ML17355A281

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Advises of Completion of Plant Performance Review on 990203. Review Conducted to Develop Integrated Understanding of Safety Performance,Facilitate Planning & Allocation of Insp Responses.Plant Issue Matrix Encl
ML17355A281
Person / Time
Site: Turkey Point  
Issue date: 03/22/1999
From: Wert L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Plunkett T
FLORIDA POWER & LIGHT CO.
References
NUDOCS 9904050013
Download: ML17355A281 (23)


Text

~A.X'~WUwM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9904050013 DOC.DATE: 99/03/22 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit. 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION WERT,L.D.

Region 2 (Post 820201)

RECIP.NAME RECIPIENT AFFILIATION PLUNKETT,T.F.

Florida Power E Light Co.

SUBJECT:

,Advises of completion of plant performance review on 990203.

Rev"'ew conducted to develop integrated understanding of safety performance, facilitate planning

& allocation of insp responses. Plant issue matrix encl.

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Florida Power and Light Company ATTN:

Mr. T. F. Plunkett President - Nuclear Division P. O. Box 14000 Juno Beach, FL 33408-0420 March 22, 1999

SUBJECT:

PLANT PERFORMANCE REVIEW - TURKEY POINT NUCLEAR PLANT

Dear Mr. Plunkett:

On February 3, 1999, the NRC staff completed a Plant Performance Review (PPR) of the Turkey Point Nuclear Plant. The staff conducts these reviews for all operating nuclear power plants to develop an integrated understanding of safety performance.

The. results are'used by NRC management to facilitate planning and allocation of inspection resources.

PPRs provide NRC management with a current summary of licensee performance and serve as inputs to the NRC's senior management meeting (SMM) reviews.

PPRs examine information since the last assessment of licensee performance to evaluate long term trends, but emphasize the last six months to ensure that the assessments reflect current performance.

The PPR for Turkey Point involved the participation of all technical divisions in evaluating inspection results and safety performance information for the period of August 1998 through January 1999. The NRC's most recent summary of licensee performance was provided in a letter of October 1, 1998 and was discussed in a public meeting with you on October 22, 1998.

As discussed in the NRC's Administrative Letter 98-07 of October 2, 1998, the PPRs provide an assessment of licensee performance during an interim period that the NRC has suspended its Systematic Assessment of Licensee Performance (SALP) program. The NRC suspended its SALP program to complete a review of its processes for assessing performance at nuclear power plants. At the end of the revie'w period, the NRC willdecide whether to resume the SALP program or terminate it in favor of an improved process.

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During the last six months, both units continued to operate well. Unit 3 has operated continuously since completion of a fall refueling outage on October 29, 1998.

Unit 4 operated at power from October 14, 1997, through the end of the period.

Overall performance at Turkey Point continued to be acceptable.

Plant staff continued to be self-critical and proactive in self-assessments with a strong safety focus. Management consistently was conservative in decision making. Preparations for the approach of Hurricane Georges were safety-conscious.

fz Operations perlormance was consistent.

Strong operations planning and control was observed

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during the Unit 3 refueling outage and preparations for the approach of Hurricane Georges.

Self-assessments and audits were through and self-critical. Overall, operator response and control of routine evolutions and problems was effective. A few human errors occurred during the shutdown for the Unit 3 outage and during fuel movement.

Similar issues had been noted early in the last SALP period. Core inspections are planned.

9904050013 990322 PDR ADOCK 05000250 8

PDR

FP&L Maintenance performance was consistent.

Maintenance performance continued to be effective in maintaining plant material condition. The inservice inspection program was effective.

Calibration and testing activities were performed well. Corrective maintenance and surveillances were performed in an effective manner with strong quality oversight.

Core inspections are planned."

Engineering performance was consistent.

In the Engineering area, management was self-critical and provided a strong focus on nuclear safety. The design packages prepared for modifications during the period were thorough.

Engineering support for modifications and surveillances was thorough and well planned.

Lessons learned in a previous modification were appropriately applied. Your self-assessment conducted on the auxiliary feedwater system (AFW) prior to the NRC Safety System Engineering Inspection was very thorough and considered a strength.

In addition, the detail in design-basis documentation was considered a strength.

Corrective actions for AFW system problems were effectively implemented.

Core inspections are planned.

Plant Support performance was consistent.

Your chemistry and radiation protection staff effectively monitored and controlled primary and secondary system chemistry, radiological effluent releases, and radioactive source terms to maintain occupational and population doses within limits. Radiation protection equipment and systems were maintained and tested appropriately. =Early hurricane and storm responses were effective in preparing the site for weather effects.

Performance on the annual drill demonstrated that Emergency Preparedness continued to be effective. The Fire Protection Program performance continued to be acceptable.

Surveillance testing of fire protection equipment was well performed.

In the.

Security area, previous access control problems have been corrected.

A transition of security.

force contractors, occurred this assessment period with minimal difficulties. Core inspections are planned.

Enclosure 1 contains a historical listing of plant issues, referred to as the Plant Issues Matrix (PIM), that were considered during this PPR process to arrive at an integrated view of licensee performance trends.

The PIM includes items summarized from inspection reports or other docketed correspondence between the NRC and Florida Power and Light Company.

The NRC does not attempt to document all'aspects of licensee programs and performance that may be functioning appropriately.

Rather, the NRC only documents issues that the NRC believes warrant management attention or represent noteworthy aspects of performance.

This letter advises you of our planned inspection effort resulting from the Turkey Point PPR review. It is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite. details our inspection plan for the next eight 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.

FP&L We willinform you of any changes to the inspection plan.

If you have any questions, please contact me at 404-562-4540.

N Sincerely, Docket Nos. 50-250, 50-251 License Nos. DPR-31, DPR-41

Enclosures:

1. Plant Issues Matrix
2. Inspection Plan 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. Hollinger Licensing Manager Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW 344th Street Florida City, FL 33035 (cc w/encls cont'd - See pag'e'4)

( Original signed by L. Wert )

Leonard D. Wert, Chief Reactor Projects Branch 3 Division of Reactor Projects

FP&L (cc w/encls cont'd)

John Gianfrancesco, Manager Administrative Support & Special Projects Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 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 WilliamA. Passetti Bureau of Radiation Control Department of Health and Rehabilitative Services 2020 Capital Circle SE, Bin ffC21 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 2740 Centerview Drive Tallahassee, FL 32399-2100

FP&L Distribution w/encls:

S. Collins, NRR J. Zwolinski, NRR W. Dean, NRR T. Boyce, NRR K. Jabbour, NRR C. Thomas, NRR G. Tracy, EDO J. Lieberman, OE L. Wert, Rll.

S. Rudisail, Rll PUBLIC Senior Resident Inspector U. S. Nuclear Regulatory Commission 9762 Southwest 344~ Street Florida City, FL 33035

  • (See previous concurrence)

OFFICE SIGNATURE NAME RII:DRP S

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/99 YES No 3/

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, OFFICIALRECORD COPY DOCUMENT NAME: GATUR EYPRPPRLFE899.WPD

FP&L Distribution w/encls:

S. Collins, NRR J. Zwolinski, NRR W. Dean, NRR T. Boyce, NRR K. Jabbour, NRR C. Thomas, NRR G. Tracy, EDO J. Lieberman, OE KMees-,R~

L. Wert, Rll S. Rudisail, Rll

-G-.Heplmr,RH PUBLIC Senior Resident Inspector U. S..Nuclear Regulatory Commiss' 9762 Southwest 344~ Street Florida City, FL 33035 OFFICE SIGNATURE NAME DATE COPY?

RII:DRP SRudlsail 3/

/99 YES No II' olislo f 99 ES'o Rll:

KLand 3/

/99 YES'o RII:DRS Hchrlstonson 3/

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Doc ENT AME: GATURKEYPnPPRiFEB99.

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Page:

1 of 5 Region II TURKEY POINT Date Source Functional Area United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area Template ID Type Codes Item Description Date: 03/23/1999 Time: 13:05:36 12/26/1998 1g98012 pri: OPS NRC

'OS Prl: 1A Operator response to a failed channel of the reactor protection and safeguards actuation system was prompt and thorough (Section 01.2).

Sec:

Sec: 3A Ter: 3B 12/26/1998 1998012 Pri: QPS Sec:

pOS pri: 1C The controls for obtaining usage of an offsite hydrogen recombiner following a design basis accident were formalized and detailed (Section 02.1).

Sec: 4C Ter:

12/26/1998 1998012 Pri: QPS Sec:

pOS prl: 5A The licensee was self critical and proactive in the area of self assessment.

A strong focus on nuclear safety was evident throughout the presentations at the Turkey Point 1998 Self Evaluation and the November Status meetings Sec: 5B (Section 07.1).

Ter:

12/26/1998 1998012 Pri: OPS Sec:

pOS pri: 5A A Quality Assurance audit on the corrective action process was comprehensive, detailed, and well written. The licensee had appropriately addressed a weakness in the root cause analysis process identified during the audit (Section 07.2).

Sec: 5C Ter: 5B 11/14/1998 1998011 Prl: OPS Sec:

pOS prl: 5A The Florida Power and Light Company Nuclear Review Board meeting was conducted in accordance with regulatory requirements and provided an independent review of the Nuclear activities at Turkey Point. (Section 07.1)

.Sec:

Ter:

11/14/1998 1998011-01 Pri: OpS Sec:

NCy prl: 1A A non-cited licensee identified and corrected violation was issued involving one instance of personnel error and failure to comply.with fuel handling procedures.

(Section 01.2)

Sec: 3A Ter: 1C 11/14/1998 1998011 Pri: Ops Sec: MAINT pOS prl: 2B The licensee's overall planning, preparation, and execution of Unit 3 refueling outage activities were good. Thorough testing was professionally conducted to ensure reliable safety system performance.

Discrepancies identified as a result Sec: 3A of surveillance activities were corrected.

(Section 01.2)

Ter: 4B 10/03/1998 1998010 Pri: Qps Sec:

prl: 1B Changes in core flux profile during the lengthy operating interval resulted in substantial inaccuracy in intermediate range nuclear instrumentation indications during a plant shutdown. An intermediate range trip bistable did not reset at

~

Sec: 3A the expected power level. Control room supervisory oversight did not ensure that the bistable reset as the power decrease was continued. An unplanned automatic reactor trip occurred. (Section 01.5)

Ter: 3C 10/03/1998 1998010 Pri: Qps Sec: ENG pOS prl: 2B 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 Sec: 3B engineer was noted. (Section 01.4)

Tef: 4B item Type (Compliance,Followup,other), From 08/23/1998 To 01/31/1999 Enclosure 1

Page:

2 of 5 Region II

- TURKEY POINT Date Source Functional Area United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area Template ID Type

~ Codes item Description Date: 03/23/1999 Time: 13:05:36 10/03/1998 1998010 Pri: OPS Sec: ENG POS prl: 3A The receipt inspection of new fuel for Unit 3 was carefully performed by knowledgeable individuals. TS and procedural requirements were satisfied during fuel movement (Section 01.1)

'ec:

2B Ter: 3B 10/03/1998 1998010 Pri: OPS prl: 2B Containment ambient temperature monitoring instrumentation was appropriately inctuded in the scope of the maintenance rule and complied with environmental qualification requirements.

NRC inspectors identified that an error Sec: MAINT Sec: 3B had been made during implementation of a procedure change to address a previously identified problem. (Section 03.1) 10/03/1998 1998010 Pri: OPS Sec: OTHER POS prl: 5A Licensee management was very self~tical and the inspectors noted strong focus on nuclear safety in presentations a

the Turkey Point monthly status meeting.

(Section 07.1)

Sec: 5B Ter:

10/03/1998 1998010 Pri: OPS Sec: PLTSUP Pri: 1C Sec: 1B Ter: 3B NRC POS 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 detai'led guidance to plant personnel.

Operations training prior to the hurricane was prudent.

Equipment and facilities were properly secured and essential plant personnel were available to provide continuous coverage during the hurricane.

(Section 01.3) 12/26/1998

'998012 Pri: MAINT NRC POS Pri: 2B System status changes made by the maintenance rule expert panel were thoroughly evaluated with realistic goal setting and inctuded discussions of risk (Section M7.1).

Sec: ENG Sec: 4B Ter: 4C 12/26/1998 1998012 prl: MAINT NRC POS Pri: 4B The licensee satisfactorily assessed and repaired a coolant leak in the 3A emergency diesel generator radiator.

Operator actions upon identification of the radiator leak were timely and appropriate (Section E1.1).

Sec: ENG

.Sec: 2A Ter: 3A 11/14/1998 1998011 Pri:MAINT NRC POS Pri:2B ThelicenseeappropriatelycontroliedequipmentandmaterialintheUnit3containmentbuildingfollowingrefueling activities to minimize potential adverse effects on emergency core cooling systems during postulated design basis Sec:

Sec: 3A accidents.

(Section M2.1)

Ter:

11/14/1998 1998011 Pri: MAINT NRC POS Prl: 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.

Sec:

Sec: 2B Applicable FME controls, M8TE controls, PMT requirements, and QC hold points were properly accomplished.

(Section M1.1) 10/03/1998 1998010 Pri: MAINT NRC POS Pri: 3A The weekly dieseldriven 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 Sec:

Sec: 2A trends.

The engine driven fire pump was in good condition. (Section M1.3)

Ter: 1C Item Type (Comp!iance,Followup,Other)

~ From 08/23/1 998 To 01/31/1999

Page:

3 of 5 Region II TURKEY POINT United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area Date: 03/23/1999 Time: 13:05:36 Date Source Functional Area Template Type Codes Item Description 10/03/1998 1998010 Prl: MAINT NRC POS Pri: 2B Sec: ENG Sec: 3A Ter: 4B The emergency diesel generator 4A surveillance test was satisfactorily performed.

Emergency diesel generator material condition was very good. The test procedure was dear, highly detailed, and easy to use. Operators'se ofthe procedure was professional and accurate.

Continuous engineering support and supervisory oversight were provided for the test. (Section M1.2) 10/03/1998 1998010 Pri: MAINT NRC POS Pri: 2B Sec: ENG Sec: 3B Ter:

A detailed Flow Accelerated Corrosion (FAC) program was in place and was being implemented in accordance with procedural requirements by knowledgeable licensee personnel. (Section M1.5) 10/03/1998 1998010 Pri: MAINT NRC STR Pri: 2B Sec: ENG Sec: 3C Ter: 3A Inservice Inspection (ISI) activities were being performed in accordance with requirements with strong licensee directio and oversight of contract personnel.

Overall, the licensee's ISI program was considered to be a strength.

(Section

,M1.4) 10/03/1998 1998010 Pri: MAINT NRC Sec: OTHER POS Pri: 3A Sec: 2B Ter: 3C 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, M8TE controls, PMT requirements, and QC hold points were properly accomplished. (Section M1.1) 11/14/1998 1998011 Prl: ENG Sec:

NRC NEG Pri: 4B Sec: 5B Ter:

After initial repairs on a leaking EDG radiator, post maintenance testing identified additional leaking tubes.

Engineering's initial extent of condition did not identify the fullextent of the problem. Subsequently, with technical assistance from radiator repair specialists, the radiator damage was appropriately assessed and repaired.

(Section E1.1) 11/14/1998 1998011 Prl: ENG Sec:

NRC POS Pri: 4B Sec: 4A Ter: 4C The licensee's implementation of modifications PC/M 964)92, Unit 3 CCW Head Tank Addition and PC/M 97-003, Unit 3 Thermal Overpressurization of Isolated Piping Modification, was conducted in accordance with the approved modification plans. The modification packages were thorough and the safety evaluations were adequate.

(Section E2.2) 11/14/1998 1998011 Pri: FNG Sec:

NRC POS Pri: 4B Sec: 4A Ter: 5C The Unit 3 RCP oil collection system design modification installation was performed well and the design modification package was thorough.

(Section E2.1) 11/14/1998 1998011

=

Pri: ENG Sec: MAINT NRC POS Pri:4B Sec: 4A Ter: 5C The Unit 3 modifications associated with the diesel fuel oil transfer pump system, main turbine control valve servo motor test vahre, and the motor operated valves 744A and 744B equalization line were appropriately performed and the modification packages were well planned and documented.

Additionally, lessons learned from a previous modification were appropriately addressed and prevented similar issues from recurnng.

Engineering and maintenance support during these modifications was a strength.

(Section E2.3) 10/03/1998 '998010 Prl: ENG NRC POS Pri: 2A Sec: MAINT Sec:4B Tef: 2B 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)

Item Type (Compliance,Followup,Other)

~ From 08/23/1998 To 01/31/1999

Page:

4 of 5 Region II TURKEY POINT Date Source Functional Area P

United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area Template ID Type Codes Item Description Date: 03/23/1999 Time: 13:05:36 12/26/1gg8 1gg8012 prl: PLTSUP NRC POS Prl: 1C The protected area fence was observed to have good physical integrity and material condition (Section S2.1).

Sec:

Sec: 2A Ter:

12/26/1998 1998012 Pri: PLTSUP NRC 'OS Pri: 1C The fourth quarter emergency preparedness drillwas satisfactorily conducted, met the drillobjectives, and concluded in a thorough training exercise.

An issue relating to document controls and other lessons learned from the ddll were Sec:

Sec: 5A being addressed by the licensee (Section P5.1).

Ter: 3B 11/14/igg8 1gg8011 prl: PLTSUP NRC POS Pri: 1C The licensee wa5 effectively maintaining controls for personnel monitoring, controls of radioactive material, radiological postings, radiation area controls, and high radiation area controls as required by 10 CFR Part 20. (Section R1.1)

Sec:

Sec: 3A Ter:

11/14/1gg8 1gg8011 pri: PLTSUP NRC POS prl: 1C Health physics had detailed procedures describing the requirements for posting and de-posting contaminated zones.

Hea!th physics technicians exhibited a good questioning attitude prior to posting a new contaminated zone in the dry Sec:

Sec: 3B storage warehouse.

Housekeeping in the dry storage warehouse was good. (Section R1.3)

Ter: 3A 10/03/tgg8 1gg8010 prl: PLTSUP NRC POS Prl: 1C The security force demonstrated good response during drills. Simulated intruders were apprehended prior to reaching the planned objective. However. lessons learned from the drill had not been communicated to the security force. The Sec:

Sec: 5A licensee promptly initiated corrective actions to ensure lessons learned on future drills would be promptly communicated to the security force (Section S5.1).

Ter: 5C Item Type (Compliance,Followup,Other), From 08/23/1998 To 01/31/1999

Page:

5 of 5 United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area Date: 03/23/1999 Time: 13:05:36 Type Co BU CDR DEV EEI IFI LER LIC MISC MV NCV NEG NOED NON P21 POS SGI STR URI VIO WK des:

Bulletin Construction Deviation Escalated Enforcement Item Inspector follow-up item Licensee Event Report Licensing Issue Miscellaneous MinorViolation NonCited Violation Negative Notice of Enforcement Discretion Notice of Non-Conformance Part 21 Positive Safeguard Event Report Strength Unresolved item Violation Weakness Legend emplate Codes:

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 4G Programs and Processes 5A Identification 5B Analysis 5C Resolution ID Codes:

NRC.

NRC Self Self-Revealed Licensee Licensee Functional Areas:

OPS Operations MAINT Maintenance ENG Engineering PLTSUP Plant Support OTHER Other EE!s.are apparent violations of NRC Requirements Enforcement Action"(Enforcement Policy), NUREG modified when the final decisions are made.

that are being

-1600. Howev ccordance with the "General Statement of Policy and Procedure for NRC decision on the issues identified by the EEls and the PIM entries may be considered for escalated enforcement action in a er, the NRC has not reached its final enforcement 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 likely to 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 08/23/1998 To 01/31/1999

0

TURKEY POINT INSPECTION PLAN MARCH 15 THROUGH NOVEMBER 30, 1999 INSPECTION PROCEDURE/

TEMPORARY INSTRUCTION PROGRAM DIRECTIVE-NUREG-1021 TITLE/PROGRAM AREA OPERATOR - INITIAL EXAMS NUMBER OF INSPECTORS OPERATIONS 3

3'LANNED INSPECTION DATES 8/99 9/99 TYPE OF INSPECTION-COMMENTS INITIALEXAMS IP 73753 MAINTENANCE MAINTENANCE ENGINEERING 3/99 CORE INSPECTION PROGRAM - ISI None

0

INSPECTION PROCEDURE/

TEMPORARY INSTRUCTION IP 84750 IP 86750 TITLE/PROGRAM AREA RADIOACTIVEWASTE TREATMENT,AND EFFLUENT AND ENVIRONMENTAL.

MONITORING SOLID RADIOACTIVE WASTE MANAGEMENT ANDTRANSPORTATION OF RADIOACTIVE MATERIALS NUMBER OF INSPECTORS PLANTSUPPORT PLANNED INSPECTION DATES 6/99 12/99 TYPE OF INSPECTION-COMMENTS CORE INSPECTION PROGRAM IP 83750 OCCUPATIONAL RADIATIONEXPOSURE 3/99 CORE INSPECTION PROGRAM - REFUELING OUTAGE IP 82701 IP 81700 OPERATIONALSTATUS OF THE EMERGENCY PREPAREDNESS (EP)

PROGRAM PHYSICAL SECURITY-SAFEGUARDS 11/99 3/99 11/99

.CORE INSPECTION PROGRAM CORE INSPECTION PROGRAM