ML20030C005
| ML20030C005 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/11/1981 |
| From: | Boyd D, Parker M, Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20030B997 | List: |
| References | |
| 50-155-81-08, 50-155-81-8, NUDOCS 8108250303 | |
| Download: ML20030C005 (7) | |
See also: IR 05000155/1981008
Text
,
U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-155/81-08
Docket No. 50-155
License No. DPR A
Licensee:
Consumers Power Company
212 West Michigan Avenue
Jackson, MI
49201
Facility Name:
Big Rock Point Nuclear Plant
Inspection At.
Charlevoix, MI
Inspection Conducted: June 13 - July 10, 1981
h
Inspectors:
G. C. Wright
8 ~ /M8/
f
f
M. E. Parker
8~//~ 8/
Approved By:
D. C. Boyd, Chief,
6 -//- 8/
Projects Section ll.
Inspection Summarv
inspection on June 13-July 10, 1981 (Report No. 50-155/81-08)
Areas Inspected: Routine safety, resident inspector inspection involving:
operational safety verification; surveillance observation; maintenance
observation; followup on LER's, IE Bulletins and IE Circulars; independent
inspection effort; and onsite meeting between NRR and the licensee.
The
inspection involved a total of 195 inspector-hours onsite by two NRC
inspectors including 33 inspector-hours onsite during off-shifts.
Results: Of the areas inspected, one item of noncompliance was identified,
failure to post rr.diation areas (Paragraph 9).
l
l
~
8108250303 810812
PDR ADOCK 0S000155
G
I
i
l
_.
.
- - . - .
.
- - - - -
_
_
.
_-
_ - - _ _
.
1
'
J
DETAILS
J
1.
Persons Contacted
- C. J. Hartman, Plant Supern cendent
- C. R. Abel, Operations and Maintenance Superintendent
C. E. Axtell, Health Physicist
- A. C. Se.ener, Operations Supervisor
D. E. DeMoor, Technical Engineer
L. F. Monshor, Reactor Engineer
- M. G. Dickson, General Health Physics
i
-
G. L. Fox, C & R P Supervisor
-
T. R. Fisher, Quality Assurance
!
- E. Raciborcki, Quality Assurance Supervisor
j
The inspectors alsa contacted other licensee personnel includiag shift
i
supervisors, control room operators, maintenance personnel and C&RP
1
Technicians.
- Denotes those present at the exit interview.
2.
Operational Safety Verification
,
The inspector observed control room operations, reviewed applicable
logs and conducted discussions with control room operators during the
month of June. The inspector verified the operability of selected
emergency systems, reviewed tagout records and verified proper
return to service of affected components. Tours of the reactor
buildings and turbine buildings were conducted to observe plant
equipment conditions, including potential fire hazards, fluid leaks,
and excessive vibrations and to verify that maintenance requests had
been initiated for equipment in need of maintenance. The inspector
by observation and direct interview verified that the physical
security plan was being implemented in accordance with the station
security plan.
The inspector observed plant housekeeping / cleanliness conditions and
verified implementation of radiation protection controls. During the
month of June, the inspector walked down the accessible portions of
the Core Spray and Post Incident systems to verify operability. The
inspector also witnessed portions of the radioactive waste system
i
controls associated with radwaste shipments and barreling.
!
These reviews and observations were conducted to ierify that facility
operations were in conformance with the requirements established under
1
technical specifications,10 CFR, and administrative procedures.
No apparent items of noncompliance or deviations were identified.
-2-
n
3.
Monthly Maintenance Observation
Station maintenance activities of safety related systems and com-
ponents listed below were observed / reviewed to ascertain that they
were conducted in accordance with approved procedures, regulatory
guides and industry codes or standards and in conformance with
technical specifications.
The following items were considered during this review:
the limiting
conditions ior operation were met while components or systems were
removed from service; approvals were obtained prior to initiating
tha work; activities were accomplished using approved procedures and
were inspected as applicable; functional testing and/or calibrations
were performed prior to returning components or systems to service;
quality control records were maintained; activities were accomplished
by qualified personnel; parts and materials used were properly
certified; radiological controls were implemented; and, fire pre-
vention controls were implemented.
Work requests were reviewed to determine status of outstanding jobs
and to assure that priority is assigned to safety related equipment
maintenance which may affect system performance.
The following maintenance activities were observeo/ reviewed:
1.
Repair of Control Rod Drive Hydraulic Unit Accumulatot.
2.
Repair of Containment Ventilation Isolation Valve.
Following completion of maintenance on the Control Rod Drive and
Containment Isolation systems, the inspector verified that these
systems had been returned to service properly.
No apparent items of noncompliance were identified.
4.
Monthly Surveillance Observation
The inspector observed technical specifications required surveil-
lance testing on the Control Rod Drive System, Neutron Monitoring
System and the Diesel Fire Pump and verified that testing was per-
formed in accordance with adequate procedures, that test instru-
mentation was calibrated, that limiting conditions for operation
were met, that removal and restoration of the affected components
were accomplished, that test results conformed with technical
specifications and procedure requirements and were reviewed by
personnel other than tLe individual directing the test, and that any
deficiencies identified during the testing were properly reviewed
and resolved by appropriate management personnel.
No apparent items of noncompliance were identified.
-3-
_ _.
-
_
- - . .
5.
Licensee Event Reports Followup
1
i
Through direct observations, discussionr. with licensee personnel,
and review of records, the following event reports were reviewed to
,
I
determine that reportability requirements were fulfilled, immediate
corrective action was accomplished, and corrective action to prevent
recurrence had been accomplished in accordance with technical specifi-
cations.
LER 80-23 (closed): Reanalysis of containment atmosphere temperature
and pressure for Steam Line Break (SLB).
LER 80-30 (closed): Component leakage on CV 4027 in excess of
.
80-30 (update)
Technical Specification limits.
-
LER 80-33 (closed): Reactor cleanup pump leakage.
l
TIR 80-38 (closed): Feedwater check valve VFW-304 excessive
leakage during Type C leak rate test.
LER 80-40 (closed): Diesel fire pump failure to meet starting time.
!
LER 80-41 (closed): Reactor cleanup resin sluice valves CU-4092 and
4093 excessive leakage during local leak rate test.
j
,
LER 80-43 (closed): Crack like indication in reactor cleanup system
j
sample line.
LER 80-48 (closed): Q'iestionable environmental qualification on cable
splices and terminal blocks.
LER 80-49 (closed): Nonconservative drif t of containment level
transmitter corresponding to elevation 590'.
LER 81-01 (closed): Low specific gravity on RDS Channel D battery
cell 56.
LER 81-03 (closed): Containment vacuum relief valve backup nitrogen
bottle failure.
LER 81-04 (closed): Leak in chemical waste receiver tank discharge line.
LER 81-05 (closed): Emergency diesel generator failure to start in
required time.
LER 81-06 (closed): One vacuum relief loop out of service.
LER 81-07 (closed): Emergency diesel generator failed to start in
i;
required time.
LER 81-08 (closed): Emergency diesel generator failed to start in
required time.
-4-
.
I.ER 81-09 (closed): Reactor level sensing chamber temperature above
250' F.
LER 81-10 (closed): Containment isolation valve CV-4094 failed to
close in required time.
LER 80-01 update:
Emergency condenser loop 2 outlet valve M0-7053
(closed)
leaking.
LER 80-04 update:
Broken air line penetrating containment.
(closed)
LER 80-34 update:
Main steam isolation valve failed to close.
(closed)
LER 80-44 update:
Emergency diesel generator output voltage
(closed)
regulator failure.
No apparent items of noncompliance were identified.
6.
IE Bulletin Followup
For the IE Bulletins listed below the inspector verified that the
written response was within the time period stated in the bulletin,
that the written response included the information required to be
reported, that the written response included adequate corrective
action commitments based on information present in the bulletin and
the licensee's response, that licensee management forwarded copies
of the written response to the appropriate onsite management repre-
sentatives, that information discussed in the licensee's written
response was accurate, and that corrective action taken by the
licensee was as described in the written response.
IEB 80-06 update (closed): Engineered Safety Feature (ESF) Reset
Controls.
IEB 81-02 (closed): Failure of Gate Type Valves to Close Against
Differential Pressure.
IEB 81-03 (closed): Flow Blockage of Cooling Water to Safety System
Components by Corbicula SP. (Asiatic Clam) and
'
Mytilus SP. (Mussel).
No apparent items of noncompliance were identified.
7.
IE Circular Followup
For the IE Circulars listed below, the inspector verified that the
l
Circular was received by the licensee management, that a review for
applicability was performed, and that if the circular were applic-
j
'
able to the facility, appropriate corrective actions i.ere taken or
were scheduled to be taken.
t
!
-5-
1
IEC 80-15 (closed):
Loss of Reactor Coolant Pump Cooling and
Natural Circulation Cooldown.
IEC 81-01 (closed): Design Problems Involving Indicating Push-
button Switches Manufactured by Honeywell
Inco rporated.
IEC 81-02 (closed): Performance of NRC Licensed Individuals while
on Duty.
IEC 81-03 (closed):
Inoptrable Seismic Monitoring Instrumentation.
IEC 81-04 (closed): The Role of Shift Technical Advisors and
Importance of Reporting Operational Events.
IEC 81-06 (closed): Potential Deficiency Affecting Certain Foxboro 10
to 50 Mil 11 ampere Transmitters.
No apparent items of noncompliance were identified.
8.
Special Meeting on Seismic Qualifications
The inspectors attend 6d a meeting on June 30, 1981 between the
licensee and the following persons from the NRC:
W. A. Paulson
(NRR), T. M. Cheng (NRR), W. T. Russell (NRR) and W. J. Hall (NRC
Consultant).
The meeting was held to discuss and walk down selected systems from
a seismic qualifications standpoint.
9.
Independent Inspection Effort
During a routine tour of plant accessible areas conducted on June 19,
1981, the following items were observed by the inspettor:
A yellow waste drum and bagged hoses on a cart adjacent to the tool
storage warehouse, located within protected area fence. The above
items were unattended and not posted at the time. The inspector's
survey instrument indicated a radiation dose rate in excess of 40
mr/hr on contact. The inspector requested the licensee's radiation
protection personnel to perform a survey and to remove the items from
the area or to provide adequate posting. Subsequent survey performed
l
by radiation protection indicated a dose rate on contact of 35 mr/hr
and 8 mr/hr at 18" from the drum. Discussions with radiation pro-
>
tection personnel indicated that the drum contained a pump and hoses
that had been used for dewatering the resin disposal cask.
10 CFR 20.203(b) states: "Each radiation area shall be conspicuously
posted with a sign or signs bearing the radiation caution symbol and
words CAUTION RADIATION AREA." A radiation area in this context is
defined as "...any area accessible to personnel in which the radiation
levels are such that a major portion of the body could receive in
any one hour a dose in excess of 5 millirem. . ."
!
I
-6-
i
l
CLJ
. - _ - .
.-
-.
-
_ _ _ _ _ . .
_ _ -
Contrary to the above, the radiation area immediately adjacent to
the waste drum and hoses was not posted as a radiation area.
The licensee's immediate corrective action was to remove the waste
I
drum containing the dewatering pump and hoses from the area and
place them in the tool storage warehouse.
10.
Unresolved Items
On June 19, 1981, during a plant tour, the inspector observed the
waste drum storage trailer was not posted with radiation zone signs
nor was it zoned off by barricades or ropes. Radiation readings
taken by the inspector and later confirmed by licensee readings,
indicated a dose rate of 17 MR/HR on contact with the wall of the
trailer and 11 MR/HR at a distance of 18 inches from the wall of the
'
trailer. The immediate action taken by the licensee was to install
radiation signs and erect barricades around the trailer.
Later discussion on the above between the resident inspectors, the
licensee, Region III and IE: Headquarters, indicates a need for the
clarification of the intent of 10 CFR 20.204 and 10 CFR 20.203(b).
One interpretation is that since the contents of the waste drum
,
)
storage trailer was material that was packaged for shipment in
accordance with Department of Transportation (D.O.T.) requirements
that D.O.T. posting requirements were also in effect,
i.e.,
in this
case no posting or barricades were required. The other interpretation
is that D.O.T. requirements only apply when the packages to be
shipped are loaded for shipment offsite.
Clarification in this
matter has been requested from IE: Headquarters.
11.
Exit Interview
The inspectors met with the individuals denoted in Paragraph 1 at
the conclusion of the inspection and summarized the scope and findings
>
)
of the inspection. The licensee acknowledged the inspectors comments.
i
l
l
,
!
,
-7-
n