IR 05000302/1990029
| ML20058F647 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/31/1990 |
| From: | Crlenjak R, Holmesray P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058F641 | List: |
| References | |
| 50-302-90-29, NUDOCS 9011090041 | |
| Download: ML20058F647 (9) | |
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[em an gt,g'"o Utelito ST AT ES NUCLEAR HEGULATORY COMMicSION
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101 tAAnttTTA STRtt1, N.W.
b ATL ANT A,0LOROB A 30373 4-
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I Report No:
50-3N/90-29
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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
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Facility Name:
Crystal River 3
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Inspection Conducted: Sept mber 8 - October 5, 1990 Inspecto :
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to so On V. Holmes-Ray, Senior Resident Inspector DageSigned e
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Accompanying ~ Personnel:
R. Spence, Resident inspector, in Training B
esai, Resident inspector, Oconee
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chin, Project Engineer, Region 11
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-Approved by:'
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R. Cirenjak, Section' Chief-
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D6te Figned w
Division of Reactor Projects SUMMARY n
Scope:. This routine inspection was conducted by one resident inspector in the-areas of plant-operations,. security; radiological controls,
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. modifications, and licensee action on previous inspection items.
Numerous.
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-facility tours were conducted and facility operations observed.
Some of these tours and observations were conducted on backshifts.
Results:.No violations or deviations were identified.
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9011'090041 901031 PDR ADOCK 05000302
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REPORT DETAILS 1.
Persons Contacted Licensee Empt'yees
- J. Alberdi, M.r.49er, Nuclear Plant Technical S ysort i
- W. Bandhauer, Nuclear Operations Superintendent
- G. Boldt, Vice President Nuclear Production
- J. Colby, Nuclear Principal' Mechanical Engineer B. Hickle, Manager Nuclear Plant Operations
- A. Kazemfar, Supervisor, Radiological Support Services W. Marshall, Nuclear Operations Superintendent
- P. McKee, Director, Nuclear Plant Operations
- S. Robinson, Nuclear Chemistry and Radiation Protection
Superintendent
- V Roppel, Manager, Nuclear Plant Maintenance
- W Rossfeld, Manager, Nuclear Compliance
- F Sullivan, Manager, Nuclear Plant Systems Engineering E. Welch, Manager, Nuclear Electrical / Instrumentation and Control Engineering Services R. WidcM, Director, Nuclear Operations Site Support
- M, Williams, Nuclear Regulatory Specialist
- K, Wilson, Manager, Nuclear Licensing Other licensee employees contacted included office, operations,
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engineering, maintenance, chemistry / radiation, and corporate personnel.
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragrarh, 2.
ReviewofPlantOperations(71707)
The plant continued in power operation (Mode 1) for the duration of this inspection period'with power reductions for cleaning of secondary heat exchangers and to stop a condenser tube leak, a-Shift Logs and Facility Records The inspector reviewed records and discussed various entries ~ with
' operations. personnel to verify compliance with the Technical Specifications (TS)andthelicensee'sadministrativeprocedures.
The following records were reviewed:
Shift Supervisor's Log; Reactor Operator's Log; Equipment
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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 /P,adiation Protection Logs, in addition to these record reviews, the inspector independently verified clearance order tagouts.
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b.
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 facility tours and observations encompassed the following areas:
security perimeter fence; control roomt emergency diesel generator room; auxiliary building; intermediate building; battery rooms; and electrical switchgear rooms.
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 15 for the current operational mode:
I Equipment operating status; area atmospheric and liquid radiation monitors; electrical system lineup; reactor operating parameterst and auxiliary equipment operating parameters.
(2) Shift Staffing
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 profestional manner. In addition, the inspector observed shift turnovers on various occasions-to verify the continuity of plant status, operational problems, and other pertinent plant infomation during these turnovers.
(3)
Plant Housekeeping Conditions Storage of material and components, and cleanliness conditions of various ' areas throughout the f acility were observed to determine whether safety and/or fire hazards existed.
(4) Radiological Protection Program m
Radiation protection control activities were observed to verify that these activities were in confomance with the facility policies and procedures, Gnd in com>11ance with regulatory requirements. These observations included:
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Entry to and exit from contaminated areas, including
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step off pad conditions and disposal of contaminated clothing; Area postings and controls; i
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Work activity within radiation, high radiation, and
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contaminated areas; Radiation Control Area (RCA) exiting practices; and
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Proper wearing of personnel monitoring equipment,
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protective clothing, and respiratory equipment.
Area postings were independently verified for accuracy by the inspector.
The inspector also reviewed selected Radiation Work Pemits (RWPs) to verify that the RWP was current and that the controls were adequate.
(S) Security Control 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 shifts of the security force was observed
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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 Closed Circuit Television (CCTV) monitors, the Intrusion Detection system in the central and secondary alarm stations, protected area lighting, protected and vital area barrier integrity, and the
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security organization interface with operations and maintenance.
(6) Fire Protection Fire protection activities, staffing, and equipment wee observed to verify that fire brigade staffing was appropriate and that fire alarms, extinguishing equipment, actuating controls, fire fighting equipment, emergency equipment, and fire-barriers were operable.
(7) System Walkdown The inspector walked down portions of certain systems including.
Makeup, Decay _ Heat removal, Radwaste, and Fire Protection to observe calibration control of local gages and process instrumentation.
During the tour the < nspector noted that certain gages on the Radwaste Panel had calibration stickers indicating overdue calibration dates.
This was brought to the ettention of the Assistant Shift Supervisor on duty as well as the responsible Instrument and Control (180) supervisor.
The calibration status of the gages in question was checked against the information avulable on the computerized calibration tracking system.
With one exception (WD-152-TI), all the gages
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were shown to be in calibration indicating that as required by procedure some calibration stickers were not updated following calibration.
As such, not updating stickers is not a problem
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since the computerized tracking is updated following calibration and work requests for future calibrations are generated from data available on the computer; however, the need for consistency is warranted.
The resident inspectors will continue to follow this issue.
The inspectors, as a result of routine plant tours and various operational observations, determined that the general picnt and system material conditions were being satisfactorily maintained, the plant security program was being effective, and the overall performance of
)lant operations was good. No violations or deviations were identifiec.
3.
Review of Maintenance (62703) and Surveillance (61726) Activities
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Surveillance tests were observed to verify that ap> roved procedures were being used; qualified personnel were conducting tie tests; tests were adequate to verify equipment operability; calibrated equipment was
utilized; and TS requirements were followed.
The following tests were observed and/or data reviewed:
- SP-113, Power Range Nuclear Instrumentation Calibration;
- SP-146A, [FIC Monthly functional Test;
- SP-317, RC System Water Inventory Balance; and
- SP-367, fire Service Valve Alignment and Operability Check, in addition, the inspector observed maintenance activities to verify that correct equipment clearances were in effect; work requests and fire prevention crt: permits, as required, were issued and being followed; quality contrri personne1'were available for inspection activities as
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required; and TS requirements were being followed.
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Maintenance was observed and work packages were reviewed for the following maintenance activities:
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MP-118, Bolted and Screwed Valve Bonnet Maintenance, WR 2058644 repair EGV-14;
- MP-217, Rev. O, Air Test and Balance, WR NV02745229;
- MP-4020, Maintenance of limitorque Valve Operators Type SMB-0 thru SMB-4, SM3-4T, SMB-5, SB-0 thru SB-4, and HBC Units; and
- MP-805, Scaling of Penetrations, WR 272336 grouting of fire barriers.
For the surveillance and maintenance activities observed and listed above, the inspectors determined thct the work was performed in a satisfactory manner in accordance with procedural requirements and met the requirements
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of the Technical Specifications.
No violations or deviations were identified.
4.
NUREG 0737 - TMI Task Action Dlan item Review (T! 2515/065)
Item II.E.4.1.2 (ll.E.4.1.1.B), NUREG 0737 - Hydrogen Control Procedures Reviewed and Upgraded.
This item was left open in NRC Report 50-302/90 24 pending issue of the hydrogen recombiner operating procedure.
Procedure OP-4178, Operation of
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the Post-Accident Hydrogen Recombiners, was effective on September 12, l
1990. This item is closed. This also completes action on Tl 2515/65.
5.
Followup of Onsite Events (93702)
from Refuel 7 outage in June 1990, the "0" reactor Since startup(RCP) motor has been leaking more oil than normal.
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coolant pump The licensee has been trending oil leakage for all four RCPs.
The D motor leakage increased to about 2.2 gallons per day.
Trend analysis of the lube oil collection tank (LOT) levels showed that most of the oil from the 0 motor was not being collected in the LOT.
A visual inspection of the RB sump revealed a substantial amount of oil in the sump.
When questioned by the senior resident inspector as to the
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fire hazard and the effect of the oil on low pressure injection recirculating phase the licensee produced, from file, a fire hazards analysis indicating that the plant could be safely shutdown with the fire loading from the leaking oil. Also a 1988 analysis stated that i
the effectiveness of the recirculation phase of low pressure injection would not be impaired by 800 gallons of oil in the RB sump.
The licensee has planned a shutdown to Mode 3 to investigate and
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repair, if possible, the leak from RCP D and also RCP B which has an increasing leakage trend.
The outage is expected to oc~ cur on or
'i before October 12, 1990.
b.
On September 18, 1990, with the >1 ant at full power, a flow path from the RB sump to the auxiliary bu iding was inadvertently established while draining a portion of the decay heat system for maintenance.
.l This flow path was open for about fourteen hours. This violation of containment integrity is the subject of NRC report 50-302/90-32.
c.
On September 24, 1990, the licensee discovered that guard encapsulation of a portion of the decay heat system was not leak tight. The licensee repaired the encapsulation by installing plugs
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in the open adapters.
Details of this event are contained in NRC
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Report 50-302/90-32.
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Licensee Action on Previously Identified Inspection Findings (92702 &
92701)
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a.
(Closed)IFl 302/89-08-02, Review the licensee's activities to repair the motor for RCP-10 The motor rotor for the 0 reactor coolant pump was shipped to General Electric in Memphis, Tennessee for repair of rotor core slippage and
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space block installation during Refuel 8 in 1990.
In addition to RCP 0, the rotors for RCP B and C were also repaired during April /May i
1990.
The A rotor was inspected and showed no repair was necessary.
All RCPs are currently operating with the unit at full power.
This
item is closed.
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(Closed)IFl 302/89-08-05, Review the licensee's revision to the FSAR
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regarding the RB ventilation system
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When the licensee modified the reactor building ventilation system and the hydrogen purge systems to remove Emergency Safeguards (ES)
signal closure from the 48 inch butterfly valves and install the ES
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signal closure on the six inch hydrogen purge valves, this IFl was opened to track the update of the FSAR.
The inspector reviewed the affected cha)ters of the FSAR and found that revisions have been made reflecting tie current plant configuration. This item is closed, c.
(Closed) IFl 302/89-11-05, Review the revision to Section 9.9 of the FSAR regarding hydrogen and nitrogen storage Section 9.9 of the FSAR was revised to accurately describe the storge location of hydrogen and nitrogen.
This change was
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accomplished in revision 13 to the FSAR. This item is closed.
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(Closed)IFl 302/89-19-04, Follow the licensee's efforts to revise TS
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on DHR and-BS system total allowable leakage
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As part of the Technical Specifications Improvement Program (TSIP),
which has been submitted to NRR on Technical Specification Change Notice 171, the total leakage values for the Decay Heat Removal (~DH)
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and Reactor Building Spray (BS) systems and the appropriate pressures have been corrected.
The procedure, SP-412. ECCS and Containment Spray System Leak Rate Test is correct. This item is closed, e.
(Closed) Violation 302/89-19 05, Failure to aerform channel functional tests _on the containment hydrogen mon 9 tors
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in addition to the corrective action for LER 89-27 (Closed in Repcrt 90-26) which reported this event, the licensee has implemented a computer tracking system to insure that the appropriate procedures are revised to reflect a TS change. A formal tracking system coupled with heightened sensitivity of Department Managers completes,the corrective action for this item.
This item is closed.
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(Closed) Violation 302/89-20-01, Failure to follow procedure and maintain ASV-167 locked
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Procedures requiring verification of Raw Water Pump mating sufaces'
l condition prior to assembly and locLing of valve ASV-167 wen reviewed. The inspector reviewed the documentation and verified that the licensee modified MP-150, Maintenance of Raw Water Pumps, to specify the mating surfaces to be inspected and to include Hold Points to verify the deburring of these surfaces as the parts are being assembled.
The inspector verified that valve ASV-167 was locked in a throttled position and that a spacer was installed on the valve stem to prevent the valve from being fully closed.
A label plate was also installed at the valve to call operator attention to relocking the valve after i
adjustment. This item is closed.
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(Closed) violation 302/90-09-02, Inadequate range of testing to prove correct index marks The licensee took prompt action to correct the index lettering of the fuel handling bricge by placing temporary, and a few days later
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permanent, correct index marking on the bridge. Also, a letter dated June 19, 1990, was sent to all design engineers detailing this event and stressing the importance of detailed review of vendor submittals.
This item is closed.
No violations or deviations were identified.
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7.
Followup of Part 21 Reports (36100)
P2188-05, Potential deviation to specifications in RY vertical indicators, series 15, all versions of RY 1 and 2.
A Bailey Controls Company letter to the NRC dated October 10, 1988, described a safety concern about a poteritial deviation to specifications in RY Vertical Indicators, in
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compliance with 10 CFR 21.
This was followed by a letter from Babcock &
Wilcox to the NRC dated October 20, 1988, which stated that the above
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referenced RY Vertical Indicators were supplied by B&W to FPC as non-safety related components and therefore do not constitute a
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substantial safety hazard reportable under 10 CFR 21 for Crystal River 3.
The licensee closed this item after testing all Bailey RY indicators at Crystal River 3, as of September 30, 1989, per the vendor's recommended testing method - none of these indicators exhibited the symptoms described by the vendor. This item is closed.
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ExitInterview(30703)
The inspector met with licensee representatives (denoted in paragraph 1)
'at the conclusion of the inspection on October 9,1990.
During this meeting, the inspector sumarized the scope and findings of the inspection as they are detailed in-this report.
The licensee representatives acknowledged the inspector's coments and did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
Dissenting comments were not received from the licensee.
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Acronyms and Abbreviations Auxiliary Feedwater System AFW
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ALARA - As low as Reasonably Achievable Reactor Building Spray BS
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Babcock & Wilcox B&W
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Closed Circuit Television CCTV
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Code of Federal Regulations CFR
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Deviation DEV
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EmergencyCoreCoolingSystem(s)
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Emergency Diesel Generators EDG
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Final Safety Analysis Report FSAR
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Instrumentation and Control 1&C
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Inadequate Core Cooling ICC
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Integrated Control System ICS
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Inspector Followup item IF1-
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Inservice Inspection 151
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Inservice Test IST
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Licensee Event Report LER
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Lube Oil Tank LOT
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Modification Approval Record MAR
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Maintenance Procedure MP
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Make Up Pump MVP
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Nonconforming Operation Report NCOR
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Nuclear Regulatory Commission NRC
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Office of Nuclear Reactor Regulation NRR
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Preventive Maintenance PM
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Quality Control QC
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Quality Assurance QA
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Reactor Building RB
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Radiation Control Area RCA
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Reactor Coolant Pump RCP
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Reactor Operator RO
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Radiation Work Pemit.
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Steam Generator S/G
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Surveillance Procedure SP
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Short Term Instruction
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Nuclear Services Closed Cycle Cooling System D
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Three Mile Island
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Technical Specification
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. Technical Specifications improvement Program
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Unresolved-Item UNR
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-VIO Violation
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Work Request WR
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