IR 05000302/1989029
| ML20005E157 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/22/1989 |
| From: | Bradford W, Crlenjak R, Holmesray P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20005E156 | List: |
| References | |
| 50-302-89-29, NUDOCS 9001040002 | |
| Download: ML20005E157 (9) | |
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UNITED STATES '
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' NUCLEAR REGULATORY COMMIS$lON
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' 101 MARIETTA STREET N.W.
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50-302/89-29-
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Licensee:. Florida Power Corporation
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~3201-34th Street, South.
St; Petersburg, FL'33733
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Docket No:
50-302 License No.: DPR-72
.i Facility Name:. Crystal River Unit 3
- Inspection Conducted:: November 9 - December 15, 1989
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Inspectogs:
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. Holmes-Ray, Senior Resident Inspector Date Signed C. Mars t>%)s9
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p.Bradf
, R side t Inspector
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- Approved by:
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-R. Arlenjak, Chief _ '
Dat'e Si'gned'
Reactor Projects.Section 28 Division of Reactor Projects -
SUMMARY
. Scope:'
This routine inspection was conducted by two resident inspectors in-
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the. areas of plant -operations, security, radiological controls, Licensee Event Reports, Fitness for Duty. Training, cold weather preparations, and licensee action on previous inspection items.
-Numerous facility tours were conducted and facility operations observed.
Some of these tours and observations were conducted on backshifts.
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.Results:
No violations or deviations were identified.
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i 9001040002 891222 PDR ADOCK 05000302 Q
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-REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. Alberdi~, Manager, Nuclear Plant Technical-Support
- W. Bandhauer, Nuclear Operations Superintendent
- G. Becker,-Manager Site Nuclear Engineering Services
- D. Black, Nuclear'Results Specialist G. Boldt, Vice President Nuclear Production
- J. Brandely, Manager, Nuclear Integrated Planning
- P. Breedlove, Nuclear Records Management Supervisor
- L. Ceci11a, Nuclear Project Engineer
- J. Cooper, Superintendent, Technical Support
- G.-Cowles,_ Senior Nuclear Results Engineer R. Fuller, Senior Nuclear Licensing Engineer
'B. Hickle, Manager, Nuclear Plant Operations
- S. Johnson, Manager, Site Nuclear Services
- H. Koon, Assistant Nuclear Maintenance Superintendent
- K Lancaster, Manager, Site Nuclear Quality Assurance-W. Marshall,. Nuclear Operations Superintendent.
- P. McKee, Director,' Nuclear Plant Operations V. Roppel : Manager, Nuclear Operations Maintenance and Outages
- W..Rossfeld, Manager,_ Nuclear Compliance
- J. Russell, Senior Nuclear Fire Protection Specialist
- R. Thompson, Supervisor, Site Nuclear Engineering Services E. Welch, Manager, Nuclear Electrical / Instrumentation and Control Engineering _ Services
- R. Widell, Director, Nuclear Operations Site Support
- M. Williams, Nuclear Regulatory Specialist
- K. Wilson, Manager, Nuclear Licensing Other licensee _ employees contacted included office, operations, engineering, maintenance, chemistry / radiation and corporate personnel.
- Attended exit interview Acronyms and initialisms used throughouc
- : s report are listed in the s
last paragraph.
2.
Review of Plant Operations (71707)
Crystal River Unit 3 operated at a maximum power level of 96% during the reporting period with the following exceptions:
Power was reduced to 86% on November 17, 1989 to repair a leak on the
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feedwater line for the SB feedwater heater.
Power was reduced to 75% on November 25, 1989 to repair a salt water
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leak on "A" condenser waterbox.
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o The; plant was taken off line on December 8,1989 for a maintenance outage to replace a control rod drive stator. The plant.was returned to power operation-December 10, 1989.
Power was reduced to 75% on December 12,-_1989 to replace a sheared
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pin on the condenser circulating water inlet filter on "D" water box.
-- Power was increased to 96% and was limited by condenser delta temperature.
The plant operated at maximum allowed power for the remainder of the report per_iod, a.
Shift' Logs and Facility Records
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The. inspector reviewed records and discussed various entries 'with operations _ personnel to verify compliance with the Technical Specifications,(TS) and the licensee's administrative procedures.
The following records were; reviewed:
e Shift Supervisor's Log; Reactor Operator's Log; Equipment j
Out-0f-Service-Log; Shift Relief Checklist; Auxiliary Building Operator's Log;- Active Clearance Log; Daily Operating Surveillance Log; Short Term Instructions (STI); and ' Selected Chemistry / Radiation j
Protection. Logs.
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In addition to these record reviews, the inspector independently verified. clearance order tagouts.
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No _v_iolations or deviations were identified.
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Facility Tours and Observations
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-Throughout the inspection period, facility tours were conducted to observe-operations and maintenance activities in progress.
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operations and maintenance activity observations were conducted
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Also, during this inspection period, licensee meetings were attended by the inspector to observe planning and management activities.
The facility tours and observations encompassed the following areas:
security perimeter fence; control room; emergency diesel generator
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room; auxiliary building; intermediate building; battery rooms; and, electrical switchgear rooms.
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p The inspectors also observed-conditions in the following areas:
(1) Monitoring Instrumentation The following -instrumentation: and/or indications were observed to verify that indicated parameters were in accordance with the
- TS for the current operational mode:
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Equiprr.en t operating status; area atmospheric and liquid radiation monitors; electrical system lineup;. reactor operating parameters; and auxiliary-equipment operating-parameters.
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No violations or deviations were identified.
-(2) Shift Staffing
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The. inspector verified that operating shift staffing was in accordance with TS requirements and that control room operations were being conducted in an orderly and professional manner. In addition, the inspector observed shift turnovers on various occasions to verify the continuity of plant status, operational problems, and other pertinent plant information during these turnovers.
No violations or deviations were identified.
(3) Plant Housekeeping Conditions Storage of material and components, and cleanliness. conditions of various areas throughout the facility were observed to determine whether. safety and/or fire hazards existed.
No violations or deviations were identified.
(4) Radiological Protection Program L
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
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step-off pad conditions and disposal of contaminated clothing;
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Area postings and controls;
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Work activity within radiation, high radiation, and contaminated areas; Radiation Control Area (RCA) exiting practices; and,
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Proper wearing of personnel monitoring equipment,
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I protective clothing, and respiratory equipment.
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Area. postings were independently verified for accuracy by the
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inspector..The inspector also reviewed selected Radiation ~ Work Permits (RWPs) to verify that the RWP was current and that the
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controls were adequate.
No violations or deviations were identified.
. (5) Security Control
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In:the course of the monthly activities, the inspector included '
a review' of the licensee's physical security. program.
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performance of various shif ts of. the security force was observed in the conduct of daily activities to include: protected and
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vital area-access controls; searching of personnel, packages, and vehicles; badge issuance and retrieval; escorting 'of.
visitors; patrols;- and compensatory posts.
In addition, the
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inspector observed the operational status of Closed Circuit
Television (CCTV) monitors, the Intrusion Detection system in:
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the central and secondary alarm stations, protected area j
lighting, protected and vital area barrier integrity, and the security organization interface with operations and maintenance.
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No violations or deviations were identified.
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. (6).' Fire Protection Fire protection activities, staffing and equipment were observed to verify that-fire brigade staffing was appropriate and that i
fire alarms, extinguishing _ equipment, actuating controls, fire l
fighting equipment, emergency equipment, and fire barriers were
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operable, j
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No violations or deviations were identified.
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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 operability; calibrated equipment was
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utilized; and TS requirements were followed.
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The following tests were observed and/or data reviewed:
- SP-110, Reactor Protective System Functional Testing;
-.SP-130, Engineered Safeguards Monthly Functional Test; and,
- SP-3498, Emergency Feedwater Pump (EFP-2) Monthly Operability Demonstration.
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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 followed.
Maintenance was observed and work packages were-reviewed for the following maintenance activities:
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' Check and clean stator windings, rotor insulation test / check of-
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brushes, stator insulation test, and generator bearing insulation check, in accordance with Preventive Maintenance procedure (PM) 123, Periodic' Electrical Checks of Emergency Diesel Generator;
.DC ground investigation in accordance with Maintenance Procedure
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(MP) 531, Troubleshooting Plant Equipment; Motor replacement of ' penetration cooling fan Air Handling Fan
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(AHF) 9A; Clean engine oil strainer and replace strainer Delta P pressure gage
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on Diesel Generator IB; Isolation of the SB feedwater heater for leak repair and return to
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service in accordance with Operating Procedure (0P) 605, Feedwater
, System; Modification of spent fuel handling mechanism; and,
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Motor operated valves environmental qualification walkdown.
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No violations or deviations were identified.
4.
Review of Licensee Event Reports (92700)'.and honconforming Operations Reports (71707)
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Licensee Event Reports (LERs) were reviewed for potential generic
' impact, to detect trends, and to determine whether corrective actions appeared appropriate.
Events that 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.
(0 pen) LER 89-39:
This LER reported a 10 CFR 50 Appendix R
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separation criteria violation which would prevent the isolation of the letdown flow in the makeup system by remotely operated valves.
Manual valves were available and accessible.
This error in separation was discovered by the licensee during an engineering review of drawings to support an inspection by NRC personnel.
Upon discovery of the condition it was confirmed that a roving fire watch was in effect. The control circuit for the third letdowr. cooler outlet valve was checked and found to be acceptable.
This item is an additional part of licensee identified violation NCV 50-302/89-26-01. This LER will remain open to track the corrective action state g, o
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Cold Weather Preparations (71714)
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The -inspector. verified that cold weather protection measures were established. in accordance with the requirements. listed in Enclosure 16 4:
" Adverse Weather Conditions Checklist" of Administrative Instruction (AI)
- 500, Conduct of Operations.
F Also, 'as part of this inspection, discussions were held with licensee
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personnel to verify that areas of the plant'normally heated during plant
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i-operation were adequately protected during periods of prolonged plant
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shutdown.
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Generally, the climate at the Crystal River Facility is such that freezing temperatures do not occur for extended periods of time and do not generally create freezing problems.
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Fitness for Duty Training (TI 2515/104)
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On December 04, 1989, the inspector attended the licensee's Fitness for Duty (FFD) training sessions. The training covered general employee FFD training, general employee escorts FFD, and managers and supervisors FFD.
- Approximately 54 employees attended the general employee and escort
' training, and 15 managers / supervisors attended the managers and supervisors training.
The general employee escort-training presentation was designed to make the-employee aware of the personal responsibility to be competent in his work performance; to recognize the signs and symptoms that may indicate that a individual ~might not be fit for duty; the options available for help; and that all-employees remain fit for duty in order to ensure safe plant operation.
The managers and. supervisors training pointed out the managers / supervisors responsibility to be aware of the employee's work habits and personality; how alcohol and drugs, as well as personal problems, can affect the employee's job performance; and how to refer the employee for professional care.
The ' inspector had no further questions.
This TI is closed.
7.
Followup of On-Site Events (93702)
On November 30, 1989 at 12:51 PM the reactor experienced a turbine runback from 97% power to 60% power. The runback was caJsed by safety control rod
- 2_in group 3 dropping into the core. The control rod dropped during the conduct of Surveillance Procedure (SP) 110, Reactor Protection System Functional Testing, Section 9.12.12. The cause of the dropped control rod was a failed stator in the rod control mechanism.
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The. licensee initiated the required actions of Technical Specification 3.1.- 3.1.
The plant was stabilized at 55% power. The ejected control rod analysis was performed. ' The ejected rod worths are less than the zero l
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power. and full power limits specified in the-technical specifications, Due to system load restrictions and cool weather predictions the plant remained on line :at 55% to 60% power until' 11:00 PM, on December 8,1989.
The planned 5 day maintenance outage was completed in 3 days and the unit
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was returned to service on December 10, 1989 at 10:38 AM.
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A strength was observed during this event: After the rod drop a meeting was held to plan the trouble shooting and determination of the cause of the rod drop. Operations, maintenance, quality control, plant management,
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health physics, and system engineering discussed the probable causes, i
formulated a trouble shes ;ng plan and implemented the plan. The failed stator was identified in a timely and-professional manner.
8.
Licensee Action on Previously Identified Inspection Findings (92702 &
92701)
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(Closed) IFI 302/87-34-05, Replace Undersized delay Coils and Balance Relay Contacts for the Engineered Safeguards (ES) System.
The completion of work to balance the relays in the ES System is planned for refuel 7 outage and will be tracked as an outage item. This IFI
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is closed.
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(Closed) Violation 302/87-17-07, Failure to Retain ISI Records as Required by TS 6.10.2.B.
The licensee's corrective. action was to i
review the testing done in the 1980 and 1983 outages and a review of
hydrostatic testing associated with plant modifications. The hydros of the 1985 outage were also reviewed. Any tests that could not be
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verified to have sufficient evidence of being properly performed were retested during refueling 6.
This item is closed, f
9.
Evaluation of Licensee Quality Assurance Program Implementation (3E502)
An internal office evaluation was conducted on November 28, 1980, of the
. licensee's quality assurance program implementation by revieting recent inspection reports. SALP reports, open items, licensee corrective actions for NRC inspection findings, and licensee event reports.
Particular emphasis was placed on new items or findings since the last SALP report period (December 31, 1988).
It was recognized that there has been an improvement in engineering support, in the day-to-day support to the operations staff.
In the area of the electrical systems, it was determined to continue the in-depth review of the licensees corrective actions and modifications.
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10.
Exit Interview (30703)
The inspector met with licensee repre.sentatives (denoted in paragraph 1)
at the conclusion of the inspection on December 15 1989.
During this meeting, the inspector summarized the scope and fir, ngs of the inspection as they are detailed in this repor {
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The licensee representatives acknowledged the inspector's comments and did I
not. identify as proprietary any of the materials provided to or reviewed:
by the inspectors during,this inspection.
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10. Acronyms and Abbreviations
'AHF:
- Air Handling Fan
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- Administrative Instruction
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-CCTV - Closed Circuit Television CFR
- Code of Federal-Regulations lEFP-
- Emergency Feedwater Pump
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- Engineered Safeguard System FFD- - Fitness for Duty IFI Inspector Followup Item LER
- Licensee Event Report -.
MAR _ - Modification Approval Record MP
- Maintenance Procedure NCOR
. Nonconforming.0peration Report-
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- Non-Cited Violation NRC
.- Nuclear Regulatory Commission OP 0perating Procedure-g PM
- Preventive Maintenance RCA:
--1 Radiation Control Area i
- Radiation Work Permit SP
- Surveillance Procedure STI.
--Short' Term Instruction TS
--Technical Specification
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