ML20141E500
| ML20141E500 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/05/1986 |
| From: | Boardman J, Ireland R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20141E456 | List: |
| References | |
| 50-382-85-31, NUDOCS 8602250270 | |
| Download: ML20141E500 (6) | |
See also: IR 05000382/1985031
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' APPENDIX B
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..U.S.
NUCLEAR REGULATORY COMISSION
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REGION IV
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NRC Inspection Report:
50-382/85-31
Operating License:
- Docket
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LLicensee:
Louisiana Power and Light Company (LP&L)
142 Delaronde Street
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New Orleans, Louisiana 70174
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Facility Name: Waterford Steam Electric Station,, Unit 3
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Inspection At:
Taft, Louisiana
Inspection Conducted:
December 2-6,-1985
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Inspector:
4? / .CN b d
.2/S/r2
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p J. R.
30ardman, Reactor Inspector, Operations
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Section, Reactor Safety Branch
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Approved:
N / . c I s /e M
4/5/vd,
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R. :. Ireland, Acting Chief, Operations
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Section, Reactor Safety Branch
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Inspection Summary
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Inspection Conducted December 2-6, 1985 (Renort 50-382/85-31)
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Areas Inspected:
Reactive, announced inspection of the licensee preventive
maintenance program and nonlicensed staff training.
The inspection involved 36
inspector-hours onsite by one NRC inspector.
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Results: Within the one area inspected (corrective maintenance), one violation
was identified (failure to adequately evaluate and report defective General
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Electric AKR-50 circuit breakers in accordance with 10 CFR Part 21,' paragraph 3).-
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DETAILS
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Persons Contacted
Principal Licensee Employees
- R. P. Barkhurst, Plant Manager
- L. W. Myers, Operations Superintendent
- S. Alleman, Assistant Plant Manager Technical Service
- F. J. Englebracht, Manager Plant Administrative Services
,*A. S. Lockhart, Site Quality Manager
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- R. B. Willis, Manager, Engineering and Nuclear Safety
- D. Packer, Manager, Training
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- H. A.-Trigg', Records and Administration Manager
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- P. V. Prasankumar, Technical Support Supervisor
- R. V. Seidle, Engineering and Nuclear Safety
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- K. L. Brewster, Onsite Licensing
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L. Laughlin, Technical Support
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J. Mahoney, Maintenance
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- Denotes those attending the exit interview on December 6, 1985.
The NRC inspector also interviewed other licensee personnel.
2.
Followup on Previously Identified Items
a.
(0 pen) (382/8425-01) Licensee Document Controls for Vendor
Manuals and Technical Data
The NRC inspector began the inspection on licensee corrective action
for the subject violation by reviewing the following licensee pro-
cedures relating to the review and control of vendor manuals:
PMI-016, " Vendor Manual Program," Revision 1,
dated July 31, 1985
PPP-306, " Engineering Review," Revision 0, dated June 13, 1984,
and Revision 1, dated September 21, 1984
PMP-004, " Control of Vendor Manuals," Revisions 0, 1, and 2,
dated April 16, 1984, November 15, 1984, and May 27, 1985
respectively
PMP-002, " Document Control," Revision 1, dated October 22, 1985
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The NRC inspector found no apparent programmatic problems or concerns
in these procedures, except as follows:
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During review by the NRC inspector of potentially reportable
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events (PRE's)'for possible maintenance and training causes, a'.
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case was discovered on Condition Identification Work
Authorization (CIWA) 01740 where the incorrect hydraulic fluid
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was added to the valve operator of safety-related feed' water
isolation valve FW-1848.
Based on-technical evaluation of this
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error by the licensee, the use of incorrect fluid could have
adversely affected elastomeric parts of the valve, and
consequently valve operation.
Thelicensee'svendormanualforvalveFW-1848andits'operEtor
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did not identify the hydraulic fluid to be used.
Since a
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primary purpose of controlled vendor manuals is maintenance, the
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NRC inspector, during a subsequent inspection, will evaluate
documentation of the licensee's technical review of vendor
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manuals to assure that vendor instructions exist for required
preventive and corrective maintenance.
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The NRC inspector also reviewed Vendor Technical Information
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(VTI) for Agastat Relays used tn safety-related applications.
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The VTI identified by the Emergency Diesel Generator (EDG)
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supplier was for originally provided nonsafety related relays.
used for safety-related applications.
Licensee personnel stated
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that original relays were qualified by the EDG supplier.
Replacement relays will be safety-related (E-series). The
licensee will verify that no unqualified relays have been
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Installed as replacements.
Maintenance instructions will require
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the periodic replacement specified for E-series relays. This
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will remain an open item (382/8531-01) pending further review
during a subsequent inspection.
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Further review by the NRC inspector of the licensee's response
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to 382/8425-01 will be accomplished during a subsequent
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inspection.
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b.
(Closed) (382/8527-01) Microflim identification of
safety-related preventive maintenance records showing required
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designations, such as Equipment Qualification (EQ).
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licensee now stamps preventive maintenance documents with the
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special designation (EQ) prior to their issue,
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c.
(Closed) (382/8527-05) Possible Use of Preventive Maintenance
(PM) Task Cards to Perform Corrective Maintenance.
The NRC
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inspector reviewed a sampling of PM task cards having a 3 and 5
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year accomplishment periodicity that had two or more recorded
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accomplishments in the first year of operation, with the following
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findings:
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Partial accomplishments of PM tasks were entered in the
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licensee's maintenance information system as complete
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accomplishments, indicating erroneous multiple
accomplishments.
In some cases, task cards were lo , and replacement task
cards issued.
Subsequently, the licensee determined that
both task cards were accomp14shed, and both were entcred in
the licensee's maintenance management information system.
In some cases, upon recalibration, measuring and test
equipment (M&TE) used for PMs subsequently was determined to
be out-of-calibration and the PM task was redone.
In one case, there were two identical pieces of equipment
having a 5 year PM periodicity based on Technical
Specification requirements.
FSAR requirements were
purported by licensee personnel to be the accomplishment of
10% of this equipment every 18 months.
The licensee
interpreted this to require PM on one of the two pieces of
equipment every 18 months.
The NRC inspector suggested to licensee personnel that they
assure that similar practices resulting in much more frequent
PMs than required do not degrade safety-related equipmer.t.
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licensee's new maintenance information management system, having
the acronym "SIMS" (Station Information Management System), can
eliminate unnecessarily redundant accomplishment of PMs.
SIMS
is scheduled to go "on line" in calendar year 1986.
3.
Licensee Corrective Maintenance Program
The NRC inspector reviewed the licensee's program for corrective
maintenance.
This review included licensee procedures, and licensee
potentially reportable events (PRES), to determine if they were caused by,
or adversely affected by, licensee maintenance practices.
The licensee is evaluating and accomplishing site-specific, modifications
to the Middle South version of the SIMS which is presently used for
control of maintenance at Arkansas Nuclear One (ANO) for both units.
The
ifcensee has targeted to have this system, with site-specific
modifications, on-line by October 1, 1986.
Review of the Arkansas Power
and Light (AP&L) version of SIMS indicates that this program can provide
effective management visibility and control of maintenance,
a.
Corrective Maintenance Administrative Procedures
Overall programmatic control of licensee maintenance activities is
covered by Administrative Procedure MD-1-014. " Conduct of
Maintenance," Revision 1, approved November 21, 1984.
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Corrective maintenance is performed using a work control document
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entitled a " Condition Identification and Work Authorization (CIWA)."
The governing procedure is UNT-5-002, " Administrative Procedure .
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Condition Identification and Work Authorization," Revision 4, dated
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September 5, 1984.
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Plant engineering technical review and processing of CIWAs is
Procedure PE-2-005, " Plant Engineering CIWA Processites." Revision 5,
approved June 21, 1985.
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The NRC inspector noted no programmatic violations or deviations in
these procedures.
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b.
Review of Licensee Potentially Reportable Events (PRES) for Events
That May Have 8een Caused, or Adversely Af fected, by Licensee Maintenance
Practices
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The NRC inspector reviewed all licensee PRES for maintenance
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implications.
Administrative Procedure UNT-6-010 " Event Evaluation
and Reporting," Revision 1 (approved November 26, 1984), provides
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guidance for licensee review, evaluation, and reporting of events.
The inspector identified two problems with the evaluation of events
as follows:
One maintenance-related' PRE reviewed was.for the addition of
hydraulic fluid to safety-related feed water isolation valve
FW-1848.
This is discussed previously in this report in
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Section 2.(a).
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PRE 85-150, failure of B charging pump, GE AKR-50 circuit . .
breaker to make contact on one phase resulting in failure of the
pump motor to start was reviewed.
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The failure of the AKR-50 breaker to make contact was caused by
rotationofaphasecontactadjustingscrewduringbreakeroperation.
The cause was a low thread torque (less than 40 inch pounds) for the
adjusting screw.
The event occurred May 18, 1985, General Electric (GE) provided to
the licensee on June 6, 1985, an evaluation and engineering analyses
and specified corrective actions which required the application of
" LOCTITE-220" to the adjusting screw and verification of adequate
torquing.
To implement GE's recommendation for breakers
having an above average number of close-open operations CIWA 021716
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was approved and issued August 26, 1985, but the action had not been
accomplished at the time of the NRC inspection.
The licensee committed
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to accomplish this'CIWA prior to the next startup for those breakers
which had "an above average number of CLOSE-OPEN operations."
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Subsequent to the inspection, the licensee committed to review all
other similar safety-related GE breakers (AKR-30 and AKR-50) to
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assure provision of timely corrective maintenance for this potential
failure.
This matter will be an open item (382/8531-02) pending
review of the licensee actions during a subsequent inspection.
c.
Failure to Adequately Evaluate and Report the Defects GE AKR-50
Circuit Breakers Under 10 CFR Part 21
The failure of the 8 charging pump breaker, as noted in b. above,
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was not reported under 10 CFR 50.73.
The breaker failure had been-
evaluated under 10 CFR 21 by the licensee and determined not to be a
reportable defect.
However, the defect identified by GE to the
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licensee was generic to all AKR-50 an AKR-30 breakers as noted in a
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June 6, 1985 letter to the licensee.
Additionally, GE issued a
revision to publication GEK-64459 (applicable to all AKR-30 and
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AKR-50 breakers) to provide maintenance instructions for checking
and correcting the potential defect.
This breaker failure (rotation of a phase contact adjusting screw
during breaker operation) represented a defect in a basic component
that could create a substantial safety hazard.
The failure of the
licensee to adequately evaluate and report this defect to the NRC is
a violation of 10 CFR 21,(382/8531-03).
4.
Training of Nonlicensed Staff
The NRC inspector reviewed licensee Potentially Reportable Events (PRES)
for evidence of events that resulted from licensee training deficiencies.
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No events appeared to have been negatively influenced by training.
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5.
Exit Interview
The NRC inspector met with the licensee representatives (denoted in
paragraph 1) at the conclusion of the inspection on December 6,1985.
The NRC inspector summarized the purpose, scope and findings of the
inspection.
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