ML20203K280
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| ML20203K280 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/25/1998 |
| From: | Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| References | |
| 50-313-97-21, 50-368-97-21, EA-97-574, NUDOCS 9803050039 | |
| Download: ML20203K280 (69) | |
See also: IR 05000313/1997021
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*** February 25, 1998
C. Randy Hutchinso.1, Vice
President Operations
. Arkansas Nuclear One
Entergy Operations, Inc.
1448 S.R. 333
Russe:iville, Arkansas 728010967
SUBJECT: PREDECISIONAL ENFORCEMENT CONFERENCE (EA 97 574) TO DISCUSS
NRC INSPECTION REPORT 50-313/97 21; 50-368/97-21
Dear Mr. Hutchinson:
This refers to the meeting conducted in the Region IV office on February 20,1998. This
meeting involved discussion of three apparent violations identified in NRC Inspection
Report 50 313/97 21; 50-368/97 21. Enclosure 1 is the attendance list for this meeting and
Enclosure 2 contains the licensee's presentation.
During the meeting, your staff discussed the causes for and corrective actions taken or planned
to be taken regarding the failure to properly control activities related to the remnval of the
borated water storage tank vacuum relief valve for testing on December 4,1996. Your staff also
presented the engineering bases for concluding that the borated water storage tank was
operable at all times during the sequence of events relevant to these issues.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of
Federal Regulations, a copy of this letter will be piaced in the NRC's Pchlic Document Room.
Should you have any questions conceming this matter, we will be pleased to discuss them with
you.
Sincerely,
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Thomas F. Stetka, Acting Chief
Engineering Branch
Division of Reactor Safety
Enclosures:
1. Attendance List
2. Licensee Presei.'.ation /
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Executive Vice President -
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Entergy Operations, Inc.
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P.O. Box 31995
Jackson, Mississippi 39286-1995
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Vice President'
Operations Support '
Entergy Operations, Inc.
P.O. Box 31995
Jackson, Mississippi 30286
Manager, Washington Nuclear Operations
ABB Combustion Engineering Nuclear
Power
12300 Twinbrook Parkway, Suite 330
'Rockvil'e, Maryland 20852
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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
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ENCLOSURE 1
ATTENDANCE LIST
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PREDECISIONAL ENFORCEMENT CONFERENCE ATTENDANCE
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LICENSEE / FACILITY Entergy Operations, inc1 Arkansas Nuclear One, Unit 1
DATEmME February 20,1998/1:00 p.m.
CONFERENCE NRC Region IV
LOCATION Arlington, Texas
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, EA NUMBER 97 574
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LICENSEE / FACILITY Ente;gy Operations, Inc / Arkansas Nuclear One Unit 1
DATE/ TIME February 20,1998! 1:00 p.m.
CONFERENCE NRC Region IV Office
LOCATION Arlington, Texas
EA NUMBER 97 574
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,
AGENDA ^
Management Overview RANDY HUTCHINSON
Vice President Operations, A?O
Introduction DWIGHT MIMS
'
Director, Licensing
-
Chronology CHARLIE ZIMMERMAN l
Plant Manager, Unit 1
! Operability Assessment JERRY HOWELL
Senior Engineer, MCS
l Temporary Alteration Program JOE KOWALEWSKI ; 4
Manager, System Engineering Uniti
Non-outage Test Performance PETE DIETRICH !
Manager, Maintenance Unit 1 .
Enforcement Perspective DWIGHT MIMS
, Director, Licensing .
Closing Comments RANDY HUTCHINSON
Vice President Operations, ANO
~
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4
_ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ .
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4
-
INTRODUCTIOX -
Dwight Mims
Director, Licensing
.
-
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- -
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6 ,
;
APPAREXT VIOLATIONS
.
*
Failure to perform proper vacuum relief valve testing under the
plant conditions as prescribed in the test procedure in
accordance with 10CFR50, Appendix B, Criterion V, Instructions, .
Procedures and Drawings :
-
Failure to utilize the correct design control processes (temporary
alterations) for the temporary cover configurations placed over
the valve flange in accordance with 10CFR50, Appendix B,
Criterion III, Design Control
*
Failure to perform. proper safety evaluations as described in
10CFR50.59, Changes, Tests and Experiments
l
1
!
O
#
BORATED WATER STORAGE TAXK
.
4" Vent
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V
t. ay 8,' Flange
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(NO)
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.
9
L CHROXOLCGY
December 3,1996
- Job order for PSV testing signed into control room
* Control Room Supervisor (CRS) and craft discussed need
for " breathable" FME cover
* Craft and craft supervisor discussed need for
" breathable" FME cover
- PSV removed for testing i
- FME cover installed per surveillance test procedure :
requirement
Plastic bag with slits installed to allow " breathing" .
.
.
g - -
% . .-..
. -
.
'
PLASTIC FME COVER
Plastic bag loosely draped over flange
_p Plastic bag seam over pipe
flange
2Verticalslits
cut to allow BWS1
to breathe.
.
>
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) i j ( Bag taped
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;
To BWST 8" Schedule 10S pipe .
i
. .
__ . . . _ ..
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1i
.
CHROXOLOGY
~
*
December 4,1996
- Craft discovered crack in PSV flange late in day shift
* December 5,1996 .
'
-
~ 1300 System Engineer observes crack and notes FME cover ,
-
Condition report initiated for PSV crack ~
- System Engineer begins operability determination and i
conservatively directs a 1" gap FME cover be installed to
replace plastic cover
~ 18001" flanged gap FME cover installed
, ~ 2030 operability assessment completed for current
configuration .
<
.'
i
i
. _ - - _ _
. . - .
.
-
12
FLANGED GAP FME COVER
Note: Install screen over open flange holes
"'
~~ '
% All thread (4)
'
j,
._m
, ,'~ Blind flange (1)
o_
Screen wrap on g \
Air gap
4
outside of flanges Nuts (16)
all around . -. , - :
!?
-
i l ; i + Existing valve flange
t ri i::r .
- '
l -
1 I
I
n L
Unattended Configuration
for Vacuum Relief Valves
Using 0.0386" to 0.2187" screen
,
1
w
. _- - - . .. .-
.
.
13
CHROXOLOGY .
'
.
* December 5-12,1996
- Various departments discuss breathable FME cover as
,
possibly superior to PSV
- Various departments consider need for temporary alteration
- Temporary alteration discussions concluded that procedure ;
- provided adequate control ;
'
- Determined PSV weld repair unlikely and long lead time for
new PSV -
- System Engineer modified FME cover to independently ,
l
provide equivalent flow area io the PSV (i.e. 3" gap)
'
- Additionaljob order issued to increase gap and ,
conservatively provide dual signoffs t
l
!
,. , , - _ - _ . . -_ _ _
.
.
14
CHROXOLOGY
- January 22,1997
L - Self-assessment questions BWST PSV maintenance
Condition report initiated
- Questioned acceptability of plastic FME cover
- Questioned use of surveillance test procedure in
non-outage application
! * BWST operable in current configuration (3" flanged gap
cover)
* Past operability
- Determined operable based on slits in plastic FME
cover
- ~
--
. -. -
.
15 ,
CHROXOLOGY -
.
*
February 3,1997
'
- Condition report documents 4" vent not redundant to PSV
* Current configuration operable
- 3" flanged gap FME cover
* Past operability
- Determined operable with minor tank deformation
- Tank would not rupture
,
!
____J
-
.
6
CHROXOLOGY
-
February 5,1997 <
- Temporary alteration documentation initiated.
* 4" vent line not redundant
Surveillance test procedure not evaluated for non-outage
mode '
* Desire to provide single documentation package
Extended installation time
'
Differing opinions on whether FME cover was
.
- temporary alteration
!
-
February 18,1997 i
- Temporary alteration reviewed nnd. signed off
* No modifications required to 3" flanged gap
configuration
- Installed December 12,1996
. . . .
. .. - - - . -
.
_
-
-i
-
_
-
.
CHROXOLOGY 7
._
*
February / March 1997
-
.
- AE Design Basis Inspection team BWST questions answered
~
October / December 1997
- Engineering Open Items Follow-up Inspection questioned
.
plastic FME cover past operability determination ,
,
, - Performed analysis using bounding assumptions { * Assumed plastic bag would not fail- only 4" vent
Demonstrated BWST would not significantly deform and l
l would perform design function [ - Performed testing which showed plastic FME cover would i rupture before significant tank deformation
]
, .
* Validated earlier engineeringjudgments/ evaluations
t
i 4
- Conclusion !
i
.
BWST remained operable in each configuration
i
1
s . . _ . _ . . -. . .- . - _- _ _ _ . _ -- !
_
_ -
.
8
.
CHROXOLOGY
* Summary
- Controls satisfying procedural requirements of temporary
alteration procedure should have been used to perform task
-
Inadequate review of test conversion resulted in
inappropriate performance of task during operation
* Incorrect impact statement information made detection
difficult
- Personnel on several occasions sought to improve a situation
that they felt was already operable (i.e. recover margin),
-
focus was on safety and operability of a common mode
component
! - Conditions were self-identified
- Subsequent calculations and tests confirmed that BW5T
'
remained operable in each configuration -
.6 Asa~
0 '
I
- !
l
~
.
.. ,
1
x
- M
m m
l
CO U 60
! %
cn
y .5
L =W a : l
W yw
s
W .b
I o g w
& *g C
l -
C W
H
H
W d
v u bb
% % og
w *5 w
r *
w a
1
-
1
.
nH
1
,
l l l
_ .._ , -
_ - . - _ . - _ . ._ _ .-_ _ _ . - . - . . , - - _ - . _ . - - . - - _ _ _ _ _ - . _ - _ - - _ . - - _ - . -,_ .._-- - .--_.. ___ _ -_ _ . _ _._ - - -
_-
.
-
20
-
OPERABILITY ASSESSMENT
* CR 1-96-0663 - December 5,1996 - PSV Flange Crack ,
- FME controls - i.e.1" gap plus 4" vent line
!
- Technical specification reviews
- BWST backleakage issues
* CR 1-97-0019 -January 22,1997 - Plastic FME Cover
* CR 1-97-0031 - February 3,1997 - Inadequacy of4" Vent / Single
'
Failure Concern
.
_-_
. - .
. .
.
.
21
,
OPERABILITY ASSESSMENT
4
* CR-1-96-0663 - December 5,1996 - PSV Flange Crack
.
- Operability addressed the adequacy of the PSV as well as
other issues (Technical Specifications and BWST
backleakage)
- The System Engineer understood that the basis for solely
crediting the 4" overflow vent was not fully developed;
therefore, he considered it prudent to re-establish a vent
path equivalent to the vacuum breaker. Therefore,
.
calculations were performed to supportinstalladon of a i
flanged 1" gap !
i
,
_ _ _
i
- .
.
.
:
22- t
i
r -
OPERABILITY ASSESSMEXT . i
, .
*
CR-1-97-0019 - January 22,1997 - Plastic FME Cover
1
,
i !
- - At this time, the 3" flanged gap had already been installed
l based on additional calculations which established
substantial margin. Therefore, no current operability t
L concerns existed. I
- System Engineer acknowledged that previous CRs did not ,
i
explicitly address the p .t operability implications of the use
- of the plastic bag FME cover.
j * Initial conclusions of indeterminate past operability were [ revised based on confirmation that slits were made in the
- cover. t
] - Design Engineers had concurrently concluded no past j operability concerns existed based on engineering judgment '
that the bag would rupture during a rapid tank drawdown.
i
i
! , I
_
- :_ __ _
- . .
p .
23
i
a ,
.
OPERABILITY ASSESSMENT ,
!
*
CR-1-97-0031 - February 3,1997 - Inadequacy of4" Vent / Single
Failure Concern
-
- Standard engineering methods could not support capability
of the 4 " vent line as redundant to the vacuum breaker line
- - Single failure concerns which resulted in the condition
report, were quickly resolved, i.e. PSV considered a passive
component ,
- At this time, the 3" flanged gap cover provided an operable
!
configuration !
:
I
.
6 )
.
.
24
OPERABILITY ASSESSMEXT
February 1997 follow-up questions
-
During the NRC AE Design Basis Inspection, additional detail
supporting operability of the 1" flanged gap design was '
provided to address the effects of the wire screen. This was
previously judged acceptable based on comparison with the
screen on the PSV and a knowledge that margin existed in these
calculations.
-
The re-assessment provided to the inspection team confirmed
the validity of the previous engineering evaluation.
l
_
, .
.
~
.
25
.
OPERABILITY ASSESSMENT
November 1997 follow-up inspection
-
During the NRC AE Design Basis Follow-up inspection, first
l time questions were raised concerning adequacy of the original
past operability determinations for the plastic bag FME. cover
-
ANO decided to perform additional efforts to respond to NRC
questions (two approaches): '
- Testing to demonstrate fragility of the bag
- Analysis of tank effects assuming bag is not fragile, (i.e. does
not rupture)
..
--_------ - - _ _ _ _ - _ - _ . _ __. . _ _ _ _ _ _ . _ ._ . -- . _. _
_ .
26 ,
~
OPERABILITY ASSESSMEXT 1
,
-
,
November / December 1997 follow-up
-
Test results confirmed that the plastic bag would easily rupture
under postulated conditions
*
Tank analyses determined that the overflow line by itself was ,
capable of venting the tank without tank breach or any .
significant damage
- Sealed 8" PSV mounting flange
*
Evaluated ECCS performance and was determined to be
adequate '
i
!
-
t
.
.
"
OPERABILITY ASSESSMENT
Operator impact
- Large Break LOCA Case 1 (expected)
- Full ECCS actuation (12,340 gpm)
'
- Plastic bag vents through slits
* No impact
- Plastic bag seals and quickly ruptures
Momentary level indication perturbation
- Transparent to operators
. ,
- - . .
. - -
-
- - -. . . - - -
.-
. - _ ._. .
.
"
OPERABILITY ASSESSMENT
Operator impact (Cont)
'
=
Large Break LOCA Case 2 (bounding) ;
- Full ECCS actuation (12,340 gpm)
- Plastic bag seals without bursting
- 4" vent limits tank vacuum to 2.7 psi
- Level error results in early manual transfer to reactor
building sump suction (6' maximum) :
- Level indication rises as tank vents
- Operators dispatch HP personnel to monitor for BWST
backleakage
- Calculations show adequate NPSH for ECCS pumps
!
L
8
i
_ _ .- . __ _ - _
.
"
.
OPERABILITY ASSESSMEXT
Operator Impact (Cont)
~
*
Additional conservatisms not considered
- Actual ECCS flows less than assumed result in smaller level
error
- Reactor building sump suction transfer time results in 3-4
feet of additional BWST inventory injection not credited
;
,
1
6
t
s
-
.
30
. OPERABILITY ASSESSMEXT
Engineering judgment
-
Determining operability
- IE Manual 9900, Detailed Discussion ofSpecific Operability
Issues
SSC outside TS, engineering judgment must be used to
determine safety significance
, * Decision based on best information available l . l * Predicated on reasonable expectation that the SSC is
operable
May be based on analysis, test, partial test, experience
with operating events, engineering judgment, or a
combinaHon of factors
* Revise as appropriate
.
- - - -
--
-- -
.
--
-
,
- - _ - -_ ._ -- _. __ _ _ _ _ _ _ - _ _ _ _ _ _ _ -. .
..
. 31
.
OPERABILITY ASSESSMENT
. Engmeerma judgment (Cont)
*
NUREG 1022, Rev.1 - Event Reporting Guidelines 10CFR50.72 and
'5 0.73
- Engineering judgment
* "May include either a documented engineering analysis
or a judgment by a technically qualified individual,
depending on the complexity, seriousness, and nature of
. the event or condition" '
-
" Staff considers that the use of engineering judgment
implies a logical thought process that supports the
judgment"
. . . . _ . . . - - . . - _ ._. -
. - -
,
.
32
!
OPERABILITY ASSESSMENT
'
Conclusions
-
The original determination that the BWST was operable with t
-
the plastic bag installed was re-confirmed. The original efforts
- to support the engineering judgment determination were
confirmed to be valid - The original tank evaluations in January and the additional tank analyses in November 1997 confirmed that no significant effects would have occurred even had the original premise been in error (i.e. even if the bag had not broken) ; - Use of engineering judgment was applied consistently in
l accordance with regulatory guidance ,
!
._ ..
. -. - - .
, _ _ _ _ . _ ---_ .. _
.
33
i
'
,
TEMPORARY ALTERATIOX PROGRAM
Joe Kowalewski
Manager, Unit 1 System Engineering
. ._ _
.
1
'
34
TEMP ALT PROGRAM
!
*
Apparent violations
- Failure to perform 50.59 reviews for installation of FME
covers
- Failure to utilize proper design controls for the installation
-of FME covers
-
Temporary alteration program
- Temporary alteration procedure initiates both the design
controls and 50.59 reviews
- Error made in application of temporary alteration decision
,
criteria
t
i
-- _ _ -
_. .
.
35
TEMP ALT PROGRAM
* Introduction
,
- Temporary alteration program description
- Criteria for initiating temporary alteration controls
'
- Application of criteria to the BWST PSV removal
- Evaluation of temporary alteration program implementation
-- Planned corrective actions
1
. '
,
-
.
- . .
.
36
TEMP ALT PROGRAM
-
1
Program Description
*
Temporary alterations controlled by Procedure 1000.028
*
Two methods which initiate 50.59 review
- Procedures or work plans
.
;
- Temporary alteration packages .
i
*
Both methods require:
l
- Engineering review
- 50.59 review
.
! - Independent verification .
*
INPO Good Practice used as reference for temporary alteration
procedure development
:
- - _ -
- .
37
.
.
TEMP ALT PROGRAM
'
Criteria for temporary alteration controls
*
Addressed in Attachment 1 of temporary alteration procedure
*
Determine if maintenance controls adequate
- Affected structure / system / component (SSC) released by !
Operations to Maintenance
'
'
- Affected SSC in use by Operations
*
Determine if temporary alteration package required
- Activity controlled by existing procedure or work plan
- Activity a design change
.
--
- . . . .
__
.
.
.- - ,... .
...; .
,. _
. - . - - -
.
38
TEMP ALT PROGRAM . .
Application of the temporary alteration decision process to the BWST
.
4
PSV removal
-
Error occurred in evaluating criteria to determine if maintenance
controls adequate '
- Was the SSC under the control of Maintenance (removed from .
service)-
- Was the SSC depended upon by Operations (function still '
required) .
*
Condition Report issued on February 5,1998 ,
I
.
.
39
, TEMP ALT PROGRAM
Application of the temporary alteration decision process to the
BWST PSV removal (Cont)
* Affected component seen as the PSV
* Performance of maintenance on an operable and unisolated SSC
unusual
* Venting function at PSV valve flange not seen as required for
operability of BWST
* FME cover seen as normal maintenance activity
.~,
.. . -
.
*
COXFIGURATION EXAMPLES
NORMALOPERATION
.
,
f
1
,
.
*
COXFIGURATION EXAMPLES
NORMALOPERATION
h
/
< +
MAINTENANCE ; OPERABLE
I
A
< -
+
/
~
HOLDCARD
l
.
Not a temporary alteration
. . .. .
..
.
. .
. .
.
. .
.
.
..
.. ..
..
m , 4 ,.
_ m - _ e a
p' O
4?
~
COXFIGURATION EXAMPLES
NORMALOPERATION
A
<
+ MAINTENANCE OPERABLE
<
#
l
l TEMPORARYALTERATION '
,
-
f
43
BORATED WATER STORAGE TAXK
Maint 4" Vent
n
8" flange U
i
u a / :
U .
- -
_
y
Operable-
k (NO)
Drawing not to scale
. .
_
.
..
_ _ _ _
_ _.
.
44
TEMP ALT PROGRAM
Evaluation of temporary alteration program _
* Current plant configuration
- Walkdown of accessible areas of ANO l&2
'
.
* Minor deviations noted
- Six drains altered
- One pressure gauge removed
- Review of in-progress or delayed ANO l&2 JO's
* No undocumented temporary alterations noted ,
.
,
. . . . . . . . . . . . . . . .
. . . . , . .
. , .
, . . . . .
i
... .
. . . _ .
.
.......i
. . . . . . . . . . . .
. .-
_ . _ _ _ _ _ _ _ _ _
_
45
TEMP ALT PROGRAM
Evaluation of temporary alteration' program (Cont).
* Condition reports
- Review of temporary alteration condition reports since 1994
Do not reflect similar condition
,
* 1995 condition report on interconnecting systems has
some similarities, but not the same causes
*
Independent assessments
- INPO " blue card" challenge, August 1996
.
* No undocumented temporary alterations identified
- System Engineering corporate assessment, October 199'7
Temporary alterations was a focus area
No undocumented temporary alterations identified
.
t
'
-~
- . _ _ _ _ .
. . . - - _ _
.
.
-
.;
.
-
;46 1
~
.
TEMP ALT PROGRAM t
!
1
Evaluation of temporary alteration program (Cont)
*
Independent assessments (Cont)
- QA Surveillance, September 1997
>
a No undocumented temporary alterations identified- '
.
* Condition report issued to document administrative
,
issues
-
,
* Action initiated to benchmark industry {:
l-
!
-
! ;
- .
a
. .
. _ _ .
%
47
TEMP ALT PROGRAM
.
*
Evaluation conclusions
;
- Existing procedure is providing adequate controls of plant
configuration
- Removal of BWST PSV involved an unusual condition
* Maintenance on operable system without isolation .
* Temporary alteration process does not provide adequate
guidance for this situation
.
'I
_ _ - _ _ ____...______ _ __ _ -____________________ :
. -
-
( * l- TEMP ALT PROGRAM
Corrective Actions
-
Completed
- Finalized temporary alteration package on BWST
- Letter issued to plant personnel to heighten awareness of the
potential for creating temporary alterations during
maintenance and to clarify temporary alteration decision
criteria '
*
In-Progress
- Appropriate training will be completed by March 13,1998
'
- Root cause analysis and comprehensive corrective action
plan is scheduled for completion by March 5,1998
- Initial review of implementing documents for Operations
and Maintenance is scheduled for completion by March 5,
1998
.
.
.
s
49
-
TEMP ALT PROGRAM
4
Corrective Actions (Cont)
-=
Planned Actions .
- Completion of industry benchmarking
'
- Changes to the temporary alteration procedure to provide
clarification /
.
- Additional written gyldance for Maintenance Planners and
Operations Liaisons
- Training of personnel on the procedure changes
_
. .. - - -
---. _. .. .
..
. 50
-
TEMP ALT PROGRAM
Summary
*
Temporary alteration procedure initiates the design control and
50.59 review processes
*
The process implementing temporary alteration controls and
50.59 reviews is sound
*
Error made in application of temporary alteration decision
criteria i
*
Procedure did not provide guidance addressing the unusual
'
situation of-maintenance performed on an operable and -
unisolated component -
*
Interim guidance issued and appropriate training will be
performed
f
___ _ , __ _ _ _ . _ _ _ _ _ _ -
_ _ _ .
__ ~ -
-
51
XOX-OUTAGE TEST PERFORMAXCE
~
Pete Dietrich
'
Manager, Unit 1 Maintenance.
.
-- .
- --
52
~
XOX-OLTAGE TEST PERFORMAXCE
= Statement of Apparent Violation
- Use of BWST PSV testing procedure during power
operations was improper.. Paragraph 4.3.1 stated that
inspection of the valve would be performed each refueling
outage.-
* BWST PSV testing procedure (January 1995 version) referenced l
IEB 80-05, Vacuum Condition ~Resulting in Damage to CVCS Holdup '
Tanks, but contained no description of reference
- Response to IEB 80-05 stated that PSV inspection will be
scheduled during each refueling outage
- Response was not adequately reviewed when PSV testing
moved to non-outage performance in January 1995
.
.
_ _ _ _ _
.
53
XOX-OLTAGE TEST PERFORMAXCE
.
'
- BWST PSV testing procedure l
- Procedure revision used on December 3,1996 listed
response to IEB 80-05 in paragraph 4.3.1 as a commitment
implemented in the document but did not provide
description of commitment
- Revision approved July 21,1997 added specific wording in
step 4.3.1 referenced in the violation as a result of
commitment implementation improvements started in 1995
- Agree with violation but commitment not easily recognized
I
- Conversion effort should have incorporated temporary
alteration controls
.
. . . . _ . . . . . . , ,
. . , _ . . . . . . . . . . . . . , . , , , . . - . . . .
.
_ . . .
.
. . . . _
..
.. . . . . . . . . . . . .
.
.v~
~ '
-
-
54
.
-
-
XOX-OLTAGE TEST PERFORMAXCE i
,
Cause-
*
Process for conversion of activities from outage to non-outage
performance was not as encompassing as desired
'
Corrective Actions
*
Enhanced conversion process by adding cross-functional team
review with specific review criteria for activities
*
Performing review of previously converted activities against
specific review criteria
- Unrevie.wed activities placed on hold
*
Converted the performance of this activity back to outage
- _ -
- -
- _ _ _.
,
-
55
L
.
XOX-OLTAGE TEST PERFORMANCE
Issue
l
* Deviated from the commitment requirement for testing the PSV !
'
during refueling outages
Corrective Actions
-
Adjusted processes to ensure proper reviews on changes in
activities which implement commitments
-
Procedure control process enhanced to ensure effects on
commitment implementation are evaluated as part of procedure
app val
-
Site procedures are under review for incorporation of
appropriate references to commitments to ensure continued
compliance
. _.
- _--
O
56
XOX-OUTAGE TEST PERFORMAXCE
l
Issue. ,
* The ULD contained misleading information on the redundancy l
!
of the 4" vent line
Corrective Actions
* ULD corrected
- Cause determined
I - Open ULD discrepancies reviewed for ability to create a
similar condition
l l l
.. - . . . . . . _ . . . .
.
..... -
. .
~-
.
._.
__ . . .
_
.
57
.
XOX-OUTAGE TEST PERFORMAKCE
Issue ,
* BWST PSV testing was performed non-outage in April 1995
Related Information
* Testing lasted approximately 10 hours
* Type of FME cover used cannot be determined
- Corrective actions same as for December 1996 performance
l i l
. . . .
. . _ . . . . .
. . . . . . . . . .
_ _ _
. . . . . . . . . . . . . . . . . . . .
_ ,
.
...
_ . . _
, ---
, .
.
58
-
XON-OLTAGE TEST PERFORMAXCE
.
-
Summary
* BWST PSV test should not have been performed non-outage
without commitment change and temporary alteration controls
"
- Recognition of commitment by individuals involved in the
l '
conversion and performance of the activity would not be
obvious
'
* Problems were self-identified
* Corrective action plans to address issues are comprehensive and
should prevent recurrence
m. --w.--s--==-- %--- -- - - - -- - -am- -
_ _ _ _ _ _ _ _ _
-
. _ . .
.
.
59
EXFORCEMKNT PERSPECTIVE
~
.
l i
Dwight Mims
Director, Licensing
'
.
'
' ' ' ' ' '
- . . . . - - -
_ _ _ _ _ _ _ , _ _ _
.._-.__.---....-7
.
60
APPARENT VIOLATION
T-ALT /50.59 !
:
'
* Failure to utilize the correct design control processes (temporary
alterations) for the temporary cover configurations placed over
the PSV valve flange
* Failure to perform proper safety evaluations
NOTE:
The failure to utilize the correct design control process and the
'
.
failure to perform a proper safety evaluation are consequential
with each other and should be considered as one apparent
violation
l . u _ _ _ _ _ _ _ _ _ _ _ . _ _ . . . _ = _ . . . _.
_
.
61
T-ALT /50.59 ISSLES
Actual and Potential Safety Consequences
* BWST remained operable
- Would have performed intended safety function
- Operator response minimally affected by BWST level
l indication l - System Engineer focused on operability and safety
Conclusion
'
* Low actual or potential safety consequences
I
.
62
T-ALT /50.59 ISSUS
Regulatory Significance
- Self-identified
- ANO recognizes our regulatory responsibility as a licensee to
perform engineering activities in accordance with established
procedures
! * ANO has shown commitment to taking comprehensive
'
corrective actions to address the root and contributing causes
independent of any enforcement actions
* Condition not representative of overall ANO performance
- Not representative of overall engineering performance
- No major program breakdown
* Condition not repetitive
* Condition not willful
- Violations do not appear to have a common root cause
Conclusion
* Low regulatory significance
-
-_
.
_
_
.
.
63
T-ALT /50.59 ISSUS
Severity Level
* Failure to invoke temporary alteration requirements
- Procedure guidance insufficient j
* Precluded invoking the 50.59 process
- BWST remained operable, therefore, the condition had low
actual or potential safety consequences
'
- Basis exists in Supplement I.D.3 to conclude that the issue is
a Severity LevelIV violation -
* Failure to meet regulatory requirements that have more
than minor safety significance
_
.
64
APPAREXT VIOLATION
Non-outage test performance
- Failure to perform proper PSV valve testing under the plant
conditions as prescribed in the test procedure I
i
.
.
,
_. o
~ '
-
65
.
XOX-OLTAGE PERFORMAXCE
s
Actual and Potential Safety Consequences
.
*
~BWST remained operable -
Conclusion
-
Low actual or potential safety consequences
- Confirmed by test and calculation
.
.
.
.
XOX-OLTAGE PERFORMAXCE
Regulatory Significance .
.
- Self-Identified ,
* ANO recognizes our regulatory responsibility as a licensee to
perform maintenance in accordance with established
procedures
ANO has shown commitment to taking comprehensive
'
-
corrective actions to address the root and contributing causes
independent of any enforcement actions
- Condition not representative of overall ANO performance
- Not representative of overall maintenance performance
'
f
- No major program breakdown
- Condition not repetitive
- Condition not willful
- Violations do not appear to have a common cause
Conclusion
,
= Low regulatory significance -----
. . --
.
<
67
=
XOX-OETAGE PERFORMANCE
Severity Level
The failure to perform an adequate review of the PSV test
procedure for non-outage performance did not cause the BWST
to be inoperable; therefore, basis exists in Supplement I.D.3 to
conclude that the condition is a Severity LevelIV violation
I - Failure to meet regulatory requirements that have more than '
minor safety significance or environmental significance
-
The performance of BWST PSV testing during non-outage
- conditions was a deviation from a commitment made in '
response to IEB 80-05
4
-
i
l
t
!
_
.-
.
.
68
CLOSIXG COMMElNTS
l
l
Randy Hutchinson
.
Vice President, Operations
}}