ML20136G505
| ML20136G505 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/01/1985 |
| From: | Craig Harbuck, Jaudon J, Skow M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20136G493 | List: |
| References | |
| 50-458-85-71, NUDOCS 8511220374 | |
| Download: ML20136G505 (4) | |
See also: IR 05000458/1985071
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APPENDIX B
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U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-458/85-71
Docket:
50-458
License:
Licensee:
Gulf States Utilities
P. O. Box 2951
Beaumont, Texas 77704
Facility Name:
River Bend Station
Inspection At:
St. Francisville, Louisiana
Inspection Conducted:
October 7-11, 1985
Inspectors:
/0/Jo/F.5"
M. E. Skow, Project Engineer, Project
Da'te '
Section A, Reactor Projects Branch
(pars. 2, 3, 4, 5)
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.jarfuck, Project 7ngineer, Project
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Section A, Reactor Projects Branch
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(pars.
3)
- Approved:
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.(Jaupon, Chief,'ProjectSectionA,
Date
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Rea& tor Projects Branch
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Inspection Summary
Inspection Conducted October 7-11, 1985 (Report 50-458/85-71)
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. Areas Inspected:
Routine, unannounced inspect 1on of various open items and
license conditions for follow-up for possible closure.
The inspection involved 58 inspector-hours onsite by two NRC inspectors.
Results: Within the areas inspected, one violation was identified (and is
-discussed in paragraph 3).
8511220374 851105
ADOCK 05000458
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DETAILS
1.
Persons Contacted
Gulf States Utilities
- J. Deddens, Vice President, River Bend-Nuclear Group
- D. R. Gipson, Assistant Plant Manager
- A. D. Kowalczuk, Assistant Plant Manager
- T. C. Crouse, QA Manager
- P. E. Freehill, Superintendent
- E. R. Grant, Licensing
- E. R. Oswood, QA Engineer
- G. V. King, Plant Services Supervisor
H. M. McClellan, Compliance Group
B. E. Hey, Licensing
S. R. Radebaugh, Superirtendent
A. O. Fredien, Operations
J. E. Spivey, Operations QA Engineer
P. D. Graham, Assistant Plant Manager
R. Kosmala, Technical Staff Engineer
Others
D. Hill, Stone & Webster, Staff Specialist
H. E. Stubbs, Stone & Webster, Supervisor Field QC
0. V. B. Rice, GE, Technical Staff Engineer
- Denotes those present at exit interview
2.
Technical Specifications and Implementing Procedures
The objective of this follow-up inspection to the NRC inspection
conducted April 19 through May 3, 1985 (NRC Inspection Report
50-458/85-35), was to determine whether the Technical Specifications (TS)
will be properly implemented through the approved facility procedures.
The NRC inspectors reviewed the specific inspection findings documented
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on the data sheets attached to NRC Inspection Report 50-458/85-35 that
were left open and renumbered in NRC Inspection Report 50-458/85-58 as
open items 8558-01 through 8558-24.
The NRC inspectors reviewed the
procedures for adequacy and to ensure the specific issues identified in
the Data Sheets had been resolved.
As a result of this review, the NRC
inspectors considered the following items CLOSED:
8558-01, 8558-03, 8558-07, and 8558-09 through 8558-24.
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3.
Previously Identified Open Items
(Closed) Open Items 8558-25 and 8558-27: Changes have been made to
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STP-051-4201, Revision 3, to reflect changes in the TS. However, both
STP-051-4201 and STP-051-4228, Revision 0 have set points with a
tolerance specified arcund the set points. The TS list the set points
as a limit, using the notation 2 (greater than cr equal to) in some cases
or s (less than or equal to) in other cases.
Although there had apparently been no calibrations conducted outside of
Technical Specifications, this situation allows the aossibility that,
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should the trip point be found to exceed the " allowable value" of the TS
and thus require resetting, the reset trip point could be set within the
tolerance band of the procedure but not within the " trip setpoint" liniit
of the TS. This is is an apparent violation (8571-01). Open
Items 8558-25 and 8558-27 are closed.
(Closed) Open Item (8563-02):
Review of Revision 1 to startup procedure
ST-14 " Reactor Core Isolation Cooling." This item was open because of
the many changes being made to this procedure by the licensee. The f4RC
inspector reviewed a draft copy of Revision 1 and determined that it
appeared to meet all FSAR test cornitments and wculd provide for adequate
testing of the RCIC system.
This item is Closed.
(Closed) Open Item (8554-01):
Control Room E&DCR files and drawings
used for training of control room operators.
This item was open to track a licensee commitment to conduct uscage
familiarization training for licensed control room operators on the E8DCR
files and system drawings in the control room. The fiRC inspector
verified that of the persons designated to be trained to meet this
cornitment, all 9 shift supervisors, all 9 shif t foremen, and 18 out of
21 fluclear Control Operators (fiC0s) had received this training. The 3
remaining NCOs had not received this training because administrative
reasons.
It appeared that they would be trained prior to initial
criticality. The NRC inspectors concluded that GSU appeared to have met
their commitment. This itcm is Closed.
4.
IE Bulletins
IE Bulletin fio. 83-03, " Check Valve Failures in Rcw 1:cter Cooling Systems
of Diesel Generators." This bulletin required licensees to ensure certain
check valves were tested not only in the fon<ard ficw conditions, but
also in a means to ensure internal integrity of the valve.
STP-256-3301
and STP-256-3302, Division I and II Standby Service Water Valve Operability
Tests, test the check valves in the standby service water lires to the
diesel generators. The valves are tested with both forward flow and back
flow means. These are also routinely checked surveillance tests. This
item is Closed.
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Licensee Identified Construction Deficiency Review
This area of inspection was conducted to review action taken on the
following licensee identified construction deficiency.
(Closed) Deficiency P. port'DR-313: "E :essive Temperature in Excitation
Cabinets"
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Initial NRC notification date: June 7, 1985
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Final report: GSU letter RBG-21453 of July 3,1985
.The corrective action for this reportable deficiency was to provide a
source of ventilation to the subject panels, procure necessary material,
and implement the required modification. .A review of documentation by
the NRC inspector revealed that all activities related to this
modification had been completed. This item is Closed.
6.
Exit Interview
An exit interview was held on October 11, 1985, with the Mr. Deddens and
other. personnel as denoted in paragraph 1 of this report. The NRC senior
resident inspector also attended this meeting. At the meeting, the scope
of the inspection and findings were summarized.
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