ML19259B213
| ML19259B213 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/04/1978 |
| From: | Dickerson M, Johnson E, Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19259B188 | List: |
| References | |
| 50-267-78-19, NUDOCS 7901170171 | |
| Download: ML19259B213 (7) | |
See also: IR 05000267/1978019
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U. S. flUCLEAR REGULATORY COMMISSION
OFFICE OF ItiSPECTI0il AND ENFORCEMEflT
REGION IV
IE Inspection Report No. 50-267/78-19
Docket flo. 50-267
License No. DN1-34
Licensee:
Public Service Company of Colorado
P. O. Box b40
Denver, Colorado
80201
Facility Name:
Fort St. Vrain fiuclear Generating Station
Inspection At:
Fort St. Vrain Si te, Platteville, Colorado
Inspection Conducted:
November 13-16, 1978
Inspectors:
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M. W. Dickerson, Reactor Inspector
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E. II. Johnson, Reactor Inspector
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Accompanying
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Personnel:
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G.11. Verduzcd Reactor Inspector (Training)
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Approved by:
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G. L. Madsen, Chief, Reactor Operations
Date
and Nuclear Support Branch
Inspection Summary
Inspection on November 13-16, 1978 (Report No. 50-267/78-19)
Areas Insp_ected:
Routine, unannounced inspection of training; requalifica-
tion training; reserve shutdown system; review of plant operations; and
follow-up on inspector identified and unresolved problems.
The inspection
involved fifty-six (56) inspector-hours on-site by two (2) NRC inspectors.
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DETAILS
1.
Persons Contacted
Public Service Company of Colorado
- L. Brey, QA Manager
M. Bruxvort, Electrician
R. Erwin, Junior Storekeeper
D. Evans, Reactor Operator
W. Franek, Results Supervisor
M. Ferris, Engineer Technical Services
D. Frye, Plant Mechanic
- J. Gamm, Supervisor Technical Services
- E. Hill, Supervisor Operations
- W. Hillyard, Administrative Services Manager
D. Hood, Shift Supervisor, Operations
J. Hunter, Reactor Operator
- F. Mathie, Operations Manager
S. Shaeffer, Reactor Operator
L. Singleton, Shift Supervisor, Operations
J. Solakiewicz, QA Engineer
M. Thiel, Temporary Employee
D. Warembourg, Manager, Nuclear Production
R. Wadas, Training Supervisor
V. Wetzbarger. Supervisor QC and Scheduling
- Attended exit interview.
2.
Licensee Action on Previous Inspection Findings
(Closed) Unresolved Item (50-267/78-08):
Inconsistencies in procedure
SR 5.3.5-A.
Surveillance procedure SR 5.3.5-A, " Hydraulic Power
System Calibration," was revised and approved on October 30, 1978, to
resolve the inconsistencies.
3.
Review of Plant Operations
During the inspection, the conduct of plant operations was reviewed
to determine that they confonn to requirements of the facility license
and the licensee's procedures.
Included in the review were observation
of control room activities, logs, and records.
In addition, the
inspector completed a tour of accessible areas.
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Results:
Of the five (5) areas inspected, one (1) item of noncompliance
iiaiToiind during the review of requalification training (Deficiency-
Failure to address areas in subsequent training lectures for which scores
less thari 807, had been obtained - paragraph 6).
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The inspector's review of this area included:
Shift Supervisor's Log (September 13 - November 12,1978)
Reactor Operator's Log (September 13 - November 12,1978)
Surveillance Logs 1-3 (September 13 - November 12,1978)
Operations Order Book
Form l's (Jumper Log)
Plant Trouble Reports
a.
Tour
During the tour of the facility, observations were made in the
following areas:
Monitoring Instrumentation
Radiation Controls
Housekeeping
Fluid Leaks
Piping Vibrations
Hanger / Seismic Restraints
Clearance Tags
Control Room Manning
During this tour, the inspector identified several areas which
require some remedial action.
Included were several snubbers
which appeared low on oil; greater than normal oil which had
collected under the two (2) diesel generators; and housekeeping
on the lower two levels of the reactor building.
b.
Fluctuations
Fluctuations were observed on November 4,1978, during Test RT-500.
The purpose of the test was to determine the influence of core
flow resistance on the threshold power for fluctuations and to
obtain FM data with revised instrumentation.
Data was also to
be obtained with the reg-rod held in a fixed position.
The fluctuations were observed during a rise in power from 43%
to 49% while the core pressure drop was set at 2.85 psig.
Initially the fluctuations were noted as swings of abc it 1.5%
on the channel VII nuclear detector and + 20 F of the :nuin steam
temperature. After approximataly 30 to 35 minutes into the
fluctuation the exit temperature for steam generator module
B-1-1 dropped approximately 120 F.
Some temperature drops were
also noted on other steam generator modules. With the
observation of the main steam temperature swings the reactor
power was reduced 35% to terminate the fluctuations.
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Also noted during this time were a drop in refueling region 13
exit temperature of about 2000F and an increase in refueling
region 12 temperature approaching this same magnitude. At
present, the reactor is being operated at a low pressure drop
across the core in a mode to preclude fluctuations while the
data gathered during the test is evaluated and until tests are
permitted to resume.
No items of nonconformance or deviations were identified.
4.
Reserve Shutdown System
The inspector reviewed surveillance procedures, operating procedures,
records of tests and procedures performed, and inspected the reserve
shutdown system to determine that the licensee conformed to technical
specification, the FSAR and approved procedures.
Review of the last quarterly surveillance procedure 5.1.2 ad-Q,
" Reserve Shutdown Hopper Pressure Test," performed September 11,
1978, indicated in Step 5.3.2 that all locking devices which were
removed from manually operated valves were replaced.
However, during
observation of these valves by the inspector on the morning of
November 14, 1978, valves V11684, V11333, V11672 and V11674 were
found to have broken seals (locking devices). Additionally, valves
V11652 and V11641 had no seals in place on the valves. At this
same time the cover plate was also observed to be off of PS 1106-33.
A check of the current startup records and those for startup 78-09
dated September 26, 1978, contained a system 12 sign-off sheet
indicating the system status was acceptable based on the statement
" System operable based on the fact that it has remained in normal
operating configurations or that all portions cleared out, shutdown
or altered for maintenance have been returned to service." In
addition, no locked valve check-off list was completed for system 12
(Reserve Shutdown System).
A check of startup 78-08 records for
August 20, 1978, were similar to those for 78-09. A check of startup
78-07 records for August 4, 1978, were similar to those for 78-08
and 78-09 except that the sealed valve list indicated a "not
applicable" for the system 12 valves.
Since the time when the seals were removed or broken appears to be
indeterminate, this matter is considered unresolved pending develop-
ment of a satisfactory method by the licensue for assuring that
locked valves (open or closed) are appropriately checked prior to
and during operation where necessary.
No items of nonconfomance or deviations were identified.
b
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5.
Training
The inspector reviewed various elements of the overall training
program by direct .,uestioning of personnel and review of training
records.
fio items of noncompliance were identified.
It was noted, however,
that no portion of the overall training curriculum is devoted to
plant systems familiarization for craf tsmen.
A licensee representative
as well as well as craftsmen interviewed indicated that such an
addition to the training program would be most beneficial.
6.
Requalification Training
The inspector reviewed the requalification program including the
following records and documents:
Lecture Schedule
Attendance Records
Control Manipulative Records
Annual Examination for 1977
Composite Personnel Training Records
Personnel Requalification Files
Within the scope of this inspection effort, one (1) item of noncompli-
ance was identified.
Four (4) reactor operators scored less than 80% on the safcty and
emergency systems (category E) portion of the 1977 annual examination.
Contrary to 10 CFR 55, Appendix A, Section 2, the requalification
training program administered subsequent to this examination did not
address safety and emergency systems.
This is a deficiency.
10 CFR 55, Appendix A, Section 4c. requires " systematic observation
and evaluation of the performance and competency of licensed operators
and senior operators by supervisors and/or training staff members
including evaluation of actions taken or to be taken during abnormal
and emergency conditions."
Implicit in this requirement is that
evaluations be done in a timely manner (i.e., within one (1) or two
(2) working days) and that evaluations include discussions with watch
personnel as well as review of operator logs, recorder charts, etc.
The inspector noted that plant management reviews generally did not
include a qualitative statement addressing the operator's actions
or give indication of the depth of the evaluation.
This is
particularly significant where evaluation of shift supervisors are
concerned.
Futher, it should be pointed out that evaluations may
be done by training staff members.
The absence of a date on the
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two (2) evaluation sections (15 and 18) of the Fort St. Vrain form 0-6,
reactivity manipulation form, leaves some question as to the
timeliness of the evaluation. This is an open item pending revision
of the 0-6 form.
No other items of noncompliance or deviations were identified in
this area.
7.
Unresolved Items
Unresolved items are matters about which more information is required
in order to ascertain whether they are acceptable items, items of
noncompliance, or deviations.
The following item was identified
during the inspection:
7819-1 Determination of status of locked valves - paragraph 4.
8.
Exit Interview
An exit interview was conducted with representatives of the licensee
on November 16, 1978, at the conclusion of the inspection.
At the
interview, the inspectors discussed the findings indicated in the
previous paragraphs.
The licensee acknowledged their findings.