ML20211A006
| ML20211A006 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/23/1987 |
| From: | Bryant J, Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20210V585 | List: |
| References | |
| 50-269-86-34, 50-270-86-34, 50-287-86-34, NUDOCS 8702190072 | |
| Download: ML20211A006 (7) | |
See also: IR 05000269/1986034
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION ll
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101 MARIETTA STREET, N.W.
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ATLANTA, GEORGI A 30323
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Report Nos: 50-269/86-34, 50-270/86-34, and 50-287/86-34
Licensee:
Duke Power Company
422 South Church Street
Charlotte, N.C.
28242
Facility Name: Oconee Nuclear Station
Docket Nos.: 50-269, 50-270, and 50-287
License Nos.: DPR-38, DPR-47, and DPR-55
Inspection Conducted: November 11 - January 12, 1986
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Inspector:
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J. C. Bryant
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Date Signed
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Approved by:
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Date Signed
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T. Peebles,' Section 'Chidf
Division of Reactor Projects
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-SUMMARY
Scope:
This routine, announced inspection involved resident inspection on-site
in the areas of operations, surveillance, maintenance, verification of engineered
safety features lineups, followup of events, emergency drills and performance
indicators.
Results: Of the seven areas, inspected, no. violations or deviations were identi-
fied.
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REPORT DETAILS
1.
Licensee Employees Contacted
- M. S. Tuckman, Station Manager
T. B. Owen, Maintenance Superintendent
R. L. Sweigart, Operations Superintendent
J. M. Davis, Technical Services Superintendent
- C. L. Harlin, Compliance Engineer
- F. E. Owens, Assistant Engineer, Compliance
N. A. Rutherford, System Engineer, Licensing
Other licensee employees contacted included technicians, operators,
mechanics, security force members, and staff engineers.
Resident Inspector:
- J. C. Bryant, Resident Inspector
- Attended exit interview.
2.
Exit Interview
The inspection scope and findings were summarized on January 12,198@ with
those persons indicated in paragraph 1 above. The licensee did not identify
as proprietary any of the materials provided to or reviewed by the
inspectors during this inspection.
3.
Licensee Action on Previous Enforcement Matters
Not inspected.
4.
Unresolved Items
No unresolved items were identified during this inspection.
5.
Plant Operations
The inspector reviewed plant operations throughout the reporting period to
verify conformance with regulatory requirements, technical specifications
(TS), and administrative controls.
Control room logs, shift turnover
records, and equipment removal and restoration records were reviewed
routinely.
Interviews were conducted with plant operations, maintenance,
chemistry, health physics and performance personnel.
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Activities within the control rooms were monitored on an almost daily basis.
Inspections were conducted on day and on night shifts, during week days and
on weekends.
Some inspections were made during shift change in order to
evaluate shift turnover performance.
Actions observed were conducted as
required by Operations Management Procedure 2-1.
The complement of
licensed personnel on each shift inspected met or exceeded the requirements
of TS.
Operators were responsive to plant annunciator alarms and were
cognizant of plant conditions.
Plant tours were taken throughout the reporting period on a routine basis.
The areas toured included the following:
Turbine Building
Auxiliary Building
Units 1,2, and 3 Electrical Equipment Rooms
Units 1,2, and 3 Cable Spreading Rooms
Station Yard Zone within the Protected Area
Standby Shutdown Facility
During the plant tours, ongoing activities, housekeeping, security,
equipment status, and radiation control practices were observed.
Unit 1 began the report period operating at 99% power, restricted to that
power by high steam generator level in B steam generator.
The unit
cnntinued operation at 98% power throughout the report period.
Unit 2 began the report period restricted to 92% power by high level in B
On November 30 vibration increased in No.11 bearing of
the turbine generator.
Vibration increased to 10 mils and power reduction
began at 7:30 p.m. on Decemoer 1 (power reduction was stopped at 15% power).
The unit was taken off line at 11:08 p.m. with reactor power maintained at
15%.
Bearing examination, repair and realignment were completed at 7:30
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p.m. on December 3.
Unit 2 was returned to 94% power and remained at that
level throughout the report period.
Unit 3 began the report period in a 3 reactor coolant pump operation mode at
72% power.
As described in the previous report, reactor coolant pump (RCP)
B1 had been shut down due to apparent internal damage to the pump.
Three
pump operation continued until December 17 when Unit I was shut down due to
increasing symptoms of pump problems in RCP-B1 and increasing vibration in
RCP-82. This event is discussed in more detail in paragraph 9.
Unit 3 will
be refueled during this outage.
No violations or deviations were identified.
6.
Surveillance Testing
The surveillance tests listed below were reviewed by the inspector to verify
procedural and performance adequacy.
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The completed tests reviewed were examined for necessary test prerequisites,
instructions, acceptance criteria, technical content, authorization to begin
work, data collection, independent verification where required, handling of
deficiencies noted, and review of completed work.
Surveillances reviewed included:
WR 59002 B Monthly PM Inspection of Keowee Hydro Generator
WR 54580 E Check and Calibrate RPS Loop A Reactor Coolant
Flow Transmitter
WR 59003 B Test Keowee Electro Mechanical Trip Circuitry
PM on 16 Cylinder Diesel Generator
PM on 12 Cylinder Diesel Generator
No violations or deviations were identified.
7.
Maintenance Activities
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Maintenance activities were reviewed during the reporting period to verify
that work was performed by qualified personnel and that approved procedures
in use adequately described work that was not within the skill of the trade.
Procedures and work requests were examined to verify proper authorization to
begin work, provisions for fire, cleanliness, and exposure control, proper
return of equipment to service, and that limiting conditions for operation
were met.
Work requests reviewed included:
WR 54759 C Replace missing washers on hydraulic snubbers
WR 04863 C Valve 2 BS4: Investigate failure to open from control
room and repair
WR 04886 C Investigate and repair reactor building fire alarm
WR 04619 C Investigate and repair 1 HP16 - will not open
WR 52514 E Repair cracked electrical penetration
WR 02672 C Repair valve 1 AS 39 - Has extreme back leakage
WR 03948 C Repair relief valve 1 MS 92 at TDEFDWP; valve leaks
past seat
No violations or deviations were identified.
8.
Design,DesignChanges,andModifications(IP37700)
The inspector reviewed several design changes and modifications to verify
that they were in conformance with 10 CFR 50.59 and Technical Specifications
(TS), and that they were reviewed and approved in accordance with TS and
established QA/QC controls.
The inspector also verified that the changes
were adequately tested, operator training packages were issued when
appropriate, and that signoffs for independent verification were recorded
where required.
Modifications were inspected in work and/or after
completion.
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Station modifications examined included the following:
a.
Modifications to condenser circulating water pumps (Report No.
86-26)
b.
Modifications to Keowee battery racks and installation of new
batteries (Report No. 86-20)
c.
Installation of buried, protected cables to CCW 8 and 9, installation
of a new terminal box, and termination of cables,.
d.
StandbyShutdownFacility(SSF)Modificationsincluding:
(1) SSF submersible pump and power source
(2) Air eductor for SSF auxiliary service water pump suction line.
(3)
Installation of yard discharge for SSF service water pump.
Review of these modifications determined that requirements had been met.
The licensee's program for temporary modifications, lifted leads and juspers
and implementation of the program was reviewed and reported in Report No.
50/86-20.
An earlier report stated that the licensee had brought approxi-
mately 14 corporate engineers on site to reduce the number of outstanding
modifications by expediting completion, elimination of duplication, or
determination that the change was no longer needed. To date, the number of
open design changes has been reduced from 1000 down to 500. The goal is to
reduce it to 300, considered by the licensee to be a workable number. All
but 20 items have now been scheduled for completion or for review.
No violations or deviations were. Identified.
9.
Unit 3 - Shutdown Oue to Reactor Coolant Pump Problems
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Report No. 86-33 describes shut down of reactor coolant pump (RCP) 3B1 due
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to increased motor frame vibration and possible loose parts on October 30,
1986, and to subsequent reactor operation at 72% power with only 3 RCP's in
operation.
On November 5, loose parts monitor (LPM) alarms were received for about 35
seconds from LPM sensors located on incore ins'.rument tubes (bottom of the
reactor vessel).
A Justification for Continued Operation was issued and
additional LPM equipment was obtained from the vendor, Babcock and Wilcox
(B&W).
More sophisticated equipment for analysis of impacts was later
added.
Impacts were analyzed and taped.
It was believed that there were
several small parts of 1 to 2 ounce size and 1 or 2 pieces weighing several
pnunds but which moved very little,
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On December 15 some change was noted in patterns of vibration on RCP's 3B2
and 3A1.
Reactor coolant chemistry began showing indications of possible
fuel damage and of some wear particles in the coolant system, which
indicated that possibly 3B2 pump was beginning to wear. During the night of
December 16 and morning of December 17, vibration of RCP 382 pump shaft
began increasing rapidly.
Unit 3 was taken off line at 5:42 p.m. on
December 17 and shut down.
Unit 3 will remain shut down for refueling, with startup scheduled for
March 12, 1987.
RCP's 3B1 and 3B2 will be rebuilt, and 3Al will receive
some rework.
In mid 1985 RCP 3A2 .is rebuilt with some modifications and
3Al was rebuilt to the extent that spare parts permitted.
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To date, RCP's 3B1 and 382 have been removed and examined.
RCP 3B2 has
shown no appreciable damage but 381 has extensive damage to the-impeller,
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the wear ring and the suction adapter.
No significant damage to the pump
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casing has been detected.
Pump damage will be
iscussed in considerable
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detail in Report No. 50-287/87-01 by a Regional inspector and will not be
discussed here.
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No violations or deviations were identified.
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10.
Emergency Drill
An emergency drill, beginning at 3:00 a.m. on December 15, 1986, was held at
the Oconee site to verify proper response by appropriate personnel within
the required time frame.
A site assembly was conducted and the Technical
Support Center and Operations Support Center were activated. All personnel
arrived within the time requirements.
The resident inspector was present
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and monitored the drill,
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No violations were identified.
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11.
Licensee Event Reports and Inspector Followup Items
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The inspector reviewed nonroutine event reports to verify the report details
met license requirements, identified the cause of the event, described
corrective actions appropriate for the identified cause, and adequately
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addressed the event and any generic implications.
In addition, as appro-
priate, the inspectors examined operating and maintenance logs, and records
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and internal investigation reports.
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Where appropriate, personnel were interviewed to verify that the report
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accurately reflected the circumstances of the event, that the corrective
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action had been taken or responsibility assigned to assure completion, and
that the event was reviewed by the licensee, as stipulated in the Technical
Specifications. The following event reports were reviewed:
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(Closed) LER 269/86-06:
End of Cycle Moderator Temperature Coeffi-
cient.
This item was closed based on the Licensees description of the
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event and NRR letter of November 26, 1986 which accepted the Licensee's
evaluation.
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(Clobed)IFI 269/86-18-01: Correct Post Trip Review Deficiencies. The
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inspector reviewed changes to the Perfomance Manual and to the
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procedure for post trip review.
Changes ir.clude the following:
Qualifications of those authorized to make post trip reviews;
requirement for a list of those authorized to make post trip reviews;
lists those parts of the procedure which must be completed prior to
approval for restart;
and describes proper completion of the proce-
dure.
12. Enforcement Conference
An enforcement conference was held with Duke Power Company (DPC) officials
in the Region II offices on December 22, 1986.
The purpose of the meeting
was to discuss findings of the Safety System Functional Inspection conducted
at Oconee'in May and June 1986.
Also, findings concerning loss of suction
to tne Emergency Condenser Circulating Water system were discussed. Action
to be taken has'not been finalized at this time.
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