ML17292B230
| ML17292B230 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/16/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17292B227 | List: |
| References | |
| 50-397-97-19, NUDOCS 9801230164 | |
| Download: ML17292B230 (4) | |
See also: IR 05000397/1997019
Text
-3-
IV. Pla tSu
o
R1
Radiological Protection and Chemistry (RP&C) Controls
R1.1
x
mal Ex osur
on r
I
Ins
i n
co e
75
The inspector interviewed radiation protection personnel and reviewed the following:
Control of high radiation areas
High radiation area key control
Radiological posting
Radiation work permits
Radiological controlled area access controls
Dosimetry use
b.
b
rv
io
a d 'di
s 83750
One of the requirements of Technical Specification 5.7.2.a is that each entryway to areas
with dose rates greater than
1 rem per hour be provided with a locked door, locked gate,
or guard that prevents unauthorized entry. The licensee designated areas with dose
rates greater than
1 rem per hour as high high radiation areas.
On October 6, 1997, the senior resident inspector identified a high high radiation area
that was not locked and not guarded.
The area was the radwaste liner storage room on
the 437-foot elevation of the radwaste building. Before securing the area gate with a pad
lock and chain, a radiation protection technician failed to ensure that the chain passed
through both the gate and a chain-link fence.
Therefore, even though the pad lock was
closed, the gate was not secured.
Second-person
verification that the area was properly
secured was not performed promptly. The licensee determined the area was unlocked
for approximately 70 minutes.
The radiation dose rates within the area were as high as 3 rems per hour. However,
because of the low occupancy of the area, the time required to exceed regulatory dose
limits, and the required use of electronic, alarming dosimeters by individuals entering the
radiological controlled area, the inspector concluded that the potential for individuals
exceeding regulatory dose limits was not substantial.
The failure to provide an area with
dose rates greater than
1 rem per hour with a locked door, locked gate, or guard was a
violation of Technical Specification 5.7.2.a (50-397/9719-01).
NRC Inspection Report
50-397/95-30 described similar violations, occurring May 7 and August 8, 1995. The
licensee initiated Problem Evaluation Request 297-0807 to document the problem and
track corrective actions.
980i230i64 980ii6
ADQCK 05000397
6
-5-
examples listed. The inspector identified the four examples,
in which no evaluations
were performed on individuals with potential internal contamination, as a violation of
10 CFR 1501(a) (50-397/9719-02).
After reviewing the licensee's implementing procedures applicable to this situation, the
inspector concluded that a possible cause for the violation was the use of a poorly
worded or illogicallyconstructed procedure.
This is discussed
in Section R3.
The radiation protection manager stated, during a telephone conversation on
December 5, 1997, that, since the onsite portion of the inspection, radiation protection
representatives
reviewed the personnel contamination event Iog and identified two
additional individuals who had not been provided whole-body counts.
Allsix individuals
were contacted and provided whole-body counts.
No significant intakes of radioactive
material were identified. However, more than 6 months had elapsed since the
identification of the earliest example.
Therefore, it might have been difficultfor the
licensee to identify the presence of radionuclides with short effective half-lifes, ifthey had
been taken internally.
c.
Qggclu~s'ons
A violation involving the failure to evaluate radiological hazards associated'with potential
intakes of radioactive material was identified.
R1.3
I'0
i
iv
M
ri
I
d
mi
i
e in
n
M ni ori
a.
In
c'7
0
The inspector interviewed radiation protection personnel and reviewed the following:
Release of items from the radiological controlled area
Sealed radioactive source accountability
Sealed radioactive source leak testing
Personnel contamination events
Portable survey instrument calibration
Whole-body counter calibration
Ob erv
ion
and Findin s
Con rol f R dioac ive Material
During a review of problem evaluation requests, the inspector noted that the licensee
identified minor problems involving the release of radioactive materials from the
radiological controlled area in December 1996 and May 1997. The inspector observed
radiation protection technicians as they performed radiation surveys and released items
from the radiological controlled area.
No problems were identified. Items released
unconditionally were recorded in the licensee's material release log.
SUPPLEMENTAL IN 0
MAT0
T AL L S 0
PERSO
S CONTACTED
~Li ~nse
D. Atkinson, Quality Manager
P. Bemis, Vice President Nuclear Operations
I. Borland, ALARA/Health Physics Support Supervisor
D. Hillyer, Radiation Protection Manager
P. Inserra, Licensing Manager
J. Liles, Health Physics Operations Supervisor
M. Shepherd,
Health Physics Operations Supervisor
G. Smith, Plant General Manager
R. Webring, Vice President Operations Support
S. Boynton, Senior Resident Inspector
G. Johnston, Senior Project Engineer
INSPECTION PROCED
RES USED
83750
Occupational Radiation Exposure
0 ene
E
S OPENED CLOSED AND DISCUSSED
50-397/9719-02
Failure to control access to areas with radiation dose rates
greater than
1 rem per hour
50-397/9719-02
Failure to evaluate radiological hazards related to potential
internal contaminations
Closed
50-397/9530-01
Failure to control access to areas with radiation dose rates
greater than
1 rem per hour
Discussed
NONE