ML18044A405
| ML18044A405 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| Issue date: | 11/21/1979 |
| From: | Boyd D, Jorgensen B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18044A403 | List: |
| References | |
| 50-255-79-17, NUDOCS 8001100325 | |
| Download: ML18044A405 (6) | |
See also: IR 05000255/1979017
Text
U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-255/79-17
Docket No. 50-255
Licensee:
Consumers Power Company
212 West Michigan Avenue
Jackson, MI
49201
Facility Name:
Palisades Nuclear Generating Plant
Inspection At:
Palisades Site, Covert, MI
License No. DPR-20
Inspection Conducted:
October 1-5, 9-12, 15-19, 25, 26, and 29-31, 1979
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Inspector:AB. L . .forge'Jt.en
. tq,Zftt 4/'AlU~
Approved BylfttD. c.Jrdyd,~Chief
Reactor Projects Section 3
Inspection Summary
Inspection during October, 1979 (Report No. 50-255/79-17)
Areas Inspected:
Routine resident inspection program for October, 1979,
including records; review and audit; maintenance; and refueling prepara-
tions and activities.
The inspection involved 90 onsite inspection
hours.
Results:
Of the four areas examined, no items of noncompliance or devia-
tions were identified in three areas.
Two items of noncompliance
(Infraction-missed required chemistry sampling; and, Deficiency-violated
procedural limit on refueling water level) were identified in the remaining
area.
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1.
DETAILS
Persons Contacted
- J. G. Lewis, General Manager - Palisades
- H. W. Keiser, Plant Superintendent
- H. J. Palmer, Technical Superintendent
- R. E. McCaleb, Quality Assurance Superintendent
- B. L. Schaner, Operations Supervisor
- G. H. R. Petitjean, Technical Engineer
C. Thomas, Mechanical Maintenance Supervisor
J. A. Meineke, Reactor Engineer
D. L. Beach, Electrical Maintenance Supervisor
R. E. Mieras, Shift Supervisor
K. Ridley, PRC Secretary
- Denotes those present at exit interview on November 2, 1979.
The inspector also had discussions with various members of the
operations, maintenance, technical and administrative staffs.
2.
Plant Records
This inspection included an examination of the licensee's system for
development, review and retention of important facility records.
The overall program is defined by and administered in accordance
with Administrative Procedures Sections 10, "Plant Documents" and
11, "Plant Records".
Responsibilities are assigned for compiling,
transmitting and storing records and a matrix has been developed to
control record retention in compliance to various requirements.
Technical Specification 6.10 directly addresses numerous types of
records which must be retained, and provides required retention
times.
For this inspection, the inspector verified the licensee's control
matrix to be consistent to the technical specifications.
The onsite
document storage facility was examined and selected records identi-
fied in the technical specifications were verified present and
proper, as follows:
a.
facility operation records and logs
b.
safety-related maintenance records
c.
reportable occurrence records
d.
records of reactor tests and experiments
e.
records of changes to operating procedures
f.
chlorine treatment records
g.
limited cycle log
h.
Plant Review Committee minutes
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Micro-reproduction and duplicate offsite storage practices were
discussed with document control personnel.
The inspector noted the "Limited Cycle Logbook" has apparently not
been updated since 1977.
Discussions with the licensee indicate the
information centralized in this log remains retrievable from other
protected records, and the licensee agreed to assign an engineer to
update this document on a regular basis.
No items of noncompliance or deviations were identified.
3.
Review and Audit
The activities of the licensee's Plant Review Committee (PRC) during
1979, as documented in routine and special PRC Meeting Minutes, were
reviewed during this inspection.
The controlling primary documents
used in this review were Technical Specification 6.5.1 and Adminis-
trative Procedure Section 3. Compliance to the following items was
specifically examined:
a.
meeting frequency
b.
membership and quorum
c.
items reviewed
(1) potential unreviewed safety questions per 10 CFR 50.59
(2)
technical specification noncompliances
(3)
technical specification proposed changes
(4)
selected procedure changes
(5)
safety-related plant modifications
(6)
reportable events
(7)
selected tests and experiments
No items of noncompliance or deviations were identified.
4.
Maintenance
Selected maintenance activities were reviewed to ascertain they were
conducted in accordance with requirements.
The following specific
activities were examined:
a.
overhaul of boric acid pump, P-56A
b.
vessel head reset
c.
control rod guide rack run-in and hook-up
The examination included direct observation at the jobsite for each
item.
The inspector verified compliance to limiting conditions
for operations with an out-of-service component; obtaining of prior
approval; availability and utilization of procedural controls;
use
of qualified personnel and independent verification when appropri-
ate; and proper development of records on the activity.
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No items of noncompliance or deviations were identified.
5.
Refueling
This inspection included an examination of licensee activities,
procedures and records relating to the reactor refueling performed
during the unit outage which commenced September 8, 1979.
New fuel
receipt, inspection, and storage preparatory to the refy7ling was
examined and documented in previous inspection reports,-
including
review of pertinent procedures.
Licensee examination of recycle and
spent fuel elements for this refueling was minimal, did not include
fuel sipping, and was not specifically examined by the inspector.
a.
Procedures
The following procedures and checklists were reviewed for
content, functional and administrative controls, and proper
implementation:
(1)
CRD0-1 "Disconnecting Control Rods from CRDM' s"
(2)
CRD0-4 "Uncoupling Control Rod from its CRDM When Standard
Procedure CRD0-1 is Not Able to be Used"
(3)
FHS0-1 "Spent Fuel Pool Elevator Periodic Testing"
(4)
FHS0-2 "Refueling Procedure"
(5)
CL AS.14-1 "Refueling Operations Prerequisite Master Check
Sheet"
(6)
CL A5.14-2 "Refueling Operations Shift Check Sheet"
(7)
CL 3.3 "Containment Integrity"
(8)
CL 35 "Neutron Monitors System Check List"
(9)
CL 28-1 "Refueling Communication Check List"
(10) CL 28-2 "Fuel Elevator Check Sheet"
(11) CL 28-3 "Fuel Pool Refueling Machine Check Sheet"
(12) CL 28-4 "Refueling Machine Checklist"
(13) CL 28.5 "Tilt Machine Check Sheet"
(14) CL 28-6 "Refueling Ventilation CP,eck Sheet"
l/
IE Inspection Reports No. 050-255/79-11; No. 050-255/79-13
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(15) Special Test Procedure T-94, "Core Verification"
The procedures were determined to be inclusive of and consistent
with the technical specifications' limiting conditions.
b.
Activities
A number of requirements are in effect only when fuel handling
is in progress.
These items were checked with reference to the
Fuel Handling Log, which documents all the fuel movements.
Two
problems were identified. First, the licensee is required by
Technical Specification 3.8.1.g to check the primary coolant
system boron concentration on each shift when refueling activi-
ties are being carried out in the reactor.
This is to assure
the required shutdown boron concentration is continuously
maintained.
The Fuel Handling Log documents that refueling
activities (fuel handling) were conducted on the "A" shift on
October 2, 1979.
No boron sample results for this shift were
documented on CL AS.14-2, however, and discussions with plant
chemistry personnel established a boron sampel had not been
collected and analysed for that shift. Failure to perform the
required sampling and analysis is an item of noncompliance with
the referenced Technical Specification and is an Infraction.
The second problem relates to procedural controls stated in
CLA5.14-2, which is part of FHS0-2, "Refueling Procedure." The
check list states the minimum reactor cavity and spent fuel
pool water level for fuel handling to be one foot below the
surface skimmers.
The Fuel Handling Log documents fuel handling
on the "A" shifts of October 11 and 12, 1979, while the checklist
shows water level to have been 1.5 and 2 feet, respectively,
below the surface skimmers during those shifts.
In that implemen-
tation of procedures governing refueling operations is a require-
ment of Technical Specification 6.8.1.b, handling fuel with the
water level lower than permitted by procedures is an item of
noncompliance.
This item is a deficiency.
c.
Direct Inspection
The inspector directly observed fuel handling activities in the
reactor cavity and in the spent fuel pool on October 4 and 10,
1979. The following items were checked:
(1)
refueling machine operation and indexing
(2)
refueling area ventilation
(3)
radiation and criticality monitoring
(4)
communications
(5)
fuel accountability
(6)
housekeeping
(7)
cavity and pool water level
(8)
presence and utilization of procedures
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l
Control room activities were also witnessed on several shifts,
the inspector verifying compliance with staffing requirements
for the refueling shutdown condition.
No other items of noncompliance or deviations were identified.
6.
Management Interview
A management interview, attended as indicated in Paragraph 1, was
conducted on November 2, 1979.
The inspector summarized the scope
and findings of the inspection, specifically stating the two identi-
fied items of noncompliance.
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