ML20039G940
| ML20039G940 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/18/1981 |
| From: | Dickerson M, Plumlee K, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20039G932 | List: |
| References | |
| 50-267-81-26, NUDOCS 8201190324 | |
| Download: ML20039G940 (8) | |
See also: IR 05000267/1981026
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APPENDIX B
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U. S. NUCLEAR REGULATORY C0fSIISSION
REGION IV
NRC Inspection Report: 50-267/81-26
License DPR-34
Docket: 50-267
Licensee: Public Service Company of Colorado
P. O. Box 840
Denver, Colorado
80201
Facility Name: Fort St. Vrain Nuclear Generation Station
Inspection at: Fort St. Vrain Site, Platteville, Colorado
Inspection Conducted: November 1-30, 1981
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Inspectors:
3 [/A/
M
/2 -/F -3/
M. W. Dickerson, Senior Resident Reactor Inspector
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N&
/2 -/1- W
G. L. Plumlee III, Resident Reactor Inspector
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Approved By:
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/2-/F4/
T. F. Westerman, Chief, Reactor Project Section No. 1
Date
Inspection Summary
Inspection conducted November 1-30,1981 (Recort: 50-267/81-26)
Areas Inspected: Routine, announced inspection of Surveillance; Maintenance;
Operational Safety Verification; and Review of Periodic and Special Reports.
The inspection involved 115 insoection-hours on site by two NRC inspectors.
Results: Within the four areas inspected, three violations were identified
(Failure to adhere to Technical Specifications, Paragraph 2.A, failure to
follow procedures, Paragraphs 2.B. and 4. A. )
8201190324 811222
PDR ADOCK 05000267
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1.
Persons contacted
T. Borst, Radiatica Protection Manager
M. Block, Superintendent of Operations
R. Craun, Site Enaineering Supervisor
M. Deniston, Shift Supsrvisor
D. Evans, Shift Suoervisor
M. Ferris, QA Technical Support Supervisor
W. Franek, Nuclear Site Engineering Manaaer
W. Franklin, Shift Supervisor
C. Fuller, Technical Services Engineering Supervisor
J. Gahm, QA Manager
E. Hill, Operations Manager
D. Hood, Shift Supervisor
J. Jackson, OA/QC Supervisor
J. Liebelt, Senior Maintenance Supervisor
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M. McBride, Technical Services Manager
F. Novachek, Technical Advisor
T. Orlin, Superintendent 0A Services
T. Schleiger, Health Physics Supervisor
L. Singleton, Superintendent Operations QA
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D. Warembourg, Manager Nuclear Production
R. Webb, Maintenance Supervisor
The NRCinspectors also coittacted other plant personnel including
reactor operators, maintenance men, electricians, technicians and
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administrative personnel.
2.
Operational Safety Verification _
The NRC inspector reviewed licensee activities to ascertain that
the facility is being operated safely and in conformance with
regulatory requirements, and the licensee's manangement control
system is effectively discharging its responsibilities for continued
safe operation. The review was conducted by direct observation
of activities, tours of the facility, interviews and discussion
with licensee personnel, independent verification of safety system
status and limiting condition for operations, and review of facility
records.
Included in the inspection were observation of control room
activities, review of operational logs, records, and tours of
accessible areas. Logs and records reviewed included:
Shift Supervisor Logs
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Peactor Operator Logs
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Equipment Operator Logs
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Auxiliary Operator Logs
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Technical Specification Compliance Logs
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Operations Order Book
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Operations Deviations Reports
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Clearance Log
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Temporcry Configuration Reports
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Plant Trouble Reports
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During tours of accessible areas, particular attention was directed
to the following:
Monitoring Instrumentation
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Radiation Controls
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Housekeeping
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Fluid Leaks
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Piping Vibrations
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Hanger / Seismic Restraints
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Clearance Tags
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Fire Hazards
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Control Room Manning
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The operability of selected systems or portions of systems were
verified by walkdown of the accessible portions. The NRC inspector
verified the operability of the Turbine Generator and Auxiliaries System.
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No problems were identified during the system walkdown.
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A.
Removal of Diesel-Generators From Service
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On October 20, 1981, at 9:50 a.m. MST, the licensee removed
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the 1A Emergency Diesel-Generator set from service to change
the coolant on the diesel engines. lA was returned to service
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that same day at 3:45 a.m. MST. Also, on October 21, 1981,
at 7:40 a.m. MST, the licensee removed the 1B Emeraency Diesel-
Generator set from service for the same reason. 1B was returned
to service that same day at 10:30 a.m. MST. However, neither
Emergency Diesel-Generator set was started immediately prior
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to removal from service of tue alternate diesel-generator set
as required by Technical Specifications LC0 4.6.1.d).
Technical Specification LC0 4.6.1.d) requires that the reactor
not be operated at power unless both diesel-generator sets are
operable. However, they can be removed from service one at
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a time providing the alternate set is verified operable immedi-
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ately prior to the removal. Since the reactor was at power
this constituted a violation of the Technica? Specification.
(8126-01)
The violation was found by the licensee and reported in Report-
able Occurrence 81-066, dated November 6,1981. This violation
is similar to that reported in IE Report 81-24 and in Reportable
Occurrcr.ce 81-058, dated October 9,1931.
The NRC inspector's concern over the fact that the corrective
action addressed in Reportable Occurrence 81-066 was essentially
the same as that addressed in Reportable Occurrence 81-058, and
the licensee's management controls that permitted a reoccurrence
of this type of violation was brought to the licensee's attention.
The licensee's evaluation of this problem resulted in the commit-
ment to change all the licensee's Standard Clearance Points forms
related to the equipment addressed in LCO 4.6.i to reflect the
requirements o' LC0 4.6.1 prior to taking the equipment out-o#-
service and prior to placing it back in service.
On November 30,1981, at 10:45 a.m. MST, the NRC inspector
verified that the standard clearences for the 1 A and 1B Emergency
Diesel Generator sets had been changed to incorporate operability
verifications as required by LCD 4.6.1.
The NRC inspector also
identified two other System 92 Standard Clearance Points forms
which would yield a diesel generator set inoperable that did not
contain this new change. This was discussed with the licensee
who concurred that the change was necessary and would be made.
The NRC inspector has no further questions in this area.
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B.
Radiation Work Permit Requirements
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On November 16,1981, at 8:45 a.m. MST, during a tour of the
reactor building, the NRC inspector reviewed Radiation Work
Pe'rmit (RWP) 02861, issued to control work currently in progress
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inside the Hat Service Facility (HSF) and dctermined that a
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Health Physics (HP) technician performing surveys inside the
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HSF had failed to log in and was not wearing a pocket dosimeter
or film badge on the outside of his Anti-C's as were the other
personnel inside the HSF. Discussions with HP supervision
verified that the technician did have his film. badge underneath
his Anti-C's but no pocket dosimeter was worn as required by
the RWP. Administrative Procedure P-1 requires that each
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assigned employee log in and cut of the RWP and comply with the
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RWP requirements.
The NRC inspector discussed the above with the licensee and
informed the licensee that failure to follow procedures which
are Technical Specification requiremer.ts is considered a
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violation. (8125-02)
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The NRC inspector had no additional c,uestions in thi
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3.
Surveillance (Monthly)
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The NRC inspector reviewed all aspects of surveillance testing involving
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safety-related systems. The review included observation and review
relative to Technical Specification requirements. The surveillance
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tests reviewed and observed were:
SR 5.8.1d-W
Radioactive Gaseous Effluent Vent Monitor System
Functional Test
SR 5.2.6-X
Plateout Probe Evaluation
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SR 5.2.la-A
PCRV Rupture Disk and Safety Valve Test
SR 5.4.5-A2
PCRV Cooling Water Flow Scan Calibration
SR 5.4.1.1.6.c-R
Primary Coolant Moisture Scram Calibration
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No violations or deviations were identified.
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Maintenance (Monthly)
The NRC insoector reviewed records and observed work in progress to
ascertain that the following maintenance activities were being con-
ducted in accordance with approved procedures Technical Specifica-
tions, and appropriate Codes and Standards. The following maintenance
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activities were reviewed and observed:
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Steam Generator Module B-2-3 Penetration Modifications
CWP 81-250/CN1427
Isolation of Penetration B-2-3
CWP 81-251
Remove V-ll39 and Associated Piping and
Valves from Eystem
CWP 81-252/CN 1427A Steam Generator B-2-3 Interspace Discharge
Piping Nodification
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CWP 81-253/CN 1427B Steam Cenerator B-2-3 Interspace Discharge
Piping Modification Add Tailpiece to V-1139
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Loop Split Modification
CN 1314
Buffer Helium Piping
CN 1315
System 23/24 Valve Station
CN 1313
Radiation Monitors
CN 1321
North Stairs Modification
CN 1323
Main Control Board Modifications
CN 1322
Electrical Cable Routing
CN 1324
Process Control Equipment
Shutdown Maintenance
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PTR 11-130 Repair Control Rod Drive (CRD 17) in accordance
with MP 12-6, " Maintenance and Repair of CRD
Orificing Assemblies," and RP 5, " Control Rod Drive
Checkout"
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PTR 11-145 Remove Containment Tank Cover T-1101
PTR 11-202 Repair Hot Reheat Steam Line (B-2-1) in accordance
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with MP-lCO, " General Welding Procedures"
PTR 12-257 HV-2246 Repair in accordance with MP-4, " Maintenance
and Repair of Velan Valves," MP-5, " Valve Packing
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Procedure," and MP-39, " Installation and Maintenance
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of Limitorque Valve Operators and Retork Valve Operators"
PTR 5-9
Remove P-3105 for Repair in accordance with MP-105,
" General Pump Removal and Installation," and MP-103,
" Electric Motor Removal, Repair, and Replacement
Procedure"
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CWP 81-ll3/CN 1355A Installation of Isolation Valves on Stem
Generator Modules
A.
Steam Generator B-2-3 Modification
On Ncvember 3, 1981, at 6:30 a.m. MST, with the plant at approximately
8% reactor power,'the NRC ir,spector performed a walkdown of the work
previcusly rompleted on the steam gentrator (5/G) penetration modifi-
cation.
The i4RC inspector determined that one hydraulic support
(snubber CRS-951) required to be installed on the relief valve
tailpiece per CWP 81-253, and one pipe *,upport (hanger) required to
be installed on the helium penetration interspace ring header per
CWP 81-252, were not installed.
The question as to the system's
operability was immediately brought to the licensee's attention.
The licensee initiated an engineering safety evaluation and made
no further power increases until both the snubber and hanger had
been installec!.
The results of the engineering evaluation indicated that the hydraulic
snubber was not required to meet the system's seismic qualification,
but that the mechanical hanger was required.
From this evaluation
the licensee determined that the S/G penetration interspace pressuri-
zation portion of the PCRV Auxiliary Piping System, Loop II penetration
ring header, was not normal in that the system was not operational at
the time the equipment clearance was returned and the system returned
to operation. Administrative Procedure P-2, " Equipment Clearances
and Operation Deviations," requires the return of the equipment
clearance only when the equipment has been restored to normal
conditions.
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A review by the NRC inspector of the Change Notices and the Control
Work Permits (CVP) that authorized and documented the modification
indicated that in CWP 81-252, the QA/QC inspection verification
step for the installation of the pipe hanger on the Loop II helium
penetration interspace ring header had been signed off. This step
had been classified by QA/QC as a Witness Point (WP) and was required
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to be signed after verification by the Quality Control Technician
that the work was performed correctly. However, at the time this
verification was made, the pipe hanger had not been installed.
The NRC inspector discussed the above with the licensee and inform-
ed the licensee that failure to follow procedures, which are Technical
Specification requirements, is considered a violation (8126-03).
During this discussion, the licensee informed the NRC inspector
that communication errors within the licensee's management involved
in the performance of this modification was the underlying cause,
and that changes to the licensee's plant modification program would
be necessary to mitigate a possible reoccurrence.
The inspector had no additional questions in this area.
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B.
Loop Split
During an inspection of replacement parts and materials being used
in the loop split modification, the NRC inspector performed
traceability verifications on electrical cables used on safety
related equipment. The following cable reals located inside the
reactor building were traced to a specific Purchase Order (PO)
number and Direct Change Requisition (DC) assigned to a specific
change notice for the loop split modification.
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Reel No.
Item No.
DC No.
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042065
1733177
85949
N1702A
8CJ045
1733175
73961
N2262A
86J068
1733656
73963
N2262C
No violatio a or deviations were identified.
5.
Report Reviews
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The NRC inspector reviewed the following reports for content, reporting
requirements and adequacy:
Monthly Operating Information Report, October 1981
Monthly Operations Reports, October 1981
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Twentieth Startup Repart, May 23, 1981, through August 22, 1981
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No violations or deviations were identified.
6.
Exit Interview
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Exit interviews were conducted at the end of various segments of this
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inspection with Mr. D. W Warembourg, Manager, Nuclear Production, and/or
other members of the Public Service Company staff. At the interviews, the
inspector discussed the findings indicated in the previous paragraphs.
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The licensee acknowledged these findings.
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