PLA-6404, Relief Request 2RR07 for Third Ten-Year Interval Inservice Testing Program Plan: Difference between revisions

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{{#Wiki_filter:Britt T. McKinney Sr. Vice President  
{{#Wiki_filter:StI    4 Britt T. McKinney               PPL Susquehanna, LLC Sr. Vice President & Chief Nuclear Officer                 769 Salem Boulevard Berwick, PA 18603 AUG .0 5 2008 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@pplweb.com ppI U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION RELIEF REQUEST 2RR07 FOR THIRD TEN-YEAR INTERVAL INSERVICE TESTING PROGRAM PLAN FOR SUSQUEHANNA SES UNIT 2                                                             Docket No. 50-388 PLA-6404 Attached please find, pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3)(i), a request for relief from the requirements of ASME OM Code, ISTC-522 1(c)(3) for the Unit 2 High Pressure Coolant Injection (HPCI) Turbine Exhaust to Suppression Pool vacuum exhaust line check valve 255F076. The basis for the relief request is that the proposed alternative would provide an equivalent level of quality and safety. This proposed alternative is a one-time extension of the eight-year Inservice Test (IST) interval to correspond with the scheduled commencement of the next Unit 2 Refuel Outage.
& Chief Nuclear Officer AUG .0 5 2008 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@pplweb.com StI 4 ppI SUSQUEHANNA STEAM ELECTRIC STATION RELIEF REQUEST 2RR07 FOR THIRD TEN-YEAR INTERVAL INSERVICE TESTING PROGRAM PLAN FOR SUSQUEHANNA SES UNIT 2 PLA-6404 Docket No. 50-388 Attached please find, pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3)(i), a request for relief from the requirements of ASME OM Code, ISTC-522 1 (c)(3) for the Unit 2 High Pressure Coolant Injection (HPCI) Turbine Exhaust to Suppression Pool vacuum exhaust line check valve 255F076. The basis for the relief request is that the proposed alternative would provide an equivalent level of quality and safety. This proposed alternative is a one-time extension of the eight-year Inservice Test (IST) interval to correspond with the scheduled commencement of the next Unit 2 Refuel Outage.PPL requests NRC approval of proposed Relief Request 2RRO7 to the Third Ten-Year Interval IST Program Plan for Susquehanna SES Unit 2 be approved by February 1, 2009 to provide sufficient time to schedule and plan for the activity during the refuel outage.No new regulatory commitments are made herein.Should you have any questions, please contact Dayne R. Brophy, at (570) 542-3365.Sincerely, B. T. McKinney-7 4oq 7 M"~A Document Control Desk PLA-6404 Attachment 1 -Revision 0 to Relief Request 2RR07 cc: Regional Administrator  
PPL requests NRC approval of proposed Relief Request 2RRO7 to the Third Ten-Year Interval IST Program Plan for Susquehanna SES Unit 2 be approved by February 1, 2009 to provide sufficient time to schedule and plan for the activity during the refuel outage.
-Region 1 Mr. R. R. Janati, DEP/BRP Mr. F. W. Jaxheimer, NRC Sr. Resident Inspector Mr. B. K. Vaidya, NRC Project Manager ATTACHMENT 1 TO PLA-6404 REVISION 0 TO RELIEF REQUEST 2RR07 Attachment 1 to PLA-6404 Page 1 of 2 1. ASME Code Component Affected PPL Susquehanna Unit 2, High Pressure Coolant Injection (HPCI) Turbine Exhaust to Suppression Pool vacuum breaker line check valve, 255F076; Model number W8121381; Manufacturer:
No new regulatory commitments are made herein.
Anchor Darling Valve Company.Function This check valve is in the HPCI turbine exhaust line. It has an open safety function to prevent a vacuum relief path for the turbine exhaust line. It has a close safety function to prevent steam flow into the suppression chamber. The valve has no containment isolation function.
Should you have any questions, please contact Dayne R. Brophy, at (570) 542-3365.
The open and closed safety functions of the valve are currently verified by valve disassembly and examination.
Sincerely, B. T. McKinney
: 2. Applicable Code Edition and Addenda American Society of Mechanical Engineers (ASME)/American National Standards Institute, "Code for Operation and Maintenance of Nuclear Power Plants" (ASME OM Code), 1998 Edition through OMb-2000 Addenda.3. Applicable Code Requirement ASME OM Code, 1998 Edition through OMb-2000 Addenda.ISTC-5221(c)(3), "Valve Obturator Movement""At least one valve from each group shall be disassembled and examined at each refueling outage; all valves in each group shall be disassembled and examined at least once every 8 years." 4. Basis for Relief Pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3), relief is'requested from the requirements of ASME OM Code ISTC-5221(c)(3). "At least one valve from each group shall be disassembled and examined at each refueling outage;all valves in each group shall be disassembled and examined at least once every 8 years." The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.ASME OM Code, 1998 Edition through OMb-2000 Addenda, Section ISTC-5221(c) permits disassembly and examination of check valves when it is impractical to verify obturator movement.
                                                                                                          -74oq 7 M"~A
The Unit 2 High Pressure Coolant Injection (HPCI) Turbine Exhaust to Suppression Pool vacuum breaker line check valve, 255F076, has no external means for exercising, the valve and no external position indication.
 
Due to the lack of installed flow or pressure indication and a lack of test connections, it is not Attachment 1 to PLA-6404 Page 2 of 2 possible to use other means to verify the open and close exercising of this check valve. Disassembly and examination of the valve is the only feasible method to verify operability.
Document Control Desk PLA-6404 - Revision 0 to Relief Request 2RR07 cc:   Regional Administrator - Region 1 Mr. R. R. Janati, DEP/BRP Mr. F. W. Jaxheimer, NRC Sr. Resident Inspector Mr. B. K. Vaidya, NRC Project Manager
The check valve is grouped with similar valves as required by ASME OM Code 1998 through OMb-2000 Addenda, Section ISTC-5221(c)(1).
 
This group contains four valves: 249F064, 249F063, 255F076 and 255F077. The last disassembly and examination of check valve 255F076 occurred on March 23, 2001 during a refueling outage; therefore, to comply with the eight-year Code requirement the next disassembly and examination is due by March 22, 2009. The next scheduled Refuel Outage is scheduled to commence in early April 2009, which exceeds the eight-year Code requirement.
ATTACHMENT 1 TO PLA-6404 REVISION 0 TO RELIEF REQUEST 2RR07
There have been no problems identified during the previous disassembly/examinations of this valve or the other valves associated with this group.Extending the required inspection interval by one month for check valve 255F076 would not have an adverse impact on quality or nuclear safety.4. Proposed Alternative Pursuant to 10 CFR 50.55a(a)(3)(i), PPL proposes an alternative testing frequency for performing inservice testing to the HPCI check valve 255F076. The HPCI check valve 255F076 will be tested on a frequency of 8 years and one month to correspond with the extended operating cycle in lieu of the 8 year requirement currently allowed by the ASME OM Code, 1998 Edition through OMb 2000 Addenda, ISTC-5221 (c )(3), "Valve Obturator Movement." The other valves in this group have been tested within the required eight-year frequency of the Code.5. Duration of Proposed Alternative The proposed alternative is requested as a one-time extension from an eight-year frequency to an eight-year and one-month frequency for the HPCI check valve, 255F076. The extension will allow disassembly and inspection during the April 2009 Unit 2 Refuel Outage.}}
 
Attachment 1 to PLA-6404 Page 1 of 2
: 1. ASME Code Component Affected PPL Susquehanna Unit 2, High Pressure Coolant Injection (HPCI) Turbine Exhaust to Suppression Pool vacuum breaker line check valve, 255F076; Model number W8121381; Manufacturer: Anchor Darling Valve Company.
Function This check valve is in the HPCI turbine exhaust line. It has an open safety function to prevent a vacuum relief path for the turbine exhaust line. It has a close safety function to prevent steam flow into the suppression chamber. The valve has no containment isolation function. The open and closed safety functions of the valve are currently verified by valve disassembly and examination.
 
===2. Applicable Code Edition and Addenda===
American Society of Mechanical Engineers (ASME)/American National Standards Institute, "Code for Operation and Maintenance of Nuclear Power Plants" (ASME OM Code), 1998 Edition through OMb-2000 Addenda.
 
===3. Applicable Code Requirement===
ASME OM Code, 1998 Edition through OMb-2000 Addenda.
ISTC-5221(c)(3), "Valve Obturator Movement" "At least one valve from each group shall be disassembled and examined at each refueling outage; all valves in each group shall be disassembled and examined at least once every 8 years."
: 4. Basis for Relief Pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3), relief is' requested from the requirements of ASME OM Code ISTC-5221(c)(3). "At least one valve from each group shall be disassembled and examined at each refueling outage; all valves in each group shall be disassembled and examined at least once every 8 years." The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.
ASME OM Code, 1998 Edition through OMb-2000 Addenda, Section ISTC-5221(c) permits disassembly and examination of check valves when it is impractical to verify obturator movement. The Unit 2 High Pressure Coolant Injection (HPCI) Turbine Exhaust to Suppression Pool vacuum breaker line check valve, 255F076, has no external means for exercising, the valve and no external position indication. Due to the lack of installed flow or pressure indication and a lack of test connections, it is not
 
Attachment 1 to PLA-6404 Page 2 of 2 possible to use other means to verify the open and close exercising of this check valve. Disassembly and examination of the valve is the only feasible method to verify operability.
The check valve is grouped with similar valves as required by ASME OM Code 1998 through OMb-2000 Addenda, Section ISTC-5221(c)(1). This group contains four valves: 249F064, 249F063, 255F076 and 255F077. The last disassembly and examination of check valve 255F076 occurred on March 23, 2001 during a refueling outage; therefore, to comply with the eight-year Code requirement the next disassembly and examination is due by March 22, 2009. The next scheduled Refuel Outage is scheduled to commence in early April 2009, which exceeds the eight-year Code requirement. There have been no problems identified during the previous disassembly/examinations of this valve or the other valves associated with this group.
Extending the required inspection interval by one month for check valve 255F076 would not have an adverse impact on quality or nuclear safety.
: 4. Proposed Alternative Pursuant to 10 CFR 50.55a(a)(3)(i), PPL proposes an alternative testing frequency for performing inservice testing to the HPCI check valve 255F076. The HPCI check valve 255F076 will be tested on a frequency of 8 years and one month to correspond with the extended operating cycle in lieu of the 8 year requirement currently allowed by the ASME OM Code, 1998 Edition through OMb 2000 Addenda, ISTC-5221 (c )(3), "Valve Obturator Movement." The other valves in this group have been tested within the required eight-year frequency of the Code.
: 5. Duration of Proposed Alternative The proposed alternative is requested as a one-time extension from an eight-year frequency to an eight-year and one-month frequency for the HPCI check valve, 255F076. The extension will allow disassembly and inspection during the April 2009 Unit 2 Refuel Outage.}}

Latest revision as of 14:58, 14 November 2019

Relief Request 2RR07 for Third Ten-Year Interval Inservice Testing Program Plan
ML082270202
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 08/05/2008
From: Mckinney B
Susquehanna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-6404
Download: ML082270202 (5)
v • d • e


Text

StI 4 Britt T. McKinney PPL Susquehanna, LLC Sr. Vice President & Chief Nuclear Officer 769 Salem Boulevard Berwick, PA 18603 AUG .0 5 2008 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@pplweb.com ppI U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION RELIEF REQUEST 2RR07 FOR THIRD TEN-YEAR INTERVAL INSERVICE TESTING PROGRAM PLAN FOR SUSQUEHANNA SES UNIT 2 Docket No. 50-388 PLA-6404 Attached please find, pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3)(i), a request for relief from the requirements of ASME OM Code, ISTC-522 1(c)(3) for the Unit 2 High Pressure Coolant Injection (HPCI) Turbine Exhaust to Suppression Pool vacuum exhaust line check valve 255F076. The basis for the relief request is that the proposed alternative would provide an equivalent level of quality and safety. This proposed alternative is a one-time extension of the eight-year Inservice Test (IST) interval to correspond with the scheduled commencement of the next Unit 2 Refuel Outage.

PPL requests NRC approval of proposed Relief Request 2RRO7 to the Third Ten-Year Interval IST Program Plan for Susquehanna SES Unit 2 be approved by February 1, 2009 to provide sufficient time to schedule and plan for the activity during the refuel outage.

No new regulatory commitments are made herein.

Should you have any questions, please contact Dayne R. Brophy, at (570) 542-3365.

Sincerely, B. T. McKinney

-74oq 7 M"~A

Document Control Desk PLA-6404 - Revision 0 to Relief Request 2RR07 cc: Regional Administrator - Region 1 Mr. R. R. Janati, DEP/BRP Mr. F. W. Jaxheimer, NRC Sr. Resident Inspector Mr. B. K. Vaidya, NRC Project Manager

ATTACHMENT 1 TO PLA-6404 REVISION 0 TO RELIEF REQUEST 2RR07

Attachment 1 to PLA-6404 Page 1 of 2

1. ASME Code Component Affected PPL Susquehanna Unit 2, High Pressure Coolant Injection (HPCI) Turbine Exhaust to Suppression Pool vacuum breaker line check valve, 255F076; Model number W8121381; Manufacturer: Anchor Darling Valve Company.

Function This check valve is in the HPCI turbine exhaust line. It has an open safety function to prevent a vacuum relief path for the turbine exhaust line. It has a close safety function to prevent steam flow into the suppression chamber. The valve has no containment isolation function. The open and closed safety functions of the valve are currently verified by valve disassembly and examination.

2. Applicable Code Edition and Addenda

American Society of Mechanical Engineers (ASME)/American National Standards Institute, "Code for Operation and Maintenance of Nuclear Power Plants" (ASME OM Code), 1998 Edition through OMb-2000 Addenda.

3. Applicable Code Requirement

ASME OM Code, 1998 Edition through OMb-2000 Addenda.

ISTC-5221(c)(3), "Valve Obturator Movement" "At least one valve from each group shall be disassembled and examined at each refueling outage; all valves in each group shall be disassembled and examined at least once every 8 years."

4. Basis for Relief Pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3), relief is' requested from the requirements of ASME OM Code ISTC-5221(c)(3). "At least one valve from each group shall be disassembled and examined at each refueling outage; all valves in each group shall be disassembled and examined at least once every 8 years." The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.

ASME OM Code, 1998 Edition through OMb-2000 Addenda, Section ISTC-5221(c) permits disassembly and examination of check valves when it is impractical to verify obturator movement. The Unit 2 High Pressure Coolant Injection (HPCI) Turbine Exhaust to Suppression Pool vacuum breaker line check valve, 255F076, has no external means for exercising, the valve and no external position indication. Due to the lack of installed flow or pressure indication and a lack of test connections, it is not

Attachment 1 to PLA-6404 Page 2 of 2 possible to use other means to verify the open and close exercising of this check valve. Disassembly and examination of the valve is the only feasible method to verify operability.

The check valve is grouped with similar valves as required by ASME OM Code 1998 through OMb-2000 Addenda, Section ISTC-5221(c)(1). This group contains four valves: 249F064, 249F063, 255F076 and 255F077. The last disassembly and examination of check valve 255F076 occurred on March 23, 2001 during a refueling outage; therefore, to comply with the eight-year Code requirement the next disassembly and examination is due by March 22, 2009. The next scheduled Refuel Outage is scheduled to commence in early April 2009, which exceeds the eight-year Code requirement. There have been no problems identified during the previous disassembly/examinations of this valve or the other valves associated with this group.

Extending the required inspection interval by one month for check valve 255F076 would not have an adverse impact on quality or nuclear safety.

4. Proposed Alternative Pursuant to 10 CFR 50.55a(a)(3)(i), PPL proposes an alternative testing frequency for performing inservice testing to the HPCI check valve 255F076. The HPCI check valve 255F076 will be tested on a frequency of 8 years and one month to correspond with the extended operating cycle in lieu of the 8 year requirement currently allowed by the ASME OM Code, 1998 Edition through OMb 2000 Addenda, ISTC-5221 (c )(3), "Valve Obturator Movement." The other valves in this group have been tested within the required eight-year frequency of the Code.
5. Duration of Proposed Alternative The proposed alternative is requested as a one-time extension from an eight-year frequency to an eight-year and one-month frequency for the HPCI check valve, 255F076. The extension will allow disassembly and inspection during the April 2009 Unit 2 Refuel Outage.
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