR 98-03 NRC NRC NRC NRC The inspector found the Inslrument and Control department's initiatives to improve departmental performance and, particularly, the involvement of bargaining unit personnel in the iinprovement process, to be a positive step.
The effort was successful in developing definable, implementable corrective actions. This effort was undertaken in response to several negative events involving I&C personnel performance.
The licensee identified an adverse trend when three events involving misoperation of plant equipment by personnel painting occurred in less than two weeks.
In response, the licensee discussed the events with the workers and identified to them the sensitive equipment located in the areas they were working. Increased oversight was provided as well as a review of all other similar acitivities on site. The inspector found these corrective actions to be swift and appropriate.
The licensee has been aggressive in reduction of the maintenance backlog.
Both the overall number of items as well as the age of items has been reduced.
The backlog was being considered a priority and was being well controlled.
The inspectors observed portions of maintenance associated with 15 work orders, most notably the replacement of a Reactor Coolant Pump Seal cartridge. The inspectors conduded the work was adequately performed and procedures were being appropriately used by qualified personnel.
Applicable Foreign Material Exdusion controls, Measuring and Test Equipment controls, Post Maintenance Test requirements, and Quality Control hold points were being performed in accordance with requirements.
Additionally, the licensee was considering Maintenance Rule requirements in corrective action and disposition of equipment failures.
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A CIOHOO e OOHO co 00 12345 A OOOOCI 8 00x000 c 0 000 12345 A CIOOxOO 8 OHOOO c 0 000 1/9/98 Negative OPS IR 98-02 1/3/98 Positive IR 97-14.
2/14/98 Weakness PLT SUP IR 9842 NRC SELF NRC While maintenance of the Emergericy Core Cooling System radiation monitors was found to be performed properly. the procedure contained several steps which were confusing and difficultto follow. The method for controlling process rad monitor setpoints was considered a weakness in that the procedure required dose coordination between both Chemistry and Maintenance personnel.
The procedure used was confusing and difficultto fo!Iow.
The operators were challenged by several plant events generated by equipment failures. Notable, were failure of the 1B2 reactor coolant pump seal, failure of an Emergency Safety Features Actuation sytem power supply and occurence of a large turbine hydraulic oil leak.
The licensee took swift and appropriate corrective action when it was discovered that an unsafe scaffold was being used.
Upon identification, licensee management directed that work in progress that required the use of the scaffold be stopped.
Following repair, the work recommenced.
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ST. LUCIE 05-Jun-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
A SMM CODES 1/3/98 Strength SAQV IR 97-14 1/3/98 Positive IR 97-14 1/3/98 Positive OPS IR 97-14 1/3/98 Positive IR 97-14 12/18/97 Positive IR 97-13 Positive ENG IR 97-14 NRC NRC NRC NRC NRC NRC The licensee's root cause analysis of an event involving bent Control Element Assembly (CEA) extension shafts was extensive and comprhensive.
The licensee's performance with regard to this event was considered to be excellent. The CEAs
'ere found lodged in the reactor head as the head was being lifted. The head had previously been removed, the core unloaded and the head reset in preparation for replacement of the steam generators.
The licensee's Nuclear Assurance surveillance program during the steam generator replacement project was a major strength in providing licensee management with early notifications of problems.
Around the dock coverage was provided with "same-day" surveillance reports generated.
Unsatisfactory observations were immediately corrected.
Welding activities associated with Unit 1 steam generator replacement activities were well-controlled and in accordance with qualified welding procedures.
The documentation for primary piping welds provided adequate details of the fabrication history of the welds. The independent review of radiographs by contractor and licensee level IIIevaluators provided adequate assurance of final weld quality.
Briefings conducted in preparation for the performance of Unit 2 Engineered Safety Features Actuation System testing were considered to be thorough and professional.
Past inspections had noted that briefings had become less than formal and did not always cover potential problems.
Several maintenance activities were observed and the inspectors found that they were performed appropriately by knowledgable personnel.
Radiation controls and Foreign Material Exclusion provisions were noted to be in accordance with procedures.
Steam Generator Replacement Project welder training and qualification activities were being conducted in fullcompliance with ASME Section IX requirements.
Welding procedures for the Steam Generator Replacement Project were complete and approprialely qualified in accordance with required welding standards.
In addition, the licensees's Nuclear Assurance surveillance activities provided a comprehensive review of the contractor's welding and welding inspection activities.
Subsequent inspection verified that welding activities were being conducted in accordance with approved plans and procedures.
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A 00000 B 00xQQxQ c 0 HOO 12/18/97 Positive PLT SUP IR 97-13 NRC The inspector concluded that the transfer of Incore Instrument remnants from the Unit 1 reactor vessel to the spent fuel pool was carefully and thoroughly planned and completed with low radiation dose expended.
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ST. LUCIE 054 un-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/18/97 Positive 12/18/97 Positive 12/18/97 Positive 11/11/97 Weakness 11/11/97 VIO 11/11/97 Positive 11/11/97 VIO SAQV IR 97-13 IR 97-13 IR 97-11 SAQV IR 97-11 IR 97-11 IR 97-11 ENG IR 97-13 NRC The scope of the In Service inspection, planned preservice inspections and flow accelerated corrosion inspections were appropriate.
NRC Nine maintenance activities were observed and noted to have been completed satisfactorily and in accordance with site procedures.
Good Foreign Material Exclusion control and procedural adherence was also observed.
NRC The Work Order used to install the Unit 2 Xenon constants into the process computer, Digital Data Processing System, was poorly planned in that it did not provide clear instructions to complete the task. The inspector concluded that a lack of proper oversight and management attention led to 2 examples of Digital Data Processing System maintenance related errors.
NRC The inspector identifed several weaknesses that led to the licensee missing 2 Quality Control holdpoints during repair of the Ultimate Heat Sink Valve.
Weaknesses included; inadequate review followingwork order scope change and inadequate project oversight. Aviolation was identified.
NRC Analysis of corrective actions taken by the licensee to audit findings, Condition Reports and Licensee Event Reports, showed improvement in the area of Post Maintenance Testing over 1995 and '96 trended results.
The licensee was proactive in planning to perform a Post Maintenance Testing self-assessment by 2/28/98. The self.assessment is to determine the effectiveness of the licensee's corrective actions.
NRC The implementation of the Systematic Approach to Training for the Technical Training Programs in the area of trainee qualification was adequately defined in procedures.
However, a violation was identified for failure to implement a systems approach to training by allowing the evaluation ofworkers without specificaton and objective-based criteria.
NRC Steam Generator Replacement Project equipment removal and welding activities were being conducted in accordance with approved plans and procedures.
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ST. LUCIE 05-Jun-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 11/11/97 Positive 11/11/97 Strength ENGINEERIAGP~~~~~P; IR 97-11 IR 97-1 1 NRC NRC Personnel responsibilities for implementation of the Post Maintenance Testing (PMT) program were properly assigned by the licensee.
PMTs were also properly delineated in procedures.
A high level of PMT discrepancies had previously been identified in 1995 and 1996.
tnstrumenlation and Control supervisor and technicians, who worked on the Reactor Protection System logic drawer socket controls, were skilled and knowledgeable of both the equipment and their work responsibilities.
The depth of training and skill was noted to be consistent for each crew member.
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1/9/98 Positive 1/9/98 MISC 1/3/98 Positive 1/3/98 Positive 4/27/98 Positive MAINT MAINT MAINT IR 98-03 IR 97-16 IR 97-16, EA 98409, EEI 97-16-01, EEI 97-16-02 IR 97-14 IR 97-14 NRC NRC The inspector conctuded that the licensee acted responsibly in addressing a pin-hole leak in a filletweld on a Unit 1 Main Feedwater Isolation Valve bypass line. The licensee's early involvement of the NRC in the process of addressing the condition under the guidance of Generic Letter 91-18 was noteworthy. The licensee's
engineering organization appropriately considered operability issues associated with the issue.
The root cause effort and short term corrective actions relating to the identification of an erroneous recirculation actuation setpoint were comprehensive and timely.
Engineering acted swiftlyto resolve the known problem and methodically to determine the extent of condition elsewhere.
NRC NRC The inspector concluded that the nickel plating of the pressurizer heater sleeves on Unit 1 was well-coordinated and managed.
The use of hazardous chemicals was noted to have been well controlled as was the foreign material control LICENSEE The Unit 1 Recirculation Actuation Signal setpoint (Refueling Water Tank Level) was found to be 1'ower than required by TS. This resulted in a common mode failure mechanism for all Emergency Core Cooling System pumps due to the potential for loss of Net Positive Suction Head in a Large Break Loss of Cooling Accident. A change in instrument span, performed in 1993, indicated actual tank bottom at 0'ice 1's had previously been the case.
This error propogated through the calculation, resulting in the erroneous setpoint.
The Unit 1 instrumentation which was affected by the steam generator replacement was found to be appropriately identified and the necessary calculations and procedure revisions were comp'leted.
The licensee's effort to allow an independent review by another utilityof the subject instrumentation was a strength.
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ST. LUCIE 05-Jun-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/3/98 NCV 1/3/98 VIO 12/18/97 Positive 12/18/97 VIO 12/18/97 Positive 11/1 1/97 Positive 12/18/97 Positive IR 97-14, NCV 97-14-04 MAINT IR 97-14 NRC letter, Wiens to Plunkett, 12/18/97 IR 97-13 IR 97-13 IR 97-11 MAINT IR 97-13 LICENSEE An NCVwas identified for a failure to perform a 10 CFR 50.59 evaluation when Updated Final Safety Analysis Report setpoints associated with a seismic monitor were modified. The licensee performed the evaluation and conduded that an unresolved safety question did not exist. The cause was determined to be an error in personnel judgement.
The licensee enhanced the controlling procedure to add rigor to the review process.
NRC A violation was identified which involved the manager of the steam generator replacement project signing waivers of overtime limitations for personnel under his control. Technical Specifications limitsuch signature authority to the plant manager.
NRC Licensee was cooperative in working with the NRC in reaching a mutually acceptable schedule for submitting a response to GL 97-04 NRC The fullcore oNoad safety evaluation was well prepared and clearly documented the tack of Unresolved Safety Questions.
The evaluation was properly translated into the applicable procedures to ensure that the evaluation was valid.
NRC Aviolation was identified for failure to mark the travel limits for the steam generator temporary liftingdevice.
NRC The inspectors conduded that the preparation of engineering and heavy load lifting of the steam generators was acceptable per the design drawings and was adequate to provide for the stabilization of the steam generators for removal.
NRC Entries in the trend data base and evaluations presented in the trend reports for the licensee's MOVprogram were consistent, concise, and dear.
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ST. LUCIE 05-Jun-98 DATE TYPE(s)
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SMM CODES 11/11/97 VIO 11/11/97 Positive 11/10/97 Positive 11/10/97 VIO IR 97-11 SAQV IR 97-15 SAQV IR 97-15 MAINT IR 97-11 NRC Implementation of GL 89-10 commitments had not been adequately completed.
One example identified was that the licensee had not updated its Motor Operated Valve calculations and other design documents and the settings in its Total Equipment Data Base to reflect the results of its testing and evaluations.
NRC The inspector conduded the Steam Generator Equivelancy Report was technically sound and well documented.
The 50.59 evaluation addressed the differences between the old and new Steam Generators and identified no Unresolved Safety Questions.
LICENSEE 3 VIOs representing a Severity Level IIIproblem, identified for inadequate testing of containment cooler fan following maintenance and failure to adequately test the fans as required by Technical Specifications.
The fans were never tested in the emergency mode, SLOW (SL3, No Civil Penalty - 11/11/97) The fans are 2 speed and normally operate in FAST. This condition existed since initial startup. The cause was attributed to licensee oversight. The Technical Specifications do not explicitly require testing in SLOW, however, the FSAR describes the credits operation in SLOW.
LICENSEE The root cause analysis and corrective actions taken by the licensee, upon identification of containment cooler fans never having been tested in their emergency configuration, was both comprehensive and timely.
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A QOOOQ e QOxQOQ c O QHO 11/7/97 NCV OPS IR 97-14, NCV 97-14-05 LICENSEE The licensee's identification that control room ventilation was not being tested in accordance with Technical Specifications was considered a strength.
This item was identified while performing a review following a previous surveillance problem involving containment cooler fans.
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~t 5/4/98 Weakness IR 98-05 NRC Several weaknesses were identified during performance of the emergency exercise.
Notable items inctuded; The licensee was not pro-active in pursuing alternate paths for repair of plant equipment.
This resulted in minimal activity for the operational support center and lack of a challenge for the operational support center supervisor.
In addition, the licensee identified that non-licensed operators were not being tracked by the operational support center to ensure their avoidance of radiological conditions when warranled.
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SMM CODES 5/4/98 Positive IR 9845 NRC The inspectors concluded the the licensee successfully demonstrated its ability to implement the Emergency Plan and Implementing Instructions.
Noteworthy items Included; simulated abnormal conditions were promtply recognized, dassified, and reported, the emergency response organization responded promptly to staff the emeregency response facilities and the actions taken by the emergency responders was successful in mitigating the event. Additionally the protective action recommendations were appropriate and communicated to'the state and local authrities in a timely fashion.
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Qx QxQ Q 4/27/98 Negative 2/20/98 Positive 2/14/98 Positive 2/14/98 Positive OPS SAQV IR 98-03 IR 98-04 IR 98-02 IR 98-02
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NRC NRC NRC NRC The inspector identified a weakness in Procedure OP 1-0530020 in that it did not provide direction to Operations lo inform HP prior to placing a Gas Decay Tank in service.
This should be done to ensure the room is properly posted with radiological warnings.
Through performance testing and observation of activities in progress, the inspector determined that the licensee's access control equipment, intrusion detection equipment, closed circuit televeision assessment, alarm station, and response strategy met the requirements of the licensee's Physical Security Plan.
Regarding the area of radiation protection, the inspector noted that the licensee was meeting all requirements for controlling and posting locked high radiation areas.
In addition, an inspected shipment of radioactive waste was properly prepared and met applicable NRC/DOT shipping requirements.
Licensee personnel having responsibilties for transporting radioactive materials were very knowledgable in NRC/DOT regulations.
The inspectors concluded that the licensee's performance in the area of Emergency Preparedness (EP) was acceptable.
The program for identifying, tracking, and resolving prob'lems in emergency preparedness was effective. Selt-assessments were useful in focusing staff and management attention on problem areas.
Emergency Response Facilities were well equipped and maintained in a state ot readiness.
An einergency declaration on 4/19/97 was made in accordance with Emergency Procedures.
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C Qx QQQ 2/14/98 Positive IR 98-02 NRC The licensee's training program for its emergency response organization was in accordance with Emergency Plan training committments and regulatory guidance.
Major improvements in this program had been developed and implemented during the last 15 months. The conduct of quarterly integrated ddlls during 1997 enhanced the quality of the organization's training.
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SMM CODES 2/14/98 Negative 2/14/98 Positive 2/14/98 Positive 1/23/98 VIO 1/3/98 Positive 12/18/97 Positive 2/14/98 Negative SAQV MAINT IR 98-02 NRC IR 98-02 NRC IR 98-02 NRC IR 98-02 NRC IR 97-14 NRC IR 97-13 NRC IR 98-01, EA 98-064, EEI LICENSEE 98-0141, LER 98-S01-0 Problems documented in Condition Reports indicated that Instrumentation and Control technicians may not fullyunderstand how the radiation monitoring system implements Technical Specifications and Offsite Dose Calculation Manual requirements.
The licensee has cominitted additional Instrumentation and Control resources to the system, but none of the technicians have completed required training.
The quality of recent audits of the chemistry and radiological eNuent programs was very good. The audit findings were accurate and the licensee's responses to the audit findings were comprehensive.
In addition, improvements in the chemistry area were noted to occur as a result of the self-assessment process.
The quality of the chemistry and radiological eNuent monitoring program has been strengthened through the audit process.
Although the licensee has made some improvements in their radiation monitoring system a lack of resources and priority for the system has resulted in continued delays in system improvements. The technical specification surveillance and repair of out-of-service equipment consumed most of the staffs resources, leaving little time for corrective maintenance surveillance of non technical specification equipment.
Licensee chemistry personnel closely monitored secondary water chemistry parameters during startup to maintain parameters within limits specified in procedures.
Corrective actions for parameters outside of normal values were appropriate and timely.
Two employees were terminated without their site access being removed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the termination (a requirement of the licensee's physical security plan). One employee returned to the site and gained access to the Protected Area. Human error and lack of independent verification in the badge cancellation process led to the event. Two examples of one apparent violation.
The licensee's radiological protection plan for radiography was well-planned and executed.
The plans were noted to have been conservative with no exposure problems occurring due to radiography.
An inspection in the area of Security identified no discrepancies.
The licensee's planned compensatory measures, removal of vital area barriers, and access control of containment during the steam generator replacement project were appropriate and met the requirements specified in the plant Security Plan. The protected area barriers were in good condition, the isolation zones well lit, and the appropriate compensatory guard postings in place.
In addition, the inspector concluded that the licensee's fitness for duty program was being implemented in accordance with 10 CFR 26.
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SMM CODES 12/18/97 Positive 12/18/97 NCV 12/18/97 VIO 12/18/97 VIO 12/18/97 Positive IR 97-13 IR 97-13 IR 97-13 IR 97-13 IR 97-13 NRC The inspector conduded that the Radiation Protection program in place for the Steam Generator Replacement Project was acceptable.
Training activities for radiation workers and Health Physics technicians concerning project acIIvities were appropriate.
Radiation protection staffing levels and excellent support facilities were established to provide good support for the planned activities.
LICENSEE A non cited violation was identified for failure to followprocedures for securing access to a Very High Radiation Area. The area was the containment and it was secured with a lock controlled by Security at ail times.
NRC Inadequate written procedures for the issuance of tele4osimetry and setting dosimeter setpoints in agreement with the Radiation Work Permit requirements was identified as a violation of Technical Specifications.
NRC Licensee radiation protection controls were noted to have been appropriate and effective for the construction hatch access and eggress and equipment processing as well as the removal and movement of the original steam generators.
The inspectors noted the use of remote radiation monitoring. The inspectors conchded that AIARAconcepts were factored into estimating effective dose.
The tracking of radiation dose was noted as effective. Additionally, contamination controls were effective.
NRC Inadequate radiation worker awareness of Radiation Work Permit requirements were identified as violations of the licensee's radiation protection procedures and Technical Specifications.
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12/18/97 Positive IR 97-13 NRC The Health Physics project overview documents developed to instruct and establish radiological controls for unique steam generator replacement progect tasks were an excellent planning resource.
Examples of topics discussed in these documents were; Pressurizer heater replacement. reactor coolant system pipe end decontamination and pipe cuts.
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SALP Functionai Areas:
ID Code:
1A 1B 1C 2A 2B 3A 3B 3C 4A 4B 4C 5A 5B 5C OPERATION PERFORMANCE - Normal Operations OPERATION PERFORMANCE - Operations During Transients OPERATION PERFORMANCE - Programs and Processes MATERIALCONDITION-Equipment Condition MATERIALCONDITION-Programs and Processes HUMANPERFORMANCE - Work Performance HUMANPERFORMANCE - KSA HUMANPERFORMANCE-Work Environment ENGINEERING/DESIGN - Design ENGINEERING/DESIGN - Engineering Support ENGINEERING/DESIGN -
Programs and Processes PROBLEM IDENTIFICATION8 SOLUTION - Identification PROBLEM IDENTIFICATION8 SOLUTION - Analysis PROBLEM IDENTIFICATION& SOLUTION - Resolution ENG MAINT OPS PLT SUP SAQV ENGINEERING MAINTENANCE OPERATIONS PLANTSUPPORT SAFETY ASSESSMENT & QV LICENSEE LICENSEE NRC NRC SELF SELF-REVEALED EEls are apparent violations of NRC requirements that are being considered for escalated enforcement action in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Action" (Enforcement Policy), NUREG-1600. However, the NRC has not reached its final enforcement decision on the issues identified by the EEls and the PIM entries may be modified when the final decisions are made.
Before the NRC makes its enforcement decision, the ficensee willbe provided with an opportunity to either (1) respond to the apparent violation or (2) request a predecislonal enforcement conference.
URls aro unresolved items about which more Information Is required to determine whether the Issue in question is an acceptablo item, a deviation, a nonconformance, or a violation.
However, the NRC has not reached its final conclusions on the issues, and the PIM entries may be modified when the final conclusions are made.
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ST.
LUCIE INSPECTION PLAN Hay 20.
1998 INSPECTION PROCEDURE/
TEMPORARY INSTRUCTION PROGRAM DIRECTIVE PROGRAM DIRECTIVE TITLE/PROGRAM AREA INITIAI OPERATOR EXAMS INITIAL OPERATOR EXAHS NUMBER OF INSPECTORS OPERATIONS MAINTENANCE PLANNED INSPECTION DATES 6/98 6/98 2 WEEKS IN 12/98 TYPE OF INSPECTION COMHENTS INITIAL EXAMINATION-INITIAL EXAMINATION IP 62700 MAINTENANCE PROGRAM INSPECTION IP 73753 MAINTENANCE ISI INSPECTION IP 62707 MAINTENANCE RULE FOLLOWUP IP 73756 MAINTENANCE IST INSPECTION 8/98 11/98 6/98 11/98 REGIONAL INITIATIVE-PREDiCTIV'E AND PREVENTIVE MAINTENANCE CORE INSPECTION - DURING REFUELING OUTAGE REGIONAL INITIATIVE-REVIEW PERIODIC ASSESSMENT AND OPEN ITEMS REGIONAL INITIATIVE-REVIEW IST PROGRAM AND IMPLEMENTATION IP 37550 ENGINEERING ENGINEERING 5/98 6/98 CORE-REVIEW TECHNICAL SUPPORT, BACKLOGS, AND MODIFICATIONS Enclosure 2
0 a
FPL INSPECTION PROCEDURE/
TEMPORARY INSTRUCTION IP 86750 IP 84750 TITLE/PROGRAM AREA TRANSPORTATION AND RADIOACTIVE WASTE TREATMENT, AND EFFLUENT AND ENVIROMENTAL MONITORING NUMBER OF INSPECTORS PLANT SUPPORT PLANNED INSPECTION DATES 6/98 10/98 TYPE OF INSPECTION COMMENTS CORE - CLOSEOUT CORE ON TRANSPORTATION OF RADIOACTIVE MATERIALS AND CHEMISTRY AND EFFLUENTS IP 83750 OCCUPATIONAL EXPOSURE IP 92904 FIRE PROTECTION FOLLOWUP 11/98 10/98 11/98 CORE INSPECTION REGIONAL INITIATIVE -
FOLLOWUP ON ISSUES IDENTIFIED DURING FPFI..
IP 92903 GL 89-10 INSPECTION FOLLOWUP 1/99 REGIONAL INITIATIVE-TO CLOSE PREVIOUSLY IDENTIFIED GL 89-10 ISSUES IP 81700 PHYSICAL.SECURITY - SAFEGUARDS 6/98 11/98 CORE