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| number = ML18036B021
| number = ML18036B021
| issue date = 10/09/1991
| issue date = 10/09/1991
| title = Responds to NRC 910911 Ltr Re Violations Noted in Insp Repts 50-259/91-26,50-260/91-26 & 50-296/91-26 on 910716-0816. Corrective Actions:Fire Watch Established on 910728 & Maintained Until Fire Wrap Replaced on 910802
| title = Responds to NRC Re Violations Noted in Insp Repts 50-259/91-26,50-260/91-26 & 50-296/91-26 on 910716-0816. Corrective Actions:Fire Watch Established on 910728 & Maintained Until Fire Wrap Replaced on 910802
| author name = ZERINGUE O J
| author name = Zeringue O
| author affiliation = TENNESSEE VALLEY AUTHORITY
| author affiliation = TENNESSEE VALLEY AUTHORITY
| addressee name =  
| addressee name =  
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = NUDOCS 9110160193
| document report number = NUDOCS 9110160193
| title reference date = 09-11-1991
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 10
| page count = 10
}}
}}
See also: [[followed by::IR 05000259/1991026]]


=Text=
=Text=
{{#Wiki_filter:Tennessee Valley Authority, Post Olfice Box 2000.Decatur,'Alabama
{{#Wiki_filter:Tennessee Valley Authority, Post Olfice Box 2000. Decatur,'Alabama 35609 O. J, 'lite'eringue Vice President, Browns Ferry Operations 0CT 09
35609 O.J,'lite'eringue
>SS)
Vice President, Browns Ferry Operations
U.S. Nuclear Regulatory Commission ATTN:
0CT 09>SS)U.S.Nuclear Regulatory
Document Control Desk Washington, D.C.
Commission
20555 Gentlemen:
ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket Nos.
In the Matter of Tennessee Valley Authority Docket Nos.50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)-NRC INSPECTION
50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) NRC INSPECTION REPORT 50-259,
REPORT 50-259, 260, 296/91-26-REPLY TO NOTICE OF VIOLATION (NOV)This letter provides TVA's reply to the NOV transmitted
: 260, 296/91-26 REPLY TO NOTICE OF VIOLATION (NOV)
by letter from B.A.Wilson to D.A.Nauman dated September ll, 1991.NRC cited TVA with two violations.
This letter provides TVA's reply to the NOV transmitted by letter from B.
The first violation concerns the removal of the fire wrap from redundant trains of safe shutdown equipment without posting a fire watch.The second violation concerns two fuel movement errors within a two-week period.TVA agrees that the violations
A. Wilson to D. A. Nauman dated September ll, 1991.
noted in the NOV violated regulatory
NRC cited TVA with two violations.
requirements.
The first violation concerns the removal of the fire wrap from redundant trains of safe shutdown equipment without posting a
During the investigation
fire watch.
into the fire wrap removal, TVA determined
The second violation concerns two fuel movement errors within a two-week period.
that the Unit 3 walkdown inspection
TVA agrees that the violations noted in the NOV violated regulatory requirements.
involving the fire wrap was not necessary since the equipment had previously
During the investigation into the fire wrap removal, TVA determined that the Unit 3 walkdown inspection involving the fire wrap was not necessary since the equipment had previously been inspected during the Unit 2 walkdowns.
been inspected during the Unit 2 walkdowns.
TVA has taken action that should minimize unnecessary walkdowns and impact on the operating unit from recovery actions.
TVA has taken action that should minimize unnecessary
Enclosed is TVA's "Reply to the Notice of Violation" in accordance with 10 CFR 2.201.
walkdowns and impact on the operating unit from recovery actions.Enclosed is TVA's"Reply to the Notice of Violation" in accordance
Corrective actions are complete for both these violations.
with 10 CFR 2.201.Corrective
No commitments are made in this letter.
actions are complete for both these violations.
If there are any questions regarding this response, please telephone J.
No commitments
E. McCarthy at (205) 729-2703.
are made in this letter.If there are any questions regarding this response, please telephone J.E.McCarthy at (205)729-2703.Sincerely,//Zg':if('i:</
Sincerely,
0.Zeringue'?li0160ir?3
// Zg':if('i:</
r0iioOi?PDR I-"IDOCI;O=OOO.~q I.(PDR p(/Q1  
0
0  
. Zeringue
U.S.Nuclear Regulatory
'?li0160ir?3 r0iioOi?
Commission
PDR I-"IDOCI; O=OOO.~q I.(
OCT Pg)gg)Enclosure cc (Enclosure):
PDR p(/Q1
NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000
 
Mr.Thierry M.Ross, Project Manager U.S.Nuclear Regulatory
0
Commission
 
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr.B.A.Wilson, Project Chief U.S.Nuclear Regulatory
U.S. Nuclear Regulatory Commission OCT Pg
Commission
)gg)
Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323  
Enclosure cc (Enclosure):
NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Reply to Notice of Violation Inspection
: Athens, Alabama 35609-2000 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
Report Number 50-259 260 296 91-26 RESTATEMENT
 
OF VIOLATION 91-26-02"During the NRC inspection
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Reply to Notice of Violation Inspection Report Number 50-259 260 296 91-26 RESTATEMENT OF VIOLATION 91-26-02 "During the NRC inspection conducted on July 16 August 16,
conducted on July 16-August 16, 1991, two , violations
: 1991, two
of NRC requirements
, violations of NRC requirements were identified.
were identified.
The first violation was for removing fire wrap without posting a fire watch.
The first violation was for removing fire wrap without posting a fire watch.The second violation was for failure to follow fuel movement procedures.
The second violation was for failure to follow fuel movement procedures.
In accordance
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1991)=, the violations are listed below:
with the"General Statement of Policy and Procedure for NRC Enforcement
A.
Actions," 10 CFR Part 2, Appendix C (1991)=, the violations
Technical Specification 3.11.G.l.a requires that all fire rated assemblies separating systems important to safe shutdown within a fire a'rea shall be operable at all times or a fire watch must be established within one hour.
are listed below: A.Technical Specification
Contrary to the above, a
3.11.G.l.a
NRC inspector identified on July 28, 1991, that fire wrap had been removed from operable residual heat removal service water pump motor power cables in the intake structure and a fire watch was not established.
requires that all fire rated assemblies
This fire wrap provides a one hour fire resistance barrier between redundant safe shutdown equipment, which do not meet the minimum 20 feet Appendix R separation criteria.
separating
The fire wrap was removed on July 24, 1991, for Unit 3 walkdown inspection under an approved work order 91-35664-00, although walkdown inspections for Unit 2 had previously been performed in this area."
systems important to safe shutdown within a fire a'rea shall be operable at all times or a fire watch must be established
1.
within one hour.Contrary to the above, a NRC inspector identified
Reason for the Violation The root cause was Field Services-Modifications management failure to ensure that Unit 3 planning and implementation of work was in full compliance with site procedures.
on July 28, 1991, that fire wrap had been removed from operable residual heat removal service water pump motor power cables in the intake structure and a fire watch was not established.
, Two ma)or contributing factors were inadequate verbal communications and management's failure to ensure the existence of a complete training matrix in Field Services that
This fire wrap provides a one hour fire resistance
 
barrier between redundant safe shutdown equipment, which do not meet the minimum 20 feet Appendix R separation
identified all training needed to adequately perform a particular function.
criteria.The fire wrap was removed on July 24, 1991, for Unit 3 walkdown inspection
The missed fire watch was a direct result of personnel not following procedures.
under an approved work order 91-35664-00, although walkdown inspections
for Unit 2 had previously
been performed in this area." 1.Reason for the Violation The root cause was Field Services-Modifications
management
failure to ensure that Unit 3 planning and implementation
of work was in full compliance
with site procedures.
, Two ma)or contributing
factors were inadequate
verbal communications
and management's
failure to ensure the existence of a complete training matrix in Field Services that  
identified
all training needed to adequately
perform a particular
function.The missed fire watch was a direct result of personnel not following procedures.
The fire wrap was removed by an approved work order on July 24, 1991, to support Unit 3 Walkdown activities.
The fire wrap was removed by an approved work order on July 24, 1991, to support Unit 3 Walkdown activities.
A one hour fire watch was not established
A one hour fire watch was not established because TVA personnel did not follow procedures and failed to initiate an Attachment F as required by FPP-2, Fire Protection-Attachments.
because TVA personnel did not follow procedures
(Attachment F is the mechanism used to ensure that Fire Protection requirements, including the posting of fire watches, are met.)
and failed to initiate an Attachment
The Attachment F was identified as a prerequisite in the work order.
F as required by FPP-2, Fire Protection-
The implementing organization reduced the amount of fire wrap to be removed and discussed the reduced scope of the job with fire protection to determine whether the Attachment F was still needed.
Attachments.(Attachment
Due to miscommunication, the individuals (a craft foreman and a fire protection operator) involved in this discussion concluded that an Attachment F was not required.
F is the mechanism used to ensure that Fire Protection
The foreman then started the work without an Attachment F.
requirements, including the posting of fire watches, are met.)The Attachment
This resulted in the removal of a fire barrier without establishing the compensatory fire. watch.
F was identified
The governing procedure, SDSP 7.6 Maintenance Management
as a prerequisite
: System, requires that if the work scope changes or the work cannot be performed then the work order should be evaluated for re-planning.
in the work order.The implementing
Corrective Ste s Taken and Results Achieved As an immediate action, a fire watch was established at 2050 hours on July 28,
organization
: 1991, and maintained until the fire wrap was replaced on August 2,
reduced the amount of fire wrap to be removed and discussed the reduced scope of the job with fire protection
1991.
to determine whether the Attachment
Unit 3 work activities-were stopped until TVA determined root cause and appropriate corrective action.
F was still needed.Due to miscommunication, the individuals (a craft foreman and a fire protection
The following event specific corrective actions were taken for the failure of personnel to follow procedures.'lanners and craft personnel were specifically instructed on the procedural requirement that the planner is to initiate an Attachment F if fire protection equipment or barriers are involved in the work activity.
operator)involved in this discussion
Fire Protection operators have been instructed to perform a physical review of work packages prior to providing Fire Protection requirements.
concluded that an Attachment
Personnel corrective action, in accordance with TVA policy, was administered to the individuals who failed to follow procedure.
F was not required.The foreman then started the work without an Attachment
Corrective actions taken for management's failure to ensure full compliance to procedures were as follows:
F.This resulted in the removal of a fire barrier without establishing
The Field Services Manager briefed Field Services personnel on the requirement of supervision to be knowledgeable of and to adhere to procedural and policy requirements.
the compensatory
Written duties and responsibilities for Field Services-Modifications personnel were developed, and discussed to clarify job requirements for these individuals.
fire.watch.The governing procedure, SDSP 7.6-Maintenance
Management
System, requires that if the work scope changes or the work cannot be performed then the work order should be evaluated for re-planning.
Corrective
Ste s Taken and Results Achieved As an immediate action, a fire watch was established
at 2050 hours on July 28, 1991, and maintained
until the fire wrap was replaced on August 2, 1991.Unit 3 work activities-were
stopped until TVA determined
root cause and appropriate
corrective
action.The following event specific corrective
actions were taken for the failure of personnel to follow procedures.'lanners
and craft personnel were specifically
instructed
on the procedural
requirement
that the planner is to initiate an Attachment
F if fire protection
equipment or barriers are involved in the work activity.Fire Protection
operators have been instructed
to perform a physical review of work packages prior to providing Fire Protection
requirements.
Personnel corrective
action, in accordance
with TVA policy, was administered
to the individuals
who failed to follow procedure.
Corrective
actions taken for management's
failure to ensure full compliance
to procedures
were as follows: The Field Services Manager briefed Field Services personnel on the requirement
of supervision
to be knowledgeable
of and to adhere to procedural
and policy requirements.
Written duties and responsibilities
for Field Services-Modifications
personnel were developed, and discussed to clarify job requirements
for these individuals.
An enhanced training matrix was developed for Field Services personnel.
An enhanced training matrix was developed for Field Services personnel.
The training requirements
The training requirements for Field Services'
for Field Services'  
 
positions were verified adequate.Training identified
positions were verified adequate.
in the enhanced training matrix was completed before plant related activities
Training identified in the enhanced training matrix was completed before plant related activities were resumed.
were resumed.Operational
Operational sensitivity training was given to the Unit 3 field and engineering personnel.
sensitivity
This training included a review of this specific incident, fire protection, environmental qualification, seismic issues, unit separation, and the changed operational environment due to Unit 2 operations.
training was given to the Unit 3 field and engineering
TVA has also taken action to improve the control of inspection requests for Unit 3 components in systems that are required to be operable for Unit 2 power operation or Unit 3 layup.
personnel.
Training was given on the use of color-coded separation drawings.
This training included a review of this specific incident, f ire protection, environmental
Walkdown procedures were revised to require the categorization of physical work involved during the walkdowns and to require engineering review and approval of walkdowns requiring physical work within Unit 2 operating spaces.
qualif ication, seismic issues, unit separation, and the changed operational
Walkdowns in Unit 2 operating spaces are to be scheduled by Unit 2 Operations.
environment
These actions should minimize unnecessary walkdowns.
due to Unit 2 operations.
In order to verify the effectiveness of these improvements, contractor walkdown activities are being resumed using a phased approach.
TVA has also taken action to improve the control of inspection
Walkdowns involving Unit 3 systems or components requiring no physical work were started first.
requests for Unit 3 components
Walkdowns involving Unit 3 systems or components not in Unit 2 areas requiring physical work were resumed next.
in systems that are required to be operable for Unit 2 power operation or Unit 3 layup.Training was given on the use of color-coded
Finally, Walkdowns involving Unit 3 systems or components that are required for Unit 2/Unit 3 operations or require physical work in Unit 2 are being resumed.
separation
3.
drawings.Walkdown procedures
Corrective Ste s That Will Be Taken to Avoid Further Violations Corrective actions described above are complete and are considered adequate to preclude recurrence.
were revised to require the categorization
4 ~
of physical work involved during the walkdowns and to require engineering
Date When Full Com liance Will Be Achieved TVA was in compliance on September 9,
review and approval of walkdowns requiring physical work within Unit 2 operating spaces.Walkdowns in Unit 2 operating spaces are to be scheduled by Unit 2 Operations.
1991.
These actions should minimize unnecessary
RESTATEMENT OF VIOLATION 91-26>>03 Technical Specification Section 6.8.1.1.a, requires that written procedures be established and implemented covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
walkdowns.
This includes procedures for refueling equipment operation.
In order to verify the effectiveness
0
of these improvements, contractor
 
walkdown activities
Procedure 3-ST-91-03, Unit 3 Fuel Sipping, required that fuel bundle movements be in accordance with 3-GOI-100-3, Refueling Operations, and the Fuel Assembly Transfer Forms.
are being resumed using a phased approach.Walkdowns involving Unit 3 systems or components
Procedure 3-GOI-100-3, step 5.4.6, required that all steps on the Fuel Assembly Transfer Forms be performed line by line.
requiring no physical work were started first.Walkdowns involving Unit 3 systems or components
Contrary to the above, on June 29,
not in Unit 2 areas requiring physical work were resumed next.Finally, Walkdowns involving Unit 3 systems or components
: 1991, and July 6, 1991, during the performance of fuel sipping, fuel assemblies were placed in Unit 3 spent fuel storage pool locations other than those required by the approved Fuel Assembly Transfer Forms.
that are required for Unit 2/Unit 3 operations
The second event occurred after the implementation of corrective actions taken for the first event which included first and second party.verification of both the fuel assembly
or require physical work in Unit 2 are being resumed.3.Corrective
. serial number and spent fuel storage pool location."
Ste s That Will Be Taken to Avoid Further Violations
1.
Corrective
Reason for the Violation Procedure 3-ST-91-03, which controlled the fuel sipping activities, required that fuel 'bundle movements be performed in accordance with 3-GOI-100-3 and SDSP 26.1, Special Nuclear Material (SNM) Management.
actions described above are complete and are considered
TVA decided to use the fuel transfer form from SDSP 26.1, and use row-rack-column location with single party verification to account for fuel during fuel sipping activities.
adequate to preclude recurrence.
On June 29, during the performance of Unit 3 fuel sipping activities, a fuel movement error occurred due to fuel handlers incorrectly identifying and moving a fuel assembly different from that identified by the transfer form.
4~Date When Full Com liance Will Be Achieved TVA was in compliance
The fuel movement error was attributed to personnel error and failure to follow procedures.
on September 9, 1991.RESTATEMENT
Prior to restarting fuel moves on July 1, TVA decided to add second party verification and also use the fuel assembly serial number during the remaining fuel moves.
OF VIOLATION 91-26>>03 Technical Specification
On July 6, 1991, during the Unit 3 fuel sipping activities, a sequence of three fuel movement errors was discovered.
Section 6.8.1.1.a, requires that written procedures
be established
and implemented
covering the applicable
procedures
recommended
in Appendix A of Regulatory
Guide 1.33, Revision 2, February 1978.This includes procedures
for refueling equipment operation.
0  
Procedure 3-ST-91-03, Unit 3 Fuel Sipping, required that fuel bundle movements be in accordance
with 3-GOI-100-3, Refueling Operations, and the Fuel Assembly Transfer Forms.Procedure 3-GOI-100-3, step 5.4.6, required that all steps on the Fuel Assembly Transfer Forms be performed line by line.Contrary to the above, on June 29, 1991, and July 6, 1991, during the performance
of fuel sipping, fuel assemblies
were placed in Unit 3 spent fuel storage pool locations other than those required by the approved Fuel Assembly Transfer Forms.The second event occurred after the implementation
of corrective
actions taken for the first event which included first and second party.verification
of both the fuel assembly.serial number and spent fuel storage pool location." 1.Reason for the Violation Procedure 3-ST-91-03, which controlled
the fuel sipping activities, required that fuel'bundle movements be performed in accordance
with 3-GOI-100-3 and SDSP 26.1, Special Nuclear Material (SNM)Management.
TVA decided to use the fuel transfer form from SDSP 26.1, and use row-rack-column location with single party verification
to account for fuel during fuel sipping activities.
On June 29, during the performance
of Unit 3 fuel sipping activities, a fuel movement error occurred due to fuel handlers incorrectly
identifying
and moving a fuel assembly different from that identified
by the transfer form.The fuel movement error was attributed
to personnel error and failure to follow procedures.
Prior to restarting
fuel moves on July 1, TVA decided to add second party verification
and also use the fuel assembly serial number during the remaining fuel moves.On July 6, 1991, during the Unit 3 fuel sipping activities, a sequence of three fuel movement errors was discovered.
Fuel movement was halted pending investigation.
Fuel movement was halted pending investigation.
This second incident was also attributed
This second incident was also attributed to personnel error (misidentification of fuel assemblies) and failure to follow procedures.
to personnel error (misidentification
SFSP rack location was performed but not by row-rack-column per the fuel handling training and procedure 3-GOI-100.3.
of fuel assemblies)
Fuel handlers were identifying the rack location based on the routine of fuel assembly movements in the rack.
and failure to follow procedures.
First and second party verifications were performed based on this pattern of fuel movement.
SFSP rack location was performed but not by row-rack-column
The practice of reading the serial number off transfer form sheets before attempting to read it off the fuel assembly bail handle allowed verification errors to be introduced into the process.
per the fuel handling training and procedure 3-GOI-100.3.
Also, the bridge operator was relying on the spotter for confirmation of the fuel assembly serial number instead of reading the serial number directly from the transfer form.
Fuel handlers were identifying
0
the rack location based on the routine of fuel assembly movements in the rack.First and second party verifications
 
were performed based on this pattern of fuel movement.The practice of reading the serial number off transfer form sheets before attempting
2.
to read it off the fuel assembly bail handle allowed verification
Corrective Ste s Taken gad Results Achieved After the first incident (June 29, 1991), the fuel assembly was immediately returned to its proper location and the surrounding fuel assemblies'ocations were verified correct.
errors to be introduced
An incident investigation was initiated to determine the cause and identify appropriate corrective action.
into the process.Also, the bridge operator was relying on the spotter for confirmation
As a corrective action, fuel handlers were briefed on the importance of correctly identifying the SFSP rack locations.
of the fuel assembly serial number instead of reading the serial number directly from the transfer form.0  
An additional pre-)ob briefing was held to address second party verification requirements prior to resuming fuel sipping activities.
2.Corrective
This corrective action was not effective as evidenced by the second incident on July 6, 1991 involving a sequence of fuel movement errors.
Ste s Taken gad Results Achieved After the first incident (June 29, 1991), the fuel assembly was immediately
The fuel assemblies'ocations were verified and a field change to the transfer form was generated to permit return of the fuel assemblies to their correct rack location.
returned to its proper location and the surrounding
An incident investigation was conducted to determine the cause and appropriate corrective action.
fuel assemblies'ocations
This time the fuel handlers were counselled as a group and individually on the importance of performing second party verification.
were verified correct.An incident investigation
Communications were improved by placing a supervisor on the bridge to monitor fuel handling activities and communications.
was initiated to determine the cause and identify appropriate
An operator's communication aid (list of questions) was established to formalize oral communications between the bridge and the Senior Reactor Operator (SRO),
corrective
and a radio was provided to the bridge and the SRO to assist in communications.
action.As a corrective
Personnel corrective action, in accordance with contractor policies, was administered to the personnel involved.
action, fuel handlers were briefed on the importance
Special Test 3-ST-91-03, Unit 3 Fuel Sipping, was completed on July 13, 1991.
of correctly identifying
No further fuel movement errors occurred during the remaining sipping activities, which required the movement of approximately 590 fuel assemblies.
the SFSP rack locations.
An additional
pre-)ob briefing was held to address second party verification
requirements
prior to resuming fuel sipping activities.
This corrective
action was not effective as evidenced by the second incident on July 6, 1991 involving a sequence of fuel movement errors.The fuel assemblies'ocations
were verified and a field change to the transfer form was generated to permit return of the fuel assemblies
to theircorrect rack location.An incident investigation
was conducted to determine the cause and appropriate
corrective
action.This time the fuel handlers were counselled
as a group and individually
on the importance
of performing
second party verification.
Communications
were improved by placing a supervisor
on the bridge to monitor fuel handling activities
and communications.
An operator's
communication
aid (list of questions)
was established
to formalize oral communications
between the bridge and the Senior Reactor Operator (SRO), and a radio was provided to the bridge and the SRO to assist in communications.
Personnel corrective
action, in accordance
with contractor
policies, was administered
to the personnel involved.Special Test 3-ST-91-03, Unit 3 Fuel Sipping, was completed on July 13, 1991.No further fuel movement errors occurred during the remaining sipping activities, which required the movement of approximately
590 fuel assemblies.
The fuel sipping involved the handling of a total of 1004 assemblies.
The fuel sipping involved the handling of a total of 1004 assemblies.
3.Corrective
3.
Ste s That Will Be Taken to Avoid Further Violations
Corrective Ste s That Will Be Taken to Avoid Further Violations Corrective actions described above are complete and are considered adequate to preclude recurrence.
Corrective
4.
actions described above are complete and are considered
Date When Full Com liance Will Be Achieved TVA was in compliance on July 26, 1991 with the completion of contractor corrective actions.}}
adequate to preclude recurrence.
4.Date When Full Com liance Will Be Achieved TVA was in compliance
on July 26, 1991 with the completion
of contractor
corrective
actions.
}}

Latest revision as of 01:35, 7 January 2025

Responds to NRC Re Violations Noted in Insp Repts 50-259/91-26,50-260/91-26 & 50-296/91-26 on 910716-0816. Corrective Actions:Fire Watch Established on 910728 & Maintained Until Fire Wrap Replaced on 910802
ML18036B021
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/09/1991
From: Zeringue O
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9110160193
Download: ML18036B021 (10)


Text

Tennessee Valley Authority, Post Olfice Box 2000. Decatur,'Alabama 35609 O. J, 'lite'eringue Vice President, Browns Ferry Operations 0CT 09

>SS)

U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of Tennessee Valley Authority Docket Nos.

50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) NRC INSPECTION REPORT 50-259,

260, 296/91-26 REPLY TO NOTICE OF VIOLATION (NOV)

This letter provides TVA's reply to the NOV transmitted by letter from B.

A. Wilson to D. A. Nauman dated September ll, 1991.

NRC cited TVA with two violations.

The first violation concerns the removal of the fire wrap from redundant trains of safe shutdown equipment without posting a

fire watch.

The second violation concerns two fuel movement errors within a two-week period.

TVA agrees that the violations noted in the NOV violated regulatory requirements.

During the investigation into the fire wrap removal, TVA determined that the Unit 3 walkdown inspection involving the fire wrap was not necessary since the equipment had previously been inspected during the Unit 2 walkdowns.

TVA has taken action that should minimize unnecessary walkdowns and impact on the operating unit from recovery actions.

Enclosed is TVA's "Reply to the Notice of Violation" in accordance with 10 CFR 2.201.

Corrective actions are complete for both these violations.

No commitments are made in this letter.

If there are any questions regarding this response, please telephone J.

E. McCarthy at (205) 729-2703.

Sincerely,

// Zg':if('i:</

0

. Zeringue

'?li0160ir?3 r0iioOi?

PDR I-"IDOCI; O=OOO.~q I.(

PDR p(/Q1

0

U.S. Nuclear Regulatory Commission OCT Pg

)gg)

Enclosure cc (Enclosure):

NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637

Athens, Alabama 35609-2000 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Reply to Notice of Violation Inspection Report Number 50-259 260 296 91-26 RESTATEMENT OF VIOLATION 91-26-02 "During the NRC inspection conducted on July 16 August 16,

1991, two

, violations of NRC requirements were identified.

The first violation was for removing fire wrap without posting a fire watch.

The second violation was for failure to follow fuel movement procedures.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1991)=, the violations are listed below:

A.

Technical Specification 3.11.G.l.a requires that all fire rated assemblies separating systems important to safe shutdown within a fire a'rea shall be operable at all times or a fire watch must be established within one hour.

Contrary to the above, a

NRC inspector identified on July 28, 1991, that fire wrap had been removed from operable residual heat removal service water pump motor power cables in the intake structure and a fire watch was not established.

This fire wrap provides a one hour fire resistance barrier between redundant safe shutdown equipment, which do not meet the minimum 20 feet Appendix R separation criteria.

The fire wrap was removed on July 24, 1991, for Unit 3 walkdown inspection under an approved work order 91-35664-00, although walkdown inspections for Unit 2 had previously been performed in this area."

1.

Reason for the Violation The root cause was Field Services-Modifications management failure to ensure that Unit 3 planning and implementation of work was in full compliance with site procedures.

, Two ma)or contributing factors were inadequate verbal communications and management's failure to ensure the existence of a complete training matrix in Field Services that

identified all training needed to adequately perform a particular function.

The missed fire watch was a direct result of personnel not following procedures.

The fire wrap was removed by an approved work order on July 24, 1991, to support Unit 3 Walkdown activities.

A one hour fire watch was not established because TVA personnel did not follow procedures and failed to initiate an Attachment F as required by FPP-2, Fire Protection-Attachments.

(Attachment F is the mechanism used to ensure that Fire Protection requirements, including the posting of fire watches, are met.)

The Attachment F was identified as a prerequisite in the work order.

The implementing organization reduced the amount of fire wrap to be removed and discussed the reduced scope of the job with fire protection to determine whether the Attachment F was still needed.

Due to miscommunication, the individuals (a craft foreman and a fire protection operator) involved in this discussion concluded that an Attachment F was not required.

The foreman then started the work without an Attachment F.

This resulted in the removal of a fire barrier without establishing the compensatory fire. watch.

The governing procedure, SDSP 7.6 Maintenance Management

System, requires that if the work scope changes or the work cannot be performed then the work order should be evaluated for re-planning.

Corrective Ste s Taken and Results Achieved As an immediate action, a fire watch was established at 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br /> on July 28,

1991, and maintained until the fire wrap was replaced on August 2,

1991.

Unit 3 work activities-were stopped until TVA determined root cause and appropriate corrective action.

The following event specific corrective actions were taken for the failure of personnel to follow procedures.'lanners and craft personnel were specifically instructed on the procedural requirement that the planner is to initiate an Attachment F if fire protection equipment or barriers are involved in the work activity.

Fire Protection operators have been instructed to perform a physical review of work packages prior to providing Fire Protection requirements.

Personnel corrective action, in accordance with TVA policy, was administered to the individuals who failed to follow procedure.

Corrective actions taken for management's failure to ensure full compliance to procedures were as follows:

The Field Services Manager briefed Field Services personnel on the requirement of supervision to be knowledgeable of and to adhere to procedural and policy requirements.

Written duties and responsibilities for Field Services-Modifications personnel were developed, and discussed to clarify job requirements for these individuals.

An enhanced training matrix was developed for Field Services personnel.

The training requirements for Field Services'

positions were verified adequate.

Training identified in the enhanced training matrix was completed before plant related activities were resumed.

Operational sensitivity training was given to the Unit 3 field and engineering personnel.

This training included a review of this specific incident, fire protection, environmental qualification, seismic issues, unit separation, and the changed operational environment due to Unit 2 operations.

TVA has also taken action to improve the control of inspection requests for Unit 3 components in systems that are required to be operable for Unit 2 power operation or Unit 3 layup.

Training was given on the use of color-coded separation drawings.

Walkdown procedures were revised to require the categorization of physical work involved during the walkdowns and to require engineering review and approval of walkdowns requiring physical work within Unit 2 operating spaces.

Walkdowns in Unit 2 operating spaces are to be scheduled by Unit 2 Operations.

These actions should minimize unnecessary walkdowns.

In order to verify the effectiveness of these improvements, contractor walkdown activities are being resumed using a phased approach.

Walkdowns involving Unit 3 systems or components requiring no physical work were started first.

Walkdowns involving Unit 3 systems or components not in Unit 2 areas requiring physical work were resumed next.

Finally, Walkdowns involving Unit 3 systems or components that are required for Unit 2/Unit 3 operations or require physical work in Unit 2 are being resumed.

3.

Corrective Ste s That Will Be Taken to Avoid Further Violations Corrective actions described above are complete and are considered adequate to preclude recurrence.

4 ~

Date When Full Com liance Will Be Achieved TVA was in compliance on September 9,

1991.

RESTATEMENT OF VIOLATION 91-26>>03 Technical Specification Section 6.8.1.1.a, requires that written procedures be established and implemented covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

This includes procedures for refueling equipment operation.

0

Procedure 3-ST-91-03, Unit 3 Fuel Sipping, required that fuel bundle movements be in accordance with 3-GOI-100-3, Refueling Operations, and the Fuel Assembly Transfer Forms.

Procedure 3-GOI-100-3, step 5.4.6, required that all steps on the Fuel Assembly Transfer Forms be performed line by line.

Contrary to the above, on June 29,

1991, and July 6, 1991, during the performance of fuel sipping, fuel assemblies were placed in Unit 3 spent fuel storage pool locations other than those required by the approved Fuel Assembly Transfer Forms.

The second event occurred after the implementation of corrective actions taken for the first event which included first and second party.verification of both the fuel assembly

. serial number and spent fuel storage pool location."

1.

Reason for the Violation Procedure 3-ST-91-03, which controlled the fuel sipping activities, required that fuel 'bundle movements be performed in accordance with 3-GOI-100-3 and SDSP 26.1, Special Nuclear Material (SNM) Management.

TVA decided to use the fuel transfer form from SDSP 26.1, and use row-rack-column location with single party verification to account for fuel during fuel sipping activities.

On June 29, during the performance of Unit 3 fuel sipping activities, a fuel movement error occurred due to fuel handlers incorrectly identifying and moving a fuel assembly different from that identified by the transfer form.

The fuel movement error was attributed to personnel error and failure to follow procedures.

Prior to restarting fuel moves on July 1, TVA decided to add second party verification and also use the fuel assembly serial number during the remaining fuel moves.

On July 6, 1991, during the Unit 3 fuel sipping activities, a sequence of three fuel movement errors was discovered.

Fuel movement was halted pending investigation.

This second incident was also attributed to personnel error (misidentification of fuel assemblies) and failure to follow procedures.

SFSP rack location was performed but not by row-rack-column per the fuel handling training and procedure 3-GOI-100.3.

Fuel handlers were identifying the rack location based on the routine of fuel assembly movements in the rack.

First and second party verifications were performed based on this pattern of fuel movement.

The practice of reading the serial number off transfer form sheets before attempting to read it off the fuel assembly bail handle allowed verification errors to be introduced into the process.

Also, the bridge operator was relying on the spotter for confirmation of the fuel assembly serial number instead of reading the serial number directly from the transfer form.

0

2.

Corrective Ste s Taken gad Results Achieved After the first incident (June 29, 1991), the fuel assembly was immediately returned to its proper location and the surrounding fuel assemblies'ocations were verified correct.

An incident investigation was initiated to determine the cause and identify appropriate corrective action.

As a corrective action, fuel handlers were briefed on the importance of correctly identifying the SFSP rack locations.

An additional pre-)ob briefing was held to address second party verification requirements prior to resuming fuel sipping activities.

This corrective action was not effective as evidenced by the second incident on July 6, 1991 involving a sequence of fuel movement errors.

The fuel assemblies'ocations were verified and a field change to the transfer form was generated to permit return of the fuel assemblies to their correct rack location.

An incident investigation was conducted to determine the cause and appropriate corrective action.

This time the fuel handlers were counselled as a group and individually on the importance of performing second party verification.

Communications were improved by placing a supervisor on the bridge to monitor fuel handling activities and communications.

An operator's communication aid (list of questions) was established to formalize oral communications between the bridge and the Senior Reactor Operator (SRO),

and a radio was provided to the bridge and the SRO to assist in communications.

Personnel corrective action, in accordance with contractor policies, was administered to the personnel involved.

Special Test 3-ST-91-03, Unit 3 Fuel Sipping, was completed on July 13, 1991.

No further fuel movement errors occurred during the remaining sipping activities, which required the movement of approximately 590 fuel assemblies.

The fuel sipping involved the handling of a total of 1004 assemblies.

3.

Corrective Ste s That Will Be Taken to Avoid Further Violations Corrective actions described above are complete and are considered adequate to preclude recurrence.

4.

Date When Full Com liance Will Be Achieved TVA was in compliance on July 26, 1991 with the completion of contractor corrective actions.