ML19263B004
| ML19263B004 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/15/1978 |
| From: | Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19263A995 | List: |
| References | |
| 50-348-78-29, NUDOCS 7901040034 | |
| Download: ML19263B004 (5) | |
See also: IR 05000348/1978029
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Report No.
50-348/78-29
Docket No.
50-348
License No.
Licensee:
Alabama Power Company
Post Office Box 2631
Birmingham, Alabama 35291
Facility Name
Farley l' nit-1
Inspection at:
Farley Site, Ashford, Alabama
Inspection Conducted:
October 17-20, 1978
Inspector:
A. K. Hardin
Accompanying Personnel:
None
Approved by:
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R . C . Lew i's , C h i e f
Date
Reactor Projects Section No. 2
Reactor Operations and Nuclear Support
Branch
Inspection Summary
Inspectson on October 17-20
1978 (Report No. 50-348/78-29):
2
Areas Inspected:
Routine , unannounced inspe ction of licensee event
reports, IE Bulletins and circulars, review and audits, and inspector
identified items.
The inspection involved 26 man-hours on-site by one
NRC inspector.
kysuIts:
Of the four areas inspected, no items of noncompliance or
deviations were identified.
790104003f
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RII Rpt. No. 50-348/78-29
-1-
DETAILS I
Prepared by: h
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A. K. Kardin, Reactor Inspector
Date
Reactor Projects Section No. 2
Reactor Operations and Nuclear
Support Branch
Dates of Inspection: October 17-20, 1978
Reviewed by.
86
/h.[5 /[
R. C. Lewis, Chief
Date
Reactor Projects Section No. 2
Reactor Operations and Nuclear
Support Branch
1.
Persons Contacted
- W.
G. Hairston, Plant Manager
kJ. D. Woodard, Assistant Plant Manager
- D. N. Morey, Maintenance Supervisor
23. R. Campbell, Manager, Operations Qaality Assurance
- D. L. Cox, Operations Quality Assurance
- J. W. Kale, Operations Quality Assurance
- F. Wurster, Operations Quality Assurance
T. C. Grozan, Plant Engineer
D. C. Poole, Operations Superintendent
L. W. Enfinger, Document Control Supervisor
D. E. Mansfield, Startup Superintendent
L. E. Ward, Startup Supervisor
- Denotes those present at the Exit Interview.
2.
Licensee Action on Previous Inspection Findings
Not applicable.
3.
Unresolved Items
None were identified during this inspection.
4.
Exst Interview
An exit laterview was held at the conclusion of the inspection on
October 20, 1978, with Mr. W. G. Hairston and other members of
Alabama Power Company as identified by an asterisk in paragraph I.
The scope and findings of the inspection were discussed.
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.
,
RII Rpt. No. 50-348/78-29
-2-
5.
Review and Audits
Selected minutes for both the on-site safety review committee and
the off-site safety review committee were reviewed to ascertain
that meetings had been held at the required frequency, that a
quorum was present, and that appropriate items as specified in the
technical specification were being reviewed.
The records reflect that + ring a 12-month period (from October 28,
1977 to November 1, 1978), more than eighty meetings of the Plant
Operations Review Committee (PORC) were conveneo.
Attendance at 30
of these meetings was noted.
No areas of noncompliance were identi-
fied in meeting frequency and agenda items for the on-site safety
committee. Selected meeting minutes for the Off-site Safety Committee
(NORB) were reviewed. These included minutes 77-5 through 77-12,
plus the minutes of 78-1 and 2.
No areas were identified where
meeting frequency, quorum requirements, and subjects reviewed were
not met as required by technical specifications.
At the exit
interview, the inspector questioned the timeliness of reviews of
licensee event reports (LER's) by the NORB, and that reports such
as LER 77-24 was listed as being reviewed in NORB minutes 78-1 of
March 15, 1978.
LER No. 77-24 is dated September 28, 1977,
The
licensee stated the scheduled meetings of the NORB were every six
months and that their review of LER's was considered timely on that
basis.
The inspector stated the item would be left open pending an
in-office review of the LER's which had been reviewed by the NORE.
An in-office review was conducted on October 25, 1978. The timell-
ness of review of 30-day licensee event reports by the off-site
NORB Committee was concluded to meet regulatory requirements.
6.
IE Bulletin 78-10 entitled "Bergen-Patterson Hydraulic Shock Suppressor
Accumulator Spring Coils", described a problem with broken spring
coils on early model BP suppressors.
The licensee was directed to
take corrective action if the affected models were installed or in
stock and to describe the condition of the springs.
The licensee
responded on July 17, 1978, that their review confirmed that no
such equipment is used or planned for use at the Farley Nuclear
plant.
On this inspection, the inspector reviewed the document
file on IE Bulletin 78-10.
Records indicate the storekeeper has
reviewed inventory files and has determ.ned there are no snubbers
of the type described in stock.
A letter in the file, from Bechtel
to Southern Company Services, states that there are no Bergen-
Patterson suppressors at Farley.
All suppressors are manufactured
by Grinnell.
The inspector had no further questions.
.
RII Rpt. No. 50-348/78-29
-3-
'
7.
IE Circular 78-09, entitled " arcing of General Electric Company
NEMA Size 2 Contsctors" described a prob.em with binding in the
contactor, resulting in arc-burn damage. The licensee was advised
to determine if the type contactor in question was installed or if
there are some in spare parts at their plant action in which case
appropriate corrective action would have to be taken.
The inspector
verified (through record review) that Bechtel, Southern Company
Services and the plant had determined that no contactors of the
type described were installed in safety systems, nor were there any
in spare parts inventory.
8.
Open Items
78-09-04
" Sequence Failure BIG Diesel"
a.
The subject open items dealt with failure of an Agastat relay
in the BlG diesel sequencer. On the current inspection, a
sequencer cabinet and the installed Agastat relays were inspected.
The sequencer and reliability of the system were discussed
with a licensee representative.
At the exit interview, the
inspector stated there were no further questions and item
78-09-04 would be closed.
b.
78-17-01 - Installation of Stem Mounted Limit Switches
In response to IE Bulletin 78-04, the licensee had determined
that some stem mounted limit switches inside containment were
not environmentally qualified.
The current status of correction
of this problem was reviewed.
The licensee has purchased sufficient numbers of switches to
replace all of the nonqualified switches; however, the vendor
could only supply one type of mounting in the environmentally
qualified switch.
The licensee stated they were able to
replace six switches directly during the September 1978 outage,
but that revisions would be required to the switch mounting in
order to install the remaining (about 80) switches.
The
licensee stated Bechtel has been requested to provide a design
for mounting of the switches and that the goal for replacement
is during the refueling outage scheduled for April 1979.
The
switches in question all provide valve position indication,
according to the licensee. This item remains open.
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RII Rpt. No. 50-348/78-29
-4-
9.
Licensee Event Report (LER) Revieu
The inspector performed an in-office review of the reportable
occurrences listed below to verify that the report details met
license requirements, identified the cause of the occurrence,
described corrective actions appropriate for the identified cause,
and adequately assessed the occurrence and any generic implications.
In addition, follow-up review at the site was conducted by examining
logs, records and internal incident reports and by interviewing
personnel to verify the report accurately reflected the circumstances
of the occurrence, that corrective action had been taken or responsi-
bility assigned to assure completion, that any violation of regula-
tions or license conditions had been identified and that the occur-
rence was reviewed as required by Technical Specifications.
Unless
otherwise stated, the event reports are closed.
LER 78/54/03, " Damaged RCP Undervoltage Relay"
a.
b.
LER 78/55/03, " Loss of IB Startup Transformer and Failure
of IB Diesel Generator to Close on 4160V Bus Automatically"
Review of this LER at the site indicated that the stated cause
of failure of the IB DG to close on the 4160V bus may not have
been the initial cause of failure. The stated cause in the
LER was that the operating mechanism for the auxiliary contacts
were out of alignment.
In discussions with a licensee represen-
tative, the inspector concluded that the originating cause may
have been a faulty contact in an Agastat relay.
At the exit
interview, this apparent discrepancy was discussed by the
inspector.
This item will remain open, pending further review
by the inspector (78-29-01).
LER 78/56/03, "T Average Decrease Below T.S. Limits"
c.
d.
LER 78/57/03, " Failure of Surveillance Test on Containment
Air Lock Door Seal"
LER 78/58/03, "Tavg Decrease During Change _F_ rom Main-Feed
e.
to_ Auxiliary Feed System"
f.
LER _78159f 03, "Tavg increase During Rapid Load Reduct_i_cn"
g.
_LER 78/60/03
"DG,-2C_ Speed Control Potentiometer Failure *f
3
h.
LER_ 78/61/03, "DG l-2A Speed Control Potentiometer"
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RIl Rpt. No. 50-348/78-29
-5-
i.
LER 78/62/01, " Missing Seismic Restraint"
10.
Current Tra ns f o rmers
During testing of Unit 1, current transformers for the 4160 switch-
gear did not meet saturation and resistance valves claimed by the
manufacturer.
The licensee determined that the transformers were suf ficiently
accurate to monitor the maximum current carrying of the switch gear
and that the nameplates should be changed to the saturation and
resistance curve valves which can be accurately read by the trans-
formers. The inspector discussed this item with licensee represent-
ative and inspected current transformer installations at Unit 2.
There were no further questions on this event.
11.
Diesel Generators - Part 21 Reports
a.
Possible Rocker Arm Defect
On September 26, 1978, Fairbanks Morse-Engine Division informed
the NRC of a possible defect in exhaust rocker arms of their
Model PC-2 diesels.
A copy of their report was transmitted to
the Farley Plant Manager, advising that an inspection / corrective
action plan was being developed for Farley Units 1 and 2, who
have three of the PC-2 diesels.
On the current inspection,
the licensee stated they expected to receive from Fairbanks
Morse a proposed inspection procedure within 10 days.
Following
review by the licensee, the actual inspection is ant 2cipated
to be done in late November 1978 (78-29-02).
b.
Potential Fuel Injection Pump Failure
On September 22, 1978, the NRC was notified by Fairbanks Morse
of a potential fuel injection pump failure due to seizing of
the pump plunger to the pump barrel.
The licensee stated they
had discussed the problem with Fairbanks Morse and had reviewed
the potential for failure on the Farley diesels.
A review had
been made of startup test documentation and documentation
related to preventative maintenance performed during 1978.
No
problems or failures had been experienced with fuel injection
Tests have also been run on the 1B diesels to detect
p ump s .
defective fuel injection pumps by means of lowered cylinder
exhaust temperatures.
No failures were indicated, except
a
t he rmoc oupl e in cylinder number 12 was defective.
Further
tests are planned by the licensee
The item remains open
(78-29-03).