IR 05000302/1990036

Insp Rept 50-302/90-36 on 901219-910125.No Violations Noted. Major Areas Inspected:Plant Operations,Security,Radiological Controls,Lers,Maint & Surveillance Activities

ML20217B272
Person / Time
Site:	Crystal River
Issue date:	02/20/1991
From:	Crlenjak R, Holmesray P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20217B241	List: IR 05000302/1990036 ML20217B237
References
50-302-90-36, NUDOCS 9103120050
Download: ML20217B272 (8)

Text

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Report No.: 50-302/90-36 Licensee: Florida Power Corporation 3201 34th Street, South St. Petersburg, FL 33733 Docket No.: 50-302 License No.: DPR-72 Facility Name: Crystal River 3 Inspection Conducted: Dec mber '.9.1990 - January 25, 1991 Inspect : Li J- 20 4I

. HolmeskRay, Senior Resident Inspector Date Signed Approved by: N'166 ,o a h- M M '?/

R. Crlenjak, Section Chief Date Signed Division of Reactor Projects SUMMARY Scope:

This routine inspection was conducted by one resident inspector in the areas of plant operations, security, radiological controls, Licensee Event Reports, maintenance, and surveillance activitie Numerous facility tours were conducted and facility operations observed. Some of these tours and observations were conducted on backshift Results:

During this inspection, violations or deviations were not identifie Plant startup was completed on December 19 and then power was held at 75 percent for two days to repair a condenser water box leak. Both operations and maintenance

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performed at a high level of competence during this perio PDR ADOCK 05000302 G PDR

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REPORT DETAILS Persons Contacted Licensee Employees

• J. Alberdi, Manager, Nuclear Plant Operations 3. Boldt, Vice President Nuclear Production P. Breedlove, Nuclear Records Management Supervisor

• R. Fuller, Senior Nuclear Licensing Engineer B. Hickle, Director, Quality Programs

• W. Marshall, Nuclear Operations Superintendent

• P. McKee, Director, Nuclear Plant Operations W. Neuman, Supervisor, inservice Inspection

• V. Roppel, Manager, Nuclear Plant Maintenance

• W. Rossfeld, Manager, Nuclear Compliance E. Welch, Manager, Nuclear Electrical / Instrumentation and Control Engineering. Services R. Widell, Director, Nuclear Operations Site Support

• M. Williams, Nuclear Regulatory Speciali3t K. Wilson, Manager, Nuclear Licensing Other licensee employees contacted included office, operations, engineering, maintenance, chemistry / radiation, and corporate personne NRC Resident Inspectors

• P. Holmes-Ray, Senior Resident Inspector

• Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragrap . Plant Status The plant completed a seven day outage to repair RCS valve leaks and commenced a startup on December 18. Power was limited to 75% for two days while repairing condenser waterbox leaks. The plant continued in power operation (Mode 1) for the duration of this inspection perio . Review of Plant Operations (71707) Shift Logs and Facility Records The inspector reviewed records and discussed various entries with operations personnel to verify compliance with the TS and the licensee's administrative procedure The following records were reviewed:

Shift Supervisor's Log; Reactor Operator's Log; Equipment Out-0f-Service Log; Shif t Relief Checklist; Auxiliary Building

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2 Operator's Log; Active Clearance log; Daily Operating Surveillance Log; STis; and Selected Chemistry / Radiation Protection Logs, Facility Tours and Observations Throughout the inspection period, facility tours were conducted to observe operations and maintenance activities in progress. Some operations and maintenance activity observations were conducted during backshifts. Also, during this inspection period, licensee meetings were attended by the inspector to observe planning and management activities. The format of the plan of the day continues to evolve. Planning now, each Friday, provides a weekly schedule covering the planned activities for each shop. This schedule is used as the focus of each day's planning meeting. Emergent work is discussed along with any problems concerning the scheduled work or carry over work. The result of this approach to the planning meeting is a shorter, more ccncise meetin The facility tours and observations encorpassed the following areas:

security perimeter fence; control room; emergency diesel generator room; auxiliary building; intermediate building; battery rooms; and electrical switchgear room The inspectors also observed conditions in the following areas:

(1) Monitoring Instrumentation l The following instrumentation and/or indications were observed l to verify that indicated parameters were in accordance with the TS for the current operational mode:

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i Equipment operating status; area atmos pheric and liquid radiation monitors; electrical system lineup; reactor operating parameters; and auxiliary equipment operating parameters,

! (2) Shift Staffing f

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The inspector verified that operating shif t staffing was in accordance with TS requirements and that control room operations were being conducted in an orderly and professional canner. In addition, the inspector observed shif t turnovers on various occasions to verify the continuity of plant status, operational problems, and other pertinent plant information during these

! turnover (3) Plant Housekeeping Conditions Storage of material and components, and cleanliness conditions of various areas throughout the facility were observed to

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4 determine whether safety and/or fire hazards existed. The formal cleanu of a specified area each week continues and is a beneficial progra Housekeeping remains an area where improvement can be mad Tape, unused protective clothing, tools, and work trash can still be seen in the auxiliary building and the intermediate building. The painting of the walls in the intermediate building not only makes the building look cleaner but also imoroves lighting effectivenes (4) Radiological Protection Program Radiation protection control activities were observed to verify that these activities were in conformance with the facility policies and procedures, and in compliance with regulatory requirements. These observations included:

- Entry to and exit from contaminated areas, including step-off pad conditions and disposal of contaminated clothing;

- Area postings and controls;

- Work activity within radiation, high radiation, and '

contaminated areas;

- RCA exiting practices; and

- Proper wearing of personnel monitoring equipment, protective clothing, and respiratory equipmen The inspector reviewed selected RWPs to verify that the RWP was current and that the controls were adequat (5) Security Control in the course of the monthly activities, the inspector included a review of the licensee's physical security program. The performance of various shif ts of the security force was observed in the conduct of daily activities to include: protected and vital area access controls; searching of personnel, packages, and vehicles; badge issuance and retrieval; escorting of visitors; patrols; and compensatory posts. In addition, the inspector observed the operational status of CCTV monito'rs, the intrusion Detection system in the central and secondary alarm stations, protected area lighting, protected and vital area barrier integrity, and the security organization interface with operations and maintenanc (6) Fire Protection Fire protection activities, s ta f fi ng , and equipment were observed to verify that fire brigade staffing was appropriate and that fire alarms, extinguishing equipment, actuating

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0 controls, fire fighting equipment, emergency equipment, and fire barriers were operabl The inspectors, as a result of routine plant tours and various operational observations, determined the general plant and system material conditions were being satisfactorily maintained, plant security program was being effective, and the overall performance of plant operations was goo Violations or deviations were not identifie . Review of Maintenance (62703) and Surveillance (61726) Activities Surveillance tests were observed to verify that approved procedures were being used: qualified personnel were- conducting the tests; tests were adequate to verify equipment operabili ty; calibrated equipment was utilized; and TS requirements were followe The following tests were observed and/or data reviewed:

- SP-110, Section 9.9, Reactor Protection System Functional Testing;

- SP-168, Section 4.5, Radiation Monitoring Flow Rate Instrumentation Calibration; and

- SP-317, Reactor Coolant System Water Inventory Balanc In addition, the inspector observed maintenance activities to verify that correct equipment clearances were in effect; work requests and fire prevention work permits, as required, were issued and being followed; quality control personnel were available for inspection activities as required; and TS requirements were being fol?cwe Maintenance was observed and work packages were reviewed for the following maintenance activities:

- PM-1800, Check Valve Predictive / Preventive Maintenance Program Inspc-tion of Piston Lift, Stop, and Angle Stop Check Valves;

- WR-02/0081 for valve RWV-131;

- WR-279576 for work on SAP-10, station air compressor, to replace the small bore tubing and fittings to stop leaks; and

- WR-89346 for flange inspection of the Emergency Diesel Generator Jacket Cooling System-on EDG-1 For the surveillance and maintenance activities observed and listed above,

the inspector determined that .the work was performed in a satisfactory l manner in accordance with procedural requirements and met the requirements L of the Technical Specification Violations or deviations were not

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identified.

l L Review of Licensee Event Reports (92700)

LERs were reviewed for potential generic impact, to detect trends, and to determine whether corrective actions appeared appropriate. Events that

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were reported immediately were reviewed as they occurred to determine if the TS were satisfied. LERs were reviewed in accordance with the current NRC Enforcement Policy. LERs 90-01 and 90-16 are close (1) (Closed) LER_ 90-01,' Plant shutdown required by technical specifications due to excessive reactor coolant system unidentified leakage caused by valve packing failur On January 22, 1990, at 11:05 a.m., RCS unidentified leakage was calculated to be 1.3 gpm, which was in excess of the 1.0 gpm leakage allowed by TS 3.4.6.2.6. A reactor shutdown was commenced at 12:05 p.m. and an Unusual Event emergency s tatus was entered. Plant shutdown was completed at 3:50 p.m. on January 22, 1990. At 5:00 p.m., the same day, the RCS leakage was determined, by the licensee, to be from the packing on the block valve (RCV-11) for the PORV. .

Valve RCV-11 was closed and the leakage reduced to 0.4 gpm as indicated by leak rate calculations at 11:30 p.m. January 22, 199 At this time the Unusual Event was terminated. On January 24, 1990, the plant was returned to service with RCV-11 shut, which is allowed by TS. Plans were made to repair RCV-11 at the next outage. On February 13, 1990, the plant was shut down and cooled down for maintenance and RCV-11 was repacked. After the plant was returned to power on February 19,1990, RCV-11 packing was not leaking with the valve open ard therefore the PORV was not isolated. Root cause investigation by the licensee determined that the packing of RCV-11 leaked due to excessive torque or, the packing gland washers, causing the anti-extrusion rings to fail. This item is close (2) . (Closed) LER 90-16, Improper wire termination causes inadvertent de-energizing of instrumentation and control power when contacted, resulting in automatic actuation of emergency feedwate On October 10, 1990, corrective maintenance was to be performed on a redundant NNI-X power supply. The possibility of loss of NNI-X was recognized and the operating shift briefed on actions to be taken if NNT-X was los During the maintenance, the power sensing wire from the operating NNI-X power supply was touched and it failed at the terminal block. This failure at the crimped lug resulted in loss of NNI- Operations took proper action and the plant systems functioned as designe The crimped terminations were replaced with soldered connections in NNI-X and this modification is planned for the 1991 mid-cycle outage for NNI-Y. This item is close (3) (Closed) LER 89-17, Emergency diesel generator start results from inadvertent operation of a manual air start valve due to inadequate pre-job briefin On May 1,1989, with the unit in cold shutdown, preparation work for painting the emergency diesels was in progress. At 11:24 a.m., the B

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EDG was started when a painter stepped on one of the manual start valves. The EDG was shut down and returned to standby lineup by the L

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operators at 11:32 a.m.. The cause of this event was determined by the licensee to be an inadequate pre-job briefing in that the contract painters were not specifically cautioned about the air start valve To prevent a recurrence, temporary metal guards were placed over the air start valves and the shif t supervisors and assistant shif t supervisors reviewed the even Also, the buddy system was used by the painters when climbing to insure proper footin This item is close (4) (Closed) LER 89-19, Lack of documentation of planned reactor protection system actuation necessitates event repor On June 8,1989, with the unit in cold shutdown, an RPS actuation took place due to ongoing work to the B loop hot leg temperature sensors. The RPS actuation caused no control rod movement in the shutdown plant conditio The actuation was expected by the operators, but since this expectation was not documented the LER was required. The pre-job briefing check list from Al-500, Conduct of Operations, may be used to document expected actuations. This item is close Violations or deviations were not identifie . Followup of Onsite Events (93702)

During this report period, a chemistry problem (contaminant in the RCBTs)

was -investigated and corrective action . formulated. The contaminant was found to be a cleaning solvent. The method of entry to the RCBTs has not been determined. . The cleanup will require draining, opening, and inspecting followed by appropriate cleaning actions. In the past there has been an algae growth in these tanks which required opening and ventilation to kill the alga Until the tank (s) are opened it will not be known if algae is a contributor to the current chemistry problem.

i Violations or deviations were not identifie . Exit Interview (30703)

The inspection scope and findings were summarized on January 28, 1991, with those persons indicated in paragraph 1.. Proprietary information is not contained in this repor Dissenting comments were not received from the license . Acronyms and Abbreviations AFW - Auxiliary Feedwater System ALARA - As low as Reasonably Achievable

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B&W - Babcock & Wilcox CCTV - Closed Circuit Talevision CFR - Code of Federal Regulations DEV - Deviation i i

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ECCS - Emergency Core Cooling System (s)

EDG - Erergency Diesel Generators EFP - Emergency Feedwater Pump F - Fahrenheit FPC - Florida Power Corp.

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FSAR - Final Safety Analysis Report gpm - gallons per minute HP - Health Physics I&C - Instrumentation and Control ICC - Inadequate Core Cooling ICS - Integrated Control System IFI - Inspector Followup Item ISI - Inservice Inspection IST - Inservice Test LC0 - Limiting Condition for Operation LER - Licensee Event Report MAR - Modification Approval Record MOV - Motor Operated Valve MP - Maintenance Procedure MVP - Make-Up Pump MW --Megawatt NCOR - Nonconforming Operation Report NNI - Non Nucleer Instrumentation NRC Nuclear Regulatory Commission PM - Preventive Maintenance PORV - Power Operated Relief Valve psig - pounds per square inch gauge QC - Quality Control-QA .- Quality Assurance RCA - Radiation Control Area RCBT - Reactor Coolant Bleed Tank RCP - Reactor Coolant Pump RCS - Reactor Coolant System RCV - Reactor Coolant Valve R0 - Reactor.0perator RWP - Radiation Work Permit SAP - Station Air Compressor SG - Steam Generator SP - Surveillance Procedure STI - Short Term Instruction SW - Nuclear Services . Closed Cycle Cooling System TS - Technical Specification UNR -- Unresolved Item V10. - Violation WR - Work Request

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