ML19323B264
| ML19323B264 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/18/1980 |
| From: | Collins R, Westerman T, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19323B258 | List: |
| References | |
| 50-267-80-02, 50-267-80-2, NUDOCS 8005120165 | |
| Download: ML19323B264 (12) | |
See also: IR 05000267/1980002
Text
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-267/80-02
Docket No. 50-267
License No. DPR-34
Licensee:
Public Service Company of Colorado
P. O. Box 840
Denver, Colorado
80201
Facility Name:
Fort St. Vrain Nuclear Generating Station
Iaspection At:
Fort St. Vrain Site, Platteville, Colorado
Inspection Conducted:
February 1-29, 1980
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Inspectors:
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M. W. DickErson,;< Senior Resi, dent Reactor
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Inspector
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"'R. G. Spangler, Rettctor inspector
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uk.~E.' Collins, ResidentvReactor Inspector
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L. A. Yandell, Reactor Inspe(tof
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Approved by:
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T. F. Westerman, Chief, Reactor Projects Section
Date
Inspection Sununary
Inspection Februacy 1-29, 1980 (Report No. 50-267/80-02)
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Areas Inspected:
Routine, announced inspection of Event Reports; Calibration;
Surveillance; Bulletins / Circulars; Maintenance; Physical Security; Plant
Operations; Followup on Items of Noncompliance; Followup on Inspector
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Identified and Unresolved Problems; Emergency Planning; Core Safety Limit;
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and Report Reviews.
The inspection involved 227 inspector-hours on-site by
four (4) NRC inspectors.
Results: Within the ten (10) areas inspected, two items of noncompliance
were identified (infraction - Failure to use latest procedure revisions
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while performing calibration, paragraph Sa; and deficiency - Failure to
provide a record of test equipment, paragraph Sa).
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DETAILS
1.
Persons Contacted
L. Brey, QA Manager
W. Craine, Maintenance Superintendent
W. Franek, Results Supervisor
C. Fuller, Engineer Technical Services
J. Gamm, Supervisor Technical Services
E. Hill, Operations Superintendent
W. Hillyard, Administrative Services Manager
F. Mathie, Operations Manager
J. Solakiewicz, Superintendent Operations QA
G. Turner, Supervisor of Security
D. Warembourg, Manager Nuclear Production
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The inspectors also contacted other plant personnel including Reactor
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Operators, Maintenance men, Electricians, Engineers, Technicians and
Administrative Personnel.
2.
Licensee Action on Previous Inspection Findirgs
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(Close) Open Item (50-267/7703):
NI accuracy (Decalibration).
The
recommended circuit design to provide a solution to the decalibration
problem, a floating trip setpoint, was submitted to NRR by the licensee
January 11, 1979, in letter P-79012.
In the interim the linear power
channel scram and RWP are calibrated daily or whenever a 10% change
in power level has occurred, or a rod is fully withdrawn.
(Close) Open Item (50-267/7914):
Hanger 11-A-H-46448 initial audit
not in accordance with observations.
The inspector reviewed the reaudit
of the hanger and confirmed that no major discrepancies were overlooked.
(Closed) Open Item (50-267/7917-01):
No portable radios available for
emergencies in control room.
Operations order dated January 31, 1980 was
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issued regarding the control of portable radios.
Observations have
indicated that the required radios are now available.
(Closed) Open Item (50-267/7917-02):
Records not maintained for required
controller settings.
The required records are now maintained on
Report No. 5276 " Fort St. Vrain Master Setpoint List - Controllers."
(Close) Unresolved Item (50-267/7919-02):
Thread Engagement Depth
Sample Enlargement - Bulletin 79-02.
The licensee completed inspection
of 50 floor mounted bolts and an additional 99 wall mounted bolts, ie:
measuring for thread engagement.
Only one was measured to have
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inadequate thread engagement and was subsequently repaired.
The
measurements were a result of ultrasonic and w;ual measurements.
(Close) Unresolved Item (50-267/7919-03):
Verification of embedment
depth - Bulletin 79-02.
The licensee completed the UT testing program
in conjunction with physical measurements to verify embedment depth for
the bolts noted it. unresolved item 7919-02. Only one bolt had insufficient
embedment depth.
(Close)-Item of Noncompliance (50-267/7922-1):
Procedural instructions
not available.
Technical Services Procedure No. 13 was revised and
reviewed with operation personnel relating to the time that flow may be
removed from the primary and secondary coolant.
(Close) Item of Noncompliance (50-267/7922-2):
(a) Trash in the auxiliary
electric room and oil soaked paper towels, garbage can overflowing,
oil stored on lower level of rear building; and (b) PME-3 not completed
p rope rly.
All maintenance personnel were reinstructed regarding their
responsibilities for maintaining clean working areas and for completion
of data sheets in accordance with procedural requirements.
3.
The inspector reviewed portions of the licensee's physical protection
program by review of selected records and observation of the activities of
access control, search, escorting, and communications.
No items of noncompliance or deviations were identified.
4.
Review of Plant Operations
A review of plant operations was conducted to ascertain whether
facility operation was in conformance with the requirements established in
Technical Specifications, 10 CFR, and Administrative Procedures, or
licensee commitments discussed in correspondence to the Commission.
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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Reactor Operator Logs
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Technical Specification Compliance Log
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Operating Order Book
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Form 1 Log (Jumper Log)
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Plant Trouble Reports
Selective Valve Lineups
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During the tour of accessible areas, particular attention was directed
to the following:
Monitoring Instrumentation
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Radiation Controls
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Housekeeping
Fluid Leaks
Piping Vibration
Hanger / Seismic Restraints
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Clearance Tags
Fire llazards
Control Room Manning
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No items of nor conformance or deviations were identified.
5.
Calibration
a.
Technical Specification Requirements
The inspectors selected a sample of various instruments to verify
that the frequency of calibration required by the licens had been
met.
From this sample, documentation from 13 of these instrument
channels was selected and reviewed for (1) completeness, (2) proper
acceptance criteria, (3) use of proper revision, and (4) qualification
of individuals performing the calibration.
In addition, the
procedures were reviewed to verify that (1) they had been approved
as required by Technical Specification, (2) calibration was to
the required accuracy, (3) as-found as as-left conditions were
recorded, (4) calibration equipment used was traceable, and (5)
calibration sheets had been initialed by the technician performing
the calibration.
The following calibration records were reviewed:
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Calibration
Reference
Dates
- SR5.1.2bd-A
Reserve Shutdown System Hopper
5.1.2d)
4/3/78
Instrumentation Calibration
3/26/79
- SRS.2.lc1 &
PCRV Overpressure Safety
5.2.1c)
(c1) 10/3/79
c2
System Instrumentation Cali-
12/14/79
bration
(c2) 6/7/79
- SR5.2.9-A
Helium Circulator Bearing Water
5.2.9
11/30/78
Accumulator Instrumentation
10/29/79
Calibration
- SR5.2.15-A
PCRV Penetration Interspace
5.2.15
1/30/79
Pressure Instrumentation Cali-
bration
2SR5.2.23-A
Fire Water Booster Pump
5.2.23
5/22/79
Instrumentation Calibration
- SRS.3.5-A
Hydraulic Oil Accumulator Gas
5.3.3
3/22/79
Pressure Instrument Calibration
- SR5.3.6-A
Instrument Air System Pressure
5.3.6
4/25/78
Instrument Calibration
7/16/79
Startup Channel Scram Cali-
5.4.1.1.3
12/1/78
b ration
12/1/79
Linear Power Channel Scram
5.4.1.1.4
Week #1 1/5-6/80
and PMP Calibration
Week #2 1/7-8/80
Week #8 2/18-22/80
- SRS.4.1.1
Primary Coolant Moisture
5.4.1.1.b
10/30/78
bc-R
Calibration
11/14/79
Reheat Scram Temperature
5.4.1.1.8
9/10/78
Sc-R
Scram Calibration
9/11/79
SRS.4.1.1
Primary Coolant Pressure
5.4.1.1.9
3/1/79
Scram Calibration
10/30/79
SRS.4.1.1
Circulator Inlet Temperature
5.4.1.1.10
6/7/78
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Scram Calibration
7/9/79
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SRS.4.1.1
Hot Reheat Header Pressure
5.4.1.1.11
7/24/78
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Scram Calibration
7/27/79
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- SRS.4.1.3
Feedwater Flow Calibration
5.4.1.3.2
6/6/78
3/19/79
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- SR5.4.5A1
PCRV Cooling Water Flow Scram
5.4.5
9/26/78
Calibration
9/17/79
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- SR5.4.10.5A/ Seismic Instrumentation
5.4.10
7/9/79
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B1-A
12/12/79
- SR5.5.1-A
Reactor Building Sub-Atmospheric 5.5.1
3/2/79
Instrument Calibration
- SRS.6. led-A
Diesel Generator Exhaust
5.6.1
5/26/79 to
Temperature Instrument
9/4/79
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Calibration
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- These channels received the expanded review.
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As a result of these reviews, the inspectors had the following
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findings.
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While reviewing the Linear Power Channel Scram and RWP Calibration
Procedure SR 5.4.1.1.4c-D for week No. 1 (1/5-6/80) and week No. 2
(1/7-8/80), it was noted by the inspector that the test conductor
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had failed to identify the calibration equipment used in Section
3.0.
ADM-13, Administrative Procedure for Technical Specification
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Surveillance, states in Section 2.5d) that the test conductor, "is
responsible for assembling test equipment, special tools and other
items specified by the test procedure and identifying them in
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Section 3.0 of the SR."
The inspector determined that the
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calibration was performed properly, but the failure to follow the
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administrative procedure as noted above constitutes an item of
noncompliance at the deficiency level.
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In addition, the inspectors found that the following calibration
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procedures had been conducted using superceded procedure revisions:
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Date
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System
Perfo rmance
Revision Revision in Effect
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Procedure No.
Calibration
Began
Used
at Performance
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5.1.2bd-A
Reserve Shutdown
3/26/79
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14 effective
1/31/79
5.3.5-A
Hydraulic Power
3/22/79
10
12 effective
2/28/79
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5.3.6-A
Instrument Air
7/16/79
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9 effective
3/5/79
5.4.1.1.11b-R
Hot Reheat
7/27/79
10
11 effective
3/5/79
5.4.1.3.2d-R
3/19/79
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15 effective
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2/28/79
With the one exception below, it appears that only nonsubstantive
changes were involved in the above procedure revisions.
Procedure
5.4.1.3.2d-R, Feedwater System Instrumentation Calibration,
appears to involve a major rewrite between revisions 13 and 15,
and will require licensee review to verify the acceptability of
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the calibration.
The licensee's Quality Assurance Plan for Operations implements
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Criterion VI of Appendix B to 10 CFR 50, Document Control, which
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specifically states that procedures, including changes thereto,
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shall be distributed to and used at the locations where the
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prescribed activity is performed. This failure to utilize the
most current procedure revisions is contrary to the requirements
identified above and constitutes an item of noncompliance at
the infraction level.
The inspector also inspected two instruments used as primary
standards for calibration of the Omega RTD Temperature Probe
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No. 8177 (PSC No. M3119) and Heise Test Gage CM-7004 (PSC No. 3167).
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No further adverse findings were ident.ified.
b.
Technical Specification Related Instruments
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The inspector selected a sample of instrumentation from safet',-
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related systems to verify that (1) these instruments are included
in the licensee's program for routine calibrations, (2) the range
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and accuracy of the components is consistent with the application,
(3) approved procedures are available to calibrate the component,
and (4) calibration records are complete.
The following calibration
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records were reviewed:
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LI-2519, Liquid Nitrogen Storage Tank Level
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FR-4101, Liquid Effluent Blowdown Low Circulating Water Flow
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LI-4102-3, Circulating Water Makeup Storage Pond Level
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PCRV Outlet Subheader and Liner Cooling Tube Indicators and
Thermocouples
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When given the instrument calibration history cards for LI-2519, the
inspector noted that nothing had been done since 1976.
Further
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investigation found that the original device had been taken out of
service and replaced with a different type sensor in 1977.
Calibration cards did exist for the new device and calibrations had
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been performed, but some confusion existed because no entry had
been made on the original cards indicating that the device was no
longer in service.
While examining the calibration cards for L1-4102-3, it was deter-
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mined that the original level device has just been replaced by
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another type. However, the original calibration cards had been
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retained with the original device number removed and the new device
number listed.
By doing so, the calibration / repair history
for the original device also appears applicable to the new instrument.
In addition, LI-4102-3 was not listed in the latest Master Calibration
List used by the licensee to schedule routine calibrations.
Although
the calibrations had been performed, there was no mechanism identified
for ensuring that this would be done on a routine basis.
The
licensee indicated that LI-4102-3 would be incorpotated into the
Master Calibration List and that the problems identified above
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related to the calibration records would be investigated.
Therefore,
pending further review, these concerns are considered open items.
(8002-01)
6.
Core Safety Limit
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The inspector reviewed surveillance procedures regarding core safety
limits to verify that procedures exist requiring (a) periodic review
of reactor power and reactor power to flow ratios to assure that undue
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migration of fuel kernels has not occurred, and (b) calculation of the
amount of fuel kernel migration as required by the technical specifica-
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tion when the reactor power to flow ratio exceeds a specified valve.
Surveillance procedure (SR 5.1.6-w) was reviewed by the inspector through
December 28, 1979. Total migration experienced for Core 1 was 0.217 and
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that for core 2 to December 28, 1979 is 0.138.
No items of noncompliance or deviations were identified.
7.
Maintenance
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The inspector reviewed selected maintenance activities to determine
that those activities met acceptable maintenance practices, the licensee's
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applicable administrative and maintenance procedures, and where applicable
were in accor -c.ce with Technical Specifications.
Additionally, the
inspector obset 'd portions of maintenance activities to verify that
procedural requirei._
let, personnel were qualified, QC hold
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points were provided, ta a :; procedures were appropriate and the items
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were not reportable as reportable occurrences.
The maintenance activities reviewed were:
Circulator Replacement PTR1-72, CWP-410, CWP-465
Moisture Monitors 1117, 1121, 1122, CWP 443, CN 1083
Hydraulic Pumps Coupling Inspection PTR2-120, Maintenance Procedure #105
Hangers 11A-H-21325, 11A-H-21326, 11A-H-21327 CN 1178, WA869-98
The hangecs identified above were the result of findings from Bulletin 79-14.
No items c,f noncompliance or deviations were identified.
8.
Surveillance
The inspector observed Technical Specification required surveillance
testing as follows:
SR 5.6.lb-SA Loss of Outside Power and Turbine Trip.
No items o.' noncompliance or deviations were identified.
9.
Review of Licensec Event Reports
The inspector reviewed licensee event reporting activities to verify that
they were in accordance with Technical Specification, Section 7, including
identification details, corrective action, review and evaluation of aspects
relative to operations and accuracy of reporting.
The following reports were reviewed by the inspector:
- R0 80-02
RO 77-17
- RO 80-03
R0 80-02 as submitted did not contain sufficient : aformation regarding
reac+ivity changes which occurred during the repert period.
For
example, the R0 did not include information concerning the control
rods which were removed and reinstalled, during installation of the
core restraint devices.
The licensee plans to resubmit the report.
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During review of R0 80-03 the inspector noted that the hangers were
incorrectly identified as 11A-H-21235, 11A-H-21236 and 11A-H-21237.
The licensee will resubmit the report with the correct hangers as
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follows:
11A-H-21325, 11A-H-21326, and 11A-H-21327.
- Still Open
No items of noncompliance or deviations were identified.
10.
Emergency Planning
The inspector observed the annual drill (FOSAVEX 80) to verify that
emergency actions were taken in accordance with the licensee's approved
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The inspector observed the drill primarily from the site command post
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and control room.
The inspector noted several minor deficiencies
including:
Battery powered phone monitors were audibly weak and the batteries
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in use have a short lifetime.
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Total accunulated doses were not monitored closely by the licensee
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for both plant operators and off site personnel until approximately
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2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 15 minutes into the drill scenario.
The accumulated doses
would not have exceeded 10 CFR 20 limits up until that time, but
it had not been considered until the accident had been reclassified
as Category III.
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The licensee is taking action to resolve these concerns.
No items of noncompliance or deviations were identified.
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11.
IE Bulletin / Circulars
The inspector verified by record review, observation, and discussion with
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representatives of the licensee, the actions taken in response to IE
Bulletin / Circulars.
The following Circulars were reviewed:
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79-23 Motor Starters and Contactors Failed to Operate.
None with the
specified date code, model and serial Number were received by
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Fort St. Vrain.
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The following Bulletins were reviewed:
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77-01 Pneumatic Time Delay Relay Setpoint Drift Change Notice #594B was
completed by CWP #349 and 418. The change required replacement
with electronic timing mechanisms.
The replacement is now complete.
79-23 Potential Failure of Emergency Diesel Generator Field Exciter Trans-
former.
A test, T-125, was completed January 11, 1980 as required
by item 2 of the bulletin.
The results appear to be satisfactory.
79-25 Failures of Westinghouse BFD Relays in Safety-Related Systems.
Westinghouse BFD/NBFD relays as listed in the bulletin were not
used at Fort St. Vrain.
79-28 Possible Malfunction of NAMC0 Model EA180 Limit Switches at
Elevated Temperatures.
NAMCO Model EA180 Limit Switches as listed
in the bulletin were not used at Fort St. Vrain.
No items of noncompliance or deviations were identified.
12.
Report Reviews
The inspector reviewed the following reports for content, reporting
requirements and adequacy.
Annual Operating Report, January 1979 through December 1979.
Report of Changes, Tests, and Experiments, January 1, 1979
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through December 31, 1979.
No items of noncompliance or deviations were identified.
13.
Exit Interviews
Exit interviews were conducted at the end of various segments of this
inspection with Mr. D. Warembourg (Manager, Nuclear Production) and
other members of the Public Service Company staff.
At the interviews,
the inspector discussed the findings indicated in the previous paragraphs.
The licensee acknowledged these findings.