ML17354B200
| ML17354B200 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/20/1998 |
| From: | Wert L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Plunkett T FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 9812020089 | |
| Download: ML17354B200 (59) | |
Text
November 20, 1998 Florida Power and Light Company ATTN:
Mr. T. F. Plunkett President - Nuclear Division P. O. Box 14000 Juno Beach, FL 33408-0420 SUBJECT'NSPECTION PLAN - TURKEY POINT
Dear Mr. Plunkett:
On November 2, 1998, the NRC staff completed an inspection resource planning meeting.
The staff conducted this review for all operating nuclear power plants in Region II to develop an integrated inspection plan. We conducted this meeting in lieu of the semiannual Plant Performance Review, which the staff has moved to February 1999 because of the agency's shift to an annual Senior Management Meeting cycle.
This letter advises you of our planned inspection effort resulting from the inspection planning meeting.
We have provided it to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved before the inspector's arrival onsite.
Enclosure 1 details our inspection plan for the next 4 months. We have provided the rationale or basis for each inspection outside the core inspection program 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.
During this scheduling cycle, we willcontinue to focus some of our discretionary inspection effort on the resolution of open inspection items. Therefore, we may conduct additional inspections, which are not listed on Enclosure 1, to close open inspection items that are ready to be resolved. We willnotifyyou at least 3 weeks before the start of these inspections.
The NRC's general policy for reactor inspections is that we willannounce each inspection, unless announcing the inspection could compromise the objectives of the inspectors.
Therefore, we may not have included some specific inspections on Enclosure 1, such as in the security and radiological protection areas, and these inspections may not be announced. contains a historical listing of plant issues, called the Plant Issues Matrix (PIM).
The PIM includes only items from inspection reports or other docketed correspondence between the NRC and Florida Power and Light Company. This material willbe placed in the public document room.
98i2020089'8ii20 PDR AMCK OM00250 6
l'I
FPL We will inform you of any changes to the enclosed inspection plan.
Ifyou have any questions, please contact me at 404-562-4540.
Sincerely, Docket Nos. 50-250, 50-251 License Nos. DPR-31, DPR-41
Enclosures:
- 1. Inspection Plan
- 2. Plant Issues Matrix cc w/encls:
Plant General Manager Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW 344th Street Florida. City, FL 33035 R. J. Hovey Site Vice President Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW 344th Street Florida City, FL 33035 G. E. Hoilinger Licensing Manager Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW 344th Street Florida City, FL 33035 John Gianfrancesco, Manager Administrative Support & Special Projects Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 (cc w/encls cont'd - See page 3)
( Original signed by S. Ninh for )
Leonard D. Wert, Chief Reactor Projects Branch 3 Division of Reactor Projects
FPL (cc w/encls cont'd)
Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 M. S. Ross, Attorney Florida Power & Light P. O. Box 14000 Juno Beach, FL 33408-0420 Attorney General Department of Legal Affairs The Capitol Tallahassee, FL 32304 William A. Passetti Bureau of Radiation Control Department of Health and Rehabilitative Services 2020 Capital Circle SE, Bin ¹C21 Tallahassee, FL 32399-1741 County Manager Metropolitan Dade County 111 NW 1st Street, 29th Floor Miami, FL 33128 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 21740 Centerview Drive Tallahassee, FL 32399-2100
FPL 4
Distribution wiencls:
L. Plisco, Rll L. Wert, Rll K. Jabbour, NRR G. Hopper, Rll PUBLIC Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 1448 Homestead, FL 33090 OFFICE SIGNATURE NAME DATE I DR Ninh 11/Ig/ 8 RII:DRS TPe ble 11/
/98 RII:D KLan 11/
/98 RII:DR PFr rl son 11/Q /98 RII:DRS Barr 1/)
/98 RII:DRS I..-i
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No YES No YES No YES No
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NO YES No OFFICIALRE RD DOCU T NAME: GATURKEYP'nINSPECT.P
ENCLOSURE 1 TURKEY POINT INSPECTION PLAN DECEMBER 1, 1998 - THROUGH MARCH 31, 1999 INSPECTION PROCEDURE/
TEMPORARY INSTRUCTION TITLE/PROGRAM AREA NUMBER OF INSPECTORS OPERATIONS PLANNED INSPECTION DATES TYPE OF INSPECTION - COMMENTS Tl 2515/1 38 OPERATOR WORKAROUNDS PLANTSUPPORT 3/99 SAFETY ISSUE PROGRAM INSPECTION IP 86750 IP 86750 IP 81700 TRANSPORTATION AND RADIOACTIVEWASTE TREATMENT, AND EFFLUENT AND ENVIRONMENTAL MONITORING PHYSICAL SECURITY-SAFEGUARDS 3/99 3/99 CORE INSPECTION PROGRAM CORE INSPECTION PROGRAM IP 82301 THE BIENNIALEMERGENCY PREPAREDNESS EXERCISE 2/99 CORE INSPECTION PROGRAM
Region II TURKEYPOINT Date Source Functional Area hNUlAJSURE 2 United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Date Template ID Type Codes item Description Date: ll/16/199)
Time 090655 Page:
1 of 6 10/03/1998 1998010 Pri: MAINT NRC POS Pri: 3A The weekly diesel-driven fire pump operability test was carefully performed by a knowledgeable operator. Observation of current pump performance and review of past pump data indicated satisfactory pump performance with no negative trends. The engine driven fire pump was ln good condition. (Section M1.3)
Ter. 1C 10/03/1998 1998010 Pri: OpS Sec:
NRC NEG Prk 1B Changes In core fluxprofiles during the lengthy operating interval resulted in substantial inaccuracy in intermediate Sec 3A range nuclear instrumentation indications dunng a plant shutdown. An intermediate range trip bistable did not reset at the expected power level. Control room supervisory oversight did not ensure that the bistable reset as the power Ter. 3C decrease was continued. An unplanned automatic reactor trip occurred. (Section 01.5) 10/03/1998 1998010 Pri: pLTSUp NRC POS Pri: 1C The security force demonstrated good response during drill. Simulated intruders were apprehended prior to reaching the planned objective. However, lessons learned from the drillhad not been communicated to the security force. The licensee promptly initiated corrective actions to ensure lessons learned on future drillswould be promptly Ter. 5C communicated to the security force (Section S5.1).
10/03/1998 1998010 Prl: ENG Sec: MAINT pOS Pri: 2A The licensee has adequately monitored, trended, and initiated corrective actions for problems related to the Intake Cooling Water/Turbine Plant Cooling Water isolation valves. (Section E2. 1)
Ter. 28 10/03/1998 1998010 pri: MAINT NRC pOS pri: 28 The emergency diesel generator 4A surveillance test was satisfactorily performed. Emergency diesel generator material condition was very good. The test procedure was clear, highly detailed. and easy to use; Operators'se ofthe procedure was professional and accurate.
Continuous engineering support and supervisory oversight were provided Ter. 4B for the test. (Section M1.2) 10/03/1998 1998010 Prl: MAINT NRC Sec: ENG pOS Pri: 28 Adetailed Row Accelerated Corrosion (FAC) program was in place and was being implemented in accordance w
procedural requirements by knowledgeable licensee personnel. (Section M1.5)
Sec: 38 Ter.
10/03/1998 1998010 Pri: MAINT
- NRC STR Pri: 28 Inservice Inspection(ISI) actiMitles were being performedin accordance withrequirements with strong licensee direction and oversight of contract personnel.
OveralL the licensee's 51 program was considered to be a strength. (Section Sec: ENG M1.4)
Ter. 3A Item Type (Compliance,Followup,Other),
From 10/01/1997 To 11/16/1998
Region Il TURKEY POINT United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Date Date:
I,i/I6/199'ime:
09:06:55 Page:2of6 Functional Template Date Source Area
~
ID Type Codes Item Description 10/03/1998 1998010 Pri: MAINT NRC pOS Pri: 3A Maintenance and surveillance actiVities were performed in a quality manner. Procedures were in place and were adhered to by qualified maintenance personnel.
Interface between maintenance and operations personnel was good. Applicable FME controls, M&TEcontrols. PMT requirements. and QC hold'points were properly accomplished.
Ter. 3C (Section Mi.l) 10/O3/1998 1998O1O Pri: OpS Sec: ENG NRC POS Pri: 28 Monthly surveillance testing of the Standby Steam Generator Feedwater Pumps was conducted in accordance with procedures.
Personnel were knowledgeable of system and procedural requirements.
Active involvement by the system engineer was noted. (Section OlA)
Ter. 48 10/03/1998 1998010 Pri: OpS Sec: ENG NRC pOS Pri: 3A The receipt Inspection of new fuel for Unit 3 was carefully performed by knowledgeable incfividuals. TS and procedural requirements were satisfied during fuel movement (Section 01.1)
Ter. 38 10/03/1998 1998010 Pri: OPS Sec: MAINT NRC NEG Pri: 28 Containment ambient temperature monitoring Instrumentatlon was appropriately included in the scope of the maintenance rule and complied withenvironmental qualification requirements.
NRC inspectors identified that an error had been made during implementation of a procedure change to address a previously Identified problem. (Section Ter.
03.1) 10/03/1998 1998010 Pri: OpS Sec: OTHER NRC pOS Prl: 5A Ucensee management was very self-critical and the inspectors noted strong focus on nuclear safety in presentations at the Turkey Point monthly status meeting..(Section 07.1)
Sec: 58 Ter.
10/03/1998 1998010 Pri: OPS Sec: PLTSUP NRC pOS Pri: iC The licensee's preparations for potential hurricane force winds and flooding caused by Hurricane Georges were excellent. Emergency Plan procedures were well developed and provided detailed guidance to plant personnel.
Operations training prior to the hurricane was prudent. Equipment and facilities were properly secured and essential Ter. 38 plant personnel were available to provide continuous coverage during the hurricane. (Section 01.3) 08/22/1998 1998008 Pri: ENG Sec:
NRC pOS Pri: 58 The exact cause of the 4A control rod drive motor generator set bearing failure could not be determined.
The most probable cause was lubrication starvation resulting from the design of the Fafnir bearing. Root cause determination efforts were thorough. (Section E2.4)
Ter.
Item Type (Compliance,Followup,Other), From 10/01/1997 To 11/1 6/1 998
Region II TURKEYPOINT Date Source Functional Area United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Date Template ID Type Codes Item Description Date:
1,1/16/1994'ime:
09:06:SS Page: 3 of 6 08/22/1998 1998008 pri: pLTSUp NRC pQS Prl: 1C The 1996 and 1997 annual radiological eNuent report met applicable requirements and no adverse trends in radiological eNuents were identified. Allradiological eNuents were well withinrelease limits. The Hcensee continued to reduce the quantities of radiological eNuents released.
(Section R3.1)
Ter.
08/22/1998 1998008 Prl: pLTSUp NRC pOS Prl: 1C The radiological effluent monitors and site meteorological station and instrumentation were adequately maintained.
Sec:
Sec: 28 Se
. 28 (Sechon R2.1)
Ter. 2A 08/22/1998 1998008 Pri: pLTSUp NRC pQS Pri: 1C Radioactive waste and radioactive material transportation documentation met licensee. NRC. and DOT regulatory Sec:
Sec: 3A requirements.
Reviewed shipping documentation and records were properly completed.
(Section Rl. 1)
Ter.
08/22/1998 199800842 Pri: MAINT Ucensee NCV PrL 28 The licensee identified a deficiency involving the qualifications of General Maintenance Leaders (GML). The licensee promptly discontinued the use of the GML.Anon-cited violation was identified addressing the failure to meet ANSI qualification criteria for the GMLposition. (Section M5.1)
Ter. 5C 08/22/1998 1998008 Pri: ENG Sec: MAINT NRC NEG Prl: 5C Two examples were noted in which corrective actions foridentitied deficient conditions were not aggressively completed.
Delays occurred in the resolution of corroded diesel generator fuel oil transfer piping (Section E2.2). A bacMog of completed but not reviewed surveillance tests was not promptly corrected.
(Section R2.2)
Ter. 28 08/22/1998 1998008 Pri: ENG Sec: MAINT NRC POS Pri: 4B Sec: 2A Ter. 5C The licensee was adequately addressing the specific and generic problems with external corrosion of piping..(Sectl E2.5) 08/22/1998 1998008 Pri: ENG Sec: QPS NRC pQS Pri: 2A The licensee appropriately addressed a steam leak causedby outer diameter pipe corrosion on the Unit 3 priming ejector system and plant management took proper personnel safety precautions.
(Section E2.1)
Sec: 5C
. Ter.48 Item Type (Compliance,Foiiowup,Other), From 10/01/1 997 To 11/1 6/1998
4
Region II TURKEY POINT United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Date Date: 1,1/16/199$
Time: 09:06:55 Page: 4 of 6 Functional Template Date Source Area ID Type Codes Item Description 08/22/1998 1998008
. Pri: MAiNT NRC pOS Pri: 3A Preventive Maintenance and surveillance activities were performed in a quality manner and documentation was good. Procedures were In place and were conscientiously followed by qualified maintenance personnel.
Interface between maintenance and operations personnel was good. Applicable FME controls. M&TEcontrols, PMT Ter. 3C requirements. and QC hold points were properly accomplished.
(Section M1.1) 08/22/1998 1998008 Pri: OPS Sec: ENG NRC pOS Pri: 1A Prong teamwork and planning by Operations, Maintenance, and Work Controls during the Unit 3 power changes was Sec 3A noted. Engineering provided good technical support in assessing a high vibration condition of the 38 turbine plant cooling water pump. (Section 01.1)
Ter. 48 08/22/1998 1998008 Pri: pLTSUp NRC NEG Prl: 4C The Inspectors veritled that the licensee was performing required TS surveillances for engineered safety feature filtration systems.
However, the licensee's review of some completed ESF surveiliances was not timely or sufficient to identify procedure errors. (Section R2.2)
Ter.
08/22/1998 199800841 Pri: OPS Sec: ENG Ucensee NCV I'rl: 1A Sec: 3A Ter. 5C Operator actions to restore Intake Cooling Water (ICW)flowto the Unit 4 CCW heat exchangers followingthe failure of a strainer inlet Isolation valve were prompt and only a slight increase in CCW temperatures occurred.
The licensee subsequently identified that numerous manual ICWvalves had incorrect pins installed in the valve operator thrust collars and initiated corrective actions to return the valves to their normal configuration. An non-cited violation was identified for failure to effectively implement corrective actions for a simi'iar valve pin problem Identified in 1992. (Section O1.2) 08/15/1998 1998009 PrL ENG Sec:
NRC pOS Prl: 4A The calculation that sized the TOLrelay heaters for AFWvalve actuators was consistent with the engineering design guidance and the inputs and assumptions used in the calculation were deemed to be adequate.
(Section E2.2.2)
The calculations performed to evaluate reduced voltage starting of the AFW MOVs were found to be complete and Ter.
technically adequate.
(Section E2.2.3) 08/15/1998 1998009 Prl: ENG Sec:
NRC pOS Prl: 4A The configuration management methods used in the licensee's engineering program are significantly enhancedby its design basis documentation.
As a result. the licensing basis for the AFWsystem is well understood and controlled.
(Section E1.2)
Ter. 48 08/15/1998 1998009 Pri: ENG Sec:
NRC POS Prl: 48 Engineering support for AFWsystem modifications was good. With one exception, documentation of AFWsystem modifications was adequate.
The exception was a modification installed in 1984 and was not representative of current design actMties. (Sections E3.2 and E3.2.1).
Engineering support for assessing conditionreports was good. Technical Ter. 4C documentation was comprehensive and was systematically developed and clearly presented. Condition Report 98-276 for the February ib, 1998 Unit 3 trip (on loss of turbine and steam leak) was a good example of effective engineering support. (Sections E3.3)
Item Type (Compliance,Followup,Other), From 10/01/1997 To 11/16/1998
Region II TURKEYPOINT Date Source Functional Area United States Nuclear Regulatory Commission PlANT ISSUE MATRIX By Date Template ID Type Codes Item Description Date: 11/16/1998 Time: 09:06:55 Page: 5 of 6 08/15/1998 19980M Prl: MAINT NRC pOS Prk 2A The plant materiol condition ond housekeeping observed during the wolkdownindicated that the auxiliary feedwater (AFW)equipment wos being adequately maintained.
AFWpiping and equipment was painted with few indications of corrosion. oil leaks or water leaks. (Section M2.1)
Ter.
08/15/1998 199800941 Prl: ENG Ucensee NCV I'rl:2B Sec:
Sec: 4C Ter.
Acceptance criteria in AFWsystem maintenance and surveillance procedures were generally consistent withthe design and licensing basis. One exception wos the In-se'rvice Test (ISI)procedure acceptonce criterio for AFW secondary boundary outside containment isolation valves and Condensate Storage Tonk (CST) discharge check valves which did not meet Section XIrequirements ofthe American Society of Mechanicol Engineers (ASME) Boiler ond Pressure Vessel (B&PV)Code.
This deficiency was identified as a Non-cited Violation. (Section M2.2) 08/15/1998 199800942 Pri: F.NG Sec:
Ucensee NCV Pri: 4C Sec: 1C Ter.
The team determined that the licensee's safety evaluation program conforms to the requirements of 10 CFR 50.59 and is effective. The program implementing procedures were generally of sufficient detail to ensure that proposed activities were processed in accordance with the regulation. Overall quolity ofsafety evaluations reviewed was good.
One exception wos on Inadequate safety review fora temporary procedure that placed the Unit 3 S/G Blowdown Heat Exchanger in Service on August 2. 1997. This deficiency was identified as an NCV. (Section E1.1) 08/15/1998 1998009 Pri: ENG NRC POS Prl: 4A Design documentation. emergency operating and calibration procedures. and alarm set pohts demonstrated that adequate NPSH was available for the ECCS pumps during the inJection ond recirculation phoses ofsafety inJection.
(Section E8.2)
Ter.
08/15/1998 1998009 Prl: ENG NRC pOS Pri: 5A The licensee's self assessment of the AFWsystem was very detailed ond thorough and Is considered a strength.
The assessment Identified weaknesses in the IST Program ond operating procedures for safety-related pumps at minimum flowconditions. The assessment olso resulted in several discrepancies in plant documentationbeing identified ond Ter. 4A corrected.
(Section E7) 08/15/1998 1998009 Pri: MAINT NRC POS Prl: 2A Maintenance history indicated that the licensee had adequately resolved AFWequipment problems to maintoln system reliability. The team found that maintenance activityon the system was consistent with the design and licensing bases.
(Section M2.3)
Ter. 48 ttem Type (Compliance,Fottowup,Other),
From 10/Of/1997 To f f/16/f998
United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Date Date: l,l/16/1998 Time: 09:06:55 Page:6of6 Type Codes:
Template Codes:
Legend Functional Areas:
BU Bulletin CDR Construction DEV Deviation EEI Escalated Enforcement Item IFI Inspector follow-upitem LER Ucensee Event Report UC Ucensing Issue MISC Miscellaneous MV MinorViolation NCV NonCited Violation NEG Negative NOED Notice of Enforcement Discretion NON Notice of Non-Conformance P21 Part 21 POS Positive SGI Safeguard Event Report STR Strength URI Unresolved item VIO Violation WK Weakness 1A Normal Operations, 1B Operations During Transients 1C Programs and Processes 2A Equipment Condition 2B Programs and'Processes 3A Work Performance 3B KSA 3C Work Environment 4A Design 4B Engineering Support 4C Programs and Processes 5A Identification 5B Analysis 5C Resolution ID Codes:
NRC NRC Self Self-Revealed Ucensee Ucensee OPS MAINT ENG PLTSUP OTHER Operations Maintenance Engineering Plant Support Other EEls are apparent violations of NRC Requirements that are being considered for escalated enforcement action in accordance withthe 'General Statement of policy and Procedure for NRC Enforcement Action'Enforcement Policy). NUREG-IHS. 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 mode.
URls are unresolved items about which more information Is required to determine whether the issue in question is an acceptable item. a deviation, a nonconformance, or a violation. A URI may also be a potential violation that is not likelyto be considered for escalated enforcement action. 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.
Item Type (Compliance,Followup,Other), From 10/01/1997 To 11/16/1998
United States Nuclear Regulatory Commission PLANT ISSUES MATRIX by SALP Functional Area TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/2/98 Positive SAQV 7/2/98 Positive SAQV 7/2/98 Positive SAQV 7/2/98 Strength SAQV 6/29/98 Positive MAINT OPERATIONS!:~'"-.k.:;<":..'". '<<'~",
-"~,'/11/98 Strength MAINT IR 98-07 IR 98-07 IR 98.07 IR 98-07 IR 98.07 IR 98-05 NRC Effective support from maintenance and engineering, and strong operator and management attention resulted in achieving and maintaining Control Room alarm status in a black board condition.
NRC In general, the timeliness of corrective actions was appropriate and was commensurate with safety. Specific information relating to late PMAls was not available on PMAI program and was only available through interviews with management or the responsible individual.
Engineering was noted to have most of the late PMAls viith reasons being attributed to ownership of the original PMAI until final closure.
NRC Good QA audits were noted and related OEF findings were appropriately documented and taken to completion via the CR and PMAItracking systems.
NRC The licensee's self-assessment program, including the on-site and off-site safety committees, was effective in identifying, addressing, and correcting problems.
NRC Operations conservatively monitored the plant during a planned U4 startup transformer outage.
NRC The operating experience feedback (OEF) program was adequate.
OEF personnel were knowledgeable of their responsibilities and requirements.
Licensee-identified OEF issues were appropriately tracked, trended, and resolved.
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TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
IDid ISSUE(s)
SMM CODES 6/29/98 Positive 6/29/98 Positive 6/29/98 Positive 6/21/98 Negative 4/18/98 Positive 4/18/98 Positive 6/29/98 Negative IR 98-05 IR 98-05 IR 98-05 MAlNT IR 98-05 IR 98-07 MAINT
'IR 98-04 PLT SUP IR 98-04 NRC Good reactor control operator shift reliefs and tumovers were observed, and related activities were noted to be performed very professionally.
NRC Control Room conduct including alarm response, communications, access control, and command and control, was positive.
NRC Operator response to a U4 main condenser vacuum problem was proactive and prompt, prevented a possible unit transient, and was in accordance with procedure requirements.
NRC Operator performance during a U3 planned load reduction and related power change was excellent.
In addition, timely and prompt operator action to a turbine plant cooling water system malfunction prevented a possible unit transient.
NRC Procedural controls associated with ICW temperature measurements and monitoring used to verifythe operability of the UHS were weak. Some measuring equipment was not included in the calibration process.
There were no promulgated expectations for increased monitoring when temperatures approached TS limits.
NRC The U4 containment air lock doors operability test was well perlormed.
Good team work among the involved disciplines and good health physics support were noted.
NRC Operator understanding of health physics requirements, and communications with both the control room and health physics were good and demonstrated a questioning attitude.
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8/12/98
TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 4/10/98 3/30/98 Positive IR 98-04 3/7/98 Strength SAQV IR 98-02 3/6/98 Positive SAQV IR 98.02 2/27/98 Positive MAINT IR 98-01 Weakness MAINT IR 98-04 NRC Aweakness was identified in operations'nowledge of the emergency diesel generator room ventilation fan operability. Consequently, operations had weak controls for fan operation and the surveillance procedure lacked specific fan operabiltiy verification.
NRC Excellent self-assessment was noted at the Turkey Point monthly status meeting attended by corporate and site senior management.
The management team demonstrated openness on critiques and a strong focus toward nuclear safety.
NRC Astrength in the effectiveness of recent operator rounds performed by non.licensed operators was noted. This was related to a thorough questioning attitude and excellent observations of abnormal equipment conditions.
NRC Quality Assurance 4th quarter 1997 evaluations were discussed with the licensee.
The evaluations covered a number of areas and were effective in identifying apparent areas where improvements were needed.
NRC Licensed operator and scheduler understanding of the use of risk-assessment tools for removal of equipment from service was good.
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2/27/98 Positive 2/27/98 Positive SAQV IR 98-01 IR 98-300 NRC Licensed operators understood their spec Tiic duties and responsibilities for implementing the Maintenance Rule. Training of operations personnel in Probabilistic Safety Assessment and the Maintenance Rule was considered good.
NRC One Senior Reactor Operator candidate received a Iob performance measurement retake exam. The examiner concluded that the candidate's performance was satisfactory.
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TURKEY POINT 16.Nov-98 DATE 2/23/98 Negative SAQV IR 98-02 2/16/98 Strength PLT SUP IR 98-02 TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
LICENSEE 'Apersonnel error and poor Iudgement resulted in a weak independent verification that was performed by a control room operator when transferring an inverter from standby to normal. No operability nor technical specification issues resulted.
NRC Training department and simulator support for evaluating the plant, induding the U3 trip were evident and demonstrated excellent performance.
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2/16/98 Positive 1/24/98 Strength 1/24/98 Positive 1/20/98 Strength 1/16/98 Negative SAQV SAQV SAQV SAQV MAINT IR 98-02, LER 98-01 IR 97-13 IR 97-13 IR 97-13 IR 97-13 NRC Control room operator response was timely and demonstrate excellent performance during a manual U3 trip. The reactor was rapidly tripped within 6 seconds after noting a complete loss of generator load.
NRC Plant Manager all hands employee briefings were well performed, selferitical and these meetings demonstrated a strong self-assessment capability.
NRC The AuxiliaryFeedwater systems were properly aligned for both units. The licensee maintained very good configuration control for these safety-related and risk significant systems.
The seismic instrumentation system was appropriately aligned and maintained.
NRC The licensee's self-assessment capability was demonstrated to be very good as evidence by effective safety committee performance, and by senior corporate and plant management involvement.
NRC Alack of questioning attitude was noted when operations personnel were performing an Intake Cooling Water pump surveillamce test.
Flow gauges (used during the test) with deficiency tags had not been questioned by the operators.
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TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/16/98 Positive 1/16/98 Positive SAQV IR 97-13 SAQV IR 97-13 NRC The inspectors conduded that all personnel received equal hours of training relative to the active watchstanders and that the total number of hours were in accordance with NRC expectations.
NRC The licensee was effective in conducting written and operating exams to ensure operator understanding of the requalification program content.
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QCI0 12345 1/16/98 Positive SAQV IR 97-13 NRC The licensee was effective in conducting remedial written and operating exams to ensure operator mastery of the requalification training program content.
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LICENSEE Anon cited violation was identified for failure to provide adequate procedures and document controls. Lack of attention to detail and poor oversight by document support personnel.
NRC Operations demonstrated good knowledge and was well prepared for operating the units in a cold weather environment. A minor weakness was identified in that no formal guidance existed on how to measure refueling water storage tank temperature.
NRC The facility's philosophy of safe reactor operation was supported and reinforced by training and consistent conservative decision making.
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HQ0 1
2 3
4 5
A Hoooo B 00000 C 0 EIOQ A 00000 B CICIHQO C 0 OCIO 1 234 5
A OOOCl0 B QQHQQ Co OOH 12345 A EIQCIOCI
~ B OQxQQx 0 CQ 00 12345 FROM: 10/1/97 TO: 11/1 6/98 Page5of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/12/97 Negative 12/12/97 Positive 12/12/97 Positive 12/12/97 Strength 12/12/97 Positive 12/11/97 Positive 12/11/97 Positive ENG ENG MAINT SAQV SAQV SAQV IR 97-12 IR 97-12 IR 97-12 IR 97-12 IR 97-12 IR 97-12 IR 97-12 NRC The conduct of the Control Room shift turnover meetings was not consistent and there were no written guidance or procedures, or documented management expectations describing the conduct of these meetings.
NRC Switch over to the containment sump recirculation was a manual operation, and there did not appear to be any net positive suction head issues.
Officiallicensee position willbe provided by response to NRC Generic Letter 97-04. Good support by training and operations feedback to revise and enhance the related Emergency Operating Procedures.
NRC The instrument air systems, Reactor Protection Systems(RPS),
and backup RPS (eg, ATWS mitigating system) were appropriately aligned and well maintained.
Good system engineer ownership and knowledge was evident.
NRC Ucensee efforts to achieve and maintain a control room annunciator condition in a blackboard status were noteworthy. Strong engineering and maintenance support were noted.
NRC Good briefings and exchange of information between operations and plant support groups was noted at the control room shift turnover meetings.
NRC The licensee demonstrated excellent self-assessment capability in the area of refueling outage critiques.
NRC The licensee conducted a thorough self-assessment of general plant issues and has demonstrated a willingness to be selferitical.
A B
C 12345 Bppp 0 ooooo pxp p 12345 A 00000 B QOQQB CB 00 1 234 5
A B
C A
B C
E PxQxQQ P OOOBO 0 000 1 234 5
Pxooo I
OPx 0Px 0 0 000 12345 A BOOOO B 0000 px CB 00 12345 A 0000 B B 00000 CB 000 12345 A
B C
OOOO Px 00000 B
OQB FROM: 10/1/97 TO: 11/1 6/98 Page 6of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/7/97 Positive PLT SUP IR 97-12 NRC Excellent training department support for the pfant using control room simulator scenarios and exercises for actual unit issues was evident.
234 5
11/28/97 Positive 11/21/97
'ositive 11/17/97 Positive 11/14/97 VIO 10/31/97 Positive 10/30/97 Positive SAQV ENG MAINT SAQV ENG SAQV IR 97-12 IR 97-12 IR 97-12 IR 97-12, LER 97-09 IR 97-11 IR 97-11 NRC Operator response to an Eagle 21 protection system channel failure was noteworthy.
NRC A U3 load reduction for secondaiy plant testing and maintenance was welt phnned and conducted, demonstrated excellent maintenance and work controls, and occurred with strong engineering support and operations oversight.
NRC Failure to have an operable AuxiliaryFeedwater initiation logic for a loss of the last running steam generator feedwater pump for Unit 3. Technical Specification Table 3.3-2 item 6e was violated for 3.5 months.
Inadequate operating procedure and operator knowledge deficiencies.
Once identified, licensee response to the issue was aggressive and appropriate.
NRC Power system stabilizer testing was well planned and executed.
Risk management controls and oversight were evident.
NRC U3 and U4 auxiliary feedwater, high head safety injection, cold feg accumulators, and containment systems were well maintainde and properly aligned.
NRC The licensee's activities to address and to minimize U4 secondary plant swings were well coordinated and controlled.
A B
C 0000 0 oooaa H Boo 12345 A
B C
Q Qx Q Qx 0 Qx Cl 0
1 2
3 A Cl OCI B Boa c.a 0
1 2
3 0 0 CI CI 0 CI Qx Qx 00 4
5 A
B C
QxClaxa CI OBOOO Cl 0CI 0 12345 A BOOQH B aaaaa co Bo 12345 A HQClClH B OOCIOO c
CI Qxoa 234 5
A QBQQ 0 B OHOOO c 0 ClClo FROM: 10/1/97 TO: 11/16/98 Page7of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16-Nov-98 DATE 10/21/97 Positive SAQV IR 97-11 10/12/97 Strength SAQV IR 97-11 TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
NRC Safety committee meetings met regulatory requirements for scope, membership, quorum, and meeting frequency.
Members displayed an excellent focus towards nuclear safety.
NRC Management's self-assessment for the U4 restart from refueling was noteworthy.
A B
C SMM CODES 12345 CIOOO B oooom 0 000 1 234 5
10/1/97 Positive 10/12/97 Positive SAQV ENG IR 97-11 IR 97-11 NRC The U4 restart from refueling was professionally conducted, with strong oversight and excellent communications.
Reactivity management controls were effective.
Mode changes, criticality, and unit online were all well accomplished.
NRC Operator testing of the standby steam generator feedwater system was well performed. System functionality and material condition were good.
A B
C BCIOQ 0 0 00 Cxl CI 0
Boo 1
2 3
4 5
A QBQOO B OBQOCI c 0 CIQQ A EIOOCIE B 00000 co EO 12345
.MAINTENANCE"~; "'~
7/11/98 NCV ENG IR 98-07, LER 98-03 LICENSEE The operation of two charging pumps was adversely affected as a result of inadequate controls during painting.
12345 7/11/98 7/2/98 Positive Positive SAQV IR 98-07 IR 98.07 NRC Observed maintenance and surveillance activities were performed well.
NRC Condition reports were appropriately written on failed inservice inspection surveillances and the corrective actions for those failures were verified to be completed.
A B
C CICIBQ 0 ommoo 0 000 12345 A 0000 E B Ooxooo co Oom A 00000
, omoo co 000 12345 FROM: 10/1/97 TO: 11/1 6/98 Page 8of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 6/29/98 Positive 6/29/98 Weakness 6/29/98 Positive 6/29/98 Positive 5/20/98 NCV 4/18/98 Positive 6/29/98 Positive OPS OPS OPS IR 98-05 IR 98-05 IR 98-05 IR 98-05 IR 98.05 IR 98.07 IR 98-08 NRC In general, housekeeping was found to be good, and material condition was considered adequate.
NRC The licensee was aggressive in the reduction and control of the maintenance backlog. However, the number of overdue preventive maintenance (PM) tasks; and moving scheduled PMs from outage to online work without adequate planning were considered a weakness.
NRC Maintenance, activities were performed in a quality manner and documentation was good. Procedures were in place and were being conscientiously followed by qualified maintenance personnel.
Interface between maintenance and operations personnel was good. Applicable foreign material exclusion controls, measuring and test equipment controls, post maintenance test requirements, and quality control hold points were being accomplished in accordance viith requirements.
NRC A surveillance test of the reactor protection logic was completed successfully, and the licensee properly followed the Technical Specification requirements.
Pretest briefings were effectively and thoroughly conducted.
LICENSEE Two charging pumps failed the inservice test surveillance as a result of inadequate documented instructions, procedures, and work controls, relating to the licensee's coatings program No TS violations occurred.
NRC Instrumentation and Control technicians demonstrated good troubleshooting In determining the cause of spiking on a deenergized source range instrument. They also demonstrated good procedure adherence and communications while performing the U3 pressurizer level surveillance test.
NRC The U3 turbine valve test was well planned and briefed, effectively coordinated and conducted, and oversight was evident.
A B
C 12345 Oox Oo CI oEaao 0
QCI0 1 234 5
A Cloooo B QEOQO Co Do 12345 A QDOOO Qaxoo 0 Co 000 12345 A
B C
OCIEQ 0 0
Qx 0 CI I I
0 QCI0 1 234 5
A Eoooo B OEOOQ Co OO 1 234 5
A CIEOOO B OEOOCl Co 000 1 234 5
A OQECIO B OoxQCI Cl Co 000 FROM: 10/1/97 TO: 11/1 6/98 Pagegof 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16-Nov.98 DATE TYPE(s)
SEC. SFA SOURCE(s)
IDid ISSUE(s)
SMM CODES 4/18/98 Weakness 4/18/98 Positive SAQV IR 98-04 IR 98-04 LICENSEE Aweakness was identified for not implementing and maintaining a component supports inspection program for safety related systems.
Astrong questioning attitude by Quality Control resulted in the discovery of this issue.
NRC Housekeeping and deanliness in the auxiliary building were good as evidencedby recent painting and a lack of loose material.
12345 a OHQOH B OHOOO-C0 000 1
2 3
4 5
3/24/98 Positive ENG IR 98-04 NRC An NRC team determined that there were no regulatory or safety issues with the site air operated valve program.
a QHOOO B 00000 CO 00 12345 3/4/98 2/27/98 Positive Positive ENG SAQV IR 98-02 IR 98-01 NRC Audits and self-assessments of the Maintenance Rute program were thorough.
Corrective actions sampled were appropriately implemented.
NRC Engineering was thoroughly involved in a vibration evaluation performed on the 3A RHR pump which was in the alert range.
A OHOOQ B OQx00 0 C 0 000 1 234 5
a OHOOO B OQxQQx 0 CO 000 12345 2/27/98 Negative 2/27/98 Positive ENG IR 98-01 IR 98-01 NRC There were neither fire detection nor automatic suppression in the sviitchyard relay building.
NRC Walkdown of systems determined that the systems were being appropriately maintained.
Minordeficiencies observed were immediately addressed by the licensee.
a QQOQH B OIZIOOO CO 00 12345 A OHOHO QQx00 0 CO 000 12345 A OQx000 B OEIQOO CO 000 FROM: 10/1/97 TO: 11/16/98 Page 10 of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
IDid ISSUE(s)
SMM CODES 2/27/98 Negative 2/27/98 Positive 2l27/98 Negative 2/27/98 Positive 2i27/98 Positive ENG IR 98-01 IR 98-01 IR 98-01 IR 98-01 IR 98-01 NRC The structures program met the requirements of the Maintenance Rule. All accessible structures had been inspected.
Aweakness was identified concerning adequate documentation of inspection deficiencies.
Additionally, responsibility for condition monitoring of foundations and baseplates was not dearly defined.
NRC The approach to balancing reliabilityand unavailability was reasonable.
NRC In general, review of structures, systems, and components in Maintenance Rule (a)(2) status determined that performance criteria were adequately established commensurate viithsafety.
Mowever, the performance criteria for the isolation function for the containment purge radiation monitors were not appropriate for monitoring the function.
NRC Required structures, systems, and components were included within the scope of the Maintenance Rule.
NRC The licensee had considered safety in establishing goals and monitoring for systems and components In (a)(1) status of the Maintenance Rule. Industry wide experience was used for both (a)(1) and (a)(2) systems and components.
The (a)(3) periodic assessments performed by the licensee met the requirements.
A B
C Oooo 0 Hao 0 0 000 1
2 3
4 5
A oaooo B OHOQO CO 000 12345 12345 A OHOOO B OHGHO Co Ooo 1 234 5
A OHOOO B OHGQQ Co Oo 12345 2/16/98 Weakness 2/16/98 Negative ENG ENG IR 98-02, LER 98-01 IR 98.02, LER 98-01 SELF External corrosion on the auxiliary feedwater steam drain piping resulted in wall thinning and eventual pipe rupture. The licensee did not have a program to periodically examine this area.
SELF Poor configuration control during 1974 resulted in the failure to have adequate procedures and drawings and a correct part number for the turbine control system auxiliary governor maintenance.
A U3 manual reactor trip resulted.
A Qoaoo B Ooxoo 0 CQ Qo
'1 234 5
A B
C OHOQx 0 OHOOO 0 000 12345 A OHQOG B OHOGO Co HQO FROM: 10/1/97 TO: 11/16/98 Page11of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT J
16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/24/98 Positive SAQV IR 97-13 NRC Observe maintenance and surveillance activities were well performed.
12345 1/22/98 Positive 1/19/98 Positive ENG ENG IR 98.02 IR 97-13 NRC Observed maintenance on the 4A Emergency Diesel Generator for replacement of air solenoid valves per a 10CFR part 21 and some electrical relays, was well performed with good independent verigcation and quality control inspections.
NRC Instrumentation and Control personnel were very knowledgeable regarding the operation and calibration of the seismic monitoring system.
A B
C A
B C
QQxQxQ 0 OoxoCI CI 0 000 12345 OCIQxCI 0 Ooxoo 0 0
0 ox 12345 1/16/98 1/9/98 1/7/98 1/5/98 Positive Positive Positive Positive ENG ENG
. SAQV SAQV IR 97-13 IR 97-13 IR 97-13 IR 97-13 NRC The Intake Cooling Water pump survei!lance continues to be one of the most challenging tests for operations.
Excellent technical support by engineering was noted. Heightened management involvement and testing performed by very well experienced operations personnel provided an excellent performed test.-
NRC The maintenance histories for the charging pumps and the Component Coiling Water pumps and heat exchangers indicated an improvement in the material condition of these components during the past two years.
NRC Quality Assurance was noted as being active in identifying weaknesses in plant work order documentation accuracy and completeness.
NRC The licensee's Quality Assurance personnel provide real. time quality assessments through a continuing surveillance program.
A B
C A
B C
OCIQxo CI QQxQO 0 0 000 1
2 3
4 5
00000 QQxQxQx Q 0
OOCI 1 234 5'
OHOOO OHOQx 0 Co 00 1 234 5
A B
C OOCIO Qx'HOOO CI HCI 0 12345 a OOQOH B CIOOO H C
CI OCIO FROM: 10/1/97 TO: 11/16/98 Page12of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16-Nov-98 DATE 12/13/97 Positive SAQV IR 97-12 TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
NRC Athird party assessment of maintenance processes and performance was
. proactive, and demonstrated the licensee's openness for independent reviews.
SMM CODES 12345 12/13/97 Positive SAQV IR 97-12 NRC The licensee has a plan in progress to improve the overall appearance and material condition of the units, and progress to date has been good.
A B
C CIBOQ H ooooo 0
OOCI 12345 12/10/97 Positive 12/2/97 Positive 12/1/97 Positive OPS OPS ENG IR 97-12 IR 97-12 IR 97-12 NRC Planned work on the AuxiliaryFeedwater system was well planned and conducted.
Good coordlriation among operations, engineering, and maintenance.
NRC Observed testing and maintenance activities on both unit's Reactor Protection Systems noted outstanding performance by operations and Instrumentation and Control personnel, NRC The licensee was proactive in addressing reference leg drifting issues forone channel of pressurizer level instrumentation.
A ClBCIClCI B OClE30Q C
Cl 00 12345 A
B C
BOCI 0 0 CIBOCI 0 0
0Exl 0 234 5
A 'OOBQ0 B PBBOP C
Cl 000 12345 12/1/97 Positive 11/26/97 Positive OPS OPS IR 97-12 IR 97-12 NRC Surveillance testing on the U3 Residual Heat Removal pumps was well performed and the licensee took appropriate action to address the data that had fallen into the alert range.
NRC Operators conservatively and appropriately stopped a U4 safeguards logic test when the observed results were not as expected as stated in the procedure.
This was due to a typograhical error.
A B
A B
C A
B C
OBOO H QOOB p a
aa ~
12345 OBBQ 0 OBOOO 0 000 12345 HOBO 0 OBQQ 0 E3 E30 0 FROM: 10/1/97 TO: 11/16/98 Page13of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
0
TURKEY POINT 16.Nov.98 DATE 10/30/97 Positive SAQV IR 97-11 TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
NRC Diesel driven fire pump maintenance work was conducted with a good level of supervisory involvement.
SMM CODES 12345 10/27/97 Positive 10/12/97 NCV 10/5/97 Negative OPS IR 97-12 ENG IR 97-11 PLT SUP IR 97-11 NRC Electrical maintenance was proactive and took conservative measures in implementing a temporary system alteration to obtain offsite backup power to perform cable tray work.
LICENSEE Failure to test the C auxiliary feedwater pump while realigned to U3 train one was a licensee identified and corrected non cited violation. Licensee response, root cause and corrective actions were timely and appropriate.
Failure to update the computerized tracking sheets when auxiliary feedwater was realigned.
NRC U4 containment doseout Inspections noted minor issues that were corrected prior to Mode 4 entiy.
A OCIOx00 B OHOOQ C 0 CICIO 1
2 3
4 5
OQHO 0 OOxQCI CI CQ OH 1 234 5
A OCIHQQ QOxOCI 0 C.0 H CI CI 12345 10/4/97 Strength OPS IR 97-11 NRC U4 engineered integrated safeguards testing was well planned and conducted, with excellent senior reactor operator oversight and strong procedural compliance.
A OHOOO B 0000 Cl CQ 000 12345 10/1/97 10/1/97 Positive NCV ENG ENG IR 97-11 IR 97-11,13 NRC Modifications to the residual heat removal motor operated injection valves were well planned and executed by mechanical maintenance.
LICENSEE Standby steam generator feedwater pump operability surveillance testing was being performed using plant installed gages that were not in a periodic calibration program. The gages were within calibration criteria. Licensee corrective actions and identification of the issue were effective.
A HQOOCI B OHClCI0 C
CI HQ 12345 A QQQxOx Q B QCIOO 0 C 0 OHO 12345 A OOOOH 8 QHCIOQ C 0 QOxO ENGINEERING
=.::;.=~,".:.-'ROM:
10/1/97 TO: 11/16/98 Page 14 of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 8/12/98 ED 7/9/98 Positive 6/29/98 VIO 6/29/98 Positive 6/29/98 Positive 6/29/98 Positive 7/16/98 Positive OPS LER 98-02, IR 98-07 NRR Exemption NRR Ucense Amendments 98-05-01 IR 98-05 IR 98-05 IR 98-05 LICENSEE Ucensee identified condition outsdie design basis where faults on non-safety related loads on the 120 vital buses could result in loss of power to valves needed to piggyback RHR.
Afterreview of this violation and consulation viiththe Director of OE, the NRC conduded that while a violation did occur, enforcement discretion was warranted and issuance of a Notice was not appropriate in this case (Ref. NRC letter to FPL on August 14. 1998).
NRC Quality and timeliness of request for an exemption from certain requirements of 10 CFR 50.71(e)(4) regarding submission of revisions to UFSAR represented good planning of licensing activities.
NRC Good performance in deleting obsolete license conditions from the Operating Ucenses and outdated references from the TSs.
NRC The inspectors conduded that failure to update the Final Safety Analysis Report for the performance of a fullcore off loads was a violation of 10 CFR 50.71(e) requirements.
NRC An engineering meeting was a good format to exchange information.
NRC The licensee's decision to retain the current trip of charging pumps during a safety injection was appropriate.
LICENSEE The licensee's response to a shift technical advisor (STA) availability issue was proper.
Based on recent inspector observations, both in the plant and in the simulator, the STA program and function remains effective.
12345 A 00000 B 00000 C
Cl QQCI 12345 A 0000 0 B CIOOQx 0 C 0 CIQ 12345 a 00000 B 0000x 0 C.Q 00 0 1 2345 A QQCIEIO B 0000 CI C 0 000 12345 a QQQCI 0 B CIOOH 0 C 0 QCI 12345 A OQOHO B ClOOHO C 0 QCIQ.
12345 A HQQQO B 0000x Cl C
CI 000 FROM: 10/1/97 TO: 11/16/98 Page15of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16-Nov-98 DATE 4/18/98 Strength IR 98-04 4/15/98 Weakness MAINT IR 98-04 4/3/98 Positive IR 98-04 3/5/98 Strength OPS IR 98-02 TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
NRC Astrength was noted in the system engineers'nowledge of their respective systems.
This included the common auxiliary feedwater system, and the unit specific spent fuel pool and cooling systems.
NRC Aweakness was identified in engingeering's documentation of the initial assessments of the corrosion found on the U3 diesel fuel oil transfer pump system.
URI pending NRC review of testing the defective section of piping, evaluation of past operability. and an assessment of the timeliness of the licensee's corrective action.
NRC Tile excellent preparation, knowledge of the subject areas, and knowledge of the modification project for cathodic protection installation for the intake structure displayed during the design review meeting was identified as a positive observation.
The design committee menbers demonstrated penetrating and detailed probing questions of the presenters.
NRC Inspectors attended a Plant Review Board meeting and concluded that the process for modification prioritization and approval was effective.
SMM CODES 12345 A
B C
0000 CI QClOH 0 Cl Clo 0 1 234 5
a OHOOQ B Oooox Ox C
CI OCI 12345
- a OOOOO B 0 Ooox CI C.o Oox 0 1 234 5
2/27/98 2/27/98 Positive Negative Negative MAINT OPS MAINT IR 98-02 IR 98-01 IR 98-01 NRC There were two inconsistencies concerning the indusion of risk significant components in the operations used risk listing, and in the classification of components on the sheets in the operations equipment out-of-service logbooks.
NRC Recent assignments and tumovers caused some lack of system specific knowledge. Some systems engineers understanding of the Maintenance Rule and implementation needed improvement. The lack of formal training for some system engineers was identified as a weakness.
NRC A positive finding was identified in the evaluation of a potentially generic problem involving a cracking condition found in a control rod drive mechanism at Prairie Island.
a OOOOO B CIOQOx0 C 0 OHOx 12345 a 00000 CIQQOx Ox C
CI 00 12345 A HOQOCI B OHQHO Co 000 12345 A Cloooo B CIEIEI Ox 0 C
Cl OCIO FROM: 10/1/97 TO: 11/16/98 Page 16 of 26 FOR PUBLIC RELEASE Last Updated 8/12/98
TURKEY POINT 16-Nov-98 DATE 2/27/98 Positive IR 98-01 TYPE(s)
SEC. SFA SOURCE(s)
IDid ISSUE(s)
NRC Good system engineer technical knowledge of their systems was demonstrated.
SMM CODES 1 234 5
2/27/98 Positive IR 98-01 NRC Review of expert panel activities concluded that the panel was a benefit to the implementation of the Maintenance rule program.
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C OCIOO 0 OOHHO 0
OCI0 1
2 3
4 5
2/27/98 Positive 2/27/98 Positive 2/23/98 Strength 1/19/98 Positive 1/15/98 Positive-MAINT MAINT SAQV MAINT MAINT IR 98-01 IR 98-01 IR 98-02 IR 97-13 IR 97-13 NRC The process for evaluation of risk for on-line removal of equipment from service was both comprehensive and effectively implemented.
The process and involvement of the risk organization in the process was good. The licensee's process for assessing shutdown risk was comprehensive.
NRC The licensee's overall approach to performing risk ranking for systems, structures, and components within the scope of the Maintenance rule using risk and the expert panel demonstrated use of probabilistic safety information.
NRC Event Response Team activities, including root cause, inspections, and repairs of the steam line rupture were well planned and conducted.
The combination of efforts for the auxiliary governor and the AuxiliaryFeedwater steam rupture were excellent and was a strength.
NRC Efforts to remove the AuxiliaryFeedwater turbine electrical overspeed trip device were well performed, with strong coordination among all site disciplines.
NRC Engineering was well focused towards a reliabilityissue for the AuxiliaryFeedwater system. Atemporary system alteration to modify the Instrument Air filter configuration was properly implemented, and excellent work coordination was observed.
A B
C QCIOO 0 QHOH p CI 000 1 234 5
A 0000 H B CIOOHO C
Cl Clp 12345 A OCxlppCI B Opppx0 Cp OQH 1 234 5
A OCIOOCI QHQQx p Cp 00 1
2 3
4 5
A OOOO CI B ppxpHp Cp 000 12345 A
B C
CI HOG 0 OHpp. 0 0 000 FROM: 10/1/97 TO: 11/16/98 Page 17 of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/9/98 12/15/97 Negative SAQV NRC letter 12/3/97 Positive IR 97-12 11/30/97 Positive MAINT IR 97-12 11/29/97 Positive MAINT IR 97-12 Positive SAQV IR 97-13 NRC Engineering performed a technical evaluation and documentation of the instrumentaion and showed that there existed no functionality concerns associated viithoperating the reactor coolant pump seal differential pressure indicators and narrow range pressures in a long term pegged high condition.
NRC Proposed change in FPL Topical Quality Assurance Report was not acceptable since it did not adequately satisfy the regulatory requirement to dearly delineate in writing the functional responsibilities of organizations performing activities on safety-related equipment.
NRC The licensee has been thorough in their investigation into normal start failures associated with the U4 Emergency Diesel Generators.
The safety related function was not effected.
NRC The Plant Review Board process for modification prioritization was effective, and demonstrated strong management oversight of the site's long range planning activities.
NRC Aself-initiative to review plant aging issues demonstrated proactive involvement by engineering.
1 234 5
A QQQQCI QOQH 0 Co 000 12345 A QQOCIQ B OOOEI 0 C 0 CIH 12345 A OHOCI0 B QQOHQ C.p 00 H 1 234 5
A CIOCIOO B QHpp.p C
CI OHO 12345 11/20/97 Negative 11/5/97 Positive SAQV MAINT IR 97-12 IR 97-12 SELF Aweakness was identified in engineering oversight of a modification that drilled a hole in the containment sump pump discharge chech valves. As a result, after completion of routine sump pump downs, a false leak rate was annunciated when water drainded back into the sump.
NRC An isolation valve modification on the intake cooling water system was well planned and executed, and minor changes in the system flow rate were negligib!e.
A OCIOCICI B OOxpp H Co QH 12345 A OQHH 0" B OI IO0 0 Cp 000 1
2 3
4 5
A OOOOQ B 0 CI Cl H 0 C 0 OHCI FROM: 10/1/97 TO: 11/16/98 Page.18 of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16.Nov.98 10/31/97 Positive SAQV IR 97-11 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
NRC Engineering support for operations and maintenance was very good during the period, with multiple examples noted.
SMM CODES 12345 10/29/97 Positive SAQV IR 97-12 NRC The licensee responded in a timely manner to a generic reactor fuel issue related to burnable absorber rods and the ability to meet cladding oxidation criteria.
A B
C OQHCI 0 0000x I
0 000 1
2 3
4 5
10/15/97 Positive OPS IR 97-11 NRC Systems engineering took prompt and appropiate corrective actions in identifying and correcting a U4 cold leg accumuhtor nitrogen leak.
A QOOHO B OOOCxl 0 C
CI OCI 12345 10/13/97 Positive 10/12/97 Strength SAQV OPS IR 97-11 IR 97-11 NRC Event response team activities relative to two U4 restart problems were thorough, demonstrated very good root cause assessment, and the implemented corrective actions were appropiate.
Rod control urgent failure alarms due to card failures during pre-startup testing, and turbine-generator lockout due to a loose fuse and potential transformer connection.
NRC U4 initialcriticalityand low power physics testing exhibited very good coordination between operations and reactor engineering.
Overall performance was noteworthy.
A B
C A
B C
QQxQQ Qx 0 0CI Qx 0 0
OCI0 1 234 5
OQxOCI 0 OOOH H 0
CIQH 12345 10/6/97 Positive MAINT
~ IR 97-11 NRC Engineering was prompt in performing the evaluation and implementing corrective actions on the required clamping for the equaliiing line on motor operated valve 4-751 (residual heat removal suction). However, the root cause was unknown.
A HOHCIO B CIQI-IQx0 CO 00 1 234 5
A QQx00 0 B QOOHQ CO OQH
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~
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7/11/98 Positive SAQV IR 98.07 NRC The licensee has been proactive in the area of hurricane preparedness.
QA was effective in identifying issues and ensuring corrective actions by the plant staff.
12345 A QOOOEI B 00000 Qx 000 FROM: 10/1/97 TO: 11/1 6/98 Page 19 of 26 FOR PUBLIC RELEASE Last Updated:
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0
TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 6/29/98 Weakness OPS IR 98-05 LICENSEE Poor followup of Nuclear Safety Speakout recommendations from a report that reviewed a fitness for duty issue was considered to be a weakness.
1 234 5
6/25/98 6/25/98 Positive Positive VIO IR 98-06 IR 98-06 98 SELF The annual security audit was determined to be thorough, effective, and in accordance with the Physical Security Plan.
NRC The licensee's failure to protect Safeguards Information was determined to be a violation of 10 CFR 73.21(b) (xi).
SELF Although a reduction of training hours for Central and Secondary Alarm Station operators had occurred, the operators were qualified in accordance with the Training and Qualification Plan.
A B
C 000 CI 0 00000 Q
OQQx 12345 A
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6/25/98 Positive IR 98-06 SELF A drillconducted by the licensee demonstrated that response officers were knowledgeable of their duties.
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- C CIOQxO 0 00000 Qx 00 CI 12345 6/25/98 Positive 6/25/98 Positive IR 98-06 IR 98-06 SELF Aminor change to response strategy initiated by the licensee was adequate to intercept the adversary from reaching vital equipment.
NRC Security's response to the steam line break that occurred on February 16, 1998, was appropriate and a one hour notification to the NRC was not required.
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Ox OQCI FROM: 10/1/97 TO: 11/16/98 Page20of 26 FOR PUBLIC RELEASE Last Updated:
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TURKEY POINT 16-Nov.98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 6/25/98 Positive 6/25/98 Positive 6/25/98 Positive 6/17/98 Positive 6/10/98 Positive 3/25/98 Positive 4/18/98 Positive OPS OPS IR 98-06 IR 98-06 IR 98-06 IR 98-07 IR 98-07 IR 98-04 IR 98-04 SELF Compensatory posts implemented for the period of Januaiy 1998 to present for degraded protected and vital area barriers were in accordance with the Physical Security Plan.
SELF Procedures and lesson plans were dear in Fitness For Duty training objectives.
Records reviewed reflected that the licensee was in compliance with 10 CFR 26.21 (b) and implementing procedures.
NRC The annual emergency preparadness drillwas satisfactory and the critique and actions were appropriate.
SELF Thee licensee's response to a U4 motor-generator set fire and the resultant Unusual Event were noteworthy. However root cause of the failure has not been condusively determined, and corrective actions from a previous failure may not have been effective.
NRC Acomprehensive health physics procedure and operator field practices review was completed.
The training was good and operators were well versed with health physics controls, induding those necesary to conduct inservice testing of equipment.
NRC An emergenct response drillwas well executed and the licensee demonstrated good site evacuation capability and employee accountability.
NRC The access control program was effective in ensuring that favorably terminated individuals'adges were deactivated in accordance with the Physical Security Plan and implementing procedures.
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12345 A 00000 B 00000 C8 000 12345 FROM: 10/1/97 TO: 11/16/98 Page 21 of 26 FOR PUBLIC RELEASE Last Updated:
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TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 3/6/98 3/4/98 2/27/98 Positive Positive Positive SAQV IR 98-03 IR 98.03 IR 98-02 NRC A proactive training exercise was conducted by the FBI with minor site participation was observed.
Weapons training observed by the inspector was well controlled, instructors were knowledgeable, and officers were attentive.
NRC The records for selected radioactive materials and waste were properly completed.
NRC A random review of records and procedures determined that the licensee's appeal process was dearly documented and available to those individuals who were denied unescorted access.
12345 A QCIOQO B OQCIQ0 CH 000 12345 A QQCIQO B OOHOO CH 00 12345 2/27/98 Positive 2/26/98 NCV SAQV OPS IR 98-02 IR 98-02 NRC The secondary chemistry program was effective in maintaining good control of ionic impurities and protecting the steam generators.
The licensee was evaluating effectiveness of existing chemistry controls and was making progress in implementing secondary chemistry program improvements.
NRC Allradioactive waste operating records were not completed and maintained as required by licensee procedures.
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C A
B C
CICIHQ CI OOOQO H 000 1 234 5
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2/16/98 LER OPS IR 98.02, LER 98-01 SELF A Notification of Unusual Event declaration due to a steam leak after a U3 trip was conservative.
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CI HO 12345 1/19/98 Positive OPS IR 97-13 NRC The fire brigade and support groups were well exercised during drills.
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TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/9/98 Negative OPS IR 97-13 1/2/98 Positive SAQV IR 97-13 1/14/98 MISC SAQV IR 97-13 LICENSEE The licensee appropriately reported a fitness for duty event. The report was made when the licensee became aware that one of their employees had been previously arrested for a possession charge.
NRC
. The inspectors identified weaknesses and poor performance in workers implementation of the licensee's radiological programs.
Examples included Radiation Work Permit knowledge and in contamination control.
NRC The licensee was proactive in upgrading the Radiation Controlled Area control point.
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1/1/98 Strength 12/1287 Positive 12/1287 Positive 12/12/97 Positive SAQV SAQV SAQV SAQV IR 97-13 IR 97-12 IR 97-12 IR 97-12 NRC Site radiation dose reduction initiatives remained strong and focused.
Areas for improvement are being appropriately pursued.
NRC No degration had occurred in the organization or management of the Emergency Preparadness program. The program appeared to be receiving solid management support at Turkey Point, but maintenance of strong oversight willbe an area of challenge.
NRC Emergency Plan Implementing Procedures were determined to be generally thorough in terms of detail needed to implement the various requirements and commitments in the Plan.
NRC 1996-97 Emergency Preparednes program audits fullysatisfied the 10CFR50.54t requirement for an annual independent audit of the program. Additional self assessments were comendable efforts by the Quality Assurance group.
A OCIOCIQ B OQBO Cl C.O O Cl H 12345 a OOOOO OOBO Q C Q OQH 12345 a QCloCIH
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TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/1287 VIO 12/11/97 Negative 12/11/97 Positive MAINT IR 97-12 SAQV IR 97-12 SAQV IR 97-12 NRC Radiological Emergency Plan revisions 30 and 31 were made in accordance with the 10 CFR 50.54(q) regulatory requirements, but a violation for decreasing the effectiveness of the plan was identified in revision 32.
NRC The designated alternate Operations Support Center was unacceptable for its intended use, and the material condition of the stock of silver zeolite cartridges represented a weakness in the licensee's surveillance program for emergency equipment and supplies.
NRC Emergency Response Facilities were well designed and equipped, and were generally well maintained at an adequate level of operational readiness.
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OCIHCI CI 00000 Qx 00 12345 12$/97 Negative SAQV 12/8/97 Positive SAQV 12/5/97 Positive SAQV 12/10/97 Positive SAQV IR 97-12 IR 97-12
'R 97-12 IR 97-13 NRC The licensee's Emergency Response Organization training program was per the Emergecy Plan commitments and with the intent of regulatory requirements and guidance.
The conduct of quarterly Integrated drills during the past year has enhanced the quality of the training.
NRC Emergency declarations on March 4 and April6, 1997 were made in accordance with applicable procedures.
NRC The licensee's operating experience feedback system was strong as evidencedby security's response to a potential weakness in explosive detector performance.
NRC Personnel contamination events during the fall 1997 U4 refueling outage were abnormally high. The licensee appropriately documented these events, followed up with specfic condition reports, and assigned skin and/or internal doses.
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A Cl 0 0 CI 0 B EOHOO C H CIOCI 12345 A CIOOCICI B OCIQOO C H HClO FROM: 10/1/97 TO: 11/16/98 Page24of 26 FOR PUBLIC RELEASE Last Updated:
8/12/98
TURKEY POINT 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 11/21/97 Positive SAQV 'R 97-12 NRC An observed quarterly Emergency Phnning drillwas well planned and conducted, met the drillobjectives, and was a good training exercise.
12345 10/3/97 MISC 10/3/97 ucensing ENG ENG IR 97-11 IR 97-11 NRC The licensee's evaluation of hot short conditions for an 10 CFR 50 Appendix R fire was comprehensive and induded all motor operated valves controlled from the control room. However, the evaluation considered only a single spurious valve action where as the NRC interpretation of IN 92-18 suggest multiple spurious actions should be considered.
The industry has objected to this position and the NRC is reevaluating.
The licensee has deferred further review pending NRC resolution.
LICENSEE The licensee's evaluation of the fire barrier penetration seals conduded no associated operability concerns with the installed seals. However, a number of seals either were not bounded by a tested configuration or justified by existing fire evaluation. Penetration seals not bounded by a tested configuration or addressed by an existing engineering justification were to be evaluated or modified.
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A OQCIHO B OQOH 0 CH 00 12345 A 00000 B OQQHQ C -H 000 10/3/97 Positive ENG IR 97-11 NRC Engineering design projects and construction activities were in process to eliminate the thermo-lag fire barrier by 12/2001. Materials received appropiate inspections and testing, and were properly stored. The fire hazards associated with the thermo-lag installed in the containments was satisfactory. Workmanship was of high quality.
Engineering support was outstanding. QC surveillance and independent verification were provided. Records were maintained.
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3 4
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TURKEY POINT 16.Nov.98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SALP Functional Areas:
ID Code:
1A 1B 1C 2A 2B 3A 3B 3C 4A 4B 4C 5A 5B SC 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 ENGINEERING MAINT MAINTENANCE OPS OPERATIONS PLT SU PLANTSUPPORT SAQV 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 licensee willbe provided with an opportunity to either (1) respond to the apparent violation or (2) request a predecisional enforcement conference.
URls are unresolved items about which more information is required to determine whether the issue In question is an acceptable 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.
FROM: 10/1/97 TO: 11/16/98 Page26of 26 FOR PUBLIC RELEASE Last Updated:
6/12/98
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