ML20037D358
| ML20037D358 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 06/15/1981 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML20037D359 | List: |
| References | |
| NUDOCS 8107100118 | |
| Download: ML20037D358 (4) | |
See also: IR 05000244/1980016
Text
-~~-
n
[pn nry.l'o
e
UNITED STATES
g
3
NUCLEAR REGULATORY COMMISSION
3
o
l
y
E
REGION I
$
[
631 PARK AVENUE
%
,8
KING OF PRUSSIA. PENNSYLVANIA 19406
g
Docket No. 50-244
M
Rochester Gas and Electric Corporation
h
e p F "l
,
p g j y/~ } O'\\
ATTN: Mr. J. E. Maier
O
Vice President
-
"
C
Electric and Steam Production
89 East Avenue
2
JUL 0 01981 e-
Rochester, New York 14604
VJ u.s.nent,. w en
ecew os
,Q
Gentlemen:
,,'3
- X
.,
Subject:
Health Physics Appraisal
3
The NRC has identified a need for licensees to strengthen the health physics
programs at nuclear power plants and has undertaken a significant effort to
assure that action is taken in this regard. As a first step in this effort,
the Office of Inspection and Enforcement is conducting special team appraisals
of the health physics programs, including the health physics aspects of radio-
active waste management and cnsite emergency preparedness, at all operating
power reactor sites.
The objectives of these appraisals are to evaluate the
overall adequacy and effectiveness of the total health physics program at each
site and to identify areas of weakness that need to be strengthened. We will
use the findings from these appraisals as a basis not only for requesting
individual licensee action to correct deficiencies and effect improvements but
also for effecting improvements in NRC requirements and guidance.
This effort
was identified to you in a letter dated January 22, 1980, from Mr. Victor
Stello, Jr., Director, NRC Office of Inspection and Enforcement.
During the period of December 7-19, 1980, the NRC conducted the special appraisal
of the health physics program at the Ginna Nuclear Generating Station. Areas
examined during this appraisal are described in the enclosed report (50-244/80-16).
Within these areas, the appraisal team reviewed selected pro edures and representa-
tive records, observed work practices, and interviewed personnel.
It is
requested that you carefully review the findings of this report for consideration
in effecting improvements to your health physics program.
The portion of the
appraisal pertaining to emergency planning and preparction will be transmitted
separately at a later date.
The findings of the appraisal at Ginna indicate that while your radiation
protection program is generally acceptable in most areas, there are some
portions of the program that require improvement to be acceptable.
Particular
findings are discussed in detail in Appendix A, "Significant Appraisal Findings."
1@b
s
//
8107100118 810615
PDR ADOCK 05000244
0
~
-
.
._.
.-
.
. .
-
-
'
,
.
.15 JUN 1981
Rochester Gas and Electric Corporation 2
__
We recognize that an explicit regulatory requirement pertaining to each significant
weakness identified in Appendix A may not currently exist.
However, to determine
whether adequate protection will be provided for the heath and safety of
workers and the public, you are requested to submit a written statement within
twenty (20) days of your receipt of this letter, describing your corrective
action for each significant weakness identified in Appendix A, including:
(1)
steps which have been taken; (2) steps which will be taken; and (3) a schedule
for completion of action.
This request is made pursuant to Section 50.54(f)
of Part 50, Title 10, Code of Federal Regulations.
No items of noncompliance were identifed within the scope of this appraisal.
You should be aware that the next step in the NRC effort to strengthen health
physics programs at nuclear power plant's will be the imposition of a requirement
by the Office of Nuclear Reactor Regulation (NRR) that each licensee develop,
submit to the NRC for approval, and implement a Radiation Protection Plan.
Each licensee will be expected to include in the Radiation Protection Plan
sufficient measures to provide lasting corrective action for significant
weaknesses identified during the special appraisal of the current health
physics program.
Guidance for the development of this plan will incorporate
pertinent findings from all special appraisals and will be issued by NRR later
this year.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,
Title 10, Code of Federa Regulations, a copy of this letter and the enclosures
will be placed in the NRC's Public Document Room.
If this material contains
any information that you believe to be proprietary, it i.s 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 accompanieo
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, this letter and the enclosures will be placed in the Public
Document Room.
Should you have any questions concerning this inspection, we will be pleased
to discuss them with you.
Sincerely,
' [c
t
W
Boy e H. Grier
Director
Enclosures:
1.
Appendix A, Significant Appraisal Findings
2.
Office of Inspection and Enforcement Inspection Report Number
50-244/80-16
.
-.
-
.
.
,15 JUN 1981
Rochester Gas and. Electric Corporation 3
cc w/encls:
B. A. Snow, Plant Superintendent
J. Bodine, QC Engineer
Harry H. Voigt, Esquire
J. T. St. Martin, Technical Assistant,
Operations Assessment Engineer
.
.
-
,
i
APPENDIX A
Significant Appraisal Findings
In the course of this appraisal, the following items were identified as needing
improvement in order to achieve an acceptable program.
1.
An accurate description of the Radiation Protection organization was not
developed, established and maintained sufficient to define the organiza-
personnel involved (porting chains or functional descripions of the
tional hierarchy, reincluding responsibilities and authorities).
Adminis-
trative Procedures have not been revised to reflect the current arrangement
of the Chemistry and Health Physics organization, nor have Job Descriptions
been established that accurately represent the positions in the organiza-
tion as it currently exists, including that of Corporate Health Physicist.
(Section1.0)
2.
The quality assurance program implemented for the vendor-supplied film
badge devices is not implemented sufficiently to assure that the device
provides an accurate estimate of personnel exposures.
(Section 3.1)
3.
There are no adequate procedures formally established, maintained and
implemented that permit the evaluation of uptakes of radioactivity from
air samrles or bicassay results.
(Section 3.2)
4.
There are nc procedures established, implemented or maintained that
discuss the process of collecting and analyzing urine and fecal material
for evaluating personnel exposure to radioactivity. (Section 3.2)
5.
There is no independent verification of the whole body counter performed
sufficient to assure that the instrument is calibrated and functioning
properly.
(Section 3.2)
6.
Personnel are not provided sufficient opportunity to physically acquaint
themselves with certain types of respiratory protective devices, particularly
self-contained breathing apparatus.
Inordinate reliance is placed upon
information provided by videotape with little effort directed to assure
that personnel are proficient in the use of the equipment.
(Section 3.2.1)
7.
The calibration program and procedures for portable survey instruments and
installed area monitors need to be revised to meet the recommendations of
ANSI N323, " Radiation Protection Instrumentation Test and Calibration."
Specifically, you need to develop operational source checks for portable
survey instruments and portable area monitors as recommended in ANSI
N323.
(Section 3.3)
!