ML19294B937
| ML19294B937 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/10/1980 |
| From: | Collins R, Rich Smith, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19294B928 | List: |
| References | |
| 50-267-79-22, NUDOCS 8003060428 | |
| Download: ML19294B937 (10) | |
See also: IR 05000267/1979022
Text
U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-267/79-22
Docket No. 50-267
License No. DPR-34
Licensee:
Public Service Company of Colorado
P. O. Bcx 840
Denver, Colorado 80201
Facility Name:
Fort St. Vrain Nuclear Generating Station
Inspection At:
Fort St. Vrain Site, Platteville, Colorado
Ins;' action Conducted:
December 1-28, 1979
' <[ me,[v /M
05'd dO'
Inspectors:
/
fl. W. Dickerson, Senlogesident Reactor Inspector
Date
f
J
') kd
,~!w/4d
th/E
R'.Smitn,Repctordnspector
Date
4 44/L
me
4. E. Col tiny, Resident / Reactor Inspector
Date /
Approved By:
b
4[#1,
/h
///f /f C
'T. F. Westerman, Chief, Reactor Projects Section
Date
Inspection Summary
Inspection December 1-28, 1979 (Report No. 50-267/79-22)
Areas Inspected:
Routine, announced inspection of Reserve Shutdown System;
Radiation Protection; Surveillance; Part 21 Report; Maintenance; Physical Security;
Plant Operations; Training; Requalification Training; followup on itemt of non-
compliance; and followup on inspector identified and unre' alved problems.
The
inspection involved 168 inspector-hours on-site by three (3) NRC inspectors.
Results:
Within the eleven (.11) areas inspected, two items of noncompliance were
identified (infraction - failure to follow procedures (.two examples), paragraphs
4 and 8; infraction - failure to write a procedure as required by Technical
Specifications, paragraph 4).
8003060 f
.
-2-
DETAILS
1.
Persons. Contacted
L. Brey, QA Manager
W. Crane, Maintenance Superintendent
W. Franek, Results Supervisor
J. Gamm, Supervisor Technical Services
E. Hill, Superinter. dent of Operations
W. Hillyard, Administrative Services Manager
J. Liebelt, Electrical Supervisor
T. Mathie, Operations Manager
J. Solakiewicz, Superintendent Operations QA
G. Turner, Supervisor of Security
D. Warembourg, Manager Nuclear Production
The inspector also contacted other plant personnel including reactor
operators, maintenance men, electricians, engineers, technicians and
administrative personnel.
2.
Licensee Action on Previous Insoection Findinas
(0 pen)
Unresolved Item (.50-267/7512-1): Records Procedure.
The records
procedure is to be changed to reflect the requirement for record retention
periods.
The change is expected to be completed by January 1, 1980.
(Closed) Open Item (50-267/76-09):
Compliance with ANSI N45.2.11, Quality
Assurance requirements for the design of nuclear plants.
The licensee
has completed and implemented procedures QAP 1400, QAP 1700, IWP 2 and
ENG 1 and 2, in accordance with the requirements of ANSI N45.2.11 - 1974.
(0 pen) Unresolved Item (50-267/7714-1):
Pulled Fuses.
The licensee has
indicated that the required input for a procedure for the control of fuses
will be completed by May 1, 1980.
(Closed)
Unresolved Item (50-267/7901-2):
PROC Review of TS 7.1.2.e(7)
requirements.
The Plant Operations Review Committee has initiated review
of additional areas of reactor operation as specified in a PORC policy
memo.
(Closed) Open Item (50-267/7912):
Status tags not controlled.
Changes have
been made to ADM-10 which provide for use and control of the status tags.
(Closed) Unresolved Item '50-267/7914): ACM diesel generator doors
unlocked.
Keys for the diesel generator doors are now controlled by the
shift supervisor and instructions for security checks of the doors by the
guards have been issued.
-3-
(Closed) Item of Noncompliance (50-267/7915):
Valves found not sealed,
valves found closed, and no PTR written for inoperative recorder.
The
inspector has reviewed the corrective action specified in the licensee's
letter dated December 3,1979 and this matter is considered closed.
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 Ooerations
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, ar 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
.
Reactor Operator Logs
.
Technical Specification Compliance Log
.
Operating Order Book
.
Form 1 Log (Jumper Log)
.
Plant Trouble Reports
.
Selective Valve Lineups
.
During the tour of accessible areas, particular attention was directed to
the following:
Monitoring Instrumentation
.
Radiation Controls
.
Housekeeping
.
Fluid Leaks
.
Piping Vibration
.
Hanger / Seismic Restraints
.
Clearance Tags
.
Fire Hazards
.
Control Room Manning
.
.
-4-
During this aspect of the inspection, the inspectors noted that (a)
a trash container located in the auxiliary electric equipment room was
found to be overflowing with paper and had a cardboard box piled on top
of the trash container, and (b) on the lower level of the reactor
building adjacent to tne hydraulic oil system, numerous oil soaked
paper towels were stuffed between the concrete wall and the work area,
a garbage can was full of soiled pacer towels and was overflowing, a
partial bucket of oil was stored adjacent to the garbage can and
additional paper towels and empty boxes were strewn about the work
area.
The failure to control the combustible material is contrary to
the requirements specified in Administrative Procedure ADM-30.
ADM-30, Procedure for Control of Combustibles, Section 4.2, requires
that, " Flammable items such as some anti-C clothing and wiping rags shall
be kept in a noncombustible bin or contai rer until required and placed
in approved small waste storage upon disposal." Additionally, Criterion
V of Appendix B to 10 CFR 50 requires in part that, " Activities affecting
quality . . . shall be accomplished in accordance with these instructions,
procedures, or drawings." This is further amplified by the licensee's
approved QA Plan, Final Safety Analysis Section B.5(c) which states in
part, "The various aspects of plant operation will be defined and con-
trolled by written procedures . . . ."
The licensee was informed that failure to control the combustibles
specified above in accordance with the approved procedures was considered
an item of noncompliance.
On December 4,1979, the inspector discussed with operators and the shift
supervisor how the instructions entered in the operations log, Book 11,
page 0-1 at 0905 on December 3,1979, were being handled.
The entry as
stated read in part that, " . . . both primary and secondary coolant can
be shut off #1 46 hrs. to not exceed 4000F Top Hd He Temp. or #2 120 hrs.
to not exceed 7600F top Hd He Temp." At 1235, the entry read "All P/C
and S/C shut off for WA 825-21." A copy of Data Sheet 2, " Calculating
the Hours Forced Cooling May Be Off (knowing maximum fuel temperature
to be allowed)" was available in the control room.
It became apparent during the discussions that no written instructions
were available to either the shift supervisor or the operators and that
confusion existed on how to utilize this information.
Some operators
had recorded core outlet temperature during the time when coolant was
off, although temperatures at this time would not be representative of
fuel or top head temperatures.
Moreover, the controlling aspect was
the time that flow could be off before the specified temperatures
would be exceeded and therefore, required return of the flow within
these times, depending upon restrictions regarding the restart of the
steam generator coolant flow.
When this became apparent, the inspector
-5-
discussed the problem with the Manager of Nuclear Production who
indicated he would correct this situation.
This failure to provide
written procedures / instructions is contrary to the requirements of
Technical Specification 7.4.a, Procedures, Administrative Controls.
Technical Specification 7.4.a requires in part that, " Written procedures
shall be established, implemented and maintained covering . .
1.
The
applicable procedures recommended in Appendix A of Regulatory Guide 1.33,
November 1972." Contrary to this requirement, no written procedure was
available to the shift supervisor or operators for the removal of forced
cooling (primary and secondary) from the reactor.
The licensee was
infonned that failure to provide the written procedure in accordance
with the requirement specified above was considered an item of noncom-
pliance.
Since the work in progress required that coolant be shut off, WA 825-21 was
broken up into discrete packages.
The coolant was restored within the
required time periods.
Some of the core outlet temperatures at specified
times with coolant restored were:
Date
Time
Deg. F
U
12/3/79
0800
254U
12/3/79
2400
234U
12/4/79
0200
237U
12/4/79
0400
236U
12/4/79
0600
239U
12/5/79
1000
273U
12/6/79
1000
370
U
12/10/79
1200
340
The inspector had no additional questions in this area.
5.
Startup Report
The thirteenth Startup Report for Fort St. Vrain for the period August 23,
1979 through November 22, 1979, reviewed by the inspector, contained no
relevant information on the initial approach to power tests since none
were performed during this period of time.
6.
Part 21 Report
On November 9, 1979, in letter P-79271, the licensee submitted to Region
IV a Part 21 Report No. 50-267/79-01 regarding 1-1/2" X 36" long full
threaded rods which did not meet the reduction area specification as required
by ASTM A-193-87.
As a result, the material in warehouse stock was replaced
by the manufacturer.
Additionally, the materials used for the steam inlet
-
.
-6-
supply pipe flange bolting on circulators C-2102 and C-2103 have been
removed and replaced.
The replacement was accomplished utilizing PTR's12-258 and 12-259.
The replacement studs,16 per circulator, were of
material procured in accordance with ASTM A-193-87.
During the removal of the defective material, it was noted that six nuts
on circulator C-2102 and two on C-2103 were finger tight.
It is suspected
that the material may have yielded.
To determine this, the licensee
intends to conduct tests on the material removed.
Additionally, several
nuts installed on one of a.e other two circulators will be checked as
confirmation that the loose nuts were related only to those placed on
defective bolts.
7.
Radiation Protection
The inspector reviewed the licensee's exposure control and high radiation
Additionall , radiation protection instruments
area posting and control.
3
in use at the time were examined for operability and calibration.
However,
at the time of the review no RWP's were in use so selected RWP's from
December 14 and December 15, 1979 were reviewed.
These were:
RWP #
Date
Reason
2243
12/14/79
Replace Cover on HV-2301 and HV-2302;
General cleanup of RWP area.
2244
12/14/79
Change out System 62 resin from cartridge.
2245
12/15/79
Change F 6201S
The following instruments and calibration records were reviewed:
Instrument & Number
Calibration Date
Calibration Due Date
Proportional Counter M3365
10/24/79
1/30/79
Eberline RM-14 - M3353
12/15/79
3/80
- M3351
12/15/79
3/80
"
"
- M3359
12/15/79
3/80
"
"
- M3360
12/15/79
3/80
"
"
- M3354
12/16/79
3/80
"
"
- M3352
12/15/79
3/80
"
"
- M3342
12/16/79
3/80
"
"
R0-2 - M3314
12/4/79
1/80
"
Eberline Portal
Monitor
- M3340
10/1/79
Eberline Beta
Particle Monitor - fi3317
Presently not calibrated (not required according
to the manufacturer).
However, a procedure for
calibration has been developed and the instrument
will be calibrated in 2/80 and then on a frequency
of every three months.
.
.
-7-
Calibration of radiation monitors for liquid effluents, gases, process
monitors and area monitors were reviewed in conjunction with the follow-
ing surveillance tests.
SR 5.4.9.A-1, Process Gamma Monitors Calibration, completed 8/31/79
SR 5.4.9.A-2, Process Beta Monitors Calibration, completed 9/11/79
SR 5.4.9.A-3, Area and Equipment Monitors Calibration, completed 8/27/79
SR 5.8.le-A, Radioactive Gaseous Effluent Flow Recorders, Calibration,
completed 9/10/79
SR 5.8.lcd-Q, Radioactive Gaseous Effluent System Calibration, completed
9/5/79
SR 5.8.2c-Q, Radioactive Liquid Effluent Activity Monitors Calibration,
completed 9/5/79
No items of noncompliance or deviations were identified.
8.
Maintenance
The inspector reviewed selected maintenance activities to determine that
those activities met acceptable maintenance practices, the licensee's
applicable administrative and maintenance procedures, and where applicable
were in accordance with Technical Specifications.
Additionally, the
inspector observed portions of maintenance activities to verify that
procedural requirements were met, personnel were qualified, QC hold
points were provided, tagging procedures were appropriate and the items
were not reportable as reportable occurrences.
The maintenance activities reviewed were:
PTR 5-805, Inspect Diesel Generator (DG) 1B - Control Cabinets
and Generator End per PME-3
PTR-12-258
PTR 12-259
During observations of maintenance performed as a result of PTR 5-805,
Inspec+ Diesel Generator (DG) 1B - Control Cabinets and Generator End
per PME-3, it was determined that Work / Test Instructions did not
indicate the data to be recorded on Attachment No. 1, Insulation
Resistance Sheet Table, of PME-3.
Moreover, the tables for data to be
recorded were not used, all of the data listed was not taken, and only
the ' Remarks' section was used to record the data.
.
.
-8-
Criterion V of Appendix B to 10 CFR 50 requires in part that, " Activities
affecting quality . . . shall be accomplished in accordance with these
instructions, procedures, or drawings." The l'censee's approved QA
Plan, Final Safety Analysis Section B.5(c) states in part, "the various
aspects of plant operation will be defined and controlled by written
procedures . . . ." Administrative Procedure (ADM) No. 12, Maintenance
and Repair Procedures, Section 5.1.3(10)d, states that work / test
instructions shall include the following " Acceptable criteria and data
to be recorded / verified."
The failure to comply with these requirements as indicated above were
discussed with the licensee who was infonned that this was an apparent
item of noncompliance for failure to follow procedures and was
considered an infraction.
The inspector had no additional questions in this area.
9.
Surveillance Activities
The inspector observed Technical Specification required surveillance
test 5.4.1.2.1.d-M, Steam Pipe Rupture (Pipe Cavity) Test.
The inspector verified that test results were in conformance with
Technical Specifications and procedure requirements and that they were
reviewed by appropriate personnel.
The inspector verified that deficiencies identified during testing were
properly resolved and reviewed by appropriate management personnel.
10.
Calibration
The inspectcr reviewed the calibration of the instruments noted in
paragraph 7 of this report and verified that calibration was in confor-
mance with requirements.
No items of noncompliance or deviations were identified.
11.
Training and Recualification Training
The purpose of this inspect #an was to evaluate the licensed operator and
maintenance personnel training program and detennine if the training
program was in conformance with the regulatory requirements and requal-
ification training program approved by NRC.
.
.
-9-
The inspector's review included the following points:
The inspector reviewed records for nine licensed operators of
.
which four were senior operators (S0), three were special
refueling (SLO), and two were licensed operators.
Annual requalification exams.
.
Records of requalification lecture attendance.
.
Records of on-the-job training, including reactivity manipulations.
.
Annual operator evaluations.
.
Reviewed three lecture lesson plans.
.
Interviewed selected operators from the group of records reviewed.
.
Reviewed requalification program for changes since last NRC review.
.
Reviewed training records for selected maintenance personnel.
.
The inspector reviewed the 1979 annual requalification exams for SLO and
R0's to determine if the subsequent training program lectures had been
scheduled and conducted for areas where the operators had made a score of
less than 70%.
No items of nonconpliance or deviations were identified.
12.
Reserve Shutdown System
The inspector reviewed surveillance procedures, operating procedures,
records of tests and procedures performed, and inspected the reserve
shutdown system to detennine that the licensee conformed to Technical
Specification, the FSAR and approved procedures.
The surveillance procedures were reviewed to determine whether the procedures:
Require application of test pressure to the reserve shutdown hoppers
.
in accordance with the Technical Specifications and the FSAR.
Identify appropriate initial conditions.
.
Include acceptance criteria related to perfonnante of the actuating
.
valves, integrity of the rupture disc, and performance of the orificed
vent.
.
.
-10-
Identify proper valve lineup to each hopper for returning the
.
system to normal and require verification of the valve lineup.
Require periodic calibration of the pressure indicators.
.
Require testing a hopper and a rupture disc in accordance with
.
requirements in the Technical Specifications and the FSAR.
Specify appropriate handling requirements, test conditions, and
.
acceptance criteria.
Require inspection of the hopper after the rupture disc ruptures
.
to determine whether all the balls were released from the hopper.
Identify appropriate specifications for the replacement rupture
.
disc and requirements for inspection of the replacement rupture
disc prior to and following installation.
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. W. Warembourg (Manager, Nuclear Production) and/or
other members of the Public Service Company staff.
At the interviews, the
inspectors discussed the findings indicated in the previous paragraphs.
The licensee acknowledged these findings.
't