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{{#Wiki_filter: | {{#Wiki_filter:~ ' | ||
_ _ . _ . . . . _ . . _ . . _ . . . - _ . _ . . . . . . | |||
. | |||
g a'a g uNiTt o statts | |||
. /- I NUCLEAR REGULATO9Y COMMISSION i | |||
' ' | |||
$ ReasoNev | |||
[k)Tf[.t | |||
* | |||
*, | |||
%, *' \*# | |||
**** | |||
/ | |||
/ 611 RY AN PLAZA f> RIVE, SUl?E 400 | |||
AR LINGTON, T E XAS 760118064 | |||
k | |||
I l | |||
February 3,1998 l | |||
&l | |||
EA 97-574 l | |||
EA 98-053 | |||
; | |||
lj | |||
C. Randy Hutchinson, Vice President - | |||
Operations | |||
Arkansas Nuclear One | |||
Entergy Operations, Inc. | |||
1448 S.R. 3S3 | |||
Russellville, Arkansas 72801-0967 | |||
SUBJECT: NRC INSPECTION REPORT 50-313/97-21; 50-368/97-21, NOTICE OF | |||
VIOLATION, AND EXERCISE OF ENFORCEMENT DISCRETION | |||
Dear Mr. Hutchinson: | |||
An NRC inspection was conducted October 27-31 and November 10-14,1997, at your Arkansas | |||
Nuclear One, Units 1 and 2, reactor facilities, and included offsite review of documents during | |||
the period November 17,1997, to January 5,1998. The enclosed report presents the scope | |||
and results of that inspection. | |||
This inspection focused on the review of previous NRC inspection findings. The report discusses | |||
several violations of NRC requirements. Examples of inadequate control of design calculations | |||
were identified in one of the violations. Separately, the items were of miriimal safety | |||
significance, but collectively, they indicated a potential problem with existing design calculations. | |||
We were encouraged that you had identified weaknesses in this area and were in the process of | |||
implementing comprehensive corrective actions as a result of a qua.lity assurance team audit in | |||
1996. These actions should iraprove the quality of future desir,n calculations. However, we | |||
; | |||
were concerned that your corrective actions did not appear to include a review to determine the i | |||
status of the technical content of your existing calculations of record. We considered this to be a j | |||
J | |||
weakness in your overah approach. f ; | |||
. | |||
l l | |||
Another violation involved a failure to include vendor-recommended emergency feedwater L | |||
system flow limits in an operating procedure. This violation was of concern because the failure H | |||
to install procedural limits resulted in at least two occasionc where the effects of the maximum ! | |||
flow limits being exceeded were not evaluated. Although this did not create an actual safety ( : | |||
concern in this instance, other failures to implement manufacturers' recommendations could | |||
i | |||
have safety implications. | |||
g | |||
11 | |||
o | |||
l' | |||
80114 900206 / jij | |||
ADOCK0500g3 | |||
- | |||
l | |||
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. | |||
D | |||
- | |||
, | |||
. | |||
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9 .. . | |||
- . - - . - - - - - - - - - - - - - . . - - - . - ~ - ~ . - | |||
S : | |||
L | |||
4 | |||
: EntErgy Operations, Inc. 2 - | |||
These violations are cited in the enciooed Notice of Violation (Notice) and the circumstances | |||
surrounding the violations are desenbod in detail in the enclosed report. Please note that you | |||
t | |||
are required to respond to this letter and should follow the instructions specified in the enclosed | |||
: Notice when preparing your response, The NRC will use your response, in part, to determine - | |||
l whether further enforcement action is t'ocessary to ensure compliance with regulatory | |||
* | |||
; . requirements. | |||
" | |||
Another identified problem involved five examples of the failure to property update the Final | |||
Safety Analysis Report with current design inSrmation. This problem would normally have been | |||
p - identiflod as a Severity Level IV violation and would have been cited because it was identified by | |||
_ | |||
- the NRC. However, the NRC is exercising discretion in accordance with Section Vll.B.3 of the , | |||
L Enforcement Policy and is not taking formal enforcsment action (EA 98-053). Specifically, the | |||
* | |||
l NRC recognizes that you have underway a comprehensive program to review and update your | |||
Final Safety Analysis Report. This program was described in your letter to the NRC dated | |||
May 7,1997. It is NRC's view, given the scope and schedule for completing this review, that | |||
j these discrt ies would likely have been identified through your final safety analysis review | |||
L Program. | |||
L | |||
: In addition, three apperent violations were identified (EA 97 574) and are being considered for | |||
, : escalated enforcement action in accordance with the " General Statement of Policy and | |||
i Procedure for NRC Enforcement Actions"(Enforcement Policy), NUREG-1600. These violations | |||
, | |||
are associated with events beginning Cecember 4,1996, when the pressure and vacuum rulief | |||
' | |||
'' | |||
valve on the borated water storage tank was removed for maintenance and testing. During the | |||
process of installing three temporary coverings on the tank flange, your activities. appeared to be | |||
in violation of three regulatory requirements; including 10 CFR 50.5g, for failure to adequat3ly | |||
, evaluate the safety concems related to the temporary coverings; 10 CFR Part 50, Aopendix B, | |||
l Criterion Ill, " Design Control," for failure to initiate the proper design control measura, and | |||
- | |||
--10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings," fo_r failure to | |||
_ | |||
follow the vacuum relief valve test procedure plant condition requirements. Accordingly, no | |||
n : Notice of Violation is presently being issued for these inspection findings. In addition, please be | |||
advised that the number and characterization of apparent violations described in the enclosed | |||
L inspection report may change as a result of further NRC review. | |||
L The NRC is concemed about the apparent violations, because of the potential safety | |||
! | |||
'' | |||
' implications associated with the installation of a Herculite plastic covering placed over the | |||
vacuum relief valve flange. The violations also suggest a breakdown of controls established to | |||
ensure that only appropriate maintenance is performed during power operations and that | |||
b : appropriate safety evaluations are performed when temporary alterations are installed. The ' | |||
L | |||
sequence of events began with the use of the borated water storage tank vacuum relief valve | |||
, | |||
: test procedure Juring power operations, although it was only intended to be used during | |||
* | |||
. refueling outage conditions, and later extended to the failure to use your temporary alteration | |||
' | |||
- | |||
program for a series of temporary coverings on the borated water storage tank vacuum relief | |||
: valve flange. As a result of bypassing the temporary alteration program, safety evaluations of | |||
' | |||
the temporary covering configurations were not performed as required. Our primary safety | |||
concern is focused on the 30-hour period during which a Hercuhte plastic bag was placed over | |||
l | |||
% , .__ .w_. . , _ | |||
. | |||
. | |||
Entergy Operations, Inc. -3- | |||
the valve flange, it appeared from your extensive testing and evaluation of this configuration | |||
(showing that the borated water storage tank was in a poten 'ly degraded state) that the initial | |||
use of engineering judgement, by itself, to consider this confi ation operable was | |||
inappropriate. | |||
A predecisional enforcement conference to discuss these apparent violations has been | |||
scheduled for February 20,1998. The decision to hold a predecisional enforcement conference | |||
does not mean that the NRC has determined that violations have occurred or that enforcement | |||
action will be taken. This conference is being held to obtain information to enable the NRC to | |||
make an enforcement decision, such as a common understanding of the facts, root causes, | |||
missed opportunities to identify the apparent violations sooner, corrective actions, significance of | |||
the issuas, and the need for lasting and effective corrective action in particular, we expect you | |||
to address the operability of the borated water storage tank during the 30-hour period that the | |||
Hercu"3 plastic bag was installed over the vacuum relief valve flange and the effect on operator | |||
actions during design basis events where the plastic bag could have affected borated water | |||
storage tank level indication. You have provided several evaluations and calculations | |||
supporting your operability determination, and we will confirm our understanding of your | |||
operability determination during the conference. | |||
In addition, this is an opportunity for you to point out any errors in our inspection report and for | |||
you to provide any information concerning your perspectives on 1) the severity of the violations, | |||
2) the application of the factors that the NRC considers when it determines the amount of a civil | |||
penalty that may be assessed in accordance with Section VI.B.2 of the Enforcement Policy, and | |||
3) any other application of the Enforcement Policy to this case, including the exercise of | |||
discretion in accordance with Section Vll. This conference will be open to public observation. | |||
You will be advised by separate correspondence of the results of our deliberations on this | |||
matter. No response regarding the apparent violations is required at this time. | |||
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its | |||
enclosure (s), and your response will be placed in the NRC Public Document Room (PDR). To | |||
the extent possible, your r_esponse should not include any personal privacy, proprietary, or | |||
safeguards information so that it can be placed in the PDR without redaction. | |||
l | |||
l Should you have any questions concerning this inspection, we will be pleased to discuss them | |||
l with you. | |||
Sincerely, | |||
\ | |||
i .g ^ 0 1 ) | |||
l h Arth r TI Howell111, Director | |||
j Division of Reactor Safety | |||
Docket Nos.: 50-313;50-368 | |||
License Nos.: DPR-51; NPF-6 | |||
. | |||
9 | |||
Entergy Operations, Inc. -4 | |||
Enclosures: | |||
1. Notice of Violation | |||
2. NRC Inspection Report | |||
50-313/97-21; 50-368/97-21 | |||
cc w/ enclosures: | |||
Executive Vice President , | |||
& Chief Operating Officer | |||
Entergy Operations, Inc. | |||
P.O. Box 31995 | |||
Jackson, Mississippi 39286-1995 | |||
Vice President | |||
Operations Support | |||
Entergy Operations, Inc. | |||
P.O. Box 31995 | |||
Jackson, Mississippi 39286 | |||
Manager, Washington Nuclear Operations | |||
ABB Comuustion Engineering Nuclear | |||
Power | |||
12300 Twinbrook Parkway, Suite 330 . | |||
Rockville, Maryland 20852 | |||
County Judge of Pope County | |||
Pope County Courthouse | |||
Russellville, Arkansas 72801 | |||
Winston & Strawn | |||
' | |||
1400 L Street, N.W. | |||
Washington, D.C. 20005-3502 | |||
David D. Snellings, Jr., Director | |||
Division of Radiation Control and | |||
Emergency Management | |||
Arkansas Department of Health | |||
4815 West Markham Street, Mail Slot 30 | |||
Little Rock, Arkansas 72205-3867 | |||
Manager | |||
Rockville Nuclear Licensing | |||
Framatome Technologies | |||
1700 Rockville Pike, Suite 525 | |||
Rockville, Maryland 20852 | |||
_ - _ _ ___ _ | |||
' | |||
l | |||
. | |||
Entergy Operations, Inc. S- | |||
t E-Mail report to T. Frye (TJF) ' | |||
E-Mail report to T. Hiltz (TGH) | |||
E-Mail report to NRR Event Tracking System (IPAS) | |||
E-Mail report to Document Control Desk (DOCDESK) | |||
bec to DCD GE01) | |||
bec distrib, by RIV: | |||
Regional Administrator ANO Resident inspector | |||
DRS Director DRS Deputy Director | |||
DRP Director MIS System | |||
Branch Chief (DRP/C) RIV File | |||
Project Engineer (DRP/C) DRS-PSB c | |||
Branch Chief (DRP/TSS) G. F. Sanborn, EO - | |||
W. L. Brown, RC J. Lieberman, OE (MS: 7-H5) | |||
OE:EAFile (MS 7-H5) | |||
DOCUMENT NAME: R:\_AN\AN721RP.MFR "N'9" | |||
g | |||
To receive copy of document, indicate in box: ac" = Copy without enclosures "E" = py ith enclosures "N" = No copy | |||
RIV:EB\SRE E RE _ E, RE E PM g C:DRS\EB _ E | |||
MRunyan:nh y PGoldbergMS RBywater @ GKatrna( TStetka @ | |||
t /2W98 // 98 / /98 / /98 l /30/98 | |||
maammmmmanumismaan a i = == == mammmmmmmmmmmii | |||
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EC'gilini' Gk8bfbqrMF ATHGb11IllJ | |||
] / $98 \ P;0/98 * 2./6 /98 I | |||
OFFICIAL RECORD COPY | |||
-- _ - _ _ _ _ _ _ _ _ _ _ _ | |||
.. | |||
>l | |||
lv | |||
. | |||
Entergy Operations, Inc. -5- | |||
E-Mail report to T. Frye (TJF) | |||
( E Mail report to T. Hiltz (TGH) | |||
' | |||
/t- E Mail report to NRR Event Tracking System (IPAS) | |||
E Mail report to Document Control Desk (DOCDESK) | |||
bec' ICD (IE01) | |||
bec distrib. by RIV: | |||
Regional Administrator ANO Resident inspector | |||
DRS Director DRS Deputy Director | |||
DRP Director MIS System | |||
s | |||
Branch Chief (DRP/C) RIV File | |||
Project Engineer (DRP/r) DRS-PSB | |||
Branch Chief (DRP/TSS) G. F. Sanborn, EO | |||
W. L. Brown, RC J. Lieberman, OE (MS: 7-H5) | |||
OE:EAFile (MS ~-HS, | |||
s. | |||
DOCUMENT NAME: R:\ AN\AN721RP.MFR "[S" | |||
g | |||
To receive copy of document, indicate in box:"C" a Copy without enclosures *E" = py ith enclosures "N" = No copy | |||
RIV:EB\SRE E RE l _ E, RE E PM g C:DRS\EB , E | |||
MRunyan:nh y PGoldbergW RBywater 9B GKalm# TStetka d)b | |||
t /2W98 / /M,/98 ~ / Q//98 / /98 ( /30/98 | |||
C:DFW)C, E ()h \s\ f })QO _ | |||
' | |||
EChljini' G W qr N V ATHEb11IllJ | |||
'/ _ /d98 \ 8 0/98 * 2./6 /98 | |||
OFFICIAL RECORD COPY | |||
W !$ ? M I1M w. | |||
_ -- | |||
.. | |||
3 | |||
l-J | |||
Entergy Operations, Inc. -5- | |||
E-Mail report to T. Fa/; 'TJF) | |||
E-Mail report to T. Hiltz (YGH) | |||
: E-Mail report to NRR Event Tracking System (IPAS) | |||
, | |||
E-Mail report to Document Contial Desk (DOCDESK) | |||
- bec to DCD (IE01) | |||
bec distrib. by RIV: | |||
Regional Administrator ANO Resident inspector | |||
DRS Director DRS Deputy Director | |||
DRP Director MIS System | |||
Branch Chief (DRP/C) RIV File | |||
Project Engineer (DRP/C) DRS-PSB | |||
Branch Chief (DRP/TSS) G. F. Sanborn,- EO | |||
W. L. Brown, RC J. Lieberman, OE (MS: 7-H5) | |||
OE:EA File (MS 7-H5) | |||
4 | |||
L | |||
i | |||
DOCUMei4l' NAME: R:\_AN\AN721RP.MFR gN"0" ,*h | |||
To receive copy of document. Indicate in box:"C" = Copy without enclosures "E" = py with enclosures "N" = No copy | |||
RIV.EB\SRE E RE E, RE E PM ,E# C:DRS\EB ..E | |||
MRunyan:nh y PGoldbergW RBywater 9B GKairr# TStetka d | |||
' | |||
ECgljinif Gk8bbqrnf ATHGellillJ | |||
[j _ /d98 \ 730/98 * 1 /6 /98 | |||
OFFICIAL RECORD COPY | |||
4 | |||
l | |||
' ' ' | |||
' ' | |||
. _ _ _ _ - _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ . - _ | |||
}} | }} |
Latest revision as of 23:14, 1 January 2021
ML20202E288 | |
Person / Time | |
---|---|
Site: | Arkansas Nuclear ![]() |
Issue date: | 02/06/1998 |
From: | Howell A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
To: | Hutchinson C ENTERGY OPERATIONS, INC. |
Shared Package | |
ML20202E294 | List: |
References | |
50-313-97-21, 50-368-97-21, EA-97-574, EA-98-053, EA-98-53, NUDOCS 9802180114 | |
Download: ML20202E288 (6) | |
See also: IR 05000313/1997021
Text
~ '
_ _ . _ . . . . _ . . _ . . _ . . . - _ . _ . . . . . .
.
g a'a g uNiTt o statts
. /- I NUCLEAR REGULATO9Y COMMISSION i
' '
$ ReasoNev
[k)Tf[.t
- ,
%, *' \*#
/
/ 611 RY AN PLAZA f> RIVE, SUl?E 400
AR LINGTON, T E XAS 760118064
k
I l
February 3,1998 l
&l
EA 97-574 l
EA 98-053
lj
C. Randy Hutchinson, Vice President -
Operations
Arkansas Nuclear One
Entergy Operations, Inc.
1448 S.R. 3S3
Russellville, Arkansas 72801-0967
SUBJECT: NRC INSPECTION REPORT 50-313/97-21; 50-368/97-21, NOTICE OF
VIOLATION, AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Mr. Hutchinson:
An NRC inspection was conducted October 27-31 and November 10-14,1997, at your Arkansas
Nuclear One, Units 1 and 2, reactor facilities, and included offsite review of documents during
the period November 17,1997, to January 5,1998. The enclosed report presents the scope
and results of that inspection.
This inspection focused on the review of previous NRC inspection findings. The report discusses
several violations of NRC requirements. Examples of inadequate control of design calculations
were identified in one of the violations. Separately, the items were of miriimal safety
significance, but collectively, they indicated a potential problem with existing design calculations.
We were encouraged that you had identified weaknesses in this area and were in the process of
implementing comprehensive corrective actions as a result of a qua.lity assurance team audit in
1996. These actions should iraprove the quality of future desir,n calculations. However, we
were concerned that your corrective actions did not appear to include a review to determine the i
status of the technical content of your existing calculations of record. We considered this to be a j
J
weakness in your overah approach. f ;
.
l l
Another violation involved a failure to include vendor-recommended emergency feedwater L
system flow limits in an operating procedure. This violation was of concern because the failure H
to install procedural limits resulted in at least two occasionc where the effects of the maximum !
flow limits being exceeded were not evaluated. Although this did not create an actual safety ( :
concern in this instance, other failures to implement manufacturers' recommendations could
i
have safety implications.
g
11
o
l'
80114 900206 / jij
ADOCK0500g3
-
l
eft
,
.
D
-
,
.
. ' ' -,+
-
e
'
Y
, . , _
- -
e u
_
9 .. .
- . - - . - - - - - - - - - - - - - . . - - - . - ~ - ~ . -
S :
L
4
- EntErgy Operations, Inc. 2 -
These violations are cited in the enciooed Notice of Violation (Notice) and the circumstances
surrounding the violations are desenbod in detail in the enclosed report. Please note that you
t
are required to respond to this letter and should follow the instructions specified in the enclosed
- Notice when preparing your response, The NRC will use your response, in part, to determine -
l whether further enforcement action is t'ocessary to ensure compliance with regulatory
- . requirements.
"
Another identified problem involved five examples of the failure to property update the Final
Safety Analysis Report with current design inSrmation. This problem would normally have been
p - identiflod as a Severity Level IV violation and would have been cited because it was identified by
_
- the NRC. However, the NRC is exercising discretion in accordance with Section Vll.B.3 of the ,
L Enforcement Policy and is not taking formal enforcsment action (EA 98-053). Specifically, the
l NRC recognizes that you have underway a comprehensive program to review and update your
Final Safety Analysis Report. This program was described in your letter to the NRC dated
May 7,1997. It is NRC's view, given the scope and schedule for completing this review, that
j these discrt ies would likely have been identified through your final safety analysis review
L Program.
L
- In addition, three apperent violations were identified (EA 97 574) and are being considered for
, : escalated enforcement action in accordance with the " General Statement of Policy and
i Procedure for NRC Enforcement Actions"(Enforcement Policy), NUREG-1600. These violations
,
are associated with events beginning Cecember 4,1996, when the pressure and vacuum rulief
'
valve on the borated water storage tank was removed for maintenance and testing. During the
process of installing three temporary coverings on the tank flange, your activities. appeared to be
in violation of three regulatory requirements; including 10 CFR 50.5g, for failure to adequat3ly
, evaluate the safety concems related to the temporary coverings; 10 CFR Part 50, Aopendix B,
l Criterion Ill, " Design Control," for failure to initiate the proper design control measura, and
-
--10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings," fo_r failure to
_
follow the vacuum relief valve test procedure plant condition requirements. Accordingly, no
n : Notice of Violation is presently being issued for these inspection findings. In addition, please be
advised that the number and characterization of apparent violations described in the enclosed
L inspection report may change as a result of further NRC review.
L The NRC is concemed about the apparent violations, because of the potential safety
!
' implications associated with the installation of a Herculite plastic covering placed over the
vacuum relief valve flange. The violations also suggest a breakdown of controls established to
ensure that only appropriate maintenance is performed during power operations and that
b : appropriate safety evaluations are performed when temporary alterations are installed. The '
L
sequence of events began with the use of the borated water storage tank vacuum relief valve
,
- test procedure Juring power operations, although it was only intended to be used during
. refueling outage conditions, and later extended to the failure to use your temporary alteration
'
-
program for a series of temporary coverings on the borated water storage tank vacuum relief
- valve flange. As a result of bypassing the temporary alteration program, safety evaluations of
'
the temporary covering configurations were not performed as required. Our primary safety
concern is focused on the 30-hour period during which a Hercuhte plastic bag was placed over
l
% , .__ .w_. . , _
.
.
Entergy Operations, Inc. -3-
the valve flange, it appeared from your extensive testing and evaluation of this configuration
(showing that the borated water storage tank was in a poten 'ly degraded state) that the initial
use of engineering judgement, by itself, to consider this confi ation operable was
inappropriate.
A predecisional enforcement conference to discuss these apparent violations has been
scheduled for February 20,1998. The decision to hold a predecisional enforcement conference
does not mean that the NRC has determined that violations have occurred or that enforcement
action will be taken. This conference is being held to obtain information to enable the NRC to
make an enforcement decision, such as a common understanding of the facts, root causes,
missed opportunities to identify the apparent violations sooner, corrective actions, significance of
the issuas, and the need for lasting and effective corrective action in particular, we expect you
to address the operability of the borated water storage tank during the 30-hour period that the
Hercu"3 plastic bag was installed over the vacuum relief valve flange and the effect on operator
actions during design basis events where the plastic bag could have affected borated water
storage tank level indication. You have provided several evaluations and calculations
supporting your operability determination, and we will confirm our understanding of your
operability determination during the conference.
In addition, this is an opportunity for you to point out any errors in our inspection report and for
you to provide any information concerning your perspectives on 1) the severity of the violations,
2) the application of the factors that the NRC considers when it determines the amount of a civil
penalty that may be assessed in accordance with Section VI.B.2 of the Enforcement Policy, and
3) any other application of the Enforcement Policy to this case, including the exercise of
discretion in accordance with Section Vll. This conference will be open to public observation.
You will be advised by separate correspondence of the results of our deliberations on this
matter. No response regarding the apparent violations is required at this time.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its
enclosure (s), and your response will be placed in the NRC Public Document Room (PDR). To
the extent possible, your r_esponse should not include any personal privacy, proprietary, or
safeguards information so that it can be placed in the PDR without redaction.
l
l Should you have any questions concerning this inspection, we will be pleased to discuss them
l with you.
Sincerely,
\
i .g ^ 0 1 )
l h Arth r TI Howell111, Director
j Division of Reactor Safety
Docket Nos.: 50-313;50-368
.
9
Entergy Operations, Inc. -4
Enclosures:
1. Notice of Violation
2. NRC Inspection Report
50-313/97-21; 50-368/97-21
cc w/ enclosures:
Executive Vice President ,
& Chief Operating Officer
Entergy Operations, Inc.
P.O. Box 31995
Jackson, Mississippi 39286-1995
Vice President
Operations Support
Entergy Operations, Inc.
P.O. Box 31995
Jackson, Mississippi 39286
Manager, Washington Nuclear Operations
ABB Comuustion Engineering Nuclear
Power
12300 Twinbrook Parkway, Suite 330 .
Rockville, Maryland 20852
County Judge of Pope County
Pope County Courthouse
Russellville, Arkansas 72801
Winston & Strawn
'
1400 L Street, N.W.
Washington, D.C. 20005-3502
David D. Snellings, Jr., Director
Division of Radiation Control and
Emergency Management
4815 West Markham Street, Mail Slot 30
Little Rock, Arkansas 72205-3867
Manager
Rockville Nuclear Licensing
Framatome Technologies
1700 Rockville Pike, Suite 525
Rockville, Maryland 20852
_ - _ _ ___ _
'
l
.
Entergy Operations, Inc. S-
t E-Mail report to T. Frye (TJF) '
E-Mail report to T. Hiltz (TGH)
E-Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK)
bec to DCD GE01)
bec distrib, by RIV:
Regional Administrator ANO Resident inspector
DRS Director DRS Deputy Director
DRP Director MIS System
Branch Chief (DRP/C) RIV File
Project Engineer (DRP/C) DRS-PSB c
Branch Chief (DRP/TSS) G. F. Sanborn, EO -
W. L. Brown, RC J. Lieberman, OE (MS: 7-H5)
OE:EAFile (MS 7-H5)
DOCUMENT NAME: R:\_AN\AN721RP.MFR "N'9"
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To receive copy of document, indicate in box: ac" = Copy without enclosures "E" = py ith enclosures "N" = No copy
RIV:EB\SRE E RE _ E, RE E PM g C:DRS\EB _ E
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Entergy Operations, Inc. -5-
E-Mail report to T. Frye (TJF)
( E Mail report to T. Hiltz (TGH)
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E Mail report to Document Control Desk (DOCDESK)
bec' ICD (IE01)
bec distrib. by RIV:
Regional Administrator ANO Resident inspector
DRS Director DRS Deputy Director
DRP Director MIS System
s
Branch Chief (DRP/C) RIV File
Project Engineer (DRP/r) DRS-PSB
Branch Chief (DRP/TSS) G. F. Sanborn, EO
W. L. Brown, RC J. Lieberman, OE (MS: 7-H5)
OE:EAFile (MS ~-HS,
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DOCUMENT NAME: R:\ AN\AN721RP.MFR "[S"
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To receive copy of document, indicate in box:"C" a Copy without enclosures *E" = py ith enclosures "N" = No copy
RIV:EB\SRE E RE l _ E, RE E PM g C:DRS\EB , E
MRunyan:nh y PGoldbergW RBywater 9B GKalm# TStetka d)b
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OFFICIAL RECORD COPY
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Entergy Operations, Inc. -5-
E-Mail report to T. Fa/; 'TJF)
E-Mail report to T. Hiltz (YGH)
- E-Mail report to NRR Event Tracking System (IPAS)
,
E-Mail report to Document Contial Desk (DOCDESK)
- bec to DCD (IE01)
bec distrib. by RIV:
Regional Administrator ANO Resident inspector
DRS Director DRS Deputy Director
DRP Director MIS System
Branch Chief (DRP/C) RIV File
Project Engineer (DRP/C) DRS-PSB
Branch Chief (DRP/TSS) G. F. Sanborn,- EO
W. L. Brown, RC J. Lieberman, OE (MS: 7-H5)
OE:EA File (MS 7-H5)
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DOCUMei4l' NAME: R:\_AN\AN721RP.MFR gN"0" ,*h
To receive copy of document. Indicate in box:"C" = Copy without enclosures "E" = py with enclosures "N" = No copy
RIV.EB\SRE E RE E, RE E PM ,E# C:DRS\EB ..E
MRunyan:nh y PGoldbergW RBywater 9B GKairr# TStetka d
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ECgljinif Gk8bbqrnf ATHGellillJ
[j _ /d98 \ 730/98 * 1 /6 /98
OFFICIAL RECORD COPY
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