ML20033C823
| ML20033C823 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 11/10/1981 |
| From: | Dickerson M, Plumlee G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20033C819 | List: |
| References | |
| 50-267-81-24, IEC-81-13, NUDOCS 8112040340 | |
| Download: ML20033C823 (9) | |
See also: IR 05000267/1981024
Text
_ _ _ _ _ - _ _ _ _ _ _ _ _ _
- _ _
_ _ _ _ _ _ _ _ _ _ _ _
_ ._
_
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ - _ _
_-
_.
-
.
APPENDIX B
U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report: 50-267/81-24
License DPR-34
Docket: 50-267
Licensee:
Publi.: Service Company of Colorado
.P. O. Bcx 840
Denver, Colorado
80201
Facility Name:
Fort St. Vrain Nuclear Generation Station
Inspection at: Fort St. Vrain Site, Platteville, Colorado
Inspection Conducted: October 1-31, 1981
Inspectors:
3I
M
/h/#Y
M. W. Dickerson, Senior Resident Ra%ctor Inspector
Date
i
.,
7?'kbES=
- d~
u-o
>
G. L. Plumlee III, Resident Reactor Inspector
Date
.
/
Approved By:
/4/#~F/
T. F. Westerman, Chief, Reactor Project Section flo.1
Date
Inspection Sumary
Inspection conducted October 1-31, 1981 (Recort:
50-267/81-24)
f-
Areas Inspected:
Routine, announced inspection of Surveillance; Maintenance;
Operational Safety Verification; Licensee Event Follow-Up; Review of Periodic
and Special Reports; and IE Circulars. The inspection involved 157 inspection-
,
hours on site by two NRC inspectors.
'
Results: Within the six areas inspected, three violations were identified
(Failure to adhere to Technical Specifications, Paragraph 3.B.,-failure to
follow procedures, Paragraphs 3.A and4.B.)'
8112040340 811116
,
PDR ADOCK 05000267
0
. -
.- -
.
- -
- - .
-
- - -
--
.
2
1.
Persons Contacted
T. Borst, Radiation Protection Manager
M. Block, Superintendent of Operations
R. Craun, Acting Site Engineering Coordinator
M. Deniston, Shift Supervisor
D. Evans, Shift Supervisor
M. Ferris, Technical Services Engineer
W. Franek, Results Supervisor
W. Franklin, Shift Supervisor
J. Gahm, QA Manager
'
E. Hill, Operations Manager
D. Hood, Shift Supervisor
J. Liebelt, Senior Maintenance Supervisor
M. McBride, Technical Services Manager
F. Novachek, Technical Advisor
G. Reigel, Shift Supervisor
L. Singleton, Superintendent Operations OA
J. Van Dyke, Shift Supervisor
D. Warembourg, Manager Nuclear Production
R. Webb, Maintenance Supervisor
The NRC inspector also contacted other plant personnel including
f
reactor operators, maintenance men, electricians, technicians and
administrative personnel.
The regional SALP meeting with PSC management was alsc conducted
during the period of this report.
A subsequent report will be issued.
2.
Licensee Action on Previous Insoection Findings
(Closed) Violation (50-267/8111-01): Tritium concentration in
'
cooling tower blowdown water discharge exceeded 10 CFR 20 limits.
'
Procedural controls are in effect while design change considerations
are being investigated by the licensee.
The design changes are
considered as an unresolved item.
(8124-05)
l
(Closed) Violation (50-267/8111-02): System Status Tags in place but
!
System Abnormalities Deviation Forrs indicated system returned to
normal. The licensee issued a speedy memo to operators recarding
the problem and has replaced the System Abnormalities Book with three
separate books containing:
(1) Temporary Change Reports, (2) P. lear-
ances, and (3) Operations Deviations Reports.
'
!
(Closed) Violation (50-267/8112-02): Surveillance test records
indicated approval even though these records contained data
omissions and data outside the prescribed acceptance criteria.
The errors have been corrected, level 1 Procedure P-4 has replaced
Administrative Procedure 13, and a group has been established to
review and rewrite Surveillance Test Procedures.
Completion of
this review is scheduled for March 1,1982. Completion of this
review is considered an unresolved item.
(8124-06)
.
- W
w
r
w
w
_ - - - - - - - _ - - . - , - - _ . - _ . _ .
. _ -
_.
.
3
'
(Closed) Violation (50-267/8113-01): Concentration of total residual
'
chlorine in the non-radioactive liquid effluent exceeded that specified
in Technical Specification LC0 NR 1.1.
No violation was determined
to have occurred since the licensee returned the concentration within
the time allowed and was therefcre not reportable.
(Closed) Violation (50-267/8113-02): Total Phosphate on February 24,
4
1981, exceeded the 50% limit, and the daily samples required
'
.
by Technical Specification SR NR 1.l(b) were not taken. The daily
samples not taken cannot be taken to backfit the requirement.
'
However, the error was discussed by the licensee with members of
the Water Chemistry Department and a rewrite of Surveillance Pro-
cedure SR NR 1.1 was completed, which included a better explanation
of the requirements.
(Closed) Violation (50-267/8113-03):
Seventeen of 20 weekly surveillances
NR 1.1-W had been started on Friday, but the Shift Supervisor's approval
i
to start the surveillances had not been given until the following
Monday. The day of issuance of the tests was changed to coincide
with the Shift Supervisor's approval on Mondays.
(Closed) Violation (50-267/8113-06): The printer for RR 93256,
" Effluent Activity Monitor," was found secured and recorder RR 93254,
" Area Monitor," was found not to have been returned to service following
a surveillance. An Operations Surveillance test was written to assure
'
that all recorders are in service and requires sign-off by the
operator each shift. For RR 93254 discussions were held by the licen-
see with the surveillance test conductor to reiterate his responsi-
4
bilities. Additionally, Surveillance SR 5.4.9-W was rewritten so that
'
it is now consistent with a standardized format for surveillance tests, and
requires the test conductor to return the recorder to normal in a more
appropriate part of the test.
(Closed) Violation (50-267/8113-07): Nine Standard Clearance Points
Forms with auxiliary tags had not been checked off as required by
r
l
Procedure P-2.
All clearances were audited by the licensee for
conformance to requirements and all personnel involved in equipment
'
clearances and operations deviations were required to review the
l
requirements as set forth in Administrative Procedure P-2.
j
(Closed) Violation (50-267/8113-09): The north stairwell access
radiation barrier to the refueling floor was not in place as required
-
by Health Physics Procedure HPP-9. The barrier was immediately
replaced and appropriate marking devices were and will be provided
independent of the barrier marking.
I
I
- _ , ,
_ ,
, _ .
_ _ - . _ _ . , _ - _ _
_ . , . _ - - _ , - . . _
, . . _ , - . . . _ . ...
- - - . .
,
-,__,_-, ,-
.
4
3.
Operational Safety Verification
Tne NRC inspector reviewed licensee ;civities to ascertain that
the facility is being operated safely and in conformance with
regulatory requirements, and the licensee's management 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
.
Reactor Operator Logs
.
Equipment Operator Logs
.
Auxiliary Operator Logs
.
Technical Specification Compliance Logs
.
Operations Order Book
.
Operations Deviations Reports
.
Clearance Log
.
Temporary Configuration Reports
.
P' ant Trouble Reports
.
During tours of accessible areas, particular attention was directed
to the following:
Monitoring Instrumentation
.
Radiation Controls
.
Housekeeping
.
Fluid :e/L3
.
Piping Vibrations
.
.- -
-_
_
_
- - _ , _ - _ . .
..
,
.
-
5
Hanger / Seismic Restraints
.
Clearance Tags
.
Fire Hazards
.
Control Room Manning
.
.
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 Alternate Cooling Method System.
No problems were identified during the system walkdown.
A.
Valve Not Sealed
On October 20,1981, at 2:20 p.m. MDT, during a tour of the
reactor building, the NRC inspector determined that V-22184,
Loop I Main Steam Electromatic Relief Valve Shutoff Valve,
was not sealed.
Reactor power was approximately 34%.
Procedure P-2 requires equipment to be returned to normal upon
return of a clearance. The normal position of V-22184 is as
stated in the Sealed Valves Checklist and,in accordance with Pro-
cedure OPOP III,is required to be in the sealed open position
when reactor power is greater than 2%.
A review of the Operations Log for October 15, 1981, indicated
that V-22184 was shut at 9:20 a.m. MDT, and reopened at 7:10 p.m.
MDT, during maintenance on V-22368, V-22184 Bypass. Clearance
number 2310, which returned Loop I to service, had been returned
at 5:45 p.m. MDT. The NRC inspector noted that the failure
to seal V-22184 upon completion of maintenance activities is a
repeated occurrence. The previous occurrence was documented in
IE inspection report 50-267/81-18, Appendix B, Paragraph 5.
The NRC inspector discussed the above item with the licensee
and informed the licensee that failure to follow procedures
'
which are Technical Specification requirements is considered
a violation.
(8124-01).
,
.
-
.-.
.-
,
.
-
6
,
B.
Removal of Station Battery 1A From Service
On September 11,1981, at 7:00 p.m. MDT, the licensee removed
station battery 1 A from service and placed it on routine over-
charge. However, the reactor was at power (greater than 2%)
and the 1B emergency diesel generator unit was out of service
for maintenance.
J
Technical Specification LC0 4.6.1.e) requires that while
operating at power one battery may be removed from service
i
for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided several conditions are met. One of
'
the required provisions is that both diesel-generators and
,
their associated essential buses be operable. However,
since diesel-generator 1B was out of service for replacement
1
of the outboard bearing on the clutch shaft of 1D engine ,
,
the removal of station battery lh from service constituted
a violation of the Technical Specifications.
(8124-02)
This violation was found by the'l.icensee and reported in
r portable Occurrence 81-058, dated October 9,1981. The
e
reportable occurrence also delineated the corrective action
completed by the licensee to return the battery to service
at 11:45 p.m. MDT, on September 11, 1981, and to preclude
.
further occurrences of this type.
Since the licensee has completed the corrective action for
this item and has been reviewed by the NRC, the licensee is
not required to respond.
The NRC inspector had no additional questions in this area.
4.
Surveillance (Monthly)
The NRC inspector reviewed all aspects of su weillance testing
involving safety-related systems. The review included observation
and review relative to Technical Soecification requirements. The
surveillance tests reviewed and observed were:
SR 5.4.1.3.4.b-M
Circulator Penetration Pressure Test
SR 5.4.1.3.1.b-M
Circulator Speed (Steam and Water) Test
SR 5.1.6-W
Core Safety Limit
SR 5.4.7.3.2.b-M
Feedwater Flow Test
SR 5.8. led-Q
Radioactive Gaseous Effluent System Calibration
SR 5.4.1.1.4c-D/5.4.1.4.2c-D Linear Power Channel Heat Balance Calibration
SR 5.4.1.1.8.b-M
Reheat Scram Temperature Scram Test
SR 5.4.1.1.8c-R
Reheat Steam Temperature Scram Calibration
~.
-
_ _ _ _ _ _ _ _ ._ _ - , _ _ _ . _ _ _ . _ _ __ _ ._. _ _ _ - _ _ _. _ ,.
.
-
7
A.
Fire Retardant Cabinets
During a review of the licensee's calibration records on
September 28,1981, the NRC inspector noted that locking
devices were being installed on the storage cabinets. The
NRC inspector's review of the licensee's records indicated
that the licensee had determined via a Quality Assurance
Deficiency Report (QA-DR 669, dated June 1980) that measures
were necessary to ensure the safekeeping of these permanent
working records as required by ANSI N45.2.9.
The cabinet
locks were installed as a result of the licensee's Corrective
Action-Action Request (CA-AR 209, dated June 1981).
During
this reporting period through a review of the ANSI /ASME
N45.2.9-1979 concerning records storage requirements, the NRC
inspector determined that the cabinets used to store the
permanent instrument calibration records, as defined by
QA-DR 669, do not meet the minimum two hour fire rating requirement.
The above item was discussed with the licensee and the
licensee was informed that this mattter is considered an
unresolved item.
(8124-03)
B.
Unattended Sources
On October 30,1981, at 9:00 a.m. MST, the NRC inspector
determined that two calibration sources had been left
unattended in the turbine building.
During the observation
of SR 5.8. led-Q, Radioactive Gaseous Effluent System Cali-
bration, the NRC inspector accompanied the Health P'ysics
n
and Results Technicians.
During the process of obtaining
the needed calibration sources, one source, number 184,
was not in the source storage room and was later located
on level 6 of the turbine building. The NRC inspector
noted that the Health Physics personnel assigned to the
source was not in the area and that another source, number 92,
had also been left unattended.
Procedure HPP-20 requires
calibration sources not to be left unattended outside their
storage room.
Both source numbers 184 and 92 are CS 137
with activity levels measured December 1,1980, of 8.6 E + 3//Ci
and 7.98 E + 4N Ci, respectively.
Both sources were locked
in their respective shielded containers.
The NRC inspector discussed the above item with the licensee
and informed the licensee that failure to follow procedures
which are Technical Specification requirements is considered
a violation.
(8124-04)
The NRC inspector had no additional questions in this area.
-.
-
_ _ - _
.__
-
.
8
5.
Maintenance (Monthly)
The NRC inspector reviewed records and observed work in progress to
ascertain that the following maintenance activities were being conducted
in accordance with approved procedures, Technical Specifications, and
appropriate Codes and Standards. The following maintenance activities
were reviewed and observed:
CN-1313
Radiation Monitors
CN-1314
Buffer Helium Piping - Loop Split
!
PM 48.1
ACM Diesel Generator Set K-4804 Semi-Annual
Preventive Maintenance
i
PTR 6-59
Remove and Test Snubber BFS-398 E in accordance
with MP 98-1, Repair of Hydraulic Pipe Snubbers
CWP 81-251/CN GSAR 243 Remove V-ll39 and Associated Piping and
Valves from System
CWP 81-250/CN 1427 Isolation of Penetration B-2-3
PTR 10-337
Repair HV 2245 in accordance with EMP 39,
Change Out Rotork Switch Mechanism from Mark l
to Mark 2
.
TCR-811033
Changes to PPS for CN 1427 to comply with
requirements of LCO 4.4.1
,
TCR-81031
Changes for Pressurization Control of Interspace
Pressure for Penetration B-2-3
PTR 10-338/MP-21
Maintenance and Repair of Backup Bearing Water
Pump Suction Filter
PM 91.2
Hydraulic Pump and Motor Inspection
No violations or deviations were identified.
6.
IE Circular
The NRC inspector verified by record review, observation and discussion
with the licensee, the action taken in response to IE Bulletins.
The following Circular was reviewed:
.
81-13 Torque Switch Electrical Bypass Circuit for Safeguard Service
Valve Motors. The licensee has determined that the type of design
used at Fort St. Vrain does not utilize the Torque Switch Bypass.
No violations or deviations were identified.
.
,,-.n,
. , . - ~ - - ,
,,a-,
, , . ,
~,,,,.,,,,,,,,~,,e.
.,-,,,,,-,,..--.,.n..,-,-n
-,.n--
, _ _ ,
n
,,.ww
,
n,-
e
.,.- -
~,e
-
e
.
_ .
-
9
7.
Review of Licensee Event Reports
The NRC 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:
80-52
81-017
81-010
81-043
81-015
81-051
8.
Feport Reviews
The NRC inspector reviewed the following reports for content,
reporting requirements and adequacy:
Monthly Operating Information Report, September 1981
Monthly Operations Reports, September 1981
No violations or deviations were identified.
9.
Unresolved Items
Unresolved items are matters about which more information is required
in order to escertain whether they are acceptable items, violations
or deviations. The unresolved items disclosed in this inspection
are:
8124-03 in paragraph 4.A
8124-05 in paragraph 2, Item 1
8124-06 in paragraph 2, Item 3
10.
Exit Interview
Exit interviews were conducted at the end of various segments of
this inspection with Mr. D. 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. The licensee acknowledged these findings.
,
(
,* .-
-..,w-m-,-,_,,,.-cm.,,,.
.-,.,,,,.,-w,
,,-,-,.,--%-%,,.,r---.y#--,,w-,,,-,
. . . * * *7-v'Fw*fP=*7****-"T--N-"**'9-"Mw
-*w
v
vW- * * * - ' '*"'i9"-"T4"a-wr
w,
-