ML18046A832
| ML18046A832 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/16/1981 |
| From: | Boyd D, James Heller, Jorgensen B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18046A830 | List: |
| References | |
| 50-255-81-10, NUDOCS 8108030258 | |
| Download: ML18046A832 (9) | |
See also: IR 05000255/1981010
Text
U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-255/81-10
Docket No. 50-255
Licensee:
Consumers Power Company
212 West Michigan Avenue
Jackson, MI
49201
Facility Name:
Palisades Nuclear Generating Plant
Inspection At:
Covert, MI
License No. DPR-20
Inspection Conducted:
June 1-6, 8-13, 15-20 and June 22 - July 3, 1981
Inspectors: r
~/#~~
B. L. Jorgensen
- ~~
/b"- J. K. Heller""'j
D.C.B~1
7-/t;;.--81
7-16-81
Approved By:
7- /~ - rt"/
Reactor Projects Section lA
Inspection Summary
Inspection during June, 1981 (Report No. 50-255/81-10)
Areas Inspected:
Augmented resident inspection program including:
operational safety; maintenance; surveillance; reportable events;
followup on IE Circulars and previous noncompliance; final review on
spent fuel rack replacement; and miscellaneous plant activity review.
The inspection involved 226 inspection-hours onsite by two NRC in-
spectors, including 93 off-shift inspection hours.
Results:
Of the eight areas examined, no items of noncompliance or
deviations were identified in seven areas.
One noncompliance (Severity
Category V - failure to follow procedures as required) was identified in
the remaining area.
.~ s10803o~'r5801o1I7 --
, PDR ADOCK 05000255
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1.
DETAILS
Persons Contacted
- R. W. Montross, General Manager
J. S. Rang, Operations/Maintenance Superintendent
- H. J. Palmer, Technical Superintendent
G. H. R. Petitjean, Technical Engineer
- J. L. Corley, General Supervisor of Quality Operations
R. E. McCaleb, Quality Assurance Administrator
- D. K. Powers, Shift Technical Advisor
W. P. Mullins, Plant Health Physicist
W. S. Skibitsky, Operations Superintendent
W. E. Adams, Senior Engineer (STA)
G. W. Ford, Senior Engineer (STA)
W. L. Burmeister, Shift Technical Advisor
A. F. Brookhouse, Shift Supervisor
S. Ghidotti, Shift Supervisor
A. S. Kanicki, Shift Supervisor
D. W. Kaupa, Shift Supervisor
R. E. Mieras, Shift Supervisor
E. I. Thompson, Shift Supervisor
C. H. Gilmor, Maintenance Superintendent
S. F. Pierce, Radioactive Materials Control Supervisor
W. M. Hodge, Property Protection Superintendent
K. M. Farr, Public Affairs Director
W. E. Adams, Senior Engineer (STA)
W. P. Mullins, Plant Health Physicist
R. L. Muzzi, Associate Engineer
- Denotes those present at Management Interview on July 3, 1981.
Numerous other members of the plant Operations/Maintenance, Technical,
and Chemistry/Health Physics staff were also contacted briefly.
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, 1981.
The inspector verified the operability of
selected emergency systems, reviewed tagout records and verified
proper return to service of affected components.
Tours of auxiliary
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 .
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The inspector observed plant housekeeping/cleanliness conditions and
verified implementation of radiation protection controls.
During
the month of June, 1981, the inspector walked down the accessible
portions of the iodine removal and diesel generator systems to
verify operability.
During walkdown of the iodine removal system
using Iodine Removal Instrumentation checklist 3.7, the Resident
Inspector found three valves closed which the checklist stipulates
to be in the open position.
Discussion with the Shift Supervisor
established the valves are properly positioned per the alarm response
procedure for high nitrogen pressure to system tanks T-103 and T-102.
The valves are required to be shut until plant conditions permit
repairs to the nitrogen pressure control valves for these tanks.
While cross checking checklist 3.7 against drawing M-204, the in-
spector observed that the print listed valve 3357 ESS twice, once as
N2 to T-102 and once as T-102 drain.
This item was brought to the
aEtention of the appropriate supervisor.
The inspector also witnessed portions of the radioactive waste system
controls associated with radwaste shipments and barreling.
A radwaste
truck awaiting shipment was independently surveyed on June 23, 1981.
This inspection included review of licensee actions under the
provisions of an NRC Generic Order dated April 20, 1981.
The
purpose of this order is to ensure the low probability of High
Pressure Safety Injection (HPSI) and Low Pressure Safety Injection
(LPSI) check valve failures which could result in an inter system
loss of coolant accident.
Until the plant is modified to permit
testing of the HPSI and LPSI checkvalves, the licensee has taken the
following actions to comply with the order requirements.
a.
The HPSI and LPSI Motor Operator Valves (MOV) are closed.
b.
The MOV's are tagged shut and the operators have been given
instructions regarding not opening the MOV's.
c.
The plant procedures which require MOV cycling have been held
in abeyance until check valve testing has been satisfactorily
accomplished.
The Resident Inspector has verified that the above actions have
been performed and that closure of the HPSI and LPSI check valves
does not constitute an unreviewed safety question.
These reviews and observations were conducted to verify that facility
operations were in conformance with the requirements established under
technical specifications, 10 CFR, and administrative procedures.
No items of noncompliance or deviations were identified.
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3.
Monthly Maintenance Observation
4.
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 for operation were met while components or systems were
removed from service; approvals were obtained prior to initiating
the 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 certi-
fied; radiological controls were implemented; and, fire prevention
controls were implemented.
The following activities were examined:
a.
81-EPS-042 and -043: preventive maintenance activities on
emergency diesel-generators
b.
81-EPS-039: overhaul of emergency diesel air-start motor
c.
81-ESS-067:
replacement of a "snubber" (hydraulic shock
suppressor) found with low fluid level
d.
81-ESS-076:
electronic adjustments to safety injection ac-
cumulator level instrumentation.
The written record on this
item is unclear both as to identification of the problem and
description of corrective action.
Personnel interviews were
successful in gaining accurate information, but this may not
have been possible were the activity not a recent one.
This
was discussed at the Management Interview.
e.
81-RPS-006:
repeat of surveillance test MI-2 to verify absence
of instrument "drift" observed in testing of RPS trip units.
No items of noncompliance or deviations were identified.
Monthly Surveillance Observation
The inspector observed technical specifications required surveillance
testing on the systems/components identified below, and verified that
testing was performed in accordance with adequate procedures, that
test instrumentation 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 the individual directing the test, and that
any deficiencies identified during the testing were properly reviewed
and resolved by appropriate management personnel.
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The inspector
a.
S0-04
b.
MC-11
c.
R0-13
d.
FT-2
e.
M0-29
witnessed portions of the following test activities:
Pressure Test of Containment Entrance/Exit Hatch
Safeguard Boron Samples (SI Bottles Only)
Test of the Normal Shutdown Sequencers.
Problems
occurred in conduct of R0-13 with both shutdown
sequencers.
The inspector followed licensee immediate
actions and will review corrective actions for a re-
sulting Event Report during a future inspection.
Containment Building Post-Tensioning System
Engineered Safety System Alignment
Completed data for several tests performed in May 1981 were reviewed.
Review of M0-23 "Inservice Test Procedure (Low Pressure Safety In-
jection Pumps)" revealed the following discrepancies:
a.
Temporary Change 81-291 requires attachment of a recent cali-
bration sheet for internal calibration of PT-504 Data Logger.
This sheet was not attached.
b.
Paragraph 5.3.3 and 5.4.3 require the serial number and cali-
bration due date of a pressure test gauge be recorded.
This
was not performed.
c.
Paragraph 5.4.3 requires recording the time the low pressure
safety injection pump was stopped.
This was not performed.
d.
Paragraph 7.4 requires attachment of a calibration sheet for
the pressure test gauge.
This was not performed.
e.
Paragraph 5.3.5 requires a second person verify that valve
MV;...3202, "Discharge to the "B" Low Pressure Injection Pump"
is
locked and so signify by signature.
This was not performed.
Prior to review by this inspector, M0-23 had gone through four
levels of review and the items listed above had not been identified
by t~e licensee17s dis~repancies.
~s shown above and stated in a ..
previous report-
the inspector believes the plant lacks an effective
procedure.review process.
This concern was !fiscussed with plant
management on June 5, 1981, and at the Management interview.
Imple-
mentation of procedures for surveillance and testing of safety-related
equipment is a requirement of Technical Specification 6.8.1.c. The
examples above of failure to implement several requirements of
procedure M0-23 thus constitute an item of noncompliance against the
referenced Specification.
No other noncompliance and no deviations were identified.
lf
IE Inspection Report No. 50-255/81-06
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-*
5 .
Licensee Event Reports Followup
Through direct observations, discussions with licensee personnel,
and review of records, the following event reports were reviewed to
determine that reportability requirements were fulfilled, immediate
corrective action was accomplished, and corrective action to prevent
recurrence had been accomplished in accordance with technical speci-
fications.
a.
(Closed) LER 81-13 and LER 81-15 "Low Safety Injection Tank
Boron Concentration." During sampling of the safety injection
tanks (SIT) on March 17, 1981 and April 14, 1981, the boron
concentration of SIT-82B was found below the requirements of
Technical Specification 3.3.1.
Boron concentration was restored
to the T.S. limit within the time allowed.
Dilution of the
boron concentration is believed caused by slow inleakage of
primary coolant system water.
Repairs to the valves in the
leakage path will be made during the refueling outage.
Interim
corrective action is to increase the sampling frequency to
twice monthly and any time the SIT water is lowered, as level
is also being affected by the inleakage.
Graphs have been
prepared for the operators to correlate concentration and
level, as an aid to making any necessary adjustments within the
time limits of the license.
Primary system inventory loss by
this leakage is included in the determination of "unidentified"
leakage, which has remained well within specification limits.
b.
(Closed) LER-81-012 "Safety Injection Tank Low Level." During
sampling of SIT 82B on March 31, 1981, the low level alarm for
SIT 82A
alarmed, resulting in two SIT(s) with low level.
c.
Level was restored to the tanks within the time limits of the
Technical Specification.
Leakage through the control valve for
SIT-82A caused the inadvertent level decrease.
Repairs to the
control valve will be made during the next refueling outage.
(Closed) LER-81-01 "Inoperable Station
Inspection Report No. 50-255/80-24 for
item and the associated noncompliance.
dated March 10, 1981 for the corrective
Batteries." See IE
a description of this
See Confirmatory Order
action.
No items of noncompliance or deviations were identified.
6.
IE Circular Followup
For the IE Circulars listed below, the inspector verified that the
Circular was received by the licensee management, that a review for
applicability was performed, and that if the circular were applicable
to the facility, appropriate corrective actions were taken or were
scheduled to be taken .
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7.
a.
(Closed) IE Circular 79-05, "Moisture Leakage In Stranded Wire
Conductors."
b.
(Closed) IE Circular 80-17, "Fuel Pin Damage to Water Jet From
Baffle Plate Corner."
t.
(Closed) IE Circular 80-18, "Safety Evaluation for Changes to
Radioactive Waste Treatment Systems."
d.
(NJ A) IE Circular 80-20, "Changes in Safe-Slab Tank Dimensions."
e.
(Closed) IE Circular 81-02, "Performance of NRG-Licensed In-
dividuals While on Duty."
f.
(Closed) IE Circular 81-03, "Inoperable Seismic Monitoring
Instrumentation."
g.
(Closed) IE Circular 81-05, "Self-Aligning Rod End Bushings for
Pipe Supports."
No items of noncompliance or deviations were identified.
Followup on Previously Identified Items
(Closed)
Noncompliance item 2, IE Inspection Report No. 50-255/81-06:
Improper storage of flammable liquid.
The licensee 1 s actions as
stated in his letter dated June 15, 1981, were verified and considered
appropriate.
No items of noncompliance or deviations were identified.
8.
Spent Fuel Pool Modifications
This inspection included final review of quality documentation
relating to removal of the original spent fuel storage racks and
replacement with new, high density racks to increase2
7~71 pool
storage capacity.
Previous reviews and observations- -
had covered
much of this activity.
While minor corrective action or unresolved
items remain open, none affect current acceptability and use of
the new racks.
No items of noncompliance or deviations were identified.
9.
Review of Plant Activities
2/
}_J
During the months of January thru June, 1981 the inspector
reviewed the following activities:
IE Inspection Report No. 50-255/79-05
IE Inspection Report No. 50-255/81-06
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a.
Review and Audits
On April 22 and June 4, 1981, the inspector sat in on offsite
and onsite safety review committee meetings.
The inspector
verified that provisions of technical specifications dealing
with membership, review process, frequency, and qualifications
were met.
The inspector also verified that decisions made were
reflected in the meeting minutes and that corrective actions
proposed were taken.
b.
Training
The inspector attended one of the licensee's operator quali-
fication lecture series and verified that lesson plan objectives
were met and that training was in accordance with the approved
operator qualification program schedule and objectives.
c.
Environmental Protection
On April 9, 1981, the inspector verified the installation and
operability of five sampling/monitoring stations and associated
equipment and reviewed records for completeness and accuracy.
d.
Security
On March 10, 1981, the inspector observed weapons training and
qualification for newly-hired security officers.
e.
Licensee Action Concerning Identified Problems
The inspector reviewed corrective actions taken by the licensee
pertaining to recurring failures and resolution of identified
discrepencies involving safety-related components.
Approximately
thirty Deviation Reports covering about a two month period in
late 1980 were examined.
No trends or recurring failures were
identified.
Licensee followup on discrepancies related to
safety equipment was considered proper.
The inspector noted both the frequency of documented corrective
actions required and the fraction of items caused by personnel
errors and procedure violations seem to be decreasing.
No items of noncompliance or deviations were identified.
10.
Management Interview
A management interview (attended as indicated in Paragraph 1) was
conducted following completion of the inspection on July 3, 1981.
The following items were discussed, with licensee response as in-
dicated.
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. J.
a.
The inspectors described the scope and areas of inspection.
b.
Inspector verification of actions on the April 20, 1981 Generic
Order was discussed. (Paragraph 2)
c.
A potential problem with accurate documentation of maintenance
activities was noted (Paragraph 3.d).
The licensee pointed out
an accurate determination and description of needed repairs
cannot always be made prior ,to commencement of work, when the
documentation is initially prepared.
d.
The apparent noncompliance was specifically identified and
discussed (Paragraph 4), the emphasis being on a proper review
by the licensee to assure important activities are correctly
done.
The licensee agreed the review process had not been
functioning as needed and indicated improvements had been under
consideration and were, in fact, being implemented beginning
early in June, 1981.
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