ML18043A647
| ML18043A647 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/06/1979 |
| From: | Jorgenson B, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18043A645 | List: |
| References | |
| 50-255-79-04, 50-255-79-4, NUDOCS 7905080093 | |
| Download: ML18043A647 (5) | |
See also: IR 05000255/1979004
Text
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Re~ort No. 50-255/79-04
Docket No. 50-255
Licensee:
Consumers Power Company
2i2 West Michigan Avenue
~ackson, MI
49201
Facility Name:
Palisades Nuclear Generating Plant
Inspection At:
Palisades Site, Covert, MI
Inspection Conducted:
February 20-23, 1979
Inspector:
~o'jfn~
RFW~
Approved By:
R. F. Warnick, Chief
Reactor Projects Section 2
Inspection Summary
License No. DPR-20
Inspection on February 20-23, 1979 (Report No. 50-255/79-04)
Areas Inspected:
Routine, unannounced inspection of plant operations,
QA program annual review, reportable events, and action on previously
identified items.
The inspection involved 26 inspection hours onsite
by one NRC inspector.
Results:
Of the four areas inspected, no items of noncompliance were
identified in three areas.
One item of noncompliance (Infraction -
failure to implement procedures - Paragraph 3) was identified in one
area *
790508 ooct 3
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DETAILS
1.
Persons Contacted
- J.
- H.
K.
- R.
B.
T.
s.
F.
w.
- G.
Lewis, Plant Superintendent
Keiser, Operations and Maintenance Superintendent
Berry, Technical Superintendent
McCaleb, Quality Assurance Superintendent
Shaner~* Operations Supervisor
Kanicki, Shift Supervisor
Ghidotti, Shift Supervisor.
Butler, Instrument .and Control Engineer
Staley, Instrument and Control Supervisor
Petitjean, Technical Engineer
- Denotes those present at management interview on February 23, 1979.
The inspector also interviewed several licensed reactor operators on
shift duty.
2.
Licensee Actions on Previous Inspection Findings
(Closed) Noncompliance Item (50-255/78-26):
Training records
inadequate to show completion of required training.
The inspector
reviewed licensee corrective action as stated in his letter of
December 19, 1978.
The review included an examination of proce-
dure revisions and implementation schedules, and discussions with
licensee personnel.
(Closed) Open Item (50-255/77-14):
Calibration program for safety-
related instrumentation for which calibration frequencies are not
specified in technical specifications.
The licensee has identified
the referenced instrumentation, established calibration frequencies,
and is implementing the program.
(Closed) Open Item (50-255/78-27):
Operability of boric acid heat
tracing system.
The licensee has completed identification and
repair of all circuit "legs" on safety-related flow paths except
for one redundant "leg" on the boric acid gravity feed line, which
can be repaired only during a unit outage.
Weekly current checks
are continuing, with no newly failed circuits being identified.
With this program in effect, the inspector has no further questions
concerning whether or not required temperatures can be maintained
in safety-related flow paths *
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3.
Reportable Events
4.
The inspector reviewed the circumstances surrounding LER 79-05,
relating to emergency diesel-generator (EDG) inoperability.
The
1-1 EDG was considered inoperable on J.anuary 3, 1979 after a drain
valve in the fuel system broke during routine testing of the diesel
and the unit was sprayed with fuel oil.
The failed drain valve was
a recent installation, having been 'installed in place of a drain
plug on the diesel fuel oil filter on November 28, 1978, during a
maintenance activity.
L.icensee Administrative Procedures provide for control of minor
field changes during maintenance, stipulating use of the Speci-
fication/Field Change Form (SFC) to provide documentation, assure
appropriate review, and obtain prior approval.
In this case,
however, no SFC form was_ initiated and the required reviews and
approvals were not obtained.
In that Technical Specification 6.8.1 requires implementation of the Administrative Procedures
noted above, failure to initiate the SFC and to review and approve
the modification is considered an item of noncompliance with
Technical Specification 6.8.1.
The EDG 1-1 was inspected to verify it had been returned to the
original condition and was operable.
Inspection of EDG 1-2
verified this modification had not been made on that unit.
The
licensee is examining the lube oil and fuel oil systems on both
diesels to ascertain whether other system changes of the type
discussed above have occurred.
This review and other licensee
actions underway to disposition LER 79-05 will be examined during
a future inspection.
Facility Operations
The inspector reviewed operations records and activities to verify
compliance with licensee requirements.
a.
Shift Supervisor's Log:
January and February, 1979.
b.
Secondary Plant Log:
December, 1978 and January, 1979.
c.
Reactor Log:
December, 1978 and January, 1979.
d.
Jumper/Bypass Log and Caution Tag Record.
e.
Bypass Control Checklists.
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5.
The Caution Tag Record was cross-checked against placement of sets
of Caution Tags in a dozen examples and found accurate in each case.
The Bypass Control Checklists were reviewed to ascertain corrective l/
action on questionable items identified during a previous inspection.-
The number of "open" Checklists has been reduced considerably, with
those remaining appearing accurate.
Operating staff cognizance of
bypass st.atus was considered good.
The inspector noted the operating
shift supervisors are performing scheduled routine reviews of caution*
tagging and plant jumper and bypass controls, as well as initialing
Bypass Control Checklists before bypass installation.
Finally, the
~-:ecord showed no temporary bypasses installed in safety-related
systems.
-
The inspector also observed shift manning, routine operations, and
shift turnover.
No items of noncompliance or deviations were identified.
Quality Assurance Program Review
This inspection included an examination of and discussions relating
to lic.ensee implementation of changes made to the Quality Assurance
Program (Consumers Power Company Topical Report CPC-1-A) during 1978.
Changes to QA Program Procedures were reviewed by the inspector as
they were made, to verify consistency with the QA Program.
These
changes were primarily editorial or organizational in nature.
No
problem areas were identified in this review.
Revision 7 to the Quality Assurance Program was accepted by the NRC
on December 22, 1978.
This revision addresses organizational and
programmatic changes which have little effect on day-to-day oper-
ation of the QA program at the Palisades Plant.
Discussions verified
mechanisms exist to keep plant personnel aware of, and in some cases,
involved in program changes.
Mechanisms are also in place to revise
implementing procedures as required to accomodate QA Program changes
and to provide review of other procedure revisions to assure con-
sistency with QA Program requirements.
The licensee's program for certification of QA auditors and lead
auditors was also reviewed durin~/§?is inspection, in followup
to previous inspection findings.--
This function is controlled
in accordance with Quality Assurance Department (Production and
Transmission) Procedure No. XVIII-4 "Certification of Quality
1/
IE Inspection Report No. 050-255/78-17.
2/
IE Inspection Report No. 050-255/75-19.
3!
IE Inspection Report No. 050-255/77-14.
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Assurance Audit Personnel," dated February 8, 1978.
Based on review
of this procedure and discussion of its implementation with the
licensee, this item is considered closed.
No items of noncompliance or deviations were identified.
6. .
Management Interview
A management interview, attended by licensee personnel noted in
Paragraph 1, was conducted at the conclusion of the inspection on
February 23, 1979.
The inspector summarized the scope and findi~gs
of the inspection, specifically identifying the apparent item of
noncompliance.
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