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{{#Wiki_filter: | {{#Wiki_filter:{ | ||
" | |||
, gc.e oto pre 6 4 t u a e n i ca | |||
, -C ,% NUCLEAR REGULATORY COMMISSION | |||
,, | |||
REGION IV | |||
o e 611 RYAN PLAZA ORIVE.SulTE 400 | |||
i, ' | |||
8 AR LING TON, TEMAS 76011-8064 | |||
**"' sgp - 4 E | |||
Docket No, STN 50-482 | |||
License No, NPF-42 | |||
Wolf Creek Nuclear Operating Corporation | |||
ATTN: Bart D. Withers | |||
President and Chief Executive Officer | |||
P.O. Box 411 | |||
Burlington, Kansas 66839 | |||
Gentlemen: | |||
SUBJECT: NRC INSPECTION REPORT N0. 50-482/92-13 | |||
Thank you for your_ letter of August 21, 1992, in response to the emergency | |||
preparedness weaknesses identified in NRC Inspection Report 50-482/92-13 datea | |||
July 20, 1992. -We have examined your reply and find - it responsive to the | |||
concerns raised in our inspection report. We will review the implementation of | |||
your corrective actions during a future inspection. | |||
Sincerely, | |||
.I | |||
dr. Bill Beach, Director | |||
Divisien of Reactor Projects | |||
. | |||
.cc: | |||
Wolf Creek Nuclear Operating Corp. | |||
ATTN: Otto Maynard, Director | |||
Plant Operations | |||
- | |||
P.O. Box 411 | |||
Burlington, Kansas 66830 | |||
Shaw, Pittman, Potts.& Trowbridge | |||
_ | |||
ATTN: Jay Silberg, Esq. | |||
2300 M Street, NW | |||
Washington, D.C. 20037 | |||
920913o113 920904 | |||
- ], hDR ADOCK 05000482- - I | |||
PDR g- ; | |||
_ _ _ - _ _ | |||
. . . . | |||
. . | |||
, . . - . . . . . . . . | |||
. | |||
. | |||
Wolf Creek Nuclear -2- | |||
Operating Corporation | |||
Public Service Commission | |||
ATTN: C. John Renken | |||
Policy & Federal Department | |||
P.O. Box 360 | |||
Jefferson City, Missouri 65102 | |||
U.S. Nuclear Regulatory Commission | |||
ATTN: Regional Administrator, Region 111 | |||
799 Roosevelt Road | |||
Glen Ellyn, Illinois 60137 | |||
Wolf Creek Nuclear Operating Corp. ~~ | |||
ATTN: Steven G. Wideman | |||
Supervisor Licensing | |||
P 0. Box 411 | |||
Burlington, Kansas 66839 | |||
Kansas Corporation Commission | |||
ATTH: Robert Elliot, Chief Engineer | |||
Utilities Division | |||
1500 SW Arrowhead Rd. | |||
Topeka, Kansas 66604-4027 | |||
Office of the Governor | |||
State of Kansas | |||
Topeka, Kansas 66612 | |||
c | |||
Attorney General | |||
1st Floor - The Statehouse | |||
C | |||
Topeka, Kansas 66612 | |||
, | |||
Thuirman, Cof fey. County Commission | |||
Coffey tounty Courthouse- | |||
Burlington,. Kansas 66839-1798 | |||
Kansas Department of Health | |||
and Environment | |||
Bureau of Air Quality 3 P.adiaticn | |||
Control | |||
ATIN: Gerald Allen, Public | |||
Health Physicist | |||
Division'of Environment | |||
Forbes Field Building 3?.1 | |||
-Topeka, Kansas 66620 | |||
Kansas Department of Health and Environment | |||
ATTN: Robert Eye, General Counsel | |||
LS00, 9th Floor | |||
900 SW Jackson | |||
Topeka, Kansas 66612 | |||
- - - - _ _ _ - - _ _ _ _ _ - _ _ _ - _ _ _-- | |||
.. . ... - -- . - . . . . | |||
- . .. . . -. .. ..._ -.. ..- | |||
_ _ . | |||
:- - | |||
> | |||
:' . '- | |||
. | |||
- Wolf Creek Nuclear - - | |||
3- | |||
. Operating = Corporation . | |||
Program Manager- | |||
- FEMA Region 7 | |||
911 Walnut Street, Room-200. | |||
Kansas City,-Missouri 64106 | |||
: | |||
$ | |||
s | |||
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4 | |||
l | |||
l | |||
Wolf Creek Nuclear -4- i | |||
Operating Corporation | |||
l | |||
DMB - Original (IE35) : | |||
bec w/ copy of licensee letter: ! | |||
J. L. Milhoan, RA | |||
L. J. Callan DRSS | |||
J.-P. Jaudon, DRSS i | |||
B. Hurray, flPS | |||
D. B. Spitzberg, FIPS | |||
Resident inspector, OPS - Wolf Creek | |||
A. Howell, Section Chief. DRP/0 | |||
Lisa Shea, RM/Alf (MS 4503) ' | |||
Section Chief, (Rlli, DRP/3C) | |||
Callaway, Rlli - | |||
FIPS file : | |||
RIV file | |||
DRP i | |||
M. Satorius, Project Engineer, DRP/D ! | |||
' | |||
DRS | |||
MIS System | |||
RSTS Operator- i | |||
R. Erickson, NRR (MS 9 HIS) | |||
C. A_. Hackney, SLO | |||
, | |||
-m | |||
- - M "O | |||
RIV: QPS M- til a S V. @ n D8FiSS 0:%P _ | |||
DBSpitzberynh Bf *: | |||
;M LJCallan- ABbdch , | |||
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d/3//92 8/.'r/97 / | |||
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. | |||
- | |||
y- r rr w m, . . , . . - r ,,,mv | |||
.. _ ._ - - . .- _ . ..-.... . _ _ -. . _ _ _ . _ _ _ _ . _ _ _ _ . _ . _ . _ . - _ . _ . _ _ . _ _ _ _ . . . _ . . | |||
l | |||
- | |||
t | |||
l | |||
l | |||
l | |||
Wolf Creek Nuc' ear -4- I | |||
Operating Corporation l | |||
DMB - Original (1E35) | |||
bec w/ copy of licensee letter: ' | |||
J. L. Milh an, RA | |||
L. J. Lallan, DRSS | |||
J. P. Jaudon, DRSS | |||
B. Murray, flPS | |||
D. B. Spitzberg, flPS | |||
Realdent inspector, OPS - Wolf Creek | |||
A. Howell, Section Chief, DRP/D | |||
Lisa Shea, RM/ALF (MS 4503) | |||
Section Chief, (Rlli, DRP/3C) | |||
Callaway, Rlli | |||
flPS file | |||
RIV file | |||
DRP | |||
M. Satorius, Project Engineer, DRP/D 7 | |||
' | |||
DRS * | |||
MIS System- | |||
RSTS Operator | |||
R. Erickson, NRR (MS 91115) | |||
C. A. Hackney, SLO i | |||
. | |||
P | |||
w.' | |||
'RIV:FIPS 770c C:FIPSVAF n DADRSS' D: $P | |||
DBSpitzberg:nh BMurrayOf[lJCalian ABdch , | |||
l 8 8//92 8/f//92 <1 /*A_ /92_ i /L /92 , | |||
. | |||
D | |||
we 4w-- +ws- >-+r'g- t- , +-%e,- e- ,- - -- y ~- rwy e, * ..m-- ,m,- w .,w, :r-..%-s---- 4--e=- -- ---- t- 4- -- e -?--- | |||
_. . _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ - _ _ _ _ - _ - _ _ _ _ - . _ _ _ _ _ _ _ _ | |||
t * | |||
. | |||
. | |||
o | |||
W@ NUCLEAR LF CREEK OPERATING COR | |||
August 21, 1992 | |||
Bart D wit %rs | |||
nwoent ano WM 92-0135 | |||
cmet t muiwe om c, | |||
U. 3. Nuc?. car Regulatory cornission | |||
ATTH: Document Control Denk | |||
hall Station F1-137 | |||
washington, D. C. 20555 | |||
Reference: Letter dated July 20, 1992 from A. B. Be a c' (C to | |||
B. L. Withers, WCNOC | |||
Subjecti Docket No. 50-482: Response to weaknesses . '3P 3-01, | |||
482/9213-02 and 482/9213-03 | |||
Gentlemen: | |||
This letter prov. des Wolf Creek Nuclear Operating Corporation's response to | |||
Weaknesses 482/9213-01, 482/9213-02 and 482/9213-03 as a result of an | |||
inspection of the operational status of the emergency preparedness progren and | |||
dose calculation and assessment. Weakness 482/9213-01 involved emergency | |||
classification of accident conditions by operating crews. Weaknesa 9213-02 | |||
consisted of several exemples of errors and umissions in notification messages | |||
and in the formulation and issaance of protective action recommendations. | |||
Weakness 482/9213-03 identified the failure of the dose assessment procedure | |||
to previde guidance on obtaining accurate integrated dose projections based on | |||
prior release conditions. | |||
If you have any questions concerning this matter, please contact me or | |||
Mr. Kevin J. Moles of my staff. | |||
Very truly yours, | |||
J _Af | |||
Bart D. Withers | |||
President and | |||
Chief Executive officer | |||
DDW/jra | |||
Attachment | |||
cc: A. T. howell (NRC), w/a | |||
J. L. Milhoan (URC), w/a | |||
G. A. Pick (NRC), w/a | |||
W.D. Reckley (NRC), w/a | |||
D. B. Spitsberg (N RC) , w/a | |||
( | |||
" | |||
[hh ' | |||
~ | |||
!' PO Box 411 i Burbngton, KS 66839 Phone (316) 2%BB31 | |||
An Eow Oppetsndy Encover M F HCWT | |||
. . | |||
--_______ _ ________ - -___ - - __ -____-__-_ -____-__ _- - | |||
- - . - - - - . - . + - . _ _ . . - . - . ~ . ~ - - - - - - - --._- | |||
. | |||
. | |||
. | |||
. .. | |||
Attachment to WM 92-0135 | |||
Page 1 of 3 , | |||
l | |||
. | |||
' | |||
Weakness (482/9213-01)! Eminenev ClatalligAlion of Accident conditions. | |||
l | |||
' | |||
The inspector ebserved and evaluated the ability of each crew to detect, | |||
assess, and classify abnormal and accident conditions. Two out of three crews | |||
f ailed to recognire that emergency action level initiating conditions had been | |||
met for a scenario event. Consequently, the two shift supervisors did not | |||
declare a Site Area Emergency when they became aware of plant conditions | |||
indicating a breach of, or challenge to the integrity of two fission product | |||
barriers. Specifically, fuel cladding was challenged as the result of an | |||
anticipated transient without trip, and containment was breached because of a | |||
steam generator atmospheric relief valve that was stuck open and unisolable. ; | |||
These conditions met the emergency action level for a Site Area Emergency | |||
contained in EPP 01-2.1, " Emergency Classification." | |||
Analysist | |||
During inter *.4ews with operators it was evident that Emergency Plan Procedure, | |||
EPP 01-2.1, " Emergency Classification" phraseology lead to the weakness. The | |||
wording in Step 3.6.3 of procedure EPP 01-2.1 can lead to confusion in | |||
clasAlfying a containment breach when coupled with another fission product | |||
barrier breach, | |||
fdgnpetive Actionst | |||
Proceauce EPP 01-2.1 will be revised to clarify Step 3.6.3. A course titled, | |||
" Emergency Plan Practical" will be retaught during the current operator | |||
requalification' training cycle. Classifications made dt. ring the | |||
requalifis ation training by each operating crew will also be reviewed. | |||
t | |||
p.gte When Corrective Action Will Be Comoleted: | |||
Procedure EPP 01-2.1 will be revised by October 30, 1992 and issued within 30 | |||
days of NRC approval. The current operator requalification training cycle | |||
will be completed September 11, 1992. Review and critique of classifications | |||
made by operating crews are conducted after_each session on the simulator and | |||
will also be completed by September 11, 1992. | |||
Weakness (482/9213-02): Notifications and Protective Action Recommendations | |||
Made to Offsite Authorities | |||
Errors and omissions in notification messages and in the formulation and | |||
issuance of protective action recommendations were identified during the | |||
walkthroughs as evidenced by several observations. | |||
. . - . - - . . , . _ . _ - . - . - . . . - | |||
.-. - - , - - - - - . - - . - - | |||
- - _ _ _ _ _ _ _ _ _ - - _ - _ . _ _ - _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ __ | |||
. | |||
* | |||
. | |||
. | |||
Attachment to WH 92-0135 | |||
Page 2 of 3 | |||
2kDE.1.YJiit: | |||
only the classification section of Patt A f An the Immediate Notification Form | |||
is reviewed during Opetator Requalification Examinations . Tnerefore, only | |||
this section has been emphasized during training. This has resulted in | |||
inexperience in completing the entire notification form. | |||
g,orrectivtletiong | |||
Simulator training scenarios will be reviewed to ensure they contain | |||
sufficient detail for the instructor to evaluate if the Immediate Notification | |||
Form has been completed correctly. During all future simulator sessions, with | |||
the exception of practice examinations and requalification examinations, all | |||
of Part A of the Immediate Notification Form will be completed by the Shift | |||
Supervisar. The form will be evaluated with the Shift Supervisor as part of | |||
the crit Aq.e session. Annually, Emergency Plan personnel or Training | |||
personnel 3111 monitor each crew for proper form completion. | |||
Date When Corrective Action 2 Will Be Completed: | |||
In order to allow several opportunities for each crew to be on the simulator, | |||
corrective actions will be completed by March 31, 1993. | |||
Weakness (482/9213-03): Tailure of the Dose Assessment Procedure to Providg | |||
GuidaDCm htAining Q Accurate Intearated Dose | |||
Proiecticns Unsed on Prior Release Conditions | |||
one crew was unable to obtain an accurate estimate of the offsite radiological | |||
consequences of the release, because the dose assessment procedure did net | |||
provide guidance for initiating a dose projection after initial release | |||
conditions 1:ad changed significantly. In this case, the chemictry technician | |||
had been dispatched from the centrol room by the emergency director prior to | |||
the release to obtain steam tenerator samples. When he returned, the release | |||
had been in progress for approximately 20 minutes. The chemistry technician | |||
then promptly calculated the initial post-release dose projections in | |||
accordance with EPP 01-7.2 but used real time flow data from the release | |||
source. At the time, however, the flow had decreased about 70 percent since | |||
the onset of the release because of depressurization. Therefore, this dose | |||
projection did not provide an accurate assessment of the consequences of the | |||
release from the time it began, | |||
l | |||
. _ _ .._.._..___.__.._-_.._._____.___________m_ . _ _ _ | |||
* | |||
.. | |||
9 | |||
, , | |||
4 | |||
' | |||
Attachment to WM 92-0135 | |||
P3ge 3 of 3 | |||
6a011Elit t . | |||
A review of this weakness determined that procedure EPP 01-7.2, "Cottputer Dose | |||
calculations," does not provide guidance to obtain the highest flow or release | |||
rates from the beginning of a release. | |||
Correct ive_.ACLA2aA 1 | |||
Procedure EPP 01-7.2 will be revised to provide more complete guidance. | |||
Training for personnel performir.g dose calculations will be provided following | |||
issuance of procedure EPP 01-7.2. All other dose assessment personnel will | |||
complete required reading on procedure EPP 01-7.2. Chemistry personnel | |||
continue to train on the simulator with the operating crews to provide them , | |||
with control room experience. | |||
Date When Corrective Acti2D8 Willle CCerittadt | |||
Procedure EPP 01-7.2 will be revised and issued by October 30, 1992. | |||
R6 quired reading will be completed within 60 days of issuance of the required | |||
reading notice. Training for personnel performing dose assessment will be | |||
completed by March 31, 1993, | |||
i | |||
, | |||
k | |||
h- | |||
l | |||
l | |||
t | |||
I- | |||
. . . . . - . , . . ..,- _ ,. ., - . , . _ - - . . | |||
}} | }} |
Latest revision as of 18:45, 23 July 2020
ML20127D652 | |
Person / Time | |
---|---|
Site: | Wolf Creek ![]() |
Issue date: | 09/04/1992 |
From: | Beach A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
To: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
References | |
NUDOCS 9209150113 | |
Download: ML20127D652 (5) | |
See also: IR 05000482/1992013
Text
{
"
, gc.e oto pre 6 4 t u a e n i ca
, -C ,% NUCLEAR REGULATORY COMMISSION
,,
REGION IV
o e 611 RYAN PLAZA ORIVE.SulTE 400
i, '
8 AR LING TON, TEMAS 76011-8064
- "' sgp - 4 E
Docket No, STN 50-482
License No, NPF-42
Wolf Creek Nuclear Operating Corporation
ATTN: Bart D. Withers
President and Chief Executive Officer
P.O. Box 411
Burlington, Kansas 66839
Gentlemen:
SUBJECT: NRC INSPECTION REPORT N0. 50-482/92-13
Thank you for your_ letter of August 21, 1992, in response to the emergency
preparedness weaknesses identified in NRC Inspection Report 50-482/92-13 datea
July 20, 1992. -We have examined your reply and find - it responsive to the
concerns raised in our inspection report. We will review the implementation of
your corrective actions during a future inspection.
Sincerely,
.I
dr. Bill Beach, Director
Divisien of Reactor Projects
.
.cc:
Wolf Creek Nuclear Operating Corp.
ATTN: Otto Maynard, Director
Plant Operations
-
P.O. Box 411
Burlington, Kansas 66830
Shaw, Pittman, Potts.& Trowbridge
_
ATTN: Jay Silberg, Esq.
2300 M Street, NW
Washington, D.C. 20037
920913o113 920904
- ], hDR ADOCK 05000482- - I
PDR g- ;
_ _ _ - _ _
. . . .
. .
, . . - . . . . . . . .
.
.
Wolf Creek Nuclear -2-
Operating Corporation
Public Service Commission
ATTN: C. John Renken
Policy & Federal Department
P.O. Box 360
Jefferson City, Missouri 65102
U.S. Nuclear Regulatory Commission
ATTN: Regional Administrator, Region 111
799 Roosevelt Road
Glen Ellyn, Illinois 60137
Wolf Creek Nuclear Operating Corp. ~~
ATTN: Steven G. Wideman
Supervisor Licensing
P 0. Box 411
Burlington, Kansas 66839
Kansas Corporation Commission
ATTH: Robert Elliot, Chief Engineer
Utilities Division
1500 SW Arrowhead Rd.
Topeka, Kansas 66604-4027
Office of the Governor
State of Kansas
Topeka, Kansas 66612
c
Attorney General
1st Floor - The Statehouse
C
Topeka, Kansas 66612
,
Thuirman, Cof fey. County Commission
Coffey tounty Courthouse-
Burlington,. Kansas 66839-1798
Kansas Department of Health
and Environment
Bureau of Air Quality 3 P.adiaticn
Control
ATIN: Gerald Allen, Public
Health Physicist
Division'of Environment
Forbes Field Building 3?.1
-Topeka, Kansas 66620
Kansas Department of Health and Environment
ATTN: Robert Eye, General Counsel
LS00, 9th Floor
900 SW Jackson
Topeka, Kansas 66612
- - - - _ _ _ - - _ _ _ _ _ - _ _ _ - _ _ _--
.. . ... - -- . - . . . .
- . .. . . -. .. ..._ -.. ..-
_ _ .
- - -
>
- ' . '-
.
- Wolf Creek Nuclear - -
3-
. Operating = Corporation .
Program Manager-
- FEMA Region 7
911 Walnut Street, Room-200.
Kansas City,-Missouri 64106
$
s
w
-
,q ---y % -
, ,er-p - y- -g
.. .... . .-.
,
4
4
l
l
Wolf Creek Nuclear -4- i
Operating Corporation
l
DMB - Original (IE35) :
bec w/ copy of licensee letter: !
J. L. Milhoan, RA
L. J. Callan DRSS
J.-P. Jaudon, DRSS i
B. Hurray, flPS
D. B. Spitzberg, FIPS
Resident inspector, OPS - Wolf Creek
A. Howell, Section Chief. DRP/0
Lisa Shea, RM/Alf (MS 4503) '
Section Chief, (Rlli, DRP/3C)
Callaway, Rlli -
FIPS file :
RIV file
DRP i
M. Satorius, Project Engineer, DRP/D !
'
MIS System
RSTS Operator- i
R. Erickson, NRR (MS 9 HIS)
C. A_. Hackney, SLO
,
-m
- - M "O
RIV: QPS M- til a S V. @ n D8FiSS 0:%P _
DBSpitzberynh Bf *:
- M LJCallan- ABbdch ,
'
d/3//92 8/.'r/97 /
-J ( /4\/92 i i/Z./?2 l
.
-
y- r rr w m, . . , . . - r ,,,mv
.. _ ._ - - . .- _ . ..-.... . _ _ -. . _ _ _ . _ _ _ _ . _ _ _ _ . _ . _ . _ . - _ . _ . _ _ . _ _ _ _ . . . _ . .
l
-
t
l
l
l
Wolf Creek Nuc' ear -4- I
Operating Corporation l
DMB - Original (1E35)
bec w/ copy of licensee letter: '
J. L. Milh an, RA
L. J. Lallan, DRSS
J. P. Jaudon, DRSS
B. Murray, flPS
D. B. Spitzberg, flPS
Realdent inspector, OPS - Wolf Creek
A. Howell, Section Chief, DRP/D
Lisa Shea, RM/ALF (MS 4503)
Section Chief, (Rlli, DRP/3C)
Callaway, Rlli
flPS file
RIV file
M. Satorius, Project Engineer, DRP/D 7
'
DRS *
MIS System-
RSTS Operator
R. Erickson, NRR (MS 91115)
C. A. Hackney, SLO i
.
P
w.'
'RIV:FIPS 770c C:FIPSVAF n DADRSS' D: $P
DBSpitzberg:nh BMurrayOf[lJCalian ABdch ,
l 8 8//92 8/f//92 <1 /*A_ /92_ i /L /92 ,
.
D
we 4w-- +ws- >-+r'g- t- , +-%e,- e- ,- - -- y ~- rwy e, * ..m-- ,m,- w .,w, :r-..%-s---- 4--e=- -- ---- t- 4- -- e -?---
_. . _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ - _ _ _ _ - _ - _ _ _ _ - . _ _ _ _ _ _ _ _
t *
.
.
o
W@ NUCLEAR LF CREEK OPERATING COR
August 21, 1992
Bart D wit %rs
nwoent ano WM 92-0135
cmet t muiwe om c,
U. 3. Nuc?. car Regulatory cornission
ATTH: Document Control Denk
hall Station F1-137
washington, D. C. 20555
Reference: Letter dated July 20, 1992 from A. B. Be a c' (C to
B. L. Withers, WCNOC
Subjecti Docket No. 50-482: Response to weaknesses . '3P 3-01,
482/9213-02 and 482/9213-03
Gentlemen:
This letter prov. des Wolf Creek Nuclear Operating Corporation's response to
Weaknesses 482/9213-01, 482/9213-02 and 482/9213-03 as a result of an
inspection of the operational status of the emergency preparedness progren and
dose calculation and assessment. Weakness 482/9213-01 involved emergency
classification of accident conditions by operating crews. Weaknesa 9213-02
consisted of several exemples of errors and umissions in notification messages
and in the formulation and issaance of protective action recommendations.
Weakness 482/9213-03 identified the failure of the dose assessment procedure
to previde guidance on obtaining accurate integrated dose projections based on
prior release conditions.
If you have any questions concerning this matter, please contact me or
Mr. Kevin J. Moles of my staff.
Very truly yours,
J _Af
Bart D. Withers
President and
Chief Executive officer
DDW/jra
Attachment
cc: A. T. howell (NRC), w/a
J. L. Milhoan (URC), w/a
G. A. Pick (NRC), w/a
W.D. Reckley (NRC), w/a
D. B. Spitsberg (N RC) , w/a
(
"
[hh '
~
!' PO Box 411 i Burbngton, KS 66839 Phone (316) 2%BB31
An Eow Oppetsndy Encover M F HCWT
. .
--_______ _ ________ - -___ - - __ -____-__-_ -____-__ _- -
- - . - - - - . - . + - . _ _ . . - . - . ~ . ~ - - - - - - - --._-
.
.
.
. ..
Attachment to WM 92-0135
Page 1 of 3 ,
l
.
'
Weakness (482/9213-01)! Eminenev ClatalligAlion of Accident conditions.
l
'
The inspector ebserved and evaluated the ability of each crew to detect,
assess, and classify abnormal and accident conditions. Two out of three crews
f ailed to recognire that emergency action level initiating conditions had been
met for a scenario event. Consequently, the two shift supervisors did not
declare a Site Area Emergency when they became aware of plant conditions
indicating a breach of, or challenge to the integrity of two fission product
barriers. Specifically, fuel cladding was challenged as the result of an
anticipated transient without trip, and containment was breached because of a
steam generator atmospheric relief valve that was stuck open and unisolable. ;
These conditions met the emergency action level for a Site Area Emergency
contained in EPP 01-2.1, " Emergency Classification."
Analysist
During inter *.4ews with operators it was evident that Emergency Plan Procedure,
EPP 01-2.1, " Emergency Classification" phraseology lead to the weakness. The
wording in Step 3.6.3 of procedure EPP 01-2.1 can lead to confusion in
clasAlfying a containment breach when coupled with another fission product
barrier breach,
fdgnpetive Actionst
Proceauce EPP 01-2.1 will be revised to clarify Step 3.6.3. A course titled,
" Emergency Plan Practical" will be retaught during the current operator
requalification' training cycle. Classifications made dt. ring the
requalifis ation training by each operating crew will also be reviewed.
t
p.gte When Corrective Action Will Be Comoleted:
Procedure EPP 01-2.1 will be revised by October 30, 1992 and issued within 30
days of NRC approval. The current operator requalification training cycle
will be completed September 11, 1992. Review and critique of classifications
made by operating crews are conducted after_each session on the simulator and
will also be completed by September 11, 1992.
Weakness (482/9213-02): Notifications and Protective Action Recommendations
Made to Offsite Authorities
Errors and omissions in notification messages and in the formulation and
issuance of protective action recommendations were identified during the
walkthroughs as evidenced by several observations.
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Attachment to WH 92-0135
Page 2 of 3
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only the classification section of Patt A f An the Immediate Notification Form
is reviewed during Opetator Requalification Examinations . Tnerefore, only
this section has been emphasized during training. This has resulted in
inexperience in completing the entire notification form.
g,orrectivtletiong
Simulator training scenarios will be reviewed to ensure they contain
sufficient detail for the instructor to evaluate if the Immediate Notification
Form has been completed correctly. During all future simulator sessions, with
the exception of practice examinations and requalification examinations, all
of Part A of the Immediate Notification Form will be completed by the Shift
Supervisar. The form will be evaluated with the Shift Supervisor as part of
the crit Aq.e session. Annually, Emergency Plan personnel or Training
personnel 3111 monitor each crew for proper form completion.
Date When Corrective Action 2 Will Be Completed:
In order to allow several opportunities for each crew to be on the simulator,
corrective actions will be completed by March 31, 1993.
Weakness (482/9213-03): Tailure of the Dose Assessment Procedure to Providg
GuidaDCm htAining Q Accurate Intearated Dose
Proiecticns Unsed on Prior Release Conditions
one crew was unable to obtain an accurate estimate of the offsite radiological
consequences of the release, because the dose assessment procedure did net
provide guidance for initiating a dose projection after initial release
conditions 1:ad changed significantly. In this case, the chemictry technician
had been dispatched from the centrol room by the emergency director prior to
the release to obtain steam tenerator samples. When he returned, the release
had been in progress for approximately 20 minutes. The chemistry technician
then promptly calculated the initial post-release dose projections in
accordance with EPP 01-7.2 but used real time flow data from the release
source. At the time, however, the flow had decreased about 70 percent since
the onset of the release because of depressurization. Therefore, this dose
projection did not provide an accurate assessment of the consequences of the
release from the time it began,
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Attachment to WM 92-0135
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A review of this weakness determined that procedure EPP 01-7.2, "Cottputer Dose
calculations," does not provide guidance to obtain the highest flow or release
rates from the beginning of a release.
Correct ive_.ACLA2aA 1
Procedure EPP 01-7.2 will be revised to provide more complete guidance.
Training for personnel performir.g dose calculations will be provided following
issuance of procedure EPP 01-7.2. All other dose assessment personnel will
complete required reading on procedure EPP 01-7.2. Chemistry personnel
continue to train on the simulator with the operating crews to provide them ,
with control room experience.
Date When Corrective Acti2D8 Willle CCerittadt
Procedure EPP 01-7.2 will be revised and issued by October 30, 1992.
R6 quired reading will be completed within 60 days of issuance of the required
reading notice. Training for personnel performing dose assessment will be
completed by March 31, 1993,
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