IR 05000259/1992028
| ML18036B030 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/21/1992 |
| From: | Dan Collins NRC Office of Inspection & Enforcement (IE Region II) |
| To: | Medford M Tennessee Valley Authority |
| Shared Package | |
| ML18036A833 | List: |
| References | |
| NUDOCS 9209020077 | |
| Download: ML18036B030 (9) | |
Text
Ql l I CI/<
AUG 21 1992 Docket Nos.
50-259, 50-260, 50-296 License Nos.
DPR-33, DPR-52, DPR-68 Tennessee Valley Authority ATTN:
Dr. Mark O. Medford Vice President, Nuclear Assurance, Licensing
& Fuels 3B Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Gentlemen:
SUBJECT NRC INSPECTION REPORT NOS ~
50 259/92 28 g 50 260/92 28 g AND 50-296/92-28 This refers to the inspection conducted by G. A. Todd of this office on July 20-22, 1992.
The inspection included a review of activities authorized for your Browns Ferry facility.
At the conclusion of the inspection, the findings were discussed with those members of your staff, identified in the enclosed report.
Areas examined during the inspection are identified in the report.
Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observation of activities in progress.
Within the scope of the inspection, violations or deviations were not identified.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice,"
a copy of this letter and its enclosure will be placed in the NRC Public Document Room.
Should you have any questions concerning this letter, please contact us.
9'205'020077 92082l PDR ADOCK 05000255'
Sincerely,
/~/'ouglas M. Collins, Chief Nuclear Materials Safety and Safeguards Branch Division of Radiation Safety and Safeguards
Tennessee Valley Authority
Enclosure:
NRC Inspection Report
REGION II==
101 MARIETTASTREET, N.W., SUITE 2900 ATLANTA,GEORGIA 30323 Report Nos.:
50-259/92-28, 50-260/92-28, and 50-296/92-28 Licensee:
Tennessee Valley Authority 3B Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Docket Nos.:
5'0-259, 50-260 License Nos.:
DPR-33, DPR-52, and 50-296 and DPR-68 Facility Name:
rowns Ferry 1, 2, and
Inspection Co d 4ted:
ly 2 -22, 1992 og'-a-v~
Date Signed ZO Inspector:
G.
ard Inspector D te Signed Safeguards Branch and Safeguards Approved by:
D. R. McGuire, Chief Safeguards Section=
Nuclear Materials Safety and Division of Radiation Safety SUMMARY Scope:
This routine, unannounced, inspection was conducted in the areas of material control and accountability..
Results:
In the areas inspected, violations or deviations were not identified.
One open item was closed which was reported in NRC
Inspection Report
NcA 50-259/91-33,
50-260/91-33,
50-296/91-33
and reference
Enforcement Action (EA) 91'-120.
The licensee's
procedural accountability improvements
were extensive
and
demonstrated
an upgraded
commitment to special nuclear material
~
control and accountabilit ge
REPORT DETAILS
1.
Persons
Contacted
Licensee
Employees
- G. Campbell,
Maintenance
Tech'~< Engineeri'ng
- P. Salas,
Manager,
Compliance
- J.~ Scalice,
Plant Manager
- J.~. Wallace,
Compliance Engineer,
Site Licensing
- K. Welch, Reactor Engineer,
Technical Support
+0. + Zeringue,
Vice President,
Brcwns Ferry Nuclear Plant@
(
BNF
Other licensee
employees
contacted during this inspection
included engineers,
technicians,
and administrative
g. personnel.
+Nuclear Regulatory Commission
- W.
Bearden,
Resident Inspector
- Attended exit interview
t
2.
Followup On Corrective Actions For Previous Violations
and/or Deviations
(92702)
NRC Inspection Report Nos'. 50-259/91-33,
50-260/91-33,
and
50-296/91-33 resulted in escalated
enforcement action as
referenced in NRC Enforcement Action (EA)91-120.
EA 91-120
documented
a violation involving the licensee's
failure to
perform an adequate
physical inventory of special nuclear
material
(SNM) in 1990.
Specijically, the February and
March 1990 physical invento~lVailed to include an item
containing
SNM, which was identified in the spent fuel pool
on September
7,
1991.
(CLOSED) Violation
'0-259/91-33,
50-260/91-33',
and 50-296/91-33<
Failure To Perform An
Adequate Physical Inventory Of Special Nuclear Material.
The inspector
examined the licensee.'s
programmatic
improvements
and specific corrective actions
and determined
the following:
-TVA revised four procedures
for ensuring:
(1) Plant
management
is involved in daily activities of storing
radioactive material in the Spent Fuel Storage
Pools
(SFSPs),
(2) Low-Power Range Monitors
(LPRf4) a e
properly stored, in one piece,
and
(3) the+FSP
are
expeditiously cleaned
up after an outage.
Proc dure
0-GOI-100-3
was revised to address
the Plant Manager'
responsibility for activities in the SFSP Additionally, this procedure
was revised to warn,
personnel that
SFSPs
are not to be used for long-term
storage of radioactive material and that a.yearly
inventory be performed using a form requiring the Plant
Manager's signature.
(,pe4 )
,On
Special Instrument Instruction 0-XX-92-051 Rev)
6,
was
revised to remove steps
which allowed LPRMs to be cut
upon removal from the reactor cavity.
The current
,
revision requires
the
LPRM to remain intact thereby
.avoiding confusion of whether or not an
LPRM string
contains
a "hot"
(SNM) end or not.
Without cutting the
(when they are removed from the cavity) should
prevent small "hot" LPRM pieces to be stored in
different locations in a SFSP thereby potentially
losing future inventory accountability.
Finally,
Radwaste Instruction RWI-116 was revised to allow, LPRMs
to be cut only at the time they are being packaged for
disposal.
o
The three
SFSPs
were vacuumed to clear sil't and small
debris from the
SFSP floors.
The silt contributed to
the oversight of SNM during the previous
two inventory
phases.
A camera
was used to assist in the floor
cleanup locating small material for disposal.
Irradiated waste
was removed from the SFSPs.
Additionally, all non-essential
radioactive material
was removed from the SFSPs.
A final inventory was performed and a current listing
has'een
developed to establish
a current and accurate
base-line inventory.
TVA hired an 'outside consultant to perform an
independent
assessment
of the
This assessment
investigated
the following areas:
procedures,
personnel,
SNM accountability,- storage
areas
and containers;
records,
and control of
calibration sources.
The assessment
included
interviews with selected
licensee
employees,
document
evaluation,
records
accuracy,
and extensive plant
tours.
The contractor assessment
entitled
"Browns Ferry
Nuclear Plant Special Nuclear Material Control Program
Assessment,"
dated
May 11,
1992,
concluded that there is
a heighten'ed
awareness
of the
SNM Control Program
including its requirements
and responsibilities
throughout the entire
BFN organizatio Based
on this inspection followup review the inspector
concluded that the completion of all phases
of the original
SNM baseline inventory program along with the completion of
the additional corrective actions
above, that appropriate
steps
have been taken and an adequate
program now exists to
prevent recurrence
of a similar violation.
3.
Material Control and Accounting
ower Reactors
(85102)
Nuclear
terial Balance Reports
The inspector
examined the licensee's
Material Balance
Reports
(DOE/NRC Form 742) issued under Reporting
Identification Symbols
XDP (Unit 1),
XFY (Unit 2), and XJD
(Unit 3) for the period ending March 31,
1992.
This
examination
was to determine whether the reports accurately
reflected quantities of fuel and non-fuel
SNM received
and.
shipped
and whether uranium depletion and plutonium
production had been entered.
The inspector determined that
the report was completed
and distributed in accordance
with
the printed instruction.'n
NUREG/BR-0007 and the recorded
data were found to be in agreement with associated
accountabi'lity records.
4 ~
Exit Interview
The inspection
scope
and results
were summarized
on July 22,
1992, with those persons
indicated in Paragraph
1.
The
inspector described
the areas
inspected
and discussed
in
detail the inspection results.
Although reviewed during
this inspection, proprietary information is not contained in
this report.
'issenting
c'omments
were not received from
the licensee.
The licensee
was advised by the inspector that no further
reports to the
NRC are required relative to the close-out
action on'he violation referenced in NRC Inspection Report
Nos. 50-259/91-33,
50-260/91-33,
50-296/91-33,
and/or
EA 91-120.