ML20137A279
| ML20137A279 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/13/1985 |
| From: | Bennett W, Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20137A234 | List: |
| References | |
| 50-458-85-66, IEB-82-03, IEB-82-3, NUDOCS 8511250453 | |
| Download: ML20137A279 (4) | |
See also: IR 05000458/1985066
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APPENDIX B
U.S. NUCLEAR REGULATORY C0f71ISSION
REGION IV
NRC Inspection Report: 50-458/85-66
License:
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Docket: 50-458
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Licensee:
-Gulf States Utilites
P.-0. Box 2951
Beaumont, Texas 77704
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Facility Na'me: ' diver Bend Station -
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' Inspection At: River Bend Site, St. Francisville, Louisiana
Inspection Conducted: September 30-October 4,1985
, Inspector:
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WW./R. Aenn9(t, Project Engineer, Project
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Section A, Reactor Projects Branch
. Approved:
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J.p. /auc) tin, Chief, Project Section A
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LReac' tor [ Projects Branch
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. Inspection Sumary
. Inspection Conducted September 30-October 4,1985 [ Report 50-458/8566)
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Areas Inspected:
Routine, unan'nounced inspection of licensee identified'
deficiency reports, 10 CFR 50.55(e),
IE Bulletin followup,-and operating.
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procedures. The inspection involved 37_ inspector-hours onsite by'one.NRC
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inspector.
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Results: Within the three areas inspected, three. violations were identified
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(failure to update procedures after issuance of'three TCNs, issuance of a TCN
- after final approtal and failure to properly prepare TCNs, paragraph 5).
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DETAILS
1.
Personnel Contacted
- T. L. Crouse, Manager - Quality Assurance (QA)
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- J. C. Deddens, Vice President
- A.,O. Fredieu, Assistant Operations Supervisor
- D. R. Gipson, Assistant Plant Manager
- P. D. Graham, Assistant Plant Manager
- B. E. Hey, . Engineer-Licensing
G. R. Kimmell, Supervisor, Operations QA
- G. V. King, Plant Services Supervisor
J. Miller, Senior Nuclear Engineer, Nuclear Plant Engineering (NUPE)
- J. E. Spivey, Operations QA Engineer
- R. B. Stafford, Director Quality Services
- P. F. Tomlinson, Director Operations QA
W. Trudell, Senior Reactor Operator
- J. A. Wright, NUPE Supervisor
The~NRC inspector also contacted other site personnel including
administrative, clerical, operations, and testing personnel.
- Denotes those attending the exit interview conducted on October 4, 1985.
2.
Licensee Action on Previous Inspection Findings
a.
(Closed) Violation (458/8542-01).
Control of Temporary Alterations.
Corrective action included deleting the option of not hanging
temporary alteration tags if they were required for less than one
work shift.
The NRC inspector reviewed the temporary alterations log
and determined that the procedure for temporary alterations is being
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implemented properly.
-This item is considered closed,
b.
(Closed) Open Item (458/8542-02) Implementation of a Spare-Lead
Identification System.
All spare leads in panels in the main control' room have been wrapped
and tied back. Maintenance work requests have been initiated to wrap
and tie back spare leads in the rest of the plant.
This item is considered closed.
c.
(Closed) Open Item (458/8432-03) Filling ana Venting Procedures
The NRC inspector reviewed a sample of the syctem operating
procedures and determined that instructions fm filling and venting
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of systems related to safety.have been incorporated into,the system
operating procedures.
This item is considered closed.
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Licensee Identified Deficiency Reports (DRs), 10 CFR 50.55(e)
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The purpose of this portion of the inspection was to determine the
adequacy of corrective actions taken by the licensee on construction
deficiencies identified to the NRC pursuant to the requirements of
10 CFR'50.55(e).
The NRC inspector reviewed the following " Reportable" DR and it is
considered closed:
DR
SHORT TITLE
INITIAL
GSU FINAL
NUMBER
OR SUBJECT
NOTIFICATION
REPORT LETTER
280
Loss of Torque of
07/23/85
RBG 21683-07/24/85
Reliance Rotors in
Motor-0perated Valves
(MOVs)
The NRC inspector determined that the deficiency was properly determined
to be reportable and that all required reports were made within the
appropriate time and contained all required information.
The licensee
performed an evaluation of the deficiency.
Corrective action consisted of
making changes to emergency operating procedures relative to these MOVs.
These changes are specified in the operating license for River Bend as
License Condition 2.b of Attachment 1.
The NRC inspector reviewed the
changes to the emergency operating procedures and License Condition 2.b is
considered to be completed satisfactorily.
No violations or deviations were identified in this portion of the
inspection.
4.
IE Bulletin Followup
The purpose of this portion of the inspection was to determine the status
of IE Bulletins.
a.
IE Bulletin 82-03 and Revision 1 - Stress Corrosion Cracking in
Thick-Wall, Large Diameter, St.'.inless Steel, Recirculation System
Piping at BWR Plants.
Item - A plant reported. visually detectable leakage during
hydrostatic testing of recirculation system piping.
Visual
examination revealed pin-hole leaks and cracks in piping which had
been successfully ultrasonically tested 9 months previously.
A
modified ultrasonic test verified these defects and revealed
additional defects in that piping.
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Findings - The licensee identified that the only coolant pressure
boundary piping which does not conform to NUREG 0313 Revision 1 is
small diameter instrument piping. Analysis shows that the
nonconforming piping will not be exposed to temperatures above 200*F,
which is the threshold for intergranular stress corrosion cracking as
stated in Reg. Guide 1.44, for more than 1% of expected plant life.
This bulletin is considered closed.
5.
Operating Procedures
The objective of this portion of the inspection was to confirm that the
plant operating procedures are prepared to control safety-related
operations within the applicable regulatory requirements.
The NRC inspector sampled system operating procedures specifically to
determine if filling and venting instructions were incorporated in the
procedures. River Bend Procedure ADM-0003 requires that a procedure
revision be initiated when three TCNs are outstanding against a procedure.
Eight of the system operating procedures reviewed (50Ps-2, -16, -18, -41,
-42, -48, -53, and -90) had more than 3 TCNs, which required a permanent
procedure change, outstanding. S0P-90, " Reactor Water Cleanup System,"
Revision 1, dated May'13, 1985, had 12 outstanding TCNS. Six of the eight
S0Ps, were in various stages of procedure revision, however, the revision
to S0P-90 only. incorporated 6 of the 12 outstanding TCNs. This is an
apparent violation (458/8566-01). The NRC inspector found several
instances (50Ps-35, -42, -48,- and -49) wherein TCNs were issued which did
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not incorporate previously approved TCNs to the same pages. This resulted
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in two different approved changes to the same page. This is an apparent
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violation (458/8566-02). The NRC inspector found one instance
(TCN 85-1550 to S0P-0035) where two pages of a TCH were removed and the
numbers of thez remaining pa'ges changed after the TCN was approved. This
change was apparently accomplished without the knowledge of the originator
or any of the approving personnel. 'This is also an apparent violation
(458/8566-03).
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No other violations or deviations were identified in this portion of the
inspection.
6.
Exit Interview
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An exit interview was held on October 4, 1985, with the personnel denoted
in paragraph 1 of this report. The NRC senior resident inspector also
attended this meeting. At this meeting, the scope of the inspection and
the findings were summarized.
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