IR 05000458/1990011
| ML20043D382 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/31/1990 |
| From: | Bess J, Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20043D379 | List: |
| References | |
| 50-458-90-11, IEIN-88-081, IEIN-88-81, NUDOCS 9006070441 | |
| Download: ML20043D382 (6) | |
Text
,
-
_
-
-.
.
.
.
.
-
. -
,
q s
w
,
}=,
.._
'
-
'
APPENDIX i
.
U.S. HUCLEAR REGULATORY COMMISSION
>
. REGION IV q
,
.
i NRC Inspection Report: 50-458/90-11 Operating License:
NPF-47 Docket: 50-458-Licenseei Gulf States Utilities c
P.O. Box 220
'
St. Francisville, Louisiana 70775 o > '
Facility Name: RiverBend,HuclearStation(RBNS)
i Inspection At: River Bend site, St. Francisville, Louisiana Inspection Conducted: May 7-11, 1990 f
-.
j i
I'nspector:
- ff-('
.
( 3/ f()
- '
>
/
/d
'
N.E.Bgss,R$ctor Inspector, Operational Da/te /-
l
,
L Programs Section, Division of -Reactor Safety.-
(
&
-,
,
/
/
,
.i (.
6 3/ f0
,
m
. Approved:
/
'
'
.(E. Gag [1ardo,-Chief, Operational. Programs Dete; '
'
- ^
Section,. Division of Reactor Safety
,
'
-Inspection' Summary
'
Inspection Conducted May 7-11,1990-(Report 50-458/90-11)'
i e
LAreasInspected: Routine, unannounced inspection of actions taken to correct previously. identified-inspection findings.
Results: Within the area inspected, no violations or deviations were
.
<
identified. -The licensee appeared.to have addressed the-identified concerns in
_
an appropriate manner. Due to plant conditions, action had not been completed
!!
'
in all areas;~.however, the licensee had implemented programs to ensure that all concerns were addressed during the upcoming refueling outage.
>
O
,
,
umir.
-c----
- m m
.
.
.
.m
-
&
,
.-
':
,
~'
.,.
4,,
,
I DETAILS
!
1.
PERSONS CONTACTED
,
GSU-
!
- P. D. Graham, Plant Manager
- J. E. Booker, Manager, Nuclear Industry Relations 1l
- G. A. Bysfield, Central Systems Supervisor
!
- E. M. Cargill, Director, Radiological Programs
,
,
- J. W. Cook.. Technical Assistant
!
- T. C. Crouse, Manager, Administration
'*R.~G. Eas11ck, Radwaste-Supervisor
- L.-A. England, Director, Nuclear Licensing
- A. O. Fredieu, Operations Supervisor-
.
- G. K. Henry.. Director, Quality Operations
!
.
- G. R. Kimmell, Director, Quality Services
'
- D..N. Lorfing, Supervisor, Nuclear Licensing l
- J. C.-Matter, Engineer, Licensing
,.
'
- M. A. Stein, Supervisor, Civil / Structural Design
.
Others.
l
- E. J. Ford. NRC Senior Resident Inspector-RBS
- L. Wilborn, Radiation Specialist
- W. L. Curran, Site Representative-Cajun
- Denotes those present during the exit meeting on May 11, 1990.. The in;occtor.
also contacted other plant personnel during the inspection, q
'
2., LICENSEE ACTION ON PREVIOUSLY IDENTIFIED ITEMS (92702)
t (Closed) Violation (458/8606-01): 'This violation identified the licensee's
~j failure to have:
(1), administrative procedures requiring the incorporation of
'j
vendor technical information (VTI) in maintenance procedures and the use of the Llatest available revision of VTI, (2) p(3) procedures ir.plementing root cause
'
rocedures properly prescribing preventive maintenance. intervals, and a
,
,
! L
' analysis:of" equipment failures..
To address the concerns of' Item 1, the licensee consnitted to corrective actions which included:. the issuance of River Bend Nuclear Irocedure (RBNP)-0032,
" Processing of' Vendor Technical Information," to enst re that all incoming VTI, including-changes, received the appropriate engineering / technical review,
.
l evaluation, distribution, and incorporation into the appropriate plant
. procedures; the issuance of Nuclear Plant Engineering Procedures (NUPE)-AA-65,
" Review of Vendor-Technical Information"; Procedure NUPE-AA-66, GE-NSS,
" Modification Interface"; and Procedure NUPE-AA-70, " Processing Vendor
.Information," to accomplish the above objective.
. -
-.
-.
'
,
.
'
-3-
,
To address the concerns of Item 2, the'11censee committed to corrective actions which included:
issuanceofMaintenanceSectionProcedure(MSP)-003, Revision 4, " Preventative Maintenance," to revise the requirements for establishing and scheduling the periodicity tolerances for EQ maintenance
,
activities.
lo address the concerns of Item 3, the licensee committed to corrective actions r
which included:
theissuanceofAdministrativeProcedure(ADM)-0019, Revision 4, " Initiating and Processing of Condition Reports," to ensure that i
.all safety-related, QA applicable, component failures reported on condition reports (CRs) would receive root cause analysis; and the implementation of the nuclear plant reliability data system (NPRDS) storage and retrieval program in accordance with Procedure PEP-0004, to ensure that NPRDS reportable co!nponents
'
had been reviewed for root cause and trended by INP0 for the licensee's review of equipment failures.
Through document review, the inspector verified that the committed corrective actions _had been performed.
This item'is considered closed.
.
3.
FOLLOWUP ON PREVIOUSLY IDENTIFIED ITEMS (92701)
(Closed)UnresolvedItem(458/8803-04): This item concerns the licensee's
' failure to close out in a timely manner and identify the root cause for j
ConditionReport(CR) 87-0845.
l A review of documentati in by the inspector verified that the licensee had closed out CR-87-0845. lhe CR indicated that the root cause of the discrepancy
'
-
was the failure to incorporate a drawing change implemented by General Electric. The dr wing change was made prior to the licensee's modification control program being implemented. The inspector reviewed Modification a
l
- Request (MR) 86-0800 and verified that all the discrepancies had been resolved.
i
'
LThe licensee initiated a program to review other drawing changes implemented by General Electric and verified that this concern was an isolated case.
,
.This item is considered closed.
j-(Closed) Unresolved Item (458/8803-08): This item conc 2rns the licensee's failure to determine generic implications and root causes for CRs 87-0060, 85-0519, and 85-0559.
'
The inspector reviewed various documents to determine the licensee's response to the referenced CRs. -The licensee issued Engineeri19 Evaluation and Assistance Requests (EEARs) 87-E0019 and EEAR 88-R006'. to perform an evaluation on the generic impilcation of CP,-87-0060. The safety concern, which CR-0060 documents, was caused by the hydraulic locking phenomenon which was also reported by other industry reports.
-
-
.
_-
,
i
,
. - _,
.
'
-4
.-
]
.
>
The analysis determined that eight valvrs were potentially~ susceptible to the hydraulic locking phenomenon. The licrnsee issued Maintenance
-
Request (MR) 87-0101 to correct the st/ety concern..The referenced MR corrected the, problem of two valves identified es 1E12* M0VT004 A and B.
The remaining i
six valves will be corrected on MR-88-0145. Because of plant conditions, this work will be completed during the next refueling cutage scheduled for September 1990. The inspector verified that the outage schedule listed
'
MR-88-0145 as an item to be completed during the next outage.
The licensee issued Engineering Evaluation and Request 89-00128 to address the
.'
concerns of CR-85-0519 and CR-85-0559. The inspector noted that the licensee issued CR-85-0519 to address the concerns of blown fuses in the 3rotective circuits. Further investigation by the licensee verified that t1e cause of the
blown fuses was the result of incorrect wiring of solenoid Valve C11* S0VF110A
!
and B.
The solenoid was wired in accordance with the design drawing.
It was determined that the design drawing was incorrect. The valve was corrected by MR-85-1099.- The valve was functionally tested successfully.- The licensee walked down all protective circuits to verify that other wiring problems were not identified and this concern.was not considered to be generic. The inspector found the corrective actions implemented by the licensee to be acceptable.
This item is considered closed.
(Closed)OpenItem(458/8828-01)
Review of the licensee's response to NRC Information Notice (IM) 88-81, " Failure of Thomas and Betts (T&B), Wire Caps-During Environmental Qualification Testing," October 7, 1988.
The licensee issued EEAR-88R-0344 to implement plans for addressing the concerns in Information Notice 88-81 and-NRC Open Item 458/8821-01. To ensure the continued qualification of the limitorque. actuators, engineering concluded
,
that the wire caps presently installed would be covered with qualified Okonite i
tape. This modification would eliminate any concerns regarding the qualification of the wire caps, and covering them with a qualified splice would
."
eliminate the need for replacement of the wire caps.
ModificationRequest(MR) 89-0023 was approved to reinsulate nylon insulated Thomas and Betts parallel butt splices with Okonite tape splice in accordance with Spec.248.000.
The inspector found the licensee's documentation and resolutions to this concern to be acceptable.
This item is considered closed.
(Closed)InspectorFollowupItem(458/8927-02): This item concerns the training and requalification requirements for the facility review connittee (FRC) members.
t l
L l
l'
.
.
..
-.
.
.
i;
'
,y.; A
>
.
,
'
'i 5-t
!
.t The. inspector reviewed the licensee's response to the concern pertaining to.the training requirements of facility review comittee (FRC) members. The records review indicated that the member in question of the FRC in question was qualified to participate.in meetings. The inspector also verified that the FRC member
!
who chaired Meeting 89-065 was qualified. AdministrativeProcedure(ADM)-002, j
which provided the charter of the " Facility Review Committee," had been revised i
(Revision 10) to clarify the required annual refresher training. A review of
!
the training records by the inspector verified that FRC members were qualified
!
to participate in meetings.
i This item is considered closed.
(Closed)Unresolveditem(458/8904-03): This item concerns the torque switch setting for MOVF024A being below the recommended value.
l To resolve this concern, the licensee reviewed a total of 25 closed work documents against Valve M0VF024A to verify if documentation was available that i-had required the torque switch setting to be changed. The licensee stated that
!
there was no indication of the torque switch ever being set to a lower
value(1.5)inany'ofthedocuments. Procedure CMP-1253 stated that the
'
recommended torque switch setting was 1.75 minimum and 2.00 maximum.
Procedure CPM-1253 was used in many of the reviewed work documents, but the i
torque switch section was marked "N/A" in all of them because no work was
. required to change the setting. The licensee stated that there was a chance i
that the settings could have been set below the recommended value since
'
startup. This could not be substantiated.
,
To ensure that this concern was not a generic problem, a computer check on all condition reports related to torque switches indicated that there had never-been a documented problem like this. Electrical maintenance stated that a torque switch setting had never occurred without specific instructions and documentation from engineering. This problem appeared to have been an isolated case.
~The licensee's corrective actions included issuance of the condition report (which describes the concern) to electrical maintenance to inform them of the-i problem and also to remind them to continue to be alerted when looking at
'
- torque switches. Also, Procedure ADM-0028 was revised to say any procedure step marked "N/A" aust be explained in the comment section, this would give a more accurate record of the maintenance performed or explain why the steps were not done. The inspector reviewed the. licensee's corrective actions and found
'
the program acceptable.
~
This. item is considered closed.
,
(
+
t
.
.
.
-
e'
,
,
,
,
c.
A
-
.
,
.
l.
.4;;e.,;
.
,
,i
,
4,
<
,74 -
,
-l
'
EXIT' INTERVIEW-
,
l
. The-inspectormetwiththelicensee'srepresentatives(denotedinparagraph1)
on May 11, 1990. The inspector summarized i,ne inspection purpose, scope,-and findings. The licensee acknowledveu tne coments and did not identify any of-the information. covered as proprietary.
!
.!
'
!.
,
l
.
I i's
',
-
I
..
f
,.
f'
!
i
.l t
,
.q-i H
I
-
.
,
l l
~
f
.1,
>
>.
,,
e
.
,
,