ML18024A950
| ML18024A950 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/11/1979 |
| From: | Dance H, Price D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18024A949 | List: |
| References | |
| 50-259-79-15, 50-260-79-15, 50-296-79-15, NUDOCS 7908170147 | |
| Download: ML18024A950 (4) | |
See also: IR 05000259/1979015
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100
ATLANTA,GEORGIA 30303
Report Nos. 50-259/79-15,
50-260/79-15,
and 50-296/79-15
Licensee:
Valley Authority
500A Chestnut Street
Tower II
Chattanooga,
37401
Facility Name:
Browns Ferry Nuclear Plant
Docket Nos.
50-259, 50-260,
and 50-296
License Nos.
and DPR-68
Approved by:
H. C.
ance,
ection Chief,
RONS Branch
3UMHARY
Inspection at B
wns Fe
Site near Athens,
Inspector:
C
D.
.
rice
&/~ 7
Da e
S gned
fl 'l
ate Signed
Inspection
on May 29-31,
1979
Areas Inspected
This routine,
unannounced
inspection
involved
17 inspector-hours
onsite in the
areas of Inspection and Enforcement (IE) Bulletins.
Results
Of the one area inspected,
no apparent
items of noncompliance
or deviations
were
identified.
0
DETAILS
1.
Persons
Contacted
Licensee
Employees
-J.
G. Dewease,
Plant Superintendent
>H. L. Abercrombie, Assistant Plant Superintendent
-R. Hunkapillar, Assistant Operations
Supervisor
M. A. Haney, Mechanical Maintenance
Supervisor
R. Smith, Mechanical Maintenance
Engineer
R. Mears, Assistant Unit Operator
NRC Resident. Inspector
+R. F. Sullivan
+Attended exit interview
2.
Exit Interview
The inspection
scope
and findings
were
summarized
on May 31,
1979 with
those
persons
indicated in Paragraph
1 above.
The licensee
acknowledged
the comments discussed in paragraph six.
(
3.
Licensee Action on Previous Inspection Findings
Not inspected.
4.
Unresolved Items
Unresolved items were not identified during this inspection.
5.
IE Bulletin 78-14, Deterioration of Buna-N Components in ASCO Solenoids
IE inspection report 50-259,
260, 296/79-5
documented
the initial review of
this bulletin.
A revised Bulletin response
has
been
received
from the
licensee
which includes all requested
information.
The inspectors
review
of the
program
and
discussions
with IE Headquarters
indicates
that the
licensee's
schedule
for replacement
of Buna-N components
is acceptable.
The inspector had no further questions.
6.
IE Bulletin 79-08, Events Relevent to Boiling Water Power Reactors Identified
During Three Mile Island Incident
0
The inspector performed independent
observations to verify that the licensee
had taken the actions required by this Bulletin as to review of his facilities
and operations.
-2-
For the following Unit 1 and
2 systems,
major flow path valve/breaker/switch
component positions
were verified with current
PAID diagrams.
Alignment
procedures, for all units, were also verified against the PAID diagrams:
High Pressure
Coolant Injection (HPCI)
Reactor Core Isolation Cooling Core Spray
Emergency Equipment Cooling Water (supply and return for diesel engines)
Residual Heat Removal Service Water (standby coolant supply portion)
Diesel Generator (electrical system)
Automatic Depressurization
System
It was noted that the following valves did not appear
on the system panel
check lists (the valves were included on system valve check lists):
FCV-71-10, RCIC Turbine Governing Valve
HCV-71-16, RCIC Pump Suction From Torus
FCV-73-19, HPCI Turbine Governor Valve
FCV-73-18, HPCI Turbine Stop Valve
HCV-63-506,
SLC Pump Suction Valve
The licensee stated that these valves would be included on the panel checklists
in a forthcoming revision.
The inspector had no further questions.