ML20133L796
| ML20133L796 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/09/1985 |
| From: | Chamberlain D, Craig Harbuck, Jaudon J, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20133L760 | List: |
| References | |
| 50-458-85-62, NUDOCS 8510240312 | |
| Download: ML20133L796 (7) | |
See also: IR 05000458/1985062
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APPENDIX B
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-458/35-62
License: NPF-40
Docket: 50-458
Licensee: Culf States Utilities Company (GSU)
P. O. Box 2951
Beaumont, Texas
77704
Facility Name: River Bend Station (RBS)
Inspection At: River Bend Station, St. Francisville, Louisiana
Inspection Conducted: August 16 through September 15, 1985
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Inspectors:
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D. D.VChamberlain, Senior Resident Inspector
Date
(pars. 1,2,3,5,6,7,
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Section 4, Reacto Projects Branch (par. 4)
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{ Rea[cto( Projects Branch (par. 7)
.f.P Jaufon, Chief,ProjectSectionA
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W. M. McNeill, ~Reactbr Inspector, Operations
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Section, Reactor Safety Branch (par. 7)
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Approved:
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.[.P./Jaudc[n,~ Chief,ProjectSectionA.
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6 Reactor Projects Branch
8510240312 85
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. Inspection Summary-
Inspection Conducted August 16 through September 15, 1985 (Report 50-458/85-62)
Areas Inspected: Routine, unannounced inspection of site tours, initial
fuel loading witness, overall startup test program review, surveillance
testing baseline witness, operational safety verification, and licensee
quality concern program review. The inspection involved 235 inspector-
hours onsite by four NRC inspectors.
Results: Within the areas inspected, one violation was issued in the
area of initial fuel loading witness (failure to follow an administrative
Procedure, paragraph 3).
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DETAILS
1.
Persons Contacted
Principal-Licensee Employees
- B. E. Boyer, Environmental Analyst
W. H. Cahill, Jr. Senior Vice President, River Bend Nuclear
- J. V. Conner, Supervisor, Environmental Services
- T. C. Crouse, Manager, Quality Assurance (QA)
- J. C. Deddens, Vice President River Bend Nuclear Group
D. R. Derbonne, Supervisor, Startup and Test
S. Finnegan, Control Operating Foreman
- P. E. Freehill, Superintendent, Startup and Test
- D. R. Gipson, Assistant Plant Manager, Operations
P. D. Graham, Assistant Plant Manager, Services
- M. A. Harrington, Senior Environmental Analyst
D. Hartz, Shift Supervisor, Operations
R. W. Helmick, Director, Projects
- B. D. Hey, Licensing Engineer
K. C. Hodges, Supervisor, Quality Systems
R. Jackson, Shift Supervisor, Operations
D. Jernigan, Engineer, Startup and Test
G. R. Kimmell, Supervisor, Operations QA
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A. D. Kowalczuk, Assistant Plant Manager, Maintenance
T. Lacy, Shift Supervisor, Operations
- J. M. McGhee, Radwaste Foreman
- E. R. Oswood, Engineer, QA
- T. L. Plunkett, Plant Manager
- S. R. Radebaugh, Assistant Superintendent, Startup and Test
- C. A. Rohrmann, Technical Training Coordinator
- J. E. Spivey, Engineer, QA
R. B. Stafford, Director, Qua'ity Services
- L. R. Thompson, Supervisor, Instrumentation and Control
P. F. Tomlinson, Director, Operation QA
C. Warren, Shift Supervisor, Operations
- R. G. West, Supervisor, Startup and Test
' Stone and Webster
.F. W. Finger, III, Project Manager, PTO
B. R. Hall, Assistant Superintendent, Field Quality Control
R. L. Spence, Superintendent, Field Quality Control
The NRC senior resident inspector (SRI) also interviewed additional
licensee, Stone and W'ebster (S&W), and other contractor personnel during
the inspection period.
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- Denotes those persons that attended the exit interview conducted on
September 20, 1985. NRC inspectors, R. E. Baer and J. B. Nicholas, also
attended the exit interview.
2.
Site Tours
The SRI toured areas of the site during the inspection period to gain
knowledge of the plar.t and to observe general job practices.
Special
attention was given to the containment / refueling areas in preparation for
initial fuel load which began on August 31, 1985.
No violations or deviations were identified in this area of inspection.
3.
Initial Fuel Loading Witness
This area of inspection was conducted to ascertain the conformance of the
licensee to license and procedural requirements, to observe operating
staff performance, and to ascertain the adequacy of fuel loading records
during initial fuel loading at River Bend.
Gulf States Utilities (GSU)
received the operating license on August 29, 1985, and the first fuel
bundle was placed in the reactor core at approximately 3:30 a.m. on August
31, 1985.
The SRI witnessed the placing of the first fuel bundle and
observed fuel loading activities throughout the inspection period.
During
the review of the source range monitor nuclear instrument calibration
records, it was noted by the SRI that administrative procedural
requirements were not fully implemented for surveillance test procedures
STP-503-4203 (completed 8/02/85), STP-503-4204 (completed 8/03/85),
STP-503-4205 (completed 8/06/85), and STP-503-4206 (completed 8/02/85) for
the semiannual calibration of source range monitor channels A, B, C, and
D.
The STPs were not followed exactly, Temporary Change Notices (TCN)
85-1405 and 85-1406 were issued and approved without the reason for the
change being specified on the TCN form, and other approved TCNs were not
fully implemented for the continuation of the work activity.
Examples of the failure to follow the STP procedures exactly and the
failure to fully implement TCNs include:
The following procedure steps were marked NA and not completed and
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there was no documented evidence that the steps did not apply to the
test conditions at that time:
STP-503-4203
STP-503-4204
STP-503-4205
STP-503-4206
7.1.109.2
7.1.116.18
7.1.127.13
7.1.116.18
7.1.127.13
7.1.116.19
7.1.127.14
7.1.116.19
7.1.127.14
7.1.127.13
7.1.127.15
7.1.118.5
7.1.127.15
7.1.127.14
7.2.42
7.1.122.1
7.2.6.5
7.1.127.15
7.1.127.13
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STP-503-4203
STP-503-4204
STP-503-4205
STP-503-4206
7.2.6.6
7.2.6.3
7.1.127.14
7.2.6.7
7.2.6.5
7.1.127.15
7.2.6.8
7.2.6.6
7.2.1
7.2.6.12
7.2.6.7
7.2.6.3
7.2.43.3
7.2.6.8
7.2.6.5
7.2.43.5
7.2.6.12
7.2.6.6
7.2.43.3
7.2.6.7
7.2.43.5
7.2.6.8
7.2.6.12
Table IX of STP-503-4205 for C51-K600C, SRM Period Meter Remote,
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listed a minimum value for steps 7.1.72.11 and 13 of "not on peg" but
-both the as-found and the as-left values were "on downscale peg."
Maintenance Work Request MWR 005048 listed in test results was for
replacement of meter C51-K601C and no MWR could be located for meter
C51-K600C.
TCN 85-1436 changed and rearranged steps 7.2.40, 7.2.41, and 7.2.42
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of STP-503-4203, but the original procedure steps were signed as
complete.
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TCN 85-1214 added restoration step 9 to STP-503-4205, but restoration
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step 9 was not signed as complete.
TCN 85-1440 changed step 7.1.109 of STP-503-4206, but both the
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original step 7.1.109 and the TCH step 7.1.109 were signed as
complete.
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TCN 85-1453 changed steps 7.1.119.5, 7.2.19, and 7.2.32 of
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STP-503-4206, but none of these steps were signed as complete.
TCN 85-1454 changed and rearranged steps 7.2.40, 7.2.41, and 7.2.42
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of STP-503-4206, but the original procedure steps were signed as
complete.
This failure to follow administrative procedure requirements is an
apparent violation (458/8562-01) of NRC requirements.
During the initial fuel load conduct, activities in the control room
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appeared disorganized, but GSU management took immediate action to limit
administrative activity at the control operator tables and shift briefings
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were conducted by the shift supervisor at the beginning of each shift to
help alleviate confusion regarding planned shift activities. Also, daily
planning meetings were conducted to coordinate activities and to discuss
problems encountered. Daily improvement was noted in the conduct of
control room activities.
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During this inspection period, four unplanned reactor protection system
(RPS) actuations occurred, and all four were called in to the
headquarter's duty officer as required. The licensee plans to issue
Licensee Event Reports (LERs) for these RPS actuations. None of the
unplanned RPS actuations caused any problems with fuel loading activities
and the SRI will follow up during normal LER review during a future
inspection. There were also two cases of potential loose parts in the
reactor vessel which will require additional follow up by the SRI. One
case was a lost snao cing from a pin on the fuel grapple and another case
was a "D-Ring" and two electrical pin connectors from the electrical cable
going to the fuel grapple engaged limit switch.
Both of these conditions
were repaired with direction from General Electric (GE) and the licensee
received notification from GE that fuel loading could continue. GE still
has to complete a lost parts analysis on the missing parts.
This item
will remain open (458/8562-02) pending the results of the GE lost parts
analyses. Although problems have been encountered during fuel loading,
the SRI concluded that the licensee had been identifying these problems
and taking'the required actions promptly. The SRI also concluded that the
licensee's approach to initial fuel loading activities was cautious.
4.
Overall Startup Test Program Review
The purpose of this area of the inspection was to ascertain whether the
licensee has developed administrative controls which will assure that the
startup test program will be prepared, performed, and evaluated in
accordance with regulatory requirem!nts.
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The NRC inspector verified that the licensee's startup test program, as
described in the FSAR, appears to fulfill their commitment to follow the
test program outlined in Regulatory Guide 1.68, " Initial Test Programs for
Water-Cooled Nuclear Power Plants," Revision 2, August 1978.
It was also
determined that the licensee had identified and sequenced the tests to be
. performed, and had nearly completed issuing the individual test
procedures.
The NRC inspector verified that adequate formal administrative measures
had been established to govern the conduct of testing and the evaluation
of test results.
There was some initial concern with the method of scheduling startup test
activities, but this concern was alleviated at this time with the conduct
of daily planning meetings and with the preshift briefings by the shift
supervisors.
The NRC inspector reviewed the licensee's startup test organization end
found that the operating organization (operations) had been assigned
overall responsibility for startup test activities and that the interfaces
between startup test engineers and the on-shift operating staff had been
well defined.
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The NRC inspector also reviewed the licensee's program for maintaining
test and measurement equipment to be used during startup testing. No
problems were noted.
No violations or deviations were identified in this area of the
inspection.
5.
Surveillance Testing Baseline Witness
The SRI witnessed two unsatisfactory attempts to perform STP-309-0601,
" Division I LOP /LOCA Test." This test fulfills certain 18-month
surveillance test requirements for the division I diesel generator.
One
test was unsatisfactory due to a procedure problem and the other due to an
unexplained failure of the division I diesel to start. The procedure
problem was corrected and the division I diesel was successfully started
on subsequent occasions. However, the SRI will review the licensee
actions to identify the cause of the one failure of the diesel to start
(0 pen Item 8562-03).
No violations or deviations were identified in this area of inspection.
~6.
Operational Safety Verification
This area of inspection was conducted to assure that the facility is being
operated safely and in conformance with regulatory requirements during
initial operational mode 5 activities.
Refueling is described as
operational condition mode 5 by River Bend Technical Specifications. The
SRI basically conducted a review of required mode 5 system alignments as
observed from control room indications and monitored control room
activities throughout the inspection period.
No violations or deviations were identified in this area of inspection.
7.
Licensee Quality Concern Program Review
The licensee's quality concern program was described _in NRC Inspection
Report 50-458/85-25. The SRI, assisted by Region IV personnel, continued
to review licensee actions on individual cases.
No violations or deviations were identified in this area of inspection.
8.
Exit Interview
An exit interview was conducted on September 20, 1985, with licensee
representatives (identified in paragraph 1). During this interview, the
SRI reviewed the scope and findings of the inspection.
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