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{{#Wiki_filter:acczz.~PgggggAX,DIgW~VTIQN, sYisŽACCESSION NBR:9303300135, DOC.DATE: 93/03/24 NOTARIZED: | {{#Wiki_filter:acczz.~PgggggAX,DIgW~VTIQN, sYisŽACCESSION NBR:9303300135, DOC.DATE: 93/03/24 NOTARIZED: | ||
NO ACIL:50-259 | NO ACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION ZERINGUE,O.J. | ||
Browns Ferry Nuclear Power Station, Unit 1, Tennessee 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION | Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk.)DOCKET 05000259 05000260 05000296 | ||
ZERINGUE,O.J. | |||
Tennessee Valley Authority RECIP.NAME | ==SUBJECT:== | ||
RECIPIENT AFFILIATION | Responds to NRC 930225 ltr re violations noted in insp repts 50-259/93-02,50-260/93-02 | ||
Document Control Branch (Document Control Desk.)DOCKET 05000259 05000260 05000296 SUBJECT: Responds to NRC 930225 ltr re violations | &50-296/93-02.C/As:containment purge&SBGT sys evaluated&recommendations included in sys procedures for appropriate recurrence control.DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES: RECIPIENT ID CODE/NAME HEBDONiF WILLIAMSgJ. | ||
noted in insp repts 50-259/93-02,50-260/93-02 | INTERNAL: ACRS AEOD/DSP/TPAB DEDRO t NRR/DRCH/HHFBPT NRR/DRSS/PEPB NRR PMAS/ILPB2 G FIL 02 RGN2 FILE 01 EXTERNAL EG&G/BRYCE i J~H~NSIC COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1-1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME ROSS,T.AEOD/DEIB AEOD/TTC NRR/DORS/OEAB NRR/DRIL/RPEB NRR/PMAS/ILPBl NUDOCS-ABSTRACT OGC/HDS3 RES MORISSEAU,D NRC PDR COPIES LTTR ENCL 1 1 1 1'1 1 1 1 1 1 1 1 1 1 1 1.1 1 1 0 NOTE TO ALL"RIDS" RECIPIENTS: | ||
&50-296/93-02.C/As:containment | PLEASE IIELP US TO REDUCE WASTE!CONTACT TIIE DOCUMEN'I'ONTROL DI>V, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTlON LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24 | ||
purge&SBGT sys evaluated&recommendations | |||
included in sys procedures | Tennessee Valley Autttority, Post Olfice Box 2OOO.Decatur, Alabama 35609-WOO O.J."Ike" Zeringue Vice PresldenlBrowns Perry Nuclea Pia~t MAR 34 1993 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen: | ||
for appropriate | 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, 50-260, 296/93-02 REPLY TO NOTICE OF VIOLATION (NOV)This letter provides TVA's reply to the NOV transmitted by letter from Paul J.Kellogg to M.0.Medford dated February 25, 1993.In the transmitted letter, NRC cited TVA with a technical specifications violation. | ||
recurrence | This violation had three examples for failure to conduct required surveillance tests.Example 1 discussed a failure to perform the Unit 2 refueling crane prerequisite surveillance test prior to fuel movement.Example 2 identified a missed halogenated hydrocarbon test on the Unit 2 train B CREV unit.Example 3 characterized a foreman that missed a prerequisite signoff.As described in the enclosures of this letter, TVA agrees that the violation occurred as stated.Enclosure 1 provides TVA's"Reply to the Notice of Violation" (10 CFR 2.201).280i2i 9303300i35 930324 PDR ADDCK 05000259 8'PDR~(p0 | ||
control.DISTRIBUTION | |||
CODE: IE01D COPIES RECEIVED:LTR | U.S.Nuclear Regulatory Commission eR 2,4 l993 If you have any questions regarding this reply, please telephone G.D.Pierce at (205)729-7566.Sincer'ely, (i'Z(((i(g(. | ||
ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice | 0 J.Zeringue.Enclosure cc (Enclosure): | ||
of Violation Response NOTES: RECIPIENT ID CODE/NAME HEBDONiF WILLIAMSgJ. | NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 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 s | ||
INTERNAL: ACRS AEOD/DSP/TPAB | ,)EHCLOSURE Tennessee Valley Authority Browns Ferry Huclear Plant (BFH)Reply to Hotice of Violation (HOV)Inspection Report Humber 50-25 260 2 6 93-02 RESTATEMENT OF VIOLATION"Technical Specification 6.8.1, Procedures, requires that written procedures shall be established, implemented, and maintained covering surveillance and test activities and the activities recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February,1978. | ||
DEDRO t NRR/DRCH/HHFBPT | Appendix A of Regulatory Guide 1.33 includes administrative procedures for performing maintenance. | ||
NRR/DRSS/PEPB | Contrary to the above, these requirements were not met for the following three examples: Technical Specification 4.10.D requires the Reactor Building crane operability surveillance, Surveillance Instruction 0-4.10.D, be performed prior to the handling of new fuel.Between January 10 and January 18, 1993 new fuel was handled with the Reactor Building crane: without first performing this surveillance. | ||
NRR PMAS/ILPB2 | This was identified by the licensee on January 27, 1993.2.Site Standard Practice 6.50, Post-Maintenance Testing, Section'3.1.2 requires that post-maintenance testing shall be sufficiently comprehensive to ensure that corrective and/or preventive maintenance work does not adversely affect equipment operability. | ||
G FIL 02 RGN2 FILE 01 EXTERNAL EG&G/BRYCE | On November 28, 1992, a seven day limiting condition for operation was entered,to perform maintenance on the Control Room Emergency Ventilation Unit B.The unit was breached and internal charcoal trays removed during this maintenance activity.Following its replacement on November 29, 1992, Surveillance Instruction 0-4.7.E.3.B was not performed as required to verify the maintenance activity did not adversely affect its operability. | ||
i J~H~NSIC COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1-1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME ROSS,T.AEOD/DEIB AEOD/TTC NRR/DORS/OEAB | This was identified by the licensee on December 30, 1992.3.Site Standard Practice 6.2, Maintenance Management System, provides for the planning and performance of work orders.This instruction was not followed when on February ll, 1993, an NRC inspector identified work being conducted on the High Pre'ssure Coolant'Injection system using Work Order 93-00507-1 without the job pre-requisites being signed by the foreman as having been verified.This is a Severity Level IV Violation (Supplement I)applicable to all three units." | ||
NRR/DRIL/RPEB | ~2 REPLY TO EXAMPLE 1 l.Reason for Example 1 This event was a result of ambiguous or missing instructions as to who should signoff a prerequisite verification step 4.3.1 of General Operating Instruction for new fuel operations. | ||
NRR/PMAS/ILPBl | As a contributing factor to this event, there was a lack of formal guidance to determine the status of completed SIs.Knowledge of whether or not an SI had been performed is not necessarily information that the refuel floor shift manager or mechanical foreman would have available. | ||
NUDOCS-ABSTRACT | Nevertheless, the refuel floor'shift manager signed off the step after the mechanical foreman stated that SI had been performed. | ||
OGC/HDS3 RES MORISSEAU,D | 2.Corrective Steps Taken and Results Achieved New fuel receipt and inspection activities involving use of the overhead crane to handle fuel bundles and spent fuel casks were immediately suspended. | ||
NRC PDR COPIES LTTR ENCL 1 1 1 1'1 1 1 1 1 1 1 1 1 1 1 1.1 1 1 0 NOTE TO ALL"RIDS" RECIPIENTS: | The reactor building crane surveillance to check and inspect the overhead crane on the refuel floor was performed and successfully completed. | ||
PLEASE IIELP US TO REDUCE WASTE!CONTACT TIIE DOCUMEN'I'ONTROL | GOIs were revised to identify work control as the required signoff organization to verify SI completion. | ||
DI>V, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTlON | Operations personnel were instructed to verify the latest performance of SIs through work control.3.Corrective Steps That[have been or]Will Be Taken To Prevent Recurrence No further actions are required to preclude recurrence of this violation. | ||
LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24 | 4.Date When Full Compliance Will Be Achieved TVA considers that full compliance was met when Operations personnel were instructed to verify the latest performance of SIs through work control and when the GOIs were revised on March 12, 1993. | ||
REPLY TO EXAMPLE 2 Reason for Example 2 This event was a result of issuing the work order without sufficient details and insufficient procedural controls which allowed inappropriate removal of the charcoal adsorber tray.This resulted in a lack of a detailed maintenance procedure for the disassembling of the CREV units.Therefore, no disassembly or special requirements was provided in the System, Instrument Maintenance Index (SIMI).This lack of a maintenance procedure affected both the planners and the craftsmen in the performance of their work activities. | |||
Tennessee Valley Autttority, Post Olfice Box 2OOO.Decatur, Alabama 35609-WOO O.J."Ike" Zeringue Vice PresldenlBrowns | A contributing factor to this event is that the calibration of the temperature instrument is a new preventive maintenance activity.The SIMI documents generally provide special requirements and configuration changes involved in calibration of a component, and the SIMI document was reviewed during the preparation of the work order.However, at the time of the activity (or event), the referenced SIMI for this work plan did not contain any special notes or disassembly information. | ||
Perry Nuclea Pia~t MAR 34 1993 U.S.Nuclear Regulatory | Consequently, the work plan did not include sufficient instructions for disassembling the CREV unit.As with the work order planners, the craftsmen reviewed the applicable SIMI document.Since the SIMI document did not contain any specific configuration control information, the craftsmen also presumed that no configuration changes were required.Consequently, the charcoal adsorber trays were removed to gain access to a temperature instrument without documenting the activity as a configuration change as required by the procedure. | ||
Commission | 2.Corrective Steps Taken and Results Achieved Upon being informed of the condition, Operations personnel declared the CREV train B inoperable, and a seven-day limiting condition for operation (LCO)was entered.A halogenated hydrocarbon test was initiated and satisfactorily completed after which operability of CREV train B was reestablished. | ||
ATTN: Document Control Desk Washington, D.C.20555 Gentlemen: | The applicable SIMI document was revised to include information on the configuration changes associated with calibrating of the temperature instrument. | ||
In the Matter of Tennessee Valley Authority Docket Nos.50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)-NRC INSPECTION | Preventive maintenance task files were revised to include specific steps for disassembling of the CREV units. | ||
REPORT 50-259, 50-260, 296/93-02 REPLY TO NOTICE OF VIOLATION (NOV)This letter provides TVA's reply to the NOV transmitted | Training was conducted with maintenance personnel concerning the circumstances surrounding this event.The containment purge and standby gas treatment systems were evaluated, and recommendations were included in these system procedures for appropriate recurrence control.Finally, procedures for performing both troubleshooting and configuration control of instruments and electrical equipment were revised.These revisions ensure that intrusive disassembly of major plant equipment is no longer allowed without proper administrative controls.3.Corrective"Steps That[have been or]Will Be Taken To Prevent Recurrence No further actions are required to preclude recurrence of this violation. | ||
by letter from Paul J.Kellogg to M.0.Medford dated February 25, 1993.In the transmitted | 4..Date When Full Compliance Will Be Achieved TVA considers that full compliance occurred when appropriate procedures were revised on March 5, 1993.REPLY TO EXAMPLE 3 l.Reason For Example 3 This violation example is the result of a lack of attention to details.Electrical maintenance personnel were disconnecting the electric operator on a motor operated valve in support of mechanical maintenance activities. | ||
letter, NRC cited TVA with a technical specifications | |||
violation. | |||
This violation had three examples for failure to conduct required surveillance | |||
tests.Example 1 discussed a failure to perform the Unit 2 refueling crane prerequisite | |||
surveillance | |||
test prior to fuel movement.Example 2 identified | |||
a missed halogenated | |||
hydrocarbon | |||
test on the Unit 2 train B CREV unit.Example 3 characterized | |||
a foreman that missed a prerequisite | |||
signoff.As described in the enclosures | |||
of this letter, TVA agrees that the violation occurred as stated.Enclosure 1 provides TVA's"Reply to the Notice of Violation" (10 CFR 2.201).280i2i 9303300i35 | |||
930324 PDR ADDCK 05000259 8'PDR~(p0 | |||
U.S.Nuclear Regulatory | |||
Commission | |||
eR 2,4 l993 If you have any questions regarding this reply, please telephone G.D.Pierce at (205)729-7566.Sincer'ely, (i'Z(((i(g(. | |||
0 J.Zeringue.Enclosure | |||
cc (Enclosure): | |||
NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 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 | |||
s | |||
,)EHCLOSURE Tennessee Valley Authority Browns Ferry Huclear Plant (BFH)Reply to Hotice of Violation (HOV)Inspection | |||
Report Humber 50-25 260 2 6 93-02 RESTATEMENT | |||
OF VIOLATION"Technical | |||
Specification | |||
6.8.1, Procedures, requires that written procedures | |||
shall be established, implemented, and maintained | |||
covering surveillance | |||
and test activities | |||
and the activities | |||
recommended | |||
in Appendix A of Regulatory | |||
Guide 1.33, Revision 2, February,1978. | |||
Appendix A of Regulatory | |||
Guide 1.33 includes administrative | |||
procedures | |||
for performing | |||
maintenance. | |||
Contrary to the above, these requirements | |||
were not met for the following three examples: Technical Specification | |||
4.10.D requires the Reactor Building crane operability | |||
surveillance, Surveillance | |||
Instruction | |||
0-4.10.D, be performed prior to the handling of new fuel.Between January 10 and January 18, 1993 new fuel was handled with the Reactor Building crane: without first performing | |||
this surveillance. | |||
This was identified | |||
by the licensee on January 27, 1993.2.Site Standard Practice 6.50, Post-Maintenance | |||
Testing, Section'3.1.2 requires that post-maintenance | |||
testing shall be sufficiently | |||
comprehensive | |||
to ensure that corrective | |||
and/or preventive | |||
maintenance | |||
work does not adversely affect equipment operability. | |||
On November 28, 1992, a seven day limiting condition for operation was entered,to | |||
perform maintenance | |||
on the Control Room Emergency Ventilation | |||
Unit B.The unit was breached and internal charcoal trays removed during this maintenance | |||
activity.Following its replacement | |||
on November 29, 1992, Surveillance | |||
Instruction | |||
0-4.7.E.3.B | |||
was not performed as required to verify the maintenance | |||
activity did not adversely affect its operability. | |||
This was identified | |||
by the licensee on December 30, 1992.3.Site Standard Practice 6.2, Maintenance | |||
Management | |||
System, provides for the planning and performance | |||
of work orders.This instruction | |||
was not followed when on February ll, 1993, an NRC inspector identified | |||
work being conducted on the High Pre'ssure Coolant'Injection | |||
system using Work Order 93-00507-1 | |||
without the job pre-requisites | |||
being signed by the foreman as having been verified.This is a Severity Level IV Violation (Supplement | |||
I)applicable | |||
to all three units." | |||
~2 REPLY TO EXAMPLE 1 l.Reason for Example 1 This event was a result of ambiguous or missing instructions | |||
as to who should signoff a prerequisite | |||
verification | |||
step 4.3.1 of General Operating Instruction | |||
for new fuel operations. | |||
As a contributing | |||
factor to this event, there was a lack of formal guidance to determine the status of completed SIs.Knowledge of whether or not an SI had been performed is not necessarily | |||
information | |||
that the refuel floor shift manager or mechanical | |||
foreman would have available. | |||
Nevertheless, the refuel floor'shift | |||
manager signed off the step after the mechanical | |||
foreman stated that SI had been performed. | |||
2.Corrective | |||
Steps Taken and Results Achieved New fuel receipt and inspection | |||
activities | |||
involving use of the overhead crane to handle fuel bundles and spent fuel casks were immediately | |||
suspended. | |||
The reactor building crane surveillance | |||
to check and inspect the overhead crane on the refuel floor was performed and successfully | |||
completed. | |||
GOIs were revised to identify work control as the required signoff organization | |||
to verify SI completion. | |||
Operations | |||
personnel were instructed | |||
to verify the latest performance | |||
of SIs through work control.3.Corrective | |||
Steps That[have been or]Will Be Taken To Prevent Recurrence | |||
No further actions are required to preclude recurrence | |||
of this violation. | |||
4.Date When Full Compliance | |||
Will Be Achieved TVA considers that full compliance | |||
was met when Operations | |||
personnel were instructed | |||
to verify the latest performance | |||
of SIs through work control and when the GOIs were revised on March 12, 1993. | |||
REPLY TO EXAMPLE 2 Reason for Example 2 This event was a result of issuing the work order without sufficient | |||
details and insufficient | |||
procedural | |||
controls which allowed inappropriate | |||
removal of the charcoal adsorber tray.This resulted in a lack of a detailed maintenance | |||
procedure for the disassembling | |||
of the CREV units.Therefore, no disassembly | |||
or special requirements | |||
was provided in the System, Instrument | |||
Maintenance | |||
Index (SIMI).This lack of a maintenance | |||
procedure affected both the planners and the craftsmen in the performance | |||
of their work activities. | |||
A contributing | |||
factor to this event is that the calibration | |||
of the temperature | |||
instrument | |||
is a new preventive | |||
maintenance | |||
activity.The SIMI documents generally provide special requirements | |||
and configuration | |||
changes involved in calibration | |||
of a component, and the SIMI document was reviewed during the preparation | |||
of the work order.However, at the time of the activity (or event), the referenced | |||
SIMI for this work plan did not contain any special notes or disassembly | |||
information. | |||
Consequently, the work plan did not include sufficient | |||
instructions | |||
for disassembling | |||
the CREV unit.As with the work order planners, the craftsmen reviewed the applicable | |||
SIMI document.Since the SIMI document did not contain any specific configuration | |||
control information, the craftsmen also presumed that no configuration | |||
changes were required.Consequently, the charcoal adsorber trays were removed to gain access to a temperature | |||
instrument | |||
without documenting | |||
the activity as a configuration | |||
change as required by the procedure. | |||
2.Corrective | |||
Steps Taken and Results Achieved Upon being informed of the condition, Operations | |||
personnel declared the CREV train B inoperable, and a seven-day limiting condition for operation (LCO)was entered.A halogenated | |||
hydrocarbon | |||
test was initiated and satisfactorily | |||
completed after which operability | |||
of CREV train B was reestablished. | |||
The applicable | |||
SIMI document was revised to include information | |||
on the configuration | |||
changes associated | |||
with calibrating | |||
of the temperature | |||
instrument. | |||
Preventive | |||
maintenance | |||
task files were revised to include specific steps for disassembling | |||
of the CREV units. | |||
Training was conducted with maintenance | |||
personnel concerning | |||
the circumstances | |||
surrounding | |||
this event.The containment | |||
purge and standby gas treatment systems were evaluated, and recommendations | |||
were included in these system procedures | |||
for appropriate | |||
recurrence | |||
control.Finally, procedures | |||
for performing | |||
both troubleshooting | |||
and configuration | |||
control of instruments | |||
and electrical | |||
equipment were revised.These revisions ensure that intrusive disassembly | |||
of major plant equipment is no longer allowed without proper administrative | |||
controls.3.Corrective"Steps That[have been or]Will Be Taken To Prevent Recurrence | |||
No further actions are required to preclude recurrence | |||
of this violation. | |||
4..Date When Full Compliance | |||
Will Be Achieved TVA considers that full compliance | |||
occurred when appropriate | |||
procedures | |||
were revised on March 5, 1993.REPLY TO EXAMPLE 3 l.Reason For Example 3 This violation example is the result of a lack of attention to details.Electrical | |||
maintenance | |||
personnel were disconnecting | |||
the electric operator on a motor operated valve in support of mechanical | |||
maintenance | |||
activities. | |||
The craftsman signed off step 1.0 of the work instructions. | The craftsman signed off step 1.0 of the work instructions. | ||
This signature affirmed that the craftsman reviewed and understood | This signature affirmed that the craftsman reviewed and understood the precautions/limitations and work instructions. | ||
the precautions/limitations | The next step in'the work instructions (1.1)required a Foreman/Designee to sign off that the prerequisites of the instructions have been met.However, the craftsman,did not sign off the step as the designee or obtain a foreman's signature prior to proceeding to the next step.Contributing factors for this oversight are: (1)In other work instructions, the step which requires a concurrence signature that the prerequisites have been met is generally the foreman's responsibility. | ||
and work instructions. | In the work instruction, there is no option for a designee to sign off that the prerequisites were met.Therefore, the craftsman did not sign off step 1.1 of this work instruction as'I | ||
The next step in'the work instructions | |||
(1.1)required a Foreman/Designee | |||
to sign off that the prerequisites | |||
of the instructions | |||
have been met.However, the craftsman,did | |||
not sign off the step as the designee or obtain a foreman's signature prior to proceeding | |||
to the next step.Contributing | |||
factors for this oversight are: (1)In other work instructions, the step which requires a concurrence | |||
signature that the prerequisites | |||
have been met is generally the foreman's responsibility. | |||
In the work instruction, there is no option for a designee to sign off that the prerequisites | |||
were met.Therefore, the craftsman did not sign off step 1.1 of this work instruction | |||
as'I | |||
(. | (. | ||
'l the designee.(2)Even though the individual | 'l the designee.(2)Even though the individual who was the foreman for this event has received an orientation on BFN expectations for foreman activities, the foreman had just been promoted for the Unit 2 refueling outage.Therefore, he was not fully aware of all the responsibilities of the position.2.Corrective Steps Taken and Results Achieved Work activities on this MOV repair were immediately suspended. | ||
who was the foreman for this event has received an orientation | The foreman on this work activity was interviewed and subsequently the foreman resigned from the position.A meeting was conducted with electric maintenance foremen and craftsmen to emphasize the need to pay attention to details and to emphasize work expectations during outages.3.Corrective Steps That[have been or]Will Be Taken To Prevent Recurrence No further actions are required to preclude recurrence of this violation. | ||
on BFN expectations | 4.Date When Full Compliance Will Be Achieved TVA considers that full compliance was met when the individual resigned the position and after the work expectation meeting was conducted. | ||
for foreman activities, the foreman had just been promoted for the Unit 2 refueling outage.Therefore, he was not fully aware of all the responsibilities | [-}} | ||
of the position.2.Corrective | |||
Steps Taken and Results Achieved Work activities | |||
on this MOV repair were immediately | |||
suspended. | |||
The foreman on this work activity was interviewed | |||
and subsequently | |||
the foreman resigned from the position.A meeting was conducted with electric maintenance | |||
foremen and craftsmen to emphasize the need to pay attention to details and to emphasize work expectations | |||
during outages.3.Corrective | |||
Steps That[have been or]Will Be Taken To Prevent Recurrence | |||
No further actions are required to preclude recurrence | |||
of this violation. | |||
4.Date When Full Compliance | |||
Will Be Achieved TVA considers that full compliance | |||
was met when the individual | |||
resigned the position and after the work expectation | |||
meeting was conducted. | |||
[- | |||
}} | |||
Revision as of 02:09, 17 August 2019
| ML18036B215 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 03/24/1993 |
| From: | Zeringue O TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9303300135 | |
| Download: ML18036B215 (13) | |
Text
acczz.~PgggggAX,DIgW~VTIQN, sYisŽACCESSION NBR:9303300135, DOC.DATE: 93/03/24 NOTARIZED:
NO ACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION ZERINGUE,O.J.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk.)DOCKET 05000259 05000260 05000296
SUBJECT:
Responds to NRC 930225 ltr re violations noted in insp repts 50-259/93-02,50-260/93-02
&50-296/93-02.C/As:containment purge&SBGT sys evaluated&recommendations included in sys procedures for appropriate recurrence control.DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES: RECIPIENT ID CODE/NAME HEBDONiF WILLIAMSgJ.
INTERNAL: ACRS AEOD/DSP/TPAB DEDRO t NRR/DRCH/HHFBPT NRR/DRSS/PEPB NRR PMAS/ILPB2 G FIL 02 RGN2 FILE 01 EXTERNAL EG&G/BRYCE i J~H~NSIC COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1-1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME ROSS,T.AEOD/DEIB AEOD/TTC NRR/DORS/OEAB NRR/DRIL/RPEB NRR/PMAS/ILPBl NUDOCS-ABSTRACT OGC/HDS3 RES MORISSEAU,D NRC PDR COPIES LTTR ENCL 1 1 1 1'1 1 1 1 1 1 1 1 1 1 1 1.1 1 1 0 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE IIELP US TO REDUCE WASTE!CONTACT TIIE DOCUMEN'I'ONTROL DI>V, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTlON LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24
Tennessee Valley Autttority, Post Olfice Box 2OOO.Decatur, Alabama 35609-WOO O.J."Ike" Zeringue Vice PresldenlBrowns Perry Nuclea Pia~t MAR 34 1993 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, 50-260, 296/93-02 REPLY TO NOTICE OF VIOLATION (NOV)This letter provides TVA's reply to the NOV transmitted by letter from Paul J.Kellogg to M.0.Medford dated February 25, 1993.In the transmitted letter, NRC cited TVA with a technical specifications violation.
This violation had three examples for failure to conduct required surveillance tests.Example 1 discussed a failure to perform the Unit 2 refueling crane prerequisite surveillance test prior to fuel movement.Example 2 identified a missed halogenated hydrocarbon test on the Unit 2 train B CREV unit.Example 3 characterized a foreman that missed a prerequisite signoff.As described in the enclosures of this letter, TVA agrees that the violation occurred as stated.Enclosure 1 provides TVA's"Reply to the Notice of Violation" (10 CFR 2.201).280i2i 9303300i35 930324 PDR ADDCK 05000259 8'PDR~(p0
U.S.Nuclear Regulatory Commission eR 2,4 l993 If you have any questions regarding this reply, please telephone G.D.Pierce at (205)729-7566.Sincer'ely, (i'Z(((i(g(.
0 J.Zeringue.Enclosure cc (Enclosure):
NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 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 s
,)EHCLOSURE Tennessee Valley Authority Browns Ferry Huclear Plant (BFH)Reply to Hotice of Violation (HOV)Inspection Report Humber 50-25 260 2 6 93-02 RESTATEMENT OF VIOLATION"Technical Specification 6.8.1, Procedures, requires that written procedures shall be established, implemented, and maintained covering surveillance and test activities and the activities recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February,1978.
Appendix A of Regulatory Guide 1.33 includes administrative procedures for performing maintenance.
Contrary to the above, these requirements were not met for the following three examples: Technical Specification 4.10.D requires the Reactor Building crane operability surveillance, Surveillance Instruction 0-4.10.D, be performed prior to the handling of new fuel.Between January 10 and January 18, 1993 new fuel was handled with the Reactor Building crane: without first performing this surveillance.
This was identified by the licensee on January 27, 1993.2.Site Standard Practice 6.50, Post-Maintenance Testing, Section'3.1.2 requires that post-maintenance testing shall be sufficiently comprehensive to ensure that corrective and/or preventive maintenance work does not adversely affect equipment operability.
On November 28, 1992, a seven day limiting condition for operation was entered,to perform maintenance on the Control Room Emergency Ventilation Unit B.The unit was breached and internal charcoal trays removed during this maintenance activity.Following its replacement on November 29, 1992, Surveillance Instruction 0-4.7.E.3.B was not performed as required to verify the maintenance activity did not adversely affect its operability.
This was identified by the licensee on December 30, 1992.3.Site Standard Practice 6.2, Maintenance Management System, provides for the planning and performance of work orders.This instruction was not followed when on February ll, 1993, an NRC inspector identified work being conducted on the High Pre'ssure Coolant'Injection system using Work Order 93-00507-1 without the job pre-requisites being signed by the foreman as having been verified.This is a Severity Level IV Violation (Supplement I)applicable to all three units."
~2 REPLY TO EXAMPLE 1 l.Reason for Example 1 This event was a result of ambiguous or missing instructions as to who should signoff a prerequisite verification step 4.3.1 of General Operating Instruction for new fuel operations.
As a contributing factor to this event, there was a lack of formal guidance to determine the status of completed SIs.Knowledge of whether or not an SI had been performed is not necessarily information that the refuel floor shift manager or mechanical foreman would have available.
Nevertheless, the refuel floor'shift manager signed off the step after the mechanical foreman stated that SI had been performed.
2.Corrective Steps Taken and Results Achieved New fuel receipt and inspection activities involving use of the overhead crane to handle fuel bundles and spent fuel casks were immediately suspended.
The reactor building crane surveillance to check and inspect the overhead crane on the refuel floor was performed and successfully completed.
GOIs were revised to identify work control as the required signoff organization to verify SI completion.
Operations personnel were instructed to verify the latest performance of SIs through work control.3.Corrective Steps That[have been or]Will Be Taken To Prevent Recurrence No further actions are required to preclude recurrence of this violation.
4.Date When Full Compliance Will Be Achieved TVA considers that full compliance was met when Operations personnel were instructed to verify the latest performance of SIs through work control and when the GOIs were revised on March 12, 1993.
REPLY TO EXAMPLE 2 Reason for Example 2 This event was a result of issuing the work order without sufficient details and insufficient procedural controls which allowed inappropriate removal of the charcoal adsorber tray.This resulted in a lack of a detailed maintenance procedure for the disassembling of the CREV units.Therefore, no disassembly or special requirements was provided in the System, Instrument Maintenance Index (SIMI).This lack of a maintenance procedure affected both the planners and the craftsmen in the performance of their work activities.
A contributing factor to this event is that the calibration of the temperature instrument is a new preventive maintenance activity.The SIMI documents generally provide special requirements and configuration changes involved in calibration of a component, and the SIMI document was reviewed during the preparation of the work order.However, at the time of the activity (or event), the referenced SIMI for this work plan did not contain any special notes or disassembly information.
Consequently, the work plan did not include sufficient instructions for disassembling the CREV unit.As with the work order planners, the craftsmen reviewed the applicable SIMI document.Since the SIMI document did not contain any specific configuration control information, the craftsmen also presumed that no configuration changes were required.Consequently, the charcoal adsorber trays were removed to gain access to a temperature instrument without documenting the activity as a configuration change as required by the procedure.
2.Corrective Steps Taken and Results Achieved Upon being informed of the condition, Operations personnel declared the CREV train B inoperable, and a seven-day limiting condition for operation (LCO)was entered.A halogenated hydrocarbon test was initiated and satisfactorily completed after which operability of CREV train B was reestablished.
The applicable SIMI document was revised to include information on the configuration changes associated with calibrating of the temperature instrument.
Preventive maintenance task files were revised to include specific steps for disassembling of the CREV units.
Training was conducted with maintenance personnel concerning the circumstances surrounding this event.The containment purge and standby gas treatment systems were evaluated, and recommendations were included in these system procedures for appropriate recurrence control.Finally, procedures for performing both troubleshooting and configuration control of instruments and electrical equipment were revised.These revisions ensure that intrusive disassembly of major plant equipment is no longer allowed without proper administrative controls.3.Corrective"Steps That[have been or]Will Be Taken To Prevent Recurrence No further actions are required to preclude recurrence of this violation.
4..Date When Full Compliance Will Be Achieved TVA considers that full compliance occurred when appropriate procedures were revised on March 5, 1993.REPLY TO EXAMPLE 3 l.Reason For Example 3 This violation example is the result of a lack of attention to details.Electrical maintenance personnel were disconnecting the electric operator on a motor operated valve in support of mechanical maintenance activities.
The craftsman signed off step 1.0 of the work instructions.
This signature affirmed that the craftsman reviewed and understood the precautions/limitations and work instructions.
The next step in'the work instructions (1.1)required a Foreman/Designee to sign off that the prerequisites of the instructions have been met.However, the craftsman,did not sign off the step as the designee or obtain a foreman's signature prior to proceeding to the next step.Contributing factors for this oversight are: (1)In other work instructions, the step which requires a concurrence signature that the prerequisites have been met is generally the foreman's responsibility.
In the work instruction, there is no option for a designee to sign off that the prerequisites were met.Therefore, the craftsman did not sign off step 1.1 of this work instruction as'I
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'l the designee.(2)Even though the individual who was the foreman for this event has received an orientation on BFN expectations for foreman activities, the foreman had just been promoted for the Unit 2 refueling outage.Therefore, he was not fully aware of all the responsibilities of the position.2.Corrective Steps Taken and Results Achieved Work activities on this MOV repair were immediately suspended.
The foreman on this work activity was interviewed and subsequently the foreman resigned from the position.A meeting was conducted with electric maintenance foremen and craftsmen to emphasize the need to pay attention to details and to emphasize work expectations during outages.3.Corrective Steps That[have been or]Will Be Taken To Prevent Recurrence No further actions are required to preclude recurrence of this violation.
4.Date When Full Compliance Will Be Achieved TVA considers that full compliance was met when the individual resigned the position and after the work expectation meeting was conducted.
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