IR 05000346/1977005
| ML19329B583 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/08/1977 |
| From: | Greer R, Januska A, Pogliaro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19329B448 | List: |
| References | |
| 50-346-77-05, 50-346-77-5, NUDOCS 8002050718 | |
| Download: ML19329B583 (10) | |
Text
-
..
-
.
-
_ _ _ _ -
-
&
._
.
.
_-
_. _ _. _.
-. o:
r
\\
UNITED STATES NUCLEAR REGULATORY C0}c4ISSION OFFICE OF INSPECTION AND ENFORCDIENT
REGION III
Report of Emergency Planning - Environmental Monitoring-
,
Coufircatory Measurements Inspection IE Inspec. tion Report No. 0.30-346/77-05
_
Licensee: Toledo Edison Company Edison Plaza 300 Madison Avenue
.
Toledo, OH 43652
<
_
Davis-Besse Nuclear Power Station License No. CPPR-80 Unit 1 Category:
B Oak Harbor, OH Type of Licensee:
PWR (BW) 2772 MWt
'l Type of Inspection:
Routine, Announced Dates of Inspection:
February 7-11, 1977 d. ) Anuskakk
-
g!7!? 7 _
A. G.
I Principal Inspector:
I (Date)
R.Qh
.
3/?/71 Accompanying Irispector:
R. J. Greer
'(Date)
Other Accompan g Person el: None c < o/-
,
-
.
,
Reviewed By:
. A. Paglyo, Chief
[ [7 (date)
Environmental and Special Projects Section
I (
)
.
v 80020501 %.
'
..
.
-
-
.
.
s
__-
.. _ _ _...
~
f
,
.
.
-
.
SI)MMARYOFFINDINGS
'
Inspection Summary Inspection on February 7-11 (Unit 1, 77-05): Reviewed (1) the pre-operational radiological environmental monitoring program, (2) the preoperational quality control and capability test of the confirmatory measurements program pnd (3) open items identified during an emergency planning inspection.y Enforcement Items None.
.
Licensee Action on Previously Identified Enforcement Items
"
_
No previously identified enforcemer.t items within the scope of this inspection.
Other Significant Items
,
A.
Systems and Components
,
The licensee has not completed testing of his public address sys-tem.
(Paragraph 3.c, Report Details)
J B.
Facility Items (Plans and Procedures)
Lnplementing procedures contained in the Emergency Plan and Implementing Procedures Manual have not been revised.
(Para-
-
graph 3.e, Report Details)
C.
Managerial Items None.
D.
Deviations
'
None.
E.
Status of Previously Reported Unresolved Items l
None.
?fanagement Interview
.
{
The following items were discussed on February 11 with Mr. Evans and l
members of his staff:
!
i l
/ ~s 1/ IE Inspection Report No. C50-346/76-22.
b
.
-2-
..
.
. _ _ _ _,
,,
, _
_
-. -
~
- - -
---
--
-- _
_
.. _ _
.._ _
-
is
_,
._
_
.
-
-
A.
The scope of the inspection.
(Paragraph 2, Report Details)
,
B.
Open items to be completed prior to various licensing states.
(Paragraphs 3 through 5, Report Details)
C.
Preoperational radiological environmental monitoring program.
(Paragraph 6, Report _ Details)
- -
.... _. _ _ _
D.
Preoperational quality control and capability test of the confirm-atory measurements program.
(Paragraph 7, Report Details)
J
<:'
-
w S
e e
b
I
i x
- 3-
'
~
e e
_, _. _. _.... _.
_,
.
__
_ - -.,, _. _. _ _, _ _, _..
.. _ _ _.. _
_f,,1_._._--,,.,.--..-_---_._--,___--.'.E
_.
.
_. _ _
-
_ _.. _. _
_ - -
,
,
_
-
,
'
N
,
)
, REPORT DETAILS d
1.
Persons Contacted J. Evans, Station Superintendent W. Green, Station Technical Assistant D. Briden, Chemist and Health Physicist J. Hickey, Training Supervisor B. Geddes, Radiochemistry and Health Physics Specialist R. Smith, Senior Computer Programmer J. Humphreys, Senior Assistant Engineer D. Jazwiecki, Chem and Rad Tester J. Tapley, Chemistry and Health Physics Foreman J. Buck, Operations Quality Assurance Supervisor
.
2.
General
<
_
The inspection included an examination of the licensee's environ-mental monitoring, emergency planning and analytical measurement-confirmatory measurement programs. The emergency planning portion of the inspection was an examina3pon of the open items identified during a previous inspection.-
The environmental monitoring portion was the final preoperational inspection and included an examination of the radiological monitoring program
,
results for the period January 1976 through June 1976 and a
'
,
discussion of how the preoperational environmental monitoring program relates to the program to be defined in the technical specifications. The analytical measurement-confirmatory measure-ment inspection consisted of an examination of the licensee's program to control quality of analytical measurements and of a test of the licensee's measurements of a simulated liquid waste
.
sample, a stack sampler cuarcoal cartridge containing " mock I-131,"
a simulated stack sampler particulate filter and a simulated gas standard.
,
3.
Open Items (Fuel Loading)
The following open items, identified du Ang a previous inspection 3/
and during this inspection require cotgletion prior to fi.el load-ing:
i i
a.
Letters of Agreement A recently received letter of agreement shall be ettered into Appendix C of the Emergency Plan and a list detailitg the letters of agreement updated.
,
2/ Ibid.
3/ Ibid.
.
f-4-
)
.
l l
,
,
.
.
.-
.;
..
..
..
..-.
. - - _. -. _ _.
-. _ _.. _
,
.
-
,
.
.
\\
b.
Facilities Equipment s.
Periodic testing proce'dures for supplied breathing air and those communications not related to security shall be devel-oped and implemented.
The approved periodic testing procedure for the emergency plan supply cabinet equipment shall be implemented in order to assure that emergency related equipment complies with the inventory list contained as an appendix to this procedure.
c.
Public Address System The station public address system testing shall be completed in order to determine the adequacy of the quantity and quality
of the system coverage to assure that personnel can be made
,
aware of emergency conditions.
~
d.
Training Documentation of the completion of general orientation train-ing for all station personnel, contractor personnel and consultant support groups stationed on the site shall be available for review.
e.
Laplementing Procedures Revisions to Administrative Procedures, Emergency Procedures
and Health Physics Procedures, discussed with a licensee representative during a previous inspection,-j shall be made.
f.
Emergency Classification Response
Clarification of the response to a fire alarm and/or the use of an additional emergency classification for local emergencies, where limited response is required, shall be made in the emergency plan and the FSAR. Retraining of personnel for the required response shall be perforred.
4.
Open Items (Criticality)
The'following open item discussed with licensee representatives shall be completed prior to criticality:
!
4/ lbid.
-5-
-
v i
!
.
l
.
.-
,
,
.
.
,,
. _. _
'
--
-
-
L
-. _.. _.. _
.
.
.-
,0
Public Address System s _,
Six additional speakers shall be installed in containment pur-suant to an issued Startup Field Report.
5.
Open Items (Power Escalation)
The following open iccms shall be completed prior to power escalation:
a.
Supplied Air Cascade System A permanent supplied air cascade charging system shall be installed.
.
<
A Isolation Procedure olation Emergency Plan Implementing Procedure to cope
_
- . a weather conditions which require personnel to remain at the ststion for undetermined periods shall be developed.
This procedure shall also address provisions for transporta-tion of emergency personnel to the station when needed during these periods.
c.
Implementing Procedures
'
s_,/
Pursuant to a telephone conversation with a licensee repre-sentative on February 23, 1977, it is our understanding that the following will be studied for incorporation into the Emergency Plan Lnplementing Procedures. These topics relate to those areas where there is a high degree of inaccessibility:
.
Evacuation of personnel to minimize exposure to a hazard
.
Personnel accountability to assist the person in charge
.
of emergency response actions to account for missing persons Reentry into previously evacuated areas for the purposes
.
of saving lives, and search and rescue of missing and injured persons.
Safety equipment to be worn depending on j
areas or conditions shall be addressed.
,
,
6.
Environmental Monitoring Program i
The radiological monitoring program results for the period January'1976 through June 1976 were examined. The inspectors
.w
-
\\
'
r3
'
^ ' - 6-s l
i G
-
.
O h
&# "
... _.
.
_ _.,. _,,.
-.. - -
_
.
-
noted the preoperational monitoring program?is being modified I
as recommended changes to the program are received from the
\\~
!
Staff. The current program is essentially the same as will be used during the operational phase as specified in the techni-cal specifications.
The inspectors revigved the response to deviations reported in a previous inspection-and have no further questic,ns regarding the items reported.
Air sampling sites were visited and it was determined that the licensee had taken corrective action to eliminate leakage poten-tial and that procedure ST 5099.03 incorporates a field leak test.
The inspectors stressed the importance of performing the field leak test on a prescribed frequency.
A comparative study between the environmental contractor's TLD c
results, another contractor's TLD system results and TLD results from the system being processed onsite is continuing.
The
-
results of this study will be examined during a subsequent inspec-tion.
The meteorological program remains under contract to the Nuclear Utility Services who maintain the tower, perform calibrations on instrumentation and are responsible for reduction of data.
Surveillance Test Procedures (ST's) are being developed for daily operational operability checks and semiannual calibration as cur-
- \\' 'j rent STs do not comply with technical specifications requirements.
NUS provides an annual report.
7.
Confirmatorv Measurements The licensee's quality control program for analytical measure-ments for the confirmatory measurements program was examined.
Program documentation appaars to be adequate to assure accurate and consistent measuremenet of radioactivity in liquid and gaseous effluents.
The licensee was requested to analyze a simulated liquid waste
'
sample, a stack sampler charcoal cartridge containing " cock I-131" a simulated stack sampler particulate filter, and a simulated gas standard. The results were compared against the NRC's referenced laboratory results (Table I) and tested against the criteria used by the Office of Inspection and Enforcement for comparing analytical measurements (attach =ent 1).
The comparison demonstrates the licensee's capability for measur-ing radioactivity in liquid and gaseous effluents.
Attachments:
1.
Criteria for Comparing j
Analytical Measurements 2.
Table I
-
,s (,)
5/ IE Inspection Report No. 050-346/76-05.
-7-
.
-
O
,
e e
, _.
-, - -
-
-
-
-
-
1 1 121 1 01 1 11 1 1
-
-
00000 0 'i 0 0 0 0 0 0
- S
- + * + +
4 + + 4 + + + +
+
- E EEEFE FEEEEEEE F
-
-
-
7354 9 75067233
<
'
-
.
.
-
1 4442 9681 1334
-
-
-
-
.
-
1 1 1 1 1 1 1 s1 01 C0
.
EO 00090 00i00000
cI
- - - - -
- + + - + - + +
+
ST 5FEFE FEEFEEEE E
t A 22465 04150801
-
l ER
... e
..
.
C 99738 91191911
I L
001 1 1 1 310
0
- L 11000 9000
0
- + + + +
+ + + +
+
+
+
I C
EEEEE EEEE E
E E
I
- P 37645 0323040,3
-
.
.
e
..
-
9721 1 1 115020R
-
-
T
- F 0001 0 0091
0
N
- U 00009 0000
1
H E
M
- L
+ + + + *
- + + -
-
+
D M
A
- A EEEEE EEEE E
E E
I E
R
- V 1 4452 49690507
S C
G
-
..
..
.
s S
R O
- Z 1 2943 76660502
O R
I b
M F
PE9 l
S1
-
T O'
E SS F
C T EF
-
c D
NDO
-
Y N
E
- R r
A M S F.
- O I
o EI E
- R 00000 00G.00000
T H
RVT ER c
E a
O7 R EE 0000 01700010
1:
L L
S0A S
(j B
U
A U
N A
A G
C E : D F
33444 32323333
T r
E
'I Y
CT 99901 97779009
H P
T?
I L
- - - - -
- - - - - - - -
-
S YI LU EEEEE EEEEEEEE E
- S 12083 5 37.'.71
P t'
R LFl
- E
..
.
A I
OI i
E T CT
- R 1 1239 31 21 1 442
L F
A A C
O MFP l
F D
t N
E I
F
-
55665 54534445
C F
-
00000 00000000
S I
N
- R
- - - - -
- - - - - - - -
-
v F
O
- 0 EC FFE FFEFEFEE E
U F
C
-
P. 0 0 0 0 00020320
I O
- P
- E 7361 4 4231 111 5
<,
L S
I 33443 33323333
I
- T 11000 99011900
- L
- - - - -
- - - - - - - -
-
- U EEEEE EEEEEEEE E
- S 23741 93497) 04
- F
...
..
.
.
.
T
- 9 1 1 241 3121 1442
N E
H E
E FN P
467
O 43450 904330
S TRO T
11 566 3891 1 16A
T NGS O
T L
EA I S
ESVMO 1 RRESSOE A
UTM R
I CCHZC SSCCCCB B
SNEEA
EEELP
'
D
0 RMP3M E
E E
EGI O
-
lA SC E
K K
K l
L I
I I
rrSS P
P P
P E bI OO M
S S
S TA0PN A
= =
S F
L C
T8 0PH y
.
- i i
,
- _ _ _
. _ _ _.
_-
..
...
-..
. -...
-
.
.
,.
v)
, ATTACINENT 1
CRITERIA TOR COMPARING ANALYTIL L MEASUREMENTS
.
This attachment provides criteria for comparing results of capao'lity tests and verification measurements.
The criteria are based on an
-
empirical relationship which combines prior experience and the accuracy
.
needs of this program.
In these criteria, the judgment limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated one sigma uncertainty. As that ratio, referred to in this program as
" Resolution", increases, the acceptability of a licensee's measurement
- .
should be more selective. Conversely, poorer agreement should be con-
~
sidered acceptable as che resolution decreases.
The values in the ratio
criteria may be rounded to fewer significant figures to maintain statistical consistency with the number of significant figures reported
'
by the NRC Reference Laboratory, unless such rounding will result in a
~
narrowed category of acceptance.
The acceptance category reported will be the narrowest into which the ratio fits for the resolution being used.
RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE Possible Possible f%)
Agreement Agreement "A" Agreeable "E"
'
\\
/
' ' ' '
<3
.
No Comparison No Comparison No Comparison
>3 and <4 d.4 2.5 0. 3
- 3.0 No Comparison
-
3"4 and <8 0.5 2.0 0.4
- 2.5 0.3
- 3.0
-
78 and <16 0.6 1.67 0.5
-
2.0 0.4
- 2.5
-
'
T16 and <51 0.75 - 1.33 0.6
- 1.67 0.5
-
2.0 T51 and <200 0.80 - 1.25 0.75 - 1.33 0.6
- 1.67 1.33 I_200 0.85 - 1.18 0.80 - 1.25 0.75
-
"A" criteria are applied to the following analyses:
Gamma spectrometry, where principal gamma energy used for identifi-cation is greater than 250 kev.
I
'
Tritium analyses of liquid samples.
"B" criteria are applied to the following analyses:
Gamma spectrometry, where principal gamma energy used for identifi-cation is less than 250 kev.
l
j
,
Sr,-89 and Sr-90 determinations.
Gross beta, where samples are counted on the same date using the
/'~'N same reference nuclide.
'
t
.
.
.
_
._ ___--
-_. -.
--
.
-
-
,
-
-
\\s fs-q do [v) try x
.
.
,
-
'
'
L
-
-
\\
..
i,.
-
-
.
.
.
.
.
.
.
.
.
,
.
.
.-
.
.
.
.
.
,
,I l
e
.
.
.
.
.
.
.
-
.
.
.
,
,
,
.
.
.-
.
.
,-
.
.
,
,
.
.
.
,
,
-
.
..
.
'
.
.
NO SI d i d'.03 ON=H
'
'
<
-
.
.
.
-
'
~
ll43H 3330 t 37ElSS0d=d
-
.
'
1N3H338SfSIC=0'
.
'
IN3u3399t=v
..
',
..
-
.
.tSilaSau iS31 1
,
...
.
-.
-
,
.
.
,
.
,,
.
J.
.
.
=
.
.
.
-
- .
.
t
J
.
y lo+ 9 7'l oot3 o *I 00+9 o'o oot3 0'o o 'o 90+9 s'C 50+3tl 4 0 t 9 S * V.
80 tr i
{~
s.
to 9 9 *f 8 0 -7 V'b 00,3 E*9 0 0 4-7 o 'l o 'o 90t5 S * /
5%9 o'l 9 0 t-3 9 *l f
p "$
'
y r
y Io+91*/
oot9 o'I o ot3 o *0 ' oota o*Q o'o 10 t 3 tr' I Vo+4 o'h
- )ot-7 tr'I l
bLL
-
\\f so+ 9 E'l l o-9 5'b oo m ary lo--J f.'9 o'o
. sot 9 S *5 tr o +-J O T fo+ 9 0'tr 9SE
,
._
V r o+ 93*/
10- 4. E 'h 00 + 3 b ' ~l Oat-] O'l o'o 90+9 L'C S 0 * -7 o ' t'
- 1os 9 5 no jfr(
-
,
Io rki'l 10-9 O'8 I0+:) O'E 'oOt~3a E o'9
.50+ 9 z'I
$ro+9 o r So+=13*l goE t
'
, 4.9 ?C Id5 b l
,
y lo+ 9 l'Z.
80- 9 0*t.
no t.3 0'V 004 3 Y 9 0 *o
.50*39'l tr o 4 3 l *l, ' 5 0 + i1 C * C IW
S3d 011tB 13d 3DIt A 7 800 J3 17033d o01d3 170S 3H yqj A*> W9tts 3*IdH ds
!
3 3 S N 3 3 I 'l : 7 S H 2 --- ---- ---
3 3Sil 3 3 I l---
ISH------
i,
- '
"
-
'
'
.
t
,'
.
.
.
,
'
.
9 1. 6 1. 3 0 J31dt00 E JHl. 303 sSS30 SIAf0 AlllI3e3 I
-
.
M f dSOM d Silt 3H3 JOS e 3H A.131dHdI3H03
'.,
l
'
'
'
-
-
.,
.
.
-
.
.
'
-
1N 3tl 3310 3tt 3 CN f siO I13 3d s.41 30 331330
'
l I
'
-
.,
.
,
-
.
,
N01ESIhh03.A301f70933 a f 3730:1 S 0
-
.
>
.
.
.
-
,
j (9..f 007 )
I 315 1
.
'
'
.
..
. *