ML20138R555
| ML20138R555 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/23/1985 |
| From: | Brownlee V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| Shared Package | |
| ML20138R556 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8512310363 | |
| Download: ML20138R555 (7) | |
See also: IR 05000369/1985029
Text
f
--
-
4
~
.
_
.
DEC 2 31985
/ Duke Power Company
ATTN: Mr. H. B. Tucker, Vice President
Nuclear Production Department
422 South Church Street
Charlotte, NC 28242
Gentlemen:
SUBJECT: MCGUIRE EMERGENCY RESPONSE FACILITY APPRAISAL
The NRC-is conducting special appraisals of emergency response facilities (ERFs)
at all operating nuclear power reactors to verify that licensees have completed
these facilities and have met ti respective requirements defined in Supplement 1
to NUREG-0737. The objectives of these appraisals are to determine that the ERFs
are capable of performing those functions needed to assist licensees in taking
adequate protective measures in the event of a radiological emergency, and to
assure that requirements in Supplement 1 to NUREG-0737 have been satisfied. We
will use the findings from these appraisals as a basis not only for requesting
individual licensee action to correct deficiencies, but also for effecting
improvements in NRC requirements and guidance.
During the period of September 3-11, 1985, the NRC conducted a special appraisal
of the .ERFs at the McGuire Nuclear Station. This appraisal was performed using
Draft Revision 5 of IE Inspection Procedure 82212. Areas examined during this
appraisal are identified in the. enclosed report (50-369/85-29, 50-370/85-28).
Within these areas, the appraisal team reviewed selected procedures and records,
inspected the facil'. ties, equipment and supplies, observed simulated use of the
equipment and supplies, and interviewed personnel.
Within the scope of this appraisal, no violations or deviations were identified.
The findings of this appraisal indicate that certain weaknesses exist. These are
discussed in Appendix A, Appraisal Weaknesses. The appraisal also indicates that
several areas were found to be incomplete, and could not be evaluated during the
appraisal.
These findings are listed in. Appendix B, Appraisal Open Items.
Finally, there are areas ~ which should be evaluated and considered for
improvement. These areas are listed in Appendix C, Appraisal Improvement Items.
We recognize that explicit regulatory requirements pertaining to improvement
items may not currently exist.
Notwithstanding the latter, please advise us
within 45 days of the date of this letter of action you plan _to take, showing the
estimated date of completion with regard to the findings identified in the
Appendices.
With regard to the Appraisal open items, we are particularly interested in-your
proposed reconfiguration of the McGuire Technical -Support Center (TSC) and m
completion for construction of your Crisis Management Center (CMC).
Your
continued progress regarding these facilities will be reviewed in future
inspections.
ffh
(
'\\
y
0
.r6 35
..
.-
- - - .,
.,
-
-
-. -, -
- . - . - , . - , , - -
f
.
V'
..
,
Duke Power Company-
2
4
i
i
I
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures will
l
be placed in the NRC Public Document Room, unless you notify this office, by
-
'
telephone, within ten days of the date of this letter and submit written
application to withhold information contained therein within thirty days of the
date of this letter.
Such application must be consistent with the requirements
'
of 2.790(b)(1). If we do not hear from you in this regard within the specified
periods roted above, the report will be placed in the Public Document Room.
Should you have any questions concerning this letter, please contact us.
j
Sincerely,
i
j
Virgil L. Brownlee, Chief
'
Reactor Projects Branch 2
Division of Reactor Projects
-
Enclosures:
}
1.
Appendix A, ERF Weaknesses
2.
Appendix B, ERF Open Items
'
3.
Appendix C, ERF Improvement
,
Items
-
!
4.
Inspection Report Nos.:
50-369/85-29 and 50-370/85-28
g,c w/encls:
v'T. L. McConnell, Station Manager
gccw/encls:
vu. Hood, NRR
State of South Carolina
Document Control Desk
i
State of North Carolina
J RC Resid,
Inspector
i
i
y
RII
RII
RII 4'
RII
h
W
l
.
HDa[nceVD
,
ACunningham:ht
TRDecker
DMCollins
JPS ohr
12//j,/85
12// 7/85
12A 7/85
12T/85
12/g)/85
i
f
I
e
b
'
4
~
s.
l
l
APPENDIX A
APPRAISAL WEAKNESSES
The following items indicated areas of weakness in the Emergency Response
Program:
1.
Meteorological data processed through the Operator Aid Computer had not been
validated (1.2.4.2).
(50-369/85-29-17,50-370/85-28-17)
2.
There was no procedure for use of the OAC for calculating dose assessment
(1.2.4.2).
(50-369/85-29-25,50-370/85-28-25)
6
_ _ _ -
f
,
,
APPENDIX B
APPRAISAL OPEN ITEMS
The following items were incomplete and will be reviewed in future inspections:
Definition of the ' xtent of planned spatial and configuration changes to the
1.
e
Technical Support Center and projected completion of same (1.1.1.1).
(50-369/85-29-01, 50-370/85-28-01)
2.
Implementation of Regulatory Guide 1.97, monitoring with any exceptions
confirmed by NRR (1.2.1.3).
(50-369/85-29-13,50-370/85-28-13)
3.
Submittal to NRC of complete documentation (description of the technical
basis) for the puff-advection atmospheric dispersion model and a complete
description of the upgraded meteorological measurements program (1.2.4.2).
(50-369/85-29-21, 50-370/85-28 1)
4
Submittal to NRC of anpropriate documentation required to complete
evaluation of the Class A Model computerized dose assessment (1.2.4.2).
(50-369/85-29-23, 50-370/85-28-23)
5.
Completioa of construction and establishment of ooerational readiness of the
consoiidated Crisis Management Center.
(3.1.1.2).
(50-369/85-29-33,
50-370/85-28-33)
6.
Establishment of dedicated communication lines between the CMC and VAX
computers, and use of dial-up as backup (3.2.3).
(50-369/85-29-36,
50-370/85-28-36)
i
i
-
.
. ,.
.-
-
--
-
,.
-
I
.
>
APPENDiv C
APPRAISAL IMPROVEMENT ITEMS
The following items should be evaluated and considered far improvement:
1.
Expansion of the Technical Support Center (TSC) dose assessment. area to
approximately three times its present size or approximately 300 souare feet
to accommodate the expected staff (1.1.1.1).
(IFI 50-369/85-29-02,
50-370/85-28-02)
2.
Sizing the Emergency Director's of fice - Room 913, to accommodate the
personnel
expected
to
staff
the
general
area
(1.1.1.1).
-(IFI 50-360/85-29-03, 50-370/85-28-03)
3.
Increasing the computer room by approximately two feet to provide additional
walking and maintenance space.
(1.1.1.1).
(IFI 50-369/85-29-04, 50-370/85-28-04)
4.
Providing areas of the TSC with acditional writing surfaces, dccument
lay-down
areas,
and
chairs
(1.1.1.1).
(IFI
50-369/85-25-05,
50-370/85-24-05)
5.
Main _taining radiation monitors in the TSC in an operating mode on a
continuous basis (1.1.1.5).
(IFI 50-369/85-29-06, 50-370/85-28-06)
6.
Using a different technique to alert control room operators that core
temperature
is
outsice
of
the
expected
range
(1.1.1.6).
(IFI 50-369/85-29-07. 50-370/85-28-07)
7.
Validating Goerator Aid Computer (OAC) data through 'use of appropriate
software algorithms.
(1.1.1.6).
(IFI 50-369/85-29-08, 50-370/85-28-08)
8.
Automating the presen
manual transfer of cata from the OAC to VAX
computers, providing tne VAX with continuous access to data, at or near
real-time
(1.1.1.6).
(IFI 50-369/85-29-09, 50-370/85-28-09)
9.
Providing graphic trending capability in the TSC using a sampling frequency
of _ trended data adequate to detect -significant changes (1.1.1.6).
(IFI
-
50-369/85-29-10, 50-370/85-28-10)
10. Changing the OAC terminal keyboards,
positioned in a nearly vertical
orientation, to an ergonomically correct position to minimize mis-keying
_
(1.1.1.6).
(IFI-50-369/85-29-11, 50-370/85-28-11)
11.
Providing procedures or instructions developed to describe tne method for
obtaining monitoring data from the OAC - in the TSC (1.1.2.1).
(IFI
50-369/85-29-12,50-370/85-28-12)
,
'
l
s.
, . .
. - - . ~
..
.--
-.-
{:
,
s
Appendix C
2
12. Acquiring a dedicated line if trend plotting will be relied on to support
critical
plant
safety
analysis
(1.2.3.3).
(IFI
50-369/85-29-14,
50-370/85-28-14)
13. Evaluating locations of the meteorological towers to determine the quality
of data, and the effects of the nearby warehouse buildings, proximity of
major plant structures. and uneven terrain in ' the area on such data
(1.2.4 2).
(IFI 50-369/85-23-15, 50-370/85-28-15)
14.
Incorporating the meteorological measurements program, as updated in 1983,
into the FSAR (1.2.4.2).
(IFI-50-369/85-29-16, 50-370/85-28-16).
15.
Evaluating the representativeness of meteorological data from the National
Weather Service (NWS) station at Charlotte and/or Catawba for real-time
conditions at McGuire or installating of backup or redundant onsite
meteorological measurements, including separate power supolies, cabling, and
recorders (1.2.4.2).
(IFI 50-369/85-29-18, 50-370/85-28-18)
16. Revising procedures which provide for use of meteorological data to reflect
the hierarchy for data substitution, and specifying averaging period (e.g.,
15
minutes)
and
valid
time
of
the
observations
(1.2.4.2).
(IFI 50-369/85-29-19, 50-370/85-28-19)
17. Specifying averaging period and valid time of observation for digital
displays of meteorological cata (e.g., via the OAC or the summary sheet
provided through the VAX computer) (1.2.4.2).
(IFI 50-369/85-29-20,
50-370/85-28-20)
18.
Identifying of regional and forecast n'eteorological information to be
provided on reouest by the NWS 5tation in Charlotte
(1.2.4.2.).
(IFI 50-369/85-29-22, 50-370/85-28-22)
19. Modifying the Dose Assessment Class A Model to include ingestion pathway
,
dose calculations and making available to the NRC or submitting to the NRC
documentation
related
thereto.
(1.2.4.2.B).
(IFI 50-229/85-29-24,
50-370/85-28-24).
20. Evaluating the Nuclear-23 method to assure that both whole body and thyroid
doses are appropriately considered in protective action recommendations
(1.2.4.2.8). (IFI 50-369/85-29-26, 50-370/85-28-26)
21. Making the " Nuclear-23" available for periodic use during exercises to
assure control room personnel proficiency in use of the program.
Licensee
representatives stated that use of " Nuclear-23" is prevented by interlock or
relay
until
such
time
that
an
emergency
occurs
(1.2.4.2.B).
(IFI 50-369/85-29-27, 50-370/85-28-27)
22.
Providing an uninterrupted power supply for all necessary components of the
,
data acquisition and display system,
e.g.,
the VAX computer, the dose
assessment terminal,
the Mohawk data
link,
etc.
(1.2.6.2).
(IFI
50-369/85-29-28, 50-370/85-28-28)
.
-
-
!
~
..
i
Appendix C
3
23.
Verifying that the Crisis Management Center (CMC) does not exercise priority
to the VAX thus requiring the Station to conduct manual calculation of dose
assessments.
(1.2.7.1).
(IFI 50-369/85-29-29, 50-370/85-28-29)
24.
Inserting into procedures the actual levels at which emergency action is
required for event classification in lieu of referencing " Exceeds Technical
Specifications"
or
" Exceeds
10
x
Tech
Specs"
(1.2.7.2).
(IFI
50-369/85-29-30, 50-370/85-28-30)
25. Providing emergency lighting in the OSC (2.1.1.3) . (IFI 50-369/85-29-31,
50-370/85-28-31)
26.
Improving the quality of drawings to include phone locations, phone numbers,
air supply headers, etc. (2.1.1.4).
(IFI 50-369/85-29-32, 50-370/85-28-32)
27.
Providing site emergency planning zone maps for the McGuire Station
(3.1.1.6).
(IFI 50-369/85-29-34, 50-370/85-28-34)
28.
Providing the CMC with a continuous data stream at, or near, real time
(3.1.1.6).
(IFI 50-369/85-29-35, 50-370/85-28-35)
29.
Standaroi:ing McGuire Station data sets to include all Regulatory Guide 1.97
parameters
in
the
standard format
(3.7.2).
(IFI 50-369/85-29-37,
50-370/85-28 37)
20.
Improving the method of data transmission to the CMC such that data is
real-time,
or
near
real-time data
(3.7.2).
(IFI 50-369/85-29-38,
50-370/85-29-38)
31.
Reviewing Enclosure 5.5 to procedure HP/0/B/1009/13 regarding source term-
" corresponds to" to ensure that its intended purpose is understood
(3.3.3.3).
(IFI 50-369/85-29-39, 50-370/85-28-39)
1