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See also: [[followed by::IR 05000280/1996008]]


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{{#Wiki_filter:** * VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September  
{{#Wiki_filter:**
12, 1996 United States Nuclear Regulatory  
* VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 12, 1996 United States Nuclear Regulatory Commission Attention:
Commission  
Document Control Desk Washington, D. C. 20555 Gentlemen:
Attention:  
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 REPLY TO A NOTICE OF VIOLATION Serial No. 96-425 SPS/BCB/GDM R3 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 NRC INSPECTlON REPORT NOS. 50-280/96-08 AND 50-281/96-08 We have reviewed your Inspection Report Nos. 50-280/96-08 and 50-281/96-08 dated July 11, 1996, and your August 16, 1996 letter and enclosed Notice of Violation for Surry Units 1 and 2. As discussed in the attachment, the cited violations resulted from inadequate change management when the hydrogen analyzers' calibration procedures were changed. This conclusion is based on the results of a Root Cause Evaluation of the event. We have implemented corrective actions to resolve the specific concerns associated with the violations, as well as more comprehensive actions to ensure that similar concerns do not exist. Although the violations were precipitated by events that occurred at Surry several years ago, we recognize that the procedure change process should have identified the procedural interface discrepancy.
Document Control Desk Washington, D. C. 20555 Gentlemen:  
This process was subsequently strengthened in the early 1990s and was recently enhanced further to preclude a similar event. We have no objection to this letter being made a part of the public record. Please contact us if you have any questions or require additional information.
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 REPLY TO A NOTICE OF VIOLATION  
Serial No. 96-425 SPS/BCB/GDM  
R3 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 NRC INSPECTlON  
REPORT NOS. 50-280/96-08  
AND 50-281/96-08  
We have reviewed your Inspection  
Report Nos. 50-280/96-08  
and 50-281/96-08  
dated July 11, 1996, and your August 16, 1996 letter and enclosed Notice of Violation  
for Surry Units 1 and 2. As discussed  
in the attachment, the cited violations  
resulted from inadequate  
change management  
when the hydrogen analyzers'  
calibration  
procedures  
were changed. This conclusion  
is based on the results of a Root Cause Evaluation  
of the event. We have implemented  
corrective  
actions to resolve the specific concerns associated  
with the violations, as well as more comprehensive  
actions to ensure that similar concerns do not exist. Although the violations  
were precipitated  
by events that occurred at Surry several years ago, we recognize  
that the procedure  
change process should have identified  
the procedural  
interface  
discrepancy.  
This process was subsequently  
strengthened  
in the early 1990s and was recently enhanced further to preclude a similar event. We have no objection  
to this letter being made a part of the public record. Please contact us if you have any questions  
or require additional  
information.  
Very truly yours, ~?.~ James P. O'Hanlon Senior Vice President  
Very truly yours, ~?.~ James P. O'Hanlon Senior Vice President  
-Nuclear Attachment  
-Nuclear Attachment 9609170471 960912 PDR ADOCK 05000280 G PDR ~--** .~. -*
9609170471  
1----:--cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W. Atlanta, Georgia 30323 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station   
960912 PDR ADOCK 05000280 G PDR ~--** .~. -*
** REPLY TO A NOTICE OF VIOLATION NRC INSPECTION CONDUCTED JUNE 17 -JULY 1, 1996 SURRY POWER STATION UNITS 1 AND 2 INSPECTION REPORT NOS. 50-280/96-08 AND 50-281/96-08 NRG COMMENT: "During an NRG inspection conducted on June 17 through July 1, 1996, violations of NRG requirements was identified.
1----:--cc: U.S. Nuclear Regulatory  
In accordance with the 'General Statement of Policy and Procedures for NRG Enforcement Actions,'
Commission  
NUREG-1600, the violations are listed below: A. Technical Specifications 3.7.G.1 requires that two independent containment hydrogen analyzers be operable during reactor critical or power operation.
Region II 101 Marietta Street, N.W. Atlanta, Georgia 30323 Mr. R. A. Musser NRC Senior Resident Inspector  
Contrary to the above, the Unit 1 and Unit 2 containment hydrogen analyzers were inGperable during reactor critical or power operation from February 28, 1991, and October 21, 1990, respectively, until May 22, 1996, due to the function selector switches being place in the ZERO position following calibration.
Surry Power Station   
(01013) B. Technical Specifications 6.4.A.1 and 6.4.A.2 require, in part, that detailed written procedures with appropriate instructions be provided for the operation, calibration and testing of all systems and components involving nuclear safety of the station. Contrary to the above, from October 24 and October 20, 1990 for Units 1 and 2, respectively, Emergency Operating Procedures*
** REPLY TO A NOTICE OF VIOLATION  
1-E-1 and 2-E-1, 'Loss of Reactor or Secondary Coolant,'
NRC INSPECTION  
and Calibration Procedures 1-IPT-FT-GW-A-104 and 2-IPT-FT-GW-A-204, Containment Hydrogen Analyzer H2A-GW-104(204)
CONDUCTED  
Quarterly Functional Test, did not provide appropriate instructions to place the hydrogen analyzers (systems involving nucle_ar safety of the station) in service. Specifically, the procedures did not require placing the function selector switches for the-hydrogen analyzers in the SAMPLE position, which is the required position for sampling the containment atmosphere for hydrogen concentration.
JUNE 17 -JULY 1, 1996 SURRY POWER STATION UNITS 1 AND 2 INSPECTION  
(01023) This is a Severity Level Ill problem (Supplement I)."
REPORT NOS. 50-280/96-08  
L__ ---Violation A REPLY TO A NOTICE OF VIOLATION NRC INSPECTION CONDUCTED JUNE 17-JULY 1.1996 SURRY POWER STATION UNITS 1 AND 2 INSPECTION REPORT NOS. 50-280/96-08 AND 50-281/96-08
AND 50-281/96-08  
: 1. Reason for the Violation, or, if Contested, the Basis for Disputing the Violation The violation is correct as stated and was caused by inadequate change management.
NRG COMMENT: "During an NRG inspection  
When the containment hydrogen analyzers' calibration procedures were changed to leave the function selector switch (FSS) on the local and remote panels in the ZERO position, the emergency operating procedures (EOP) did not include instructions to reposition the FSS to the SAMPLE position when placing the hydrogen analyzers in service. Although the ZERO pesition is acceptable for standby operation, the FSS must be in the SAMPLE position for the hydrogen analyzers to be capable of performing their design function.
conducted  
At the time of the subject change to the calibration procedures, a review of interfacing procedures was not required by the procedure change process. Consequently, a review of the interfacing procedures was not performed and the need to change the EOPs was not recognized.
on June 17 through July 1, 1996, violations  
As a result, a complementary change was not incorporated into the EOPs. This procedural discrepancy resulted in the FSSs being left in the ZERO position following calibration, thereby rendering the containment hydrogen analyzers inoperable for an extended period of time. 2. Corrective Steps Which Have Been Taken and the Results Achieved A Deviation Report was submitted to document the subject discrepancy.
of NRG requirements  
l&C and System Engineering personnel reviewed the vendor manual for the hydrogen analyzers to confirm the optimum operational position for the FSSs. The FSS on the local and remote panels were placed in the SAMPLE position on May 22, 1996. The hydrogen analyzer instrument calibration procedures were revised to provide instructions for placing the FSS on the local and remote panels in the SAMPLE position following calibration.
was identified.  
This is the required position to place the hydrogen analyzers in service using the emergency operating procedures.  
In accordance  
' . I I
with the 'General Statement  
* 2. Corrective Steps Which Have Been Taken and the Results Achieved (Cont'd.)
of Policy and Procedures  
A Root Cause Evaluation (RCE) of the event was performed.
for NRG Enforcement  
The results are summarized in Section 1 above. The RCE also determined that the North Anna Power Station operator watchstation logs periodically verified the position of the hydrogen analyzers' FSSs, and that the Surry logs did not. The Surry operator watchstation logs were subsequently revised to include a periodic verification that the FSSs are positioned correctly.
Actions,'  
In addition, a comparative review of the North Anna and Surry Power Stations' operator watchstation logs was performed to evaluate the commonality of equipment checks performed at each station. No safety equipment inconsistencies were identified.
NUREG-1600, the violations  
The Te.cbnical Specifications and emergency and abnormal procedures were reviewed by Operations and l&C personnel to evaluate infrequently performed evolutions and post-accident manual actions to determine whether additional procedural interface concerns existed. No additional examples were identified.
are listed below: A. Technical  
The procedure change process has been revised and improved since the subject hydrogen analyzer calibration procedure changes were processed.
Specifications  
These improvements are discussed in our response to Violation B. 3. Corrective Steps Which Will be Taken to Avoid Further Violations The corrective actions discussed in Section 2 are sufficient to avoid further violations.
3.7.G.1 requires that two independent  
A synopsis of this event is being presented during the current continuing training sessions to enhance the operators' knowledge and understanding of hydrogen analyzer operation.
containment  
Training will also be conducted for l&C technicians during the next l&C continuing training sessions.
hydrogen analyzers  
: 4. The Date When Full Compliance Will be Achieved Full compliance was achieved on May 22, 1996 when the FSS on the local and remote panels were placed in the SAMPLE position .
be operable during reactor critical or power operation.  
Violation B 1. Reason for the Violation, or, if Contested, the Basis for Disputing the Violation The violation is correct as stated. As discussed in Section 1 of Violation A, a review of interfacing procedures was not performed when the hydrogen analyzers' calibration procedures were changed. The procedure change process in place at the time the position of the FSSs was modified did not ensure that interfacing procedures were considered for potential impact. As a result, when the calibration procedures were changed to specify that the FSSs be left in the ZERO position following calibration, the emergency operating procedures were not changed to provide instructions for placing the FSSs in the SAMPLE position when placing the hydrogen analyzers in service. 2. Corrective Steps Which Have Been Taken and the Results Achieved As discblSsed in Section 2 of Violation A, the hydrogen analyzer instrument calibration procedures were revised to provide instructions for placing the FSS on the local and remote panels in the SAMPLE position following calibration.
Contrary to the above, the Unit 1 and Unit 2 containment  
This is the required position to place the hydrogen analyzers in service using the emergency operating procedures.
hydrogen analyzers  
The procedure change process has been revised and improved since the subject hydrogen analyzer calibration procedure changes were processed.
were inGperable  
Procedure revisions and upgrades have been centralized under the Procedures Department, and a technical procedures writer's guide has been developed to standardize format, style, content, and human factors considerations.
during reactor critical or power operation  
A technical review is required for new and revised procedures, and technical review guidelines have been established which address procedural methods, instructions, and configuration controls.
from February 28, 1991, and October 21, 1990, respectively, until May 22, 1996, due to the function selector switches being place in the ZERO position following  
In addition, administrative procedure VPAP-0502, "Procedure Process Control," has been revised to require an elevated level of review and approval when a procedural revision or change alters the as-left condition of a system or component.
calibration.  
This revision also added references to the Licensee Event Report and NRG Inspection Report associated with this violation.
(01013) B. Technical  
: 3. Corrective Steps Which Will be Taken to Avoid Further Violations The corrective actions noted in Section 2 of Violations A and B above are sufficient to avoid similar violations.   
Specifications  
** *
6.4.A.1 and 6.4.A.2 require, in part, that detailed written procedures  
* 4. The Date When Full Compliance Will be Achieved Full compliance was achieved on September 3, 1996 when VPAP-0502 was revised .}}
with appropriate  
instructions  
be provided for the operation, calibration  
and testing of all systems and components  
involving  
nuclear safety of the station. Contrary to the above, from October 24 and October 20, 1990 for Units 1 and 2, respectively, Emergency  
Operating  
Procedures*  
1-E-1 and 2-E-1, 'Loss of Reactor or Secondary  
Coolant,'  
and Calibration  
Procedures  
1-IPT-FT-GW-A-104  
and 2-IPT-FT-GW-A-204, Containment  
Hydrogen Analyzer H2A-GW-104(204)  
Quarterly  
Functional  
Test, did not provide appropriate  
instructions  
to place the hydrogen analyzers (systems involving  
nucle_ar safety of the station) in service. Specifically, the procedures  
did not require placing the function selector switches for the-hydrogen analyzers  
in the SAMPLE position, which is the required position for sampling the containment  
atmosphere  
for hydrogen concentration.  
(01023) This is a Severity Level Ill problem (Supplement  
I)."
L__ ---Violation  
A REPLY TO A NOTICE OF VIOLATION  
NRC INSPECTION  
CONDUCTED  
JUNE 17-JULY 1.1996 SURRY POWER STATION UNITS 1 AND 2 INSPECTION  
REPORT NOS. 50-280/96-08  
AND 50-281/96-08  
1. Reason for the Violation, or, if Contested, the Basis for Disputing  
the Violation  
The violation  
is correct as stated and was caused by inadequate  
change management.  
When the containment  
hydrogen analyzers'  
calibration  
procedures  
were changed to leave the function selector switch (FSS) on the local and remote panels in the ZERO position, the emergency  
operating  
procedures (EOP) did not include instructions  
to reposition  
the FSS to the SAMPLE position when placing the hydrogen analyzers  
in service. Although the ZERO pesition is acceptable  
for standby operation, the FSS must be in the SAMPLE position for the hydrogen analyzers  
to be capable of performing  
their design function.  
At the time of the subject change to the calibration  
procedures, a review of interfacing  
procedures  
was not required by the procedure  
change process. Consequently, a review of the interfacing  
procedures  
was not performed  
and the need to change the EOPs was not recognized.  
As a result, a complementary  
change was not incorporated  
into the EOPs. This procedural  
discrepancy  
resulted in the FSSs being left in the ZERO position following  
calibration, thereby rendering  
the containment  
hydrogen analyzers  
inoperable  
for an extended period of time. 2. Corrective  
Steps Which Have Been Taken and the Results Achieved A Deviation  
Report was submitted  
to document the subject discrepancy.  
l&C and System Engineering  
personnel  
reviewed the vendor manual for the hydrogen analyzers  
to confirm the optimum operational  
position for the FSSs. The FSS on the local and remote panels were placed in the SAMPLE position on May 22, 1996. The hydrogen analyzer instrument  
calibration  
procedures  
were revised to provide instructions  
for placing the FSS on the local and remote panels in the SAMPLE position following  
calibration.  
This is the required position to place the hydrogen analyzers  
in service using the emergency  
operating  
procedures.  
' . I I
* 2. Corrective  
Steps Which Have Been Taken and the Results Achieved (Cont'd.)  
A Root Cause Evaluation (RCE) of the event was performed.  
The results are summarized  
in Section 1 above. The RCE also determined  
that the North Anna Power Station operator watchstation  
logs periodically  
verified the position of the hydrogen analyzers'  
FSSs, and that the Surry logs did not. The Surry operator watchstation  
logs were subsequently  
revised to include a periodic verification  
that the FSSs are positioned  
correctly.  
In addition, a comparative  
review of the North Anna and Surry Power Stations'  
operator watchstation  
logs was performed  
to evaluate the commonality  
of equipment  
checks performed  
at each station. No safety equipment  
inconsistencies  
were identified.  
The Te.cbnical  
Specifications  
and emergency  
and abnormal procedures  
were reviewed by Operations  
and l&C personnel  
to evaluate infrequently  
performed  
evolutions  
and post-accident  
manual actions to determine  
whether additional  
procedural  
interface  
concerns existed. No additional  
examples were identified.  
The procedure  
change process has been revised and improved since the subject hydrogen analyzer calibration  
procedure  
changes were processed.  
These improvements  
are discussed  
in our response to Violation  
B. 3. Corrective  
Steps Which Will be Taken to Avoid Further Violations  
The corrective  
actions discussed  
in Section 2 are sufficient  
to avoid further violations.  
A synopsis of this event is being presented  
during the current continuing  
training sessions to enhance the operators'  
knowledge  
and understanding  
of hydrogen analyzer operation.  
Training will also be conducted  
for l&C technicians  
during the next l&C continuing  
training sessions.  
4. The Date When Full Compliance  
Will be Achieved Full compliance  
was achieved on May 22, 1996 when the FSS on the local and remote panels were placed in the SAMPLE position .
Violation  
B 1. Reason for the Violation, or, if Contested, the Basis for Disputing  
the Violation  
The violation  
is correct as stated. As discussed  
in Section 1 of Violation  
A, a review of interfacing  
procedures  
was not performed  
when the hydrogen analyzers'  
calibration  
procedures  
were changed. The procedure  
change process in place at the time the position of the FSSs was modified did not ensure that interfacing  
procedures  
were considered  
for potential  
impact. As a result, when the calibration  
procedures  
were changed to specify that the FSSs be left in the ZERO position following  
calibration, the emergency  
operating  
procedures  
were not changed to provide instructions  
for placing the FSSs in the SAMPLE position when placing the hydrogen analyzers  
in service. 2. Corrective  
Steps Which Have Been Taken and the Results Achieved As discblSsed  
in Section 2 of Violation  
A, the hydrogen analyzer instrument  
calibration  
procedures  
were revised to provide instructions  
for placing the FSS on the local and remote panels in the SAMPLE position following  
calibration.  
This is the required position to place the hydrogen analyzers  
in service using the emergency  
operating  
procedures.  
The procedure  
change process has been revised and improved since the subject hydrogen analyzer calibration  
procedure  
changes were processed.  
Procedure  
revisions  
and upgrades have been centralized  
under the Procedures  
Department, and a technical  
procedures  
writer's guide has been developed  
to standardize  
format, style, content, and human factors considerations.  
A technical  
review is required for new and revised procedures, and technical  
review guidelines  
have been established  
which address procedural  
methods, instructions, and configuration  
controls.  
In addition, administrative  
procedure  
VPAP-0502, "Procedure  
Process Control," has been revised to require an elevated level of review and approval when a procedural  
revision or change alters the as-left condition  
of a system or component.  
This revision also added references  
to the Licensee Event Report and NRG Inspection  
Report associated  
with this violation.  
3. Corrective  
Steps Which Will be Taken to Avoid Further Violations  
The corrective  
actions noted in Section 2 of Violations  
A and B above are sufficient  
to avoid similar violations.   
** * * 4. The Date When Full Compliance  
Will be Achieved Full compliance  
was achieved on September  
3, 1996 when VPAP-0502  
was revised .
}}

Revision as of 15:00, 31 July 2019

Forwards Response to Violations Noted in NRC Insp Repts 50-280/96-08 & 50-281/96-08.Corrective Actions:Hydrogen Analyzer Instrument Calibr Procedures Revised to Provide Instructions for Placing FSS on Local & Remote Panels
ML18153A066
Person / Time
Site: Surry  
Issue date: 09/12/1996
From: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-425, NUDOCS 9609170471
Download: ML18153A066 (7)


Text

  • VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 12, 1996 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 REPLY TO A NOTICE OF VIOLATION Serial No.96-425 SPS/BCB/GDM R3 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 NRC INSPECTlON REPORT NOS. 50-280/96-08 AND 50-281/96-08 We have reviewed your Inspection Report Nos. 50-280/96-08 and 50-281/96-08 dated July 11, 1996, and your August 16, 1996 letter and enclosed Notice of Violation for Surry Units 1 and 2. As discussed in the attachment, the cited violations resulted from inadequate change management when the hydrogen analyzers' calibration procedures were changed. This conclusion is based on the results of a Root Cause Evaluation of the event. We have implemented corrective actions to resolve the specific concerns associated with the violations, as well as more comprehensive actions to ensure that similar concerns do not exist. Although the violations were precipitated by events that occurred at Surry several years ago, we recognize that the procedure change process should have identified the procedural interface discrepancy.

This process was subsequently strengthened in the early 1990s and was recently enhanced further to preclude a similar event. We have no objection to this letter being made a part of the public record. Please contact us if you have any questions or require additional information.

Very truly yours, ~?.~ James P. O'Hanlon Senior Vice President

-Nuclear Attachment 9609170471 960912 PDR ADOCK 05000280 G PDR ~--** .~. -*

1----:--cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W. Atlanta, Georgia 30323 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

    • REPLY TO A NOTICE OF VIOLATION NRC INSPECTION CONDUCTED JUNE 17 -JULY 1, 1996 SURRY POWER STATION UNITS 1 AND 2 INSPECTION REPORT NOS. 50-280/96-08 AND 50-281/96-08 NRG COMMENT: "During an NRG inspection conducted on June 17 through July 1, 1996, violations of NRG requirements was identified.

In accordance with the 'General Statement of Policy and Procedures for NRG Enforcement Actions,'

NUREG-1600, the violations are listed below: A. Technical Specifications 3.7.G.1 requires that two independent containment hydrogen analyzers be operable during reactor critical or power operation.

Contrary to the above, the Unit 1 and Unit 2 containment hydrogen analyzers were inGperable during reactor critical or power operation from February 28, 1991, and October 21, 1990, respectively, until May 22, 1996, due to the function selector switches being place in the ZERO position following calibration.

(01013) B. Technical Specifications 6.4.A.1 and 6.4.A.2 require, in part, that detailed written procedures with appropriate instructions be provided for the operation, calibration and testing of all systems and components involving nuclear safety of the station. Contrary to the above, from October 24 and October 20, 1990 for Units 1 and 2, respectively, Emergency Operating Procedures*

1-E-1 and 2-E-1, 'Loss of Reactor or Secondary Coolant,'

and Calibration Procedures 1-IPT-FT-GW-A-104 and 2-IPT-FT-GW-A-204, Containment Hydrogen Analyzer H2A-GW-104(204)

Quarterly Functional Test, did not provide appropriate instructions to place the hydrogen analyzers (systems involving nucle_ar safety of the station) in service. Specifically, the procedures did not require placing the function selector switches for the-hydrogen analyzers in the SAMPLE position, which is the required position for sampling the containment atmosphere for hydrogen concentration.

(01023) This is a Severity Level Ill problem (Supplement I)."

L__ ---Violation A REPLY TO A NOTICE OF VIOLATION NRC INSPECTION CONDUCTED JUNE 17-JULY 1.1996 SURRY POWER STATION UNITS 1 AND 2 INSPECTION REPORT NOS. 50-280/96-08 AND 50-281/96-08

1. Reason for the Violation, or, if Contested, the Basis for Disputing the Violation The violation is correct as stated and was caused by inadequate change management.

When the containment hydrogen analyzers' calibration procedures were changed to leave the function selector switch (FSS) on the local and remote panels in the ZERO position, the emergency operating procedures (EOP) did not include instructions to reposition the FSS to the SAMPLE position when placing the hydrogen analyzers in service. Although the ZERO pesition is acceptable for standby operation, the FSS must be in the SAMPLE position for the hydrogen analyzers to be capable of performing their design function.

At the time of the subject change to the calibration procedures, a review of interfacing procedures was not required by the procedure change process. Consequently, a review of the interfacing procedures was not performed and the need to change the EOPs was not recognized.

As a result, a complementary change was not incorporated into the EOPs. This procedural discrepancy resulted in the FSSs being left in the ZERO position following calibration, thereby rendering the containment hydrogen analyzers inoperable for an extended period of time. 2. Corrective Steps Which Have Been Taken and the Results Achieved A Deviation Report was submitted to document the subject discrepancy.

l&C and System Engineering personnel reviewed the vendor manual for the hydrogen analyzers to confirm the optimum operational position for the FSSs. The FSS on the local and remote panels were placed in the SAMPLE position on May 22, 1996. The hydrogen analyzer instrument calibration procedures were revised to provide instructions for placing the FSS on the local and remote panels in the SAMPLE position following calibration.

This is the required position to place the hydrogen analyzers in service using the emergency operating procedures.

' . I I

  • 2. Corrective Steps Which Have Been Taken and the Results Achieved (Cont'd.)

A Root Cause Evaluation (RCE) of the event was performed.

The results are summarized in Section 1 above. The RCE also determined that the North Anna Power Station operator watchstation logs periodically verified the position of the hydrogen analyzers' FSSs, and that the Surry logs did not. The Surry operator watchstation logs were subsequently revised to include a periodic verification that the FSSs are positioned correctly.

In addition, a comparative review of the North Anna and Surry Power Stations' operator watchstation logs was performed to evaluate the commonality of equipment checks performed at each station. No safety equipment inconsistencies were identified.

The Te.cbnical Specifications and emergency and abnormal procedures were reviewed by Operations and l&C personnel to evaluate infrequently performed evolutions and post-accident manual actions to determine whether additional procedural interface concerns existed. No additional examples were identified.

The procedure change process has been revised and improved since the subject hydrogen analyzer calibration procedure changes were processed.

These improvements are discussed in our response to Violation B. 3. Corrective Steps Which Will be Taken to Avoid Further Violations The corrective actions discussed in Section 2 are sufficient to avoid further violations.

A synopsis of this event is being presented during the current continuing training sessions to enhance the operators' knowledge and understanding of hydrogen analyzer operation.

Training will also be conducted for l&C technicians during the next l&C continuing training sessions.

4. The Date When Full Compliance Will be Achieved Full compliance was achieved on May 22, 1996 when the FSS on the local and remote panels were placed in the SAMPLE position .

Violation B 1. Reason for the Violation, or, if Contested, the Basis for Disputing the Violation The violation is correct as stated. As discussed in Section 1 of Violation A, a review of interfacing procedures was not performed when the hydrogen analyzers' calibration procedures were changed. The procedure change process in place at the time the position of the FSSs was modified did not ensure that interfacing procedures were considered for potential impact. As a result, when the calibration procedures were changed to specify that the FSSs be left in the ZERO position following calibration, the emergency operating procedures were not changed to provide instructions for placing the FSSs in the SAMPLE position when placing the hydrogen analyzers in service. 2. Corrective Steps Which Have Been Taken and the Results Achieved As discblSsed in Section 2 of Violation A, the hydrogen analyzer instrument calibration procedures were revised to provide instructions for placing the FSS on the local and remote panels in the SAMPLE position following calibration.

This is the required position to place the hydrogen analyzers in service using the emergency operating procedures.

The procedure change process has been revised and improved since the subject hydrogen analyzer calibration procedure changes were processed.

Procedure revisions and upgrades have been centralized under the Procedures Department, and a technical procedures writer's guide has been developed to standardize format, style, content, and human factors considerations.

A technical review is required for new and revised procedures, and technical review guidelines have been established which address procedural methods, instructions, and configuration controls.

In addition, administrative procedure VPAP-0502, "Procedure Process Control," has been revised to require an elevated level of review and approval when a procedural revision or change alters the as-left condition of a system or component.

This revision also added references to the Licensee Event Report and NRG Inspection Report associated with this violation.

3. Corrective Steps Which Will be Taken to Avoid Further Violations The corrective actions noted in Section 2 of Violations A and B above are sufficient to avoid similar violations.
    • *
  • 4. The Date When Full Compliance Will be Achieved Full compliance was achieved on September 3, 1996 when VPAP-0502 was revised .