ML17053B536
| ML17053B536 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/15/1980 |
| From: | Knapp P, Thomas L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053B535 | List: |
| References | |
| 50-220-79-26, IEB-79-19, NUDOCS 8004100173 | |
| Download: ML17053B536 (26) | |
See also: IR 05000220/1979026
Text
'
U.S.
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION
AND ENFORCEMENT
Region I
Report No.
50-220/79-26
Docket No.
50-220
License
No.
Priority
Category
Licensee:
Nia ara
Mohawk Power
C r
300 Erie Boulevard West
Syracuse,
13202
Faci 1 ity Name
Nine Mi1 e Point Nuclear Station
Inspection at:
Scriba,
Inspection conducted:
December
10, 11,
and 13,
1979
Inspectors:
Lee, H. Thonus, Radiation Specialist
date signed
date signed
Approved by:
P. J.
Knapp, Chief, Radiation
upport
Section,
FFENS Branch
date signed
g r~
ate signed
Ins ection
Summar
Ins ection on December
10,
11
and 13,
1979 (Report
No. 50-220/79-26) "
A~Id:
Sp
i
1
p
y
g
p
licensees
response
to IE Bulletin 79-19 including licensee
action
on IE Circulars,
documents,
procedures,
training, audits, facility tours,
and records.
The inspection
involved 19 inspector-hours
onsite
by one
NRC regional
based inspector.
Results:
No items of noncompliance
or deviations
were identified.
.Region I Form 12
(Rev.
April 77)
800410~> <
DETAILS
Persons 'Contacted
Mr.
- Mr.
Mr.
- Mr.
- Mr.
Mr.
- Mr.
J. Aldrich, Supervisor,
Training
J. Duell, Assistant
Chemistry
and Radiation Protection Supervisor
C. Gerber,
Radwaste
Coordinator
E. Leach,
Chemistry
and Radiation Protection Supervisor
G. Leskiw, guality Control Auditor
D. Palmer, Supervisor,
guality Control-Operations
T. Perkins, Station Superintendent
- Denotes those present at the exit interview on December
13,
1979.
The inspector interviewed several
other licensee
employees
including
auxiliary operators,
radiation protection technicians
and records
clerks.
Licensee Action on IE Circul'ars
.
79-15
The licensee does'ot
use the respiratory protection equipment
described
in the circular.
The inspector
had
no further questions.
Re ul ator
Documents
The licensee's
response
to IE Bulletin 79-19 indicated that current
copies of NRC and
DOT (Department of Transportation)
regulations
were
maintained in the station 'library and that current copies of the
burial site license. were maintained
by the radwaste
operations
coordinator
and the radiation protection department
supervisor.
The inspector
examined
the
NRC regulations
(10 CFR 71) and
DOT regulations
(49
CFR
170-179) in the library.
These
copies
were page
change
copies which
are periodically updated
as
changes
in the regulations: occur.
The
copy of the burial site license
issued
by the State of South Carolina
for the Barnwell facility which is maintained
by the radiation protection
department
head
was examined
and found to be
up to date.
No items of noncompliance
or deviations
were observed.
Procedures
The licensee's
response
to IE Bulletin 79-19 indicated that revised
procedures
covering the transfer,
packaging,
and transport of waste
would be developed
by January
1, 1980.
At the time of the inspection
the procedures
had not been developed,
reviewed
and implemented; this
area will be further examined at a date after the licensee's
scheduled
date for the completion of the procedures.
(50-220/79-26-01).
A
letter from the general
superintendent,
nuclear
generation-to
the
station superintendent
dated
September
21,
1979 designated
the radwaste
c'oordinator
and the radiation protection manager
as the individuals
responsible for the safe transfer,
packaging
and transport of low
level radioactive material.
No items of noncompliance
or deviations
were identified.
'Tnaini.n
J
The licensee
implemented
changes
in the basic "radiation worker"
.training and retraining
on October
5,
1979.
These
changes
emphasized
minimizing the creation of low-level waste.
Courses for operators
and members of the radiation protection departments
were under development
by'
contractor.
This area will be further examined at
a subsequent
inspection
when the
new training programs
are implemented
(50-220/79-
26-02).
No items of noncompliance
or deviations
were identified.
Audits
The inspector reviewed the licensee's
audit program of activities
associated
with the transfer,
packaging,
and transport of low level
radioactive wastes.
The licensee's
audits
by guality Assura'nce-
Operations
are performed in accordance
with guality Assurance
Procedure
1640 which calls for an audit report within 30 days,
a response
to
nonconformance
items within 22 days for acceptance
or rejection of
plant responses
to nonconformance
items.
The. procedure
also contains
provisions for verification of the response
and provisions for escalation
of disputed
items.
The inspector
examined
the results of several
licensee
audits in the
area of radioactive material transportation
and transfer.
Audit SR-
79-026A was conducted
September
4-13,
1979
and covered shipping,
.
handling,
and receiving of radioactive material,
procedures,
compliance
with 10 CFR 71, compliance with 49
CFR 173,
IE Bulletin 79-19 response
and conformance
to burial site requirements.
Audit SR-79-026B
conducted
in the
same time period covered
compliance with 10 CFR 71 requirements.
Audit SR-79-026C
was conducted
from September
10-12,
1979
and dealt
with compliance with 49
CFR requirements.
The licensee's
normal audit
program covers radioactive material transportation
on
a more frequent
than annual basis, typically twice per year.
No items of noncompliance
or deviations
were identified.
t
~Fillt l
The inspector
toured the licensee's
radwaste
area;
no containers
of
solidified or dewatered
waste were onsite.
These
are typically shipped
offsite in casks within a day of. being. prepared.
The inspector observed
a cask being filled with resin.
At the completion of the inspection
the filling/dewatering process.had
not been
completed.
The inspector
reviewed the licensee's
method of dewatering which included repeated
'ump downs of the resin using
a well point laid horizontally on the
bottom of the cask liner.
The holes in the upper half of the well
point had been filled with a rubber compound
such that water and air
could only enter through the bottom.
While in the radwaste
area
the
inspector
examined
area posting
and high radiation area control.
No items of noncompliance
or deviations
were observed.
0
8.
Shi ment Records
Technical Specification
(T.S'.) 6. 10. 1 requires
in part that "records
shall
be retained for at least five years" including "Records of
radioactive shipments".
The inspector
examined
records of approximately
15 shipments
made during 1979.
Certificates of compliance
and supporting
documents f'r two cask types
used
by the licensee
were examined to
verify that the licensee fulfilled the requirements
for a general
license to ship radioactive materials
under
No items of noncompliance of deviations
were identified.
9.
Exit Interview
The inspector
met with licensee
representatives
(denoted in paragraph
1) at the conclusion of the inspection
on December
13,
1979.
The
inspector
summarized
the purpose
and scope of the inspection,
and the
findings as presented
in this report.
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
631 PARK AVENUE
KING OF PRUSSIA, PENNSYLVANIA19406
2
NOV IS>9
Docket No. 50-220
Niagara
Mohawk Power Corporation
ATTN:
Mr. R.
R. Schneider
Vice President
Electric Operations
300 Erie Boulevard West
Syracuse,
13202
Gentlemen:
Subject:
Inspection
50-220/79-24
This refers to the inspection
conducted
by Mr. E. T. Shaub of this office
on September
14,
1979 and September
26-27,
1979, at Nine Mile Point Nuclear
Station Unit
1 of activities authorized
by"NRC License
No.
and to
the discussions
of our findings held by Mr. Shaub with Mr. T. Perkins of
your staff at the conclusion of the inspection..
Areas
examined during this inspection are described
in the Office of
Inspection
and Enforcement Inspection
Report which is enclosed with this
letter.
Within these areas,
the inspection consisted of selective
examinations
of procedures
and representative
records,
interviews with personnel,
and
observations
by the inspector.
Within the scope of this inspection,
no items of noncompliance
were observed.
In accordance
with Section 2.790 of the NRC's "Rules of Practice," Part 2,
Title 10,
Code of Federal
Regulations,
a copy of this letter and the enclosed
inspection report will be placed in the
NRC s Public Document
Room. If
this report contains
any information that you (or your contractor)
believe
to be proprietary, it is necessary
that you make
a written application
within 20 days to this office to withhold such information from public
disclosure.
Any such application must be accompanied
by an affidavit
executed
by the owner of the information, which identifies the document or
part sought to be withheld, and which contains
a statement of reasons
which
addresses
with specificity the items. which will be considered
by the Commission
as listed in subparagraph
(b)(4) of Section 2.790.
The information sought
to be withheld shall
be incorporated
as far as possible into a separate
part of the affidavit. If we do not hear from you in this regard within
the specified. period, the report will be placed in the Public Document
Room.
- ~
Niagara
Mohawk Power Corporation
g
HOV >979
No reply to this letter is required;
however,
should you have any questions
concerning this inspection,
we will be pleased
to discuss
them with you.
'alter
G. Martin, Chief
Safeguards
Branch
Enclosure:
Office of Inspection
and Enforcement
Inspection
Report
Number
50-220/79-24
(Contains
2.790 Information)
U.
S.
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION
AND ENFORCEMENT
REGION I
Report
No.
50-220/79-24
Docket No.
50-220
License
No.
Licensee:
Nia ara
Mohawk Power Cor oration
Safeguards
Group~
300 Erie Boulevard i<est
Syracuse,
13202
Facility Name:
Nine Mile Point I
Inspection At:
Oswego,
Inspection
Conducted:
September
14, 1979,
Se tember 26-27,
1979
Date of Last Material Control
and Accounting Inspection
Type of Inspection:
Unannounced
Material Control
8 Accountin
Inspectors:
E. T. Shaub,
Safeguards
Technician
<I'c'. /
P"..H. Bissett,
Safe
ua
s
A itor
/o p2.
7
date
date
date
Approved by:
.
H.
oyne
,
ie
, Nuclear Material Control
date
port Section,
Safeguards
Branch
Ins ection
Summar
~dl
td:
P ttty g;
t
d
p
t
t
d
shipping
and receiving, storage
and internal control inventory, record
and reports,
and, management
of nuclear material control system.
The inspection
involved 26
inspector-hours
on site
by two
NRC inspectors
and was started
on the regular shift.
Results:
The licensee
was found to be in compliance with NRC requirements
in all
areas
examined during the inspection.
Region I Form 166
(August 1979)
DETAILS
l.
Persons
Contacted
"T. Perkins,
Superintendent
of Nuclear Generation
~M. Drews, Reactor Analysist Supervisor
"G. Leskin, Acting Supervisor gC-Operation
~P. Harrison,
gC Engineer
"R. Tessler,
Technician
D Reactor'Physics
B.
Eastman,
Technician
D Reactor
Physics
" denotes
those present at the exit interview.
2.
Licensee Action on Previous
Ins ection Findin s
(Closed)
Noncompliance
(77-21-01) Failure to maintain
on a current
basis Material Control Procedure
No. AP-37.
(Closed)
Noncompliance
(77-21-02) Failure to conduct
a physical
inventory
within a twelve month interval
as required
~
(Closed)
Noncompliance
(77-21-03) Failure to accumulate
and include
plutonium decay
on Form NRC-742 reports
as required to
CFR 70.53.
Licensee actions
on these
three
items were reviewed
and closed during
inspection
78-06.
3.
Exit Interview
The inspectors
met with the licensee's
representatives
(denoted in
paragraph
1) at the conclusion of the inspection
on September
27,
1979.
The inspectors
summarized
the scope
and findings of the inspec-
tion.
4.
Unresolved
Items
There were
no unresolved
items.
5.
Inde endent Ins ection Effort
No items of noncompliance
were noted.
I
The inspectors
walked through various areas of the plant to observe
plant operations.
6.
MC 85102B - Material Control
and. Accountin
No items of noncompliance
were noted.
Facilit
Or anization
and
0 eration - The inspector verified, through
review, that the licensee
has prepared,
maintained
and utilized on a
current basis,
adequate written procedures
for nuclear material control
and accounting
and that written statements
of responsibility
and
authority have
been established
for those positions with responsibility
for SNM.
Shi
in
and Receivin
- Inspection results
were attained
through
review of each of the prepared
Form NRC-741, Material Transaction
Reports,
against criteria for preparing/completing
the forms, timeliness
in issuance
and completion, correctness
of the coding information/quanti-
tative data,
and authorized signature.
Measurement
and Control - The inspectors
reviewed procedures,
ledgers
and process
computer printouts to ascertain that the licensee
has
established,
maintained
and utilized a method of computation for the
determination of the total element
and isotope composition of nuclear
materials
The licensee
uses
a General Electric supplied computer
program,
OD-12; to determine
element
and isotopic composition
and
exposure history for each fuel assembly in the reactor core.
The
licensee's
backup
method for determining thermal
power output of the
core is a calorimetric determination.
The inspector's
independent
determination of the uranium and uranium-
235 fission and transmutation
and plutonium production agrees
with the
licensee's
reported figures
as
shown
on the
Forms
NRC-742, Nuclear
Material Status
Reports,
submitted for the period July 1,
1976 through
March 31,
1979.
Stora
e and Internal Control - The licensee
has established
a system
of storage
and internal control of SNM which provides for knowledge of
the quantity and location of all
SNM within the facility.
The inspectors
reviewed
SNM accountability system
documents
maintained
by the licensee,
including Fuel
Element History Cards,
Fuel
Movement Sheets
(Internal
Transfer Forms),
and Reactor
Core and Spent
Fuel
Pool tagboards.
Ph sical Inventor
- The inspectors verified the licensee's
latest
physical inventory by an item count of the irradiated fuel elements
in
the spent fuel pool and by verification of a random sample of approxi-
mately 25K of the fuel elements
in the spent fuel pool to tagboards
and grid maps.
The core inventory was verified by selecting
a random
sample of 25K of the fuel elements
and comparing the location of each
fuel assembly selected
to the fuel element history cards,
reactor core
tagboards
and Fuel
Loading Procedure
for Cycle 6, Fuel
Loading.
The inspector's verification confirmed the facility SNM inventory to
be as follows:
Location
Fuel Assemblies
Reactor
Core
532
Spent
Fuel
Pool
844
Total
1,376
Records
and
Re orts - A 100K audit of Material Status
Reports
(Form
and Material Transaction
Reports
(Form NRC-741) filed by the
licensee for the period April 1,
1977 through March 31,
1979 was
performed to verify compliance with 10 CFR 70.53
and
respectively.
Through this review it was noted that the licensee
was
including both natural
and enriched
uranium on on line 30 (receipts)
of the enriched
u'ranium Material Status
Report.
To avoid any future
confusion,
since all future shipments
of fuel assemblies will contain
both natural
and enriched
uranium, the licensee
agreed to open
a
separate
account for all natural
uranium received
and, for reporting
purposes,
transfer the appropriate
amount of natural
uranium from the
normal
uranium Material Status
Report to line 22 of the enriched
uranium Material Status
Report.
It was also noted during the review,
that both the uranium and plutonium Material Status
Reports for the
period October
1,
1978 to March 31,
1979 were dated
and actually
reported for October
1,
1978 to March 1,
1979.
The licensee
agreed to
submit corrected
copies of both the uranium and plutonium Material
Status
Report.
Material Balance
Summaries for the, period covered
by the inspection
are
shown in Exhibits I, II, and III.
Mana ement of Material Control
S stem - The inspection results
were
obtained through review of the equality Control procedures.
The last
gC audit of the special
nuclear material accountability procedures
was
completed in July,
.1978.
Also,
gC checks
are performed continuously
when reactor fuel is received,
moved or shipped at the site.
~
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EXHIBIT I
PERIOD:
4/1/77 - 3/31/79
MATERIAL BALANCE SUMMARY
ENRICHED URANIUM
RIS:
YGX
= Beginning Inventory
8 '4/1/77
Receipts
Material to Account For
Removal s:
Shipments
Burn-Up
Total Removals
Ending Inventory 8
3/31/79
Material Accounted for
Grams
Element
221595201
31588828
0
1256373
1@HZ(
251937656
Z5318$
}ZR
~Iso to
e
3010673
893259
M3932
0
549384
3254548
p
~
EXHIBIT II
PERIOD:
4/1/77 - 3/31/79
MATERIAL BALANCE SUMMARY
RIS: YGX
Grams
Element
~lento
e
Beginning Inventory I 4/1/77
Receipts
Production
Material to Account For
Removals:
Shipments
Decay
Total
Removals
Ending Inventory 8
3/31/79
Material Accounted For
1143800
0
279703
1423~5
0
12245
12245
1411258
868149
0
189607
M1UZK
0
12245
12245
1045511
1(~57 5j
s
~
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EXHIBIT III
PERIOD:
4/1/77 " 3/31/79
MATERIAL BALANCE SUMMARY
NATURAL URANIUM
RIS:YGX
Grams
EIement
~Isoto
e
Beginning Inventory 8 4/1/77
Receipts
YLG-YGX 27-33
Material to Account For
Removals:
Shipments
Burn-Up
Total
Removals
Ending Inventory 8
3/31/79
Material Accounted For
0
958721
0
0
0
958721
0
8095
~85
0
0
0
8095
5999
Natural
uranium will be transferred to the enriched
uranium account in the
next Form NRC-742 reporting period (4/1/79 - 9/30/79), for simplication of
accounting
and reporting requirements.
(See paragraph
6 for details).
J
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