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| {{#Wiki_filter:Xcel Energy DEC 3 0 2015 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 L-PI-15-105 10 CFR 50.90 License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process -Response to Request for Additional Information | | {{#Wiki_filter:Xcel Energy DEC 3 0 2015 L-PI-15-105 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process - Response to Request for Additional Information |
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| ==References:== | | ==References:== |
| : 1. NSPM Letter, S. Sharp to NRC Document Control Desk, Application to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process, L-PI-15-030, dated June 29, 2015 (ADAMS Accession No. ML 15187A259) | | : 1. NSPM Letter, S. Sharp to NRC Document Control Desk, Application to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process, L-PI-15-030, dated June 29, 2015 (ADAMS Accession No. ML15187A259) |
| : 2. NRC email, T. Beltz to G. Carlson, Prairie Island Nuclear Generating Plant, Requests for Additional Information (Draft) re: License Amendment Request to Adopt TSTF-523, (TAC Nos. MF6449 and MF6450), dated October 27, 2015 3. NSPM Letter, S. Sharp to NRC Document Control Desk, Supplement to Responses to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" L-PI-09-122, dated November 24, 2009 (ADAMS Accession No. ML093280925), NSPM committed to submit an LAR, if necessary, within one year following NRC approval of the Technical Specification Task Force Traveler (TSTF) that provides TS resolution of GL 2008-01. This submittal satisfies the commitment. | | : 2. NRC email, T. Beltz to G. Carlson, Prairie Island Nuclear Generating Plant, Requests for Additional Information (Draft) re: License Amendment Request to Adopt TSTF-523, (TAC Nos. MF6449 and MF6450), dated October 27, 2015 |
| | : 3. NSPM Letter, S. Sharp to NRC Document Control Desk, Supplement to Responses to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" L-PI-09-122, dated November 24, 2009 (ADAMS Accession No. ML093280925), NSPM committed to submit an LAR, if necessary, within one year following NRC approval of the Technical Specification Task Force Traveler (TSTF) that provides TS resolution of GL 2008-01. This submittal satisfies the commitment. |
| In Reference 1, the Northern States Power Company, a Minnesota Corporation | | In Reference 1, the Northern States Power Company, a Minnesota Corporation |
| ("NSPM") doing business as Xcel Energy requested approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," using the Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance 1717 Wakonade Drive East | | ("NSPM") doing business as Xcel Energy requested approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," using the Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance 1717 Wakonade Drive East |
| * Welch, Minnesota 55089-9642 Telephone: | | * Welch, Minnesota 55089-9642 Telephone: 651.388.1121 |
| 651.388.1121 Document Control Desk Page2 Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowances which permit performance of the verification. | | |
| The changes are being made to address the concerns discussed in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems." In Reference 2, the NRC staff provided requests for additional information (RAI) regarding this request. Enclosure 1 to this letter provides NSPM's response to the RAis. This letter is submitted in accordance with 10 CFR 50.90. The additional information provided in this letter does not impact the conclusion of the "No Significant Hazards Evaluation or Environmental Considerations Evaluation" presented in Reference | | Document Control Desk Page2 Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowances which permit performance of the verification. The changes are being made to address the concerns discussed in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems." |
| : 1. In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this additional information by transmitting a copy of this letter to the designated State Official.
| | In Reference 2, the NRC staff provided requests for additional information (RAI) regarding this request. to this letter provides NSPM's response to the RAis. |
| If there are any questions or if additional information is needed, please contact Mr. Glenn Carlson, at 651-267-1755. | | This letter is submitted in accordance with 10 CFR 50.90. The additional information provided in this letter does not impact the conclusion of the "No Significant Hazards Evaluation or Environmental Considerations Evaluation" presented in Reference 1. |
| | In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this additional information by transmitting a copy of this letter to the designated State Official. |
| | If there are any questions or if additional information is needed, please contact Mr. |
| | Glenn Carlson, at 651-267-1755. |
| Summary of Commitments This letter contains no new commitments and no revisions to existing commitments. | | Summary of Commitments This letter contains no new commitments and no revisions to existing commitments. |
| I declare under penalty of perjury that the foregoing is true and correct. Executed on | | I declare under penalty of perjury that the foregoing is true and correct. |
| / J 11 // 1:'" * . | | Executed on ;a/.3ol&.o!6.~ |
| Davison Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company-Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota L-PI-15-1 05 Enclosure Response to Requests for Additional Information (RAI) License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process-Response to Request for Additional Information Introduction This Enclosure provides additional information from the Northern States Power Company, a Minnesota corporation (hereafter "NSPM") doing business as Xcel Energy, in support of a License Amendment Request (LAR) requesting approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the *Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowance which permit performance of the verification.
| | / J |
| The changes are being made to address the concerns disused in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray System." This enclosure to this letter provides NSPM's response to the RAI. Each of the RAI questions is quoted in italics and each question is then followed by the NSPM response in normal font. NRC Request RAI SRXB-1 a) Xcel Energy states the following in the proposed TS Bases for SR 3.4.6.4, SR 3.4. 7.4, SR 3.4.8.3 and SR 3.9.5.2: b) The SR can be met by virtue of having an RHR subsystem inservice in accordance with operating procedures. | | // |
| c) If the system is running with sufficient flow, then monitoring the running parameters is effective.
| | .0:_~ |
| If system flow is low, however, then gas voids may not transport through the system. Additionally, stagnant branch lines in an operating system may be susceptible to gas accumulation. | | ~vin Davison 1:'" 11 t~ |
| This appears to be an alternative to petforming the SR. (a) Please explain how the flowrate of the operating system and the stagnant branch lines are taken into consideration when crediting the in-service loop as meeting the SR. | | Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota |
| (b) Please explain why it is acceptable to describe this approach in the TS Bases rather than the TS surveillance. | | |
| If necessary, revise the TS Bases so that they are in agreement with the approved TSTF-523 language. | | L-PI-15-1 05 Enclosure Response to Requests for Additional Information (RAI) |
| NSPM Response (RAI SRXB-1) These questions are not applicable. | | License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process- Response to Request for Additional Information Introduction This Enclosure provides additional information from the Northern States Power Company, a Minnesota corporation (hereafter "NSPM") doing business as Xcel Energy, in support of a License Amendment Request (LAR) requesting approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the |
| NSPM is changing what we currently requested for TS Bases SR 3.4.6.4, SR 3.4.7.4, SR 3.4.8.3 and SR 3.9.5.2 by removing the statement, "The SR can be met by virtue of having an RHR subsystem in service operating procedures." By revising the TS Bases, our request will be in agreement with the approved TSTF-523 language. | | *Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowance which permit performance of the verification. The changes are being made to address the concerns disused in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray System." |
| | This enclosure to this letter provides NSPM's response to the RAI. |
| | Each of the RAI questions is quoted in italics and each question is then followed by the NSPM response in normal font. |
| | NRC Request RAI SRXB-1 a) Xcel Energy states the following in the proposed TS Bases for SR 3.4.6.4, SR 3.4. 7.4, SR 3.4.8.3 and SR 3.9.5.2: |
| | b) The SR can be met by virtue of having an RHR subsystem inservice in accordance with operating procedures. |
| | If the system is running with sufficient flow, then monitoring the running parameters is effective. If system flow is low, however, then gas voids may not transport through the system. Additionally, stagnant branch lines in an operating system may be susceptible to gas accumulation. This appears to be an alternative to petforming the SR. |
| | c) |
| | (a) Please explain how the flowrate of the operating system and the stagnant branch lines are taken into consideration when crediting the in-service loop as meeting the SR. |
| | |
| | (b) Please explain why it is acceptable to describe this approach in the TS Bases rather than the TS surveillance. If necessary, revise the TS Bases so that they are in agreement with the approved TSTF-523 language. |
| | NSPM Response (RAI SRXB-1) |
| | These questions are not applicable. NSPM is changing what we currently requested for TS Bases SR 3.4.6.4, SR 3.4.7.4, SR 3.4.8.3 and SR 3.9.5.2 by removing the statement, "The SR can be met by virtue of having an RHR subsystem in service operating procedures." |
| | By revising the TS Bases, our request will be in agreement with the approved TSTF-523 language. |
| NSPM will follow up with a supplemental to the LAR, on January 27, 2016. | | NSPM will follow up with a supplemental to the LAR, on January 27, 2016. |
| Xcel Energy DEC 3 0 2015 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 L-PI-15-105 10 CFR 50.90 License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process -Response to Request for Additional Information | | |
| | Xcel Energy DEC 3 0 2015 L-PI-15-105 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process - Response to Request for Additional Information |
|
| |
|
| ==References:== | | ==References:== |
| : 1. NSPM Letter, S. Sharp to NRC Document Control Desk, Application to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process, L-PI-15-030, dated June 29, 2015 (ADAMS Accession No. ML 15187A259) | | : 1. NSPM Letter, S. Sharp to NRC Document Control Desk, Application to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process, L-PI-15-030, dated June 29, 2015 (ADAMS Accession No. ML15187A259) |
| : 2. NRC email, T. Beltz to G. Carlson, Prairie Island Nuclear Generating Plant, Requests for Additional Information (Draft) re: License Amendment Request to Adopt TSTF-523, (TAC Nos. MF6449 and MF6450), dated October 27, 2015 3. NSPM Letter, S. Sharp to NRC Document Control Desk, Supplement to Responses to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" L-PI-09-122, dated November 24, 2009 (ADAMS Accession No. ML093280925), NSPM committed to submit an LAR, if necessary, within one year following NRC approval of the Technical Specification Task Force Traveler (TSTF) that provides TS resolution of GL 2008-01. This submittal satisfies the commitment. | | : 2. NRC email, T. Beltz to G. Carlson, Prairie Island Nuclear Generating Plant, Requests for Additional Information (Draft) re: License Amendment Request to Adopt TSTF-523, (TAC Nos. MF6449 and MF6450), dated October 27, 2015 |
| | : 3. NSPM Letter, S. Sharp to NRC Document Control Desk, Supplement to Responses to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" L-PI-09-122, dated November 24, 2009 (ADAMS Accession No. ML093280925), NSPM committed to submit an LAR, if necessary, within one year following NRC approval of the Technical Specification Task Force Traveler (TSTF) that provides TS resolution of GL 2008-01. This submittal satisfies the commitment. |
| In Reference 1, the Northern States Power Company, a Minnesota Corporation | | In Reference 1, the Northern States Power Company, a Minnesota Corporation |
| ("NSPM") doing business as Xcel Energy requested approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," using the Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance 1717 Wakonade Drive East | | ("NSPM") doing business as Xcel Energy requested approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," using the Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance 1717 Wakonade Drive East |
| * Welch, Minnesota 55089-9642 Telephone: | | * Welch, Minnesota 55089-9642 Telephone: 651.388.1121 |
| 651.388.1121 Document Control Desk Page2 Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowances which permit performance of the verification. | | |
| The changes are being made to address the concerns discussed in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems." In Reference 2, the NRC staff provided requests for additional information (RAI) regarding this request. Enclosure 1 to this letter provides NSPM's response to the RAis. This letter is submitted in accordance with 10 CFR 50.90. The additional information provided in this letter does not impact the conclusion of the "No Significant Hazards Evaluation or Environmental Considerations Evaluation" presented in Reference | | Document Control Desk Page2 Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowances which permit performance of the verification. The changes are being made to address the concerns discussed in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems." |
| : 1. In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this additional information by transmitting a copy of this letter to the designated State Official.
| | In Reference 2, the NRC staff provided requests for additional information (RAI) regarding this request. to this letter provides NSPM's response to the RAis. |
| If there are any questions or if additional information is needed, please contact Mr. Glenn Carlson, at 651-267-1755. | | This letter is submitted in accordance with 10 CFR 50.90. The additional information provided in this letter does not impact the conclusion of the "No Significant Hazards Evaluation or Environmental Considerations Evaluation" presented in Reference 1. |
| | In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this additional information by transmitting a copy of this letter to the designated State Official. |
| | If there are any questions or if additional information is needed, please contact Mr. |
| | Glenn Carlson, at 651-267-1755. |
| Summary of Commitments This letter contains no new commitments and no revisions to existing commitments. | | Summary of Commitments This letter contains no new commitments and no revisions to existing commitments. |
| I declare under penalty of perjury that the foregoing is true and correct. Executed on | | I declare under penalty of perjury that the foregoing is true and correct. |
| / J 11 // 1:'" * . | | Executed on ;a/.3ol&.o!6.~ |
| Davison Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company-Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota L-PI-15-1 05 Enclosure Response to Requests for Additional Information (RAI) License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process-Response to Request for Additional Information Introduction This Enclosure provides additional information from the Northern States Power Company, a Minnesota corporation (hereafter "NSPM") doing business as Xcel Energy, in support of a License Amendment Request (LAR) requesting approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the *Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowance which permit performance of the verification.
| | / J |
| The changes are being made to address the concerns disused in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray System." This enclosure to this letter provides NSPM's response to the RAI. Each of the RAI questions is quoted in italics and each question is then followed by the NSPM response in normal font. NRC Request RAI SRXB-1 a) Xcel Energy states the following in the proposed TS Bases for SR 3.4.6.4, SR 3.4. 7.4, SR 3.4.8.3 and SR 3.9.5.2: b) The SR can be met by virtue of having an RHR subsystem inservice in accordance with operating procedures. | | // |
| c) If the system is running with sufficient flow, then monitoring the running parameters is effective.
| | .0:_~ |
| If system flow is low, however, then gas voids may not transport through the system. Additionally, stagnant branch lines in an operating system may be susceptible to gas accumulation. | | ~vin Davison 1:'" 11 t~ |
| This appears to be an alternative to petforming the SR. (a) Please explain how the flowrate of the operating system and the stagnant branch lines are taken into consideration when crediting the in-service loop as meeting the SR. | | Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota |
| (b) Please explain why it is acceptable to describe this approach in the TS Bases rather than the TS surveillance. | | |
| If necessary, revise the TS Bases so that they are in agreement with the approved TSTF-523 language. | | L-PI-15-1 05 Enclosure Response to Requests for Additional Information (RAI) |
| NSPM Response (RAI SRXB-1) These questions are not applicable. | | License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process- Response to Request for Additional Information Introduction This Enclosure provides additional information from the Northern States Power Company, a Minnesota corporation (hereafter "NSPM") doing business as Xcel Energy, in support of a License Amendment Request (LAR) requesting approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the |
| NSPM is changing what we currently requested for TS Bases SR 3.4.6.4, SR 3.4.7.4, SR 3.4.8.3 and SR 3.9.5.2 by removing the statement, "The SR can be met by virtue of having an RHR subsystem in service operating procedures." By revising the TS Bases, our request will be in agreement with the approved TSTF-523 language. | | *Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowance which permit performance of the verification. The changes are being made to address the concerns disused in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray System." |
| | This enclosure to this letter provides NSPM's response to the RAI. |
| | Each of the RAI questions is quoted in italics and each question is then followed by the NSPM response in normal font. |
| | NRC Request RAI SRXB-1 a) Xcel Energy states the following in the proposed TS Bases for SR 3.4.6.4, SR 3.4. 7.4, SR 3.4.8.3 and SR 3.9.5.2: |
| | b) The SR can be met by virtue of having an RHR subsystem inservice in accordance with operating procedures. |
| | If the system is running with sufficient flow, then monitoring the running parameters is effective. If system flow is low, however, then gas voids may not transport through the system. Additionally, stagnant branch lines in an operating system may be susceptible to gas accumulation. This appears to be an alternative to petforming the SR. |
| | c) |
| | (a) Please explain how the flowrate of the operating system and the stagnant branch lines are taken into consideration when crediting the in-service loop as meeting the SR. |
| | |
| | (b) Please explain why it is acceptable to describe this approach in the TS Bases rather than the TS surveillance. If necessary, revise the TS Bases so that they are in agreement with the approved TSTF-523 language. |
| | NSPM Response (RAI SRXB-1) |
| | These questions are not applicable. NSPM is changing what we currently requested for TS Bases SR 3.4.6.4, SR 3.4.7.4, SR 3.4.8.3 and SR 3.9.5.2 by removing the statement, "The SR can be met by virtue of having an RHR subsystem in service operating procedures." |
| | By revising the TS Bases, our request will be in agreement with the approved TSTF-523 language. |
| NSPM will follow up with a supplemental to the LAR, on January 27, 2016.}} | | NSPM will follow up with a supplemental to the LAR, on January 27, 2016.}} |
Letter Sequence Request |
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MONTHYEARL-PI-14-125, Notification of Change in Commitment for Implementation of Technical Specification Task Force 523. Generic Letter 2008-01. Managing Gas Accumulation.2015-01-15015 January 2015
Notification of Change in Commitment for Implementation of Technical Specification Task Force 523. Generic Letter 2008-01. Managing Gas Accumulation.
Project stage: Request
L-PI-15-030, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-06-29029 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
Project stage: Request
L-PI-15-105, License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process - Response to Request..2015-12-30030 December 2015
License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process - Response to Request..
Project stage: Request
L-PI-16-003, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2016-01-25025 January 2016
Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process
Project stage: Supplement
ML16075A0802016-03-15015 March 2016
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 Request for Additional Information Related to License Amendment Request to Adopt TSTF-523, GL 2008-01, Managing Gas Accumulation
Project stage: RAI
L-PI-16-029, Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2,,Using the Consolidated..2016-03-31031 March 2016
Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2,,Using the Consolidated..
Project stage: Response to RAI
L-08-001, Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated..2016-04-14014 April 2016
Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated..
Project stage: Response to RAI
ML16133A4062016-06-16016 June 2016
Issuance of Amendment Nos. 217 and 205, Adoption of Technical Specifications Task Force TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation (CAC Nos. MF6449 and MF6450)
Project stage: Approval
2016-01-25
[Table View] |
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Category:Letter type:L
MONTHYEARL-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,
L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report
L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023
Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3
L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023
License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3
L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023
Baffle Former Bolts Alternate Aging Management Strategy
L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023
License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT
L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023
License Amendment Request to Revise Technical Specification 3.7.8 Required Actions
L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023
2022 10 CFR 50.46 LOCA Annual Report
L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023
Annual Report of Individual Monitoring
L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023
Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023
CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023
Day Steam Generator Tube Inspection Report
L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022
Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report
L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022
Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022
Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022
Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts
L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022
CFR 50.46 LOCA Annual Report
L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022
Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles
L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022
Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022
Supplement to Application for License Amendment to Implement 24-Month Operating Cycle
L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021
Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2
L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021
Response to Request for Additional Information Cooling Water System License Amendment Request
L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021
Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1
L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021
License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions
L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021
Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island
L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021
Application for License Amendment to Implement 24-Month Operating Cycle
L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021
2020 10 CFR 50.46 LOCA Annual Report
L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021
Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report
L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021
Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes
L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020
Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic
L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020
Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements
L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020
Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020
= Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule
L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020
Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)
L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020
Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI
L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020
License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13
L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020
License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1
L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019
Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements
L-PI-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019
License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019
License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency
L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report2019-09-19019 September 2019
Submittal of Revised Pressure and Temperature Limits Report
L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019
Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals
L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)2019-08-27027 August 2019
Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)
L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019
Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...
L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019
10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2
L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019
Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-PI-19-003, Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)2019-02-0404 February 2019
Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)
L-PI-19-006, Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements2019-01-29029 January 2019
Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements
L-PI-19-005, Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.692019-01-15015 January 2019
Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.69
L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018
Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805
2024-01-02
[Table view]
Category:Response to Request for Additional Information (RAI)
MONTHYEARL-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,
L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report
L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023
Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3
ML23262B0372023-09-19019 September 2023
Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports
L-PI-22-034, Response to RAI, Alternative RR-08 Related to Pressure Isolation Valve Monitoring and Testing2022-07-14014 July 2022
Response to RAI, Alternative RR-08 Related to Pressure Isolation Valve Monitoring and Testing
ML22161A9152022-06-10010 June 2022
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Response to a Request for Additional Information Xcel Energy Amendment Request to Create a Common Emergency Plan and Emergency Operations.
L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022
Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles
L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021
Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2
L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021
Response to Request for Additional Information Cooling Water System License Amendment Request
L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021
Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island
L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020
Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020
Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)
ML20045E8942020-02-14014 February 2020
Response to a Request for Additional Information for Proposed 10 CFR 50.55a(z)(2) Alternatives to Utilize ASME Code Case N-786-3, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, and AS
ML20127J0002019-11-0707 November 2019
Xcel Reply to PIIC Expansion Application
L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019
Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals
L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019
Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...
L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019
Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018
Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805
L-PI-18-051, Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2018-09-17017 September 2018
Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
L-PI-18-038, Supplement to License Amendment Request to Revise License Condition Associated with Implementation of NFPA 8052018-07-10010 July 2018
Supplement to License Amendment Request to Revise License Condition Associated with Implementation of NFPA 805
ML18131A2232018-05-11011 May 2018
Prairie and Monticello - Response to Request for Additional Information Regarding Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Di
L-PI-17-042, Response to Request for Additional Information Regarding License Amendment Request to Revise the NDE Inspection Interval for Special Lifting Devices2017-11-0606 November 2017
Response to Request for Additional Information Regarding License Amendment Request to Revise the NDE Inspection Interval for Special Lifting Devices
ML17279A1212017-10-0404 October 2017
Enclosure 2 to L-PI-17-041, Westinghouse-Prepared RAI Responses CE-17-3, Rev. 1, Attachment 2 and Enclosure 3, Marked-Up Technical Specification Page 4.0-7
L-PI-17-035, License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information2017-09-27027 September 2017
License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information
L-PI-17-032, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times2017-09-20020 September 2017
Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times
L-PI-17-007, Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors2017-03-0606 March 2017
Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors
L-PI-17-002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action2017-02-16016 February 2017
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action
L-PI-16-100, Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes2017-02-16016 February 2017
Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes
L-PI-16-090, Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors2016-12-14014 December 2016
Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors
ML16351A2102016-12-13013 December 2016
External Flooding Assessment Focused Evaluation. (Redacted)
ML16288A0972016-10-14014 October 2016
and Monticello - Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools
L-PI-16-076, Supplement to the Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report2016-09-29029 September 2016
Supplement to the Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
ML16279A4792016-09-29029 September 2016
Flood Hazard Reevaluation Report - Response to Requested Information
L-PI-16-067, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information2016-08-17017 August 2016
License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information
L-PI-16-063, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2016-08-17017 August 2016
Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
L-PI-16-005, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information2016-05-24024 May 2016
License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information
ML16144A8062016-05-23023 May 2016
Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Response to RAI-2 (Enclosure 1) & Marked-Up Technical Specification Page (Enclosure 2)
L-PI-16-040, Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Westinghouse-Prepared Response to RAI, CE-16-237, Attachment 2 (Enclosure 4)2016-05-23023 May 2016
Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Westinghouse-Prepared Response to RAI, CE-16-237, Attachment 2 (Enclosure 4)
ML16133A0412016-05-0909 May 2016
Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
L-08-001, Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated..2016-04-14014 April 2016
Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated..
L-PI-16-029, Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2,,Using the Consolidated..2016-03-31031 March 2016
Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2,,Using the Consolidated..
L-PI-16-004, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information2016-01-20020 January 2016
License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information
L-PI-16-001, Enclosure 2: Responses to Open and Pending Items from the NRC Audit Report2016-01-14014 January 2016
Enclosure 2: Responses to Open and Pending Items from the NRC Audit Report
L-PI-15-105, License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process - Response to Request..2015-12-30030 December 2015
License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process - Response to Request..
L-PI-15-052, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information - 90-Day Responses2015-06-19019 June 2015
License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information - 90-Day Responses
L-PI-14-113, Updated Final Response to NRC Request for Information Per 10CFR50.54(f) Re Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-01-16016 January 2015
Updated Final Response to NRC Request for Information Per 10CFR50.54(f) Re Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
2024-01-02
[Table view] |
Text
Xcel Energy DEC 3 0 2015 L-PI-15-105 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process - Response to Request for Additional Information
References:
- 1. NSPM Letter, S. Sharp to NRC Document Control Desk, Application to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process, L-PI-15-030, dated June 29, 2015 (ADAMS Accession No. ML15187A259)
- 2. NRC email, T. Beltz to G. Carlson, Prairie Island Nuclear Generating Plant, Requests for Additional Information (Draft) re: License Amendment Request to Adopt TSTF-523, (TAC Nos. MF6449 and MF6450), dated October 27, 2015
- 3. NSPM Letter, S. Sharp to NRC Document Control Desk, Supplement to Responses to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" L-PI-09-122, dated November 24, 2009 (ADAMS Accession No. ML093280925), NSPM committed to submit an LAR, if necessary, within one year following NRC approval of the Technical Specification Task Force Traveler (TSTF) that provides TS resolution of GL 2008-01. This submittal satisfies the commitment.
In Reference 1, the Northern States Power Company, a Minnesota Corporation
("NSPM") doing business as Xcel Energy requested approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," using the Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance 1717 Wakonade Drive East
- Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page2 Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowances which permit performance of the verification. The changes are being made to address the concerns discussed in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems."
In Reference 2, the NRC staff provided requests for additional information (RAI) regarding this request. to this letter provides NSPM's response to the RAis.
This letter is submitted in accordance with 10 CFR 50.90. The additional information provided in this letter does not impact the conclusion of the "No Significant Hazards Evaluation or Environmental Considerations Evaluation" presented in Reference 1.
In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this additional information by transmitting a copy of this letter to the designated State Official.
If there are any questions or if additional information is needed, please contact Mr.
Glenn Carlson, at 651-267-1755.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on ;a/.3ol&.o!6.~
/ J
//
.0:_~
~vin Davison 1:'" 11 t~
Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota
L-PI-15-1 05 Enclosure Response to Requests for Additional Information (RAI)
License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process- Response to Request for Additional Information Introduction This Enclosure provides additional information from the Northern States Power Company, a Minnesota corporation (hereafter "NSPM") doing business as Xcel Energy, in support of a License Amendment Request (LAR) requesting approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the
- Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowance which permit performance of the verification. The changes are being made to address the concerns disused in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray System."
This enclosure to this letter provides NSPM's response to the RAI.
Each of the RAI questions is quoted in italics and each question is then followed by the NSPM response in normal font.
NRC Request RAI SRXB-1 a) Xcel Energy states the following in the proposed TS Bases for SR 3.4.6.4, SR 3.4. 7.4, SR 3.4.8.3 and SR 3.9.5.2:
b) The SR can be met by virtue of having an RHR subsystem inservice in accordance with operating procedures.
If the system is running with sufficient flow, then monitoring the running parameters is effective. If system flow is low, however, then gas voids may not transport through the system. Additionally, stagnant branch lines in an operating system may be susceptible to gas accumulation. This appears to be an alternative to petforming the SR.
c)
(a) Please explain how the flowrate of the operating system and the stagnant branch lines are taken into consideration when crediting the in-service loop as meeting the SR.
(b) Please explain why it is acceptable to describe this approach in the TS Bases rather than the TS surveillance. If necessary, revise the TS Bases so that they are in agreement with the approved TSTF-523 language.
NSPM Response (RAI SRXB-1)
These questions are not applicable. NSPM is changing what we currently requested for TS Bases SR 3.4.6.4, SR 3.4.7.4, SR 3.4.8.3 and SR 3.9.5.2 by removing the statement, "The SR can be met by virtue of having an RHR subsystem in service operating procedures."
By revising the TS Bases, our request will be in agreement with the approved TSTF-523 language.
NSPM will follow up with a supplemental to the LAR, on January 27, 2016.
Xcel Energy DEC 3 0 2015 L-PI-15-105 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process - Response to Request for Additional Information
References:
- 1. NSPM Letter, S. Sharp to NRC Document Control Desk, Application to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process, L-PI-15-030, dated June 29, 2015 (ADAMS Accession No. ML15187A259)
- 2. NRC email, T. Beltz to G. Carlson, Prairie Island Nuclear Generating Plant, Requests for Additional Information (Draft) re: License Amendment Request to Adopt TSTF-523, (TAC Nos. MF6449 and MF6450), dated October 27, 2015
- 3. NSPM Letter, S. Sharp to NRC Document Control Desk, Supplement to Responses to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" L-PI-09-122, dated November 24, 2009 (ADAMS Accession No. ML093280925), NSPM committed to submit an LAR, if necessary, within one year following NRC approval of the Technical Specification Task Force Traveler (TSTF) that provides TS resolution of GL 2008-01. This submittal satisfies the commitment.
In Reference 1, the Northern States Power Company, a Minnesota Corporation
("NSPM") doing business as Xcel Energy requested approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," using the Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance 1717 Wakonade Drive East
- Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page2 Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowances which permit performance of the verification. The changes are being made to address the concerns discussed in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems."
In Reference 2, the NRC staff provided requests for additional information (RAI) regarding this request. to this letter provides NSPM's response to the RAis.
This letter is submitted in accordance with 10 CFR 50.90. The additional information provided in this letter does not impact the conclusion of the "No Significant Hazards Evaluation or Environmental Considerations Evaluation" presented in Reference 1.
In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this additional information by transmitting a copy of this letter to the designated State Official.
If there are any questions or if additional information is needed, please contact Mr.
Glenn Carlson, at 651-267-1755.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on ;a/.3ol&.o!6.~
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~vin Davison 1:'" 11 t~
Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota
L-PI-15-1 05 Enclosure Response to Requests for Additional Information (RAI)
License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the Consolidated Line Item Improvement Process- Response to Request for Additional Information Introduction This Enclosure provides additional information from the Northern States Power Company, a Minnesota corporation (hereafter "NSPM") doing business as Xcel Energy, in support of a License Amendment Request (LAR) requesting approval from the Nuclear Regulatory Commission (NRC) to revise Technical Specifications to Adopt TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation," Using the
- Consolidated Line Item Improvement Process. The proposed change revises or adds Surveillance Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowance which permit performance of the verification. The changes are being made to address the concerns disused in Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray System."
This enclosure to this letter provides NSPM's response to the RAI.
Each of the RAI questions is quoted in italics and each question is then followed by the NSPM response in normal font.
NRC Request RAI SRXB-1 a) Xcel Energy states the following in the proposed TS Bases for SR 3.4.6.4, SR 3.4. 7.4, SR 3.4.8.3 and SR 3.9.5.2:
b) The SR can be met by virtue of having an RHR subsystem inservice in accordance with operating procedures.
If the system is running with sufficient flow, then monitoring the running parameters is effective. If system flow is low, however, then gas voids may not transport through the system. Additionally, stagnant branch lines in an operating system may be susceptible to gas accumulation. This appears to be an alternative to petforming the SR.
c)
(a) Please explain how the flowrate of the operating system and the stagnant branch lines are taken into consideration when crediting the in-service loop as meeting the SR.
(b) Please explain why it is acceptable to describe this approach in the TS Bases rather than the TS surveillance. If necessary, revise the TS Bases so that they are in agreement with the approved TSTF-523 language.
NSPM Response (RAI SRXB-1)
These questions are not applicable. NSPM is changing what we currently requested for TS Bases SR 3.4.6.4, SR 3.4.7.4, SR 3.4.8.3 and SR 3.9.5.2 by removing the statement, "The SR can be met by virtue of having an RHR subsystem in service operating procedures."
By revising the TS Bases, our request will be in agreement with the approved TSTF-523 language.
NSPM will follow up with a supplemental to the LAR, on January 27, 2016.
