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| number = ML14132A205 | | number = ML14132A205 | ||
| issue date = 05/09/2014 | | issue date = 05/09/2014 | ||
| title = | | title = NRR E-mail Capture - MF3089 - Defueled TS Amendment Request for Additrional Information | ||
| author name = Gratton C | | author name = Gratton C | ||
| author affiliation = NRC/NRR/DORL/LPLIV-2 | | author affiliation = NRC/NRR/DORL/LPLIV-2 | ||
Line 14: | Line 14: | ||
| page count = 3 | | page count = 3 | ||
| project = | | project = | ||
| stage = | | stage = Other | ||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:NRR-PMDAPEm Resource From: Gratton, Christopher Sent: Friday, May 09, 2014 1:39 PM To: Westcott, Daniel (Daniel.Westcott@duke-energy.com) | ||
==Subject:== | ==Subject:== | ||
MF3089 - Defueled TS Amendment Request for Additrional Information Mr. Westcott, By letter dated October 29, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13316C083), Duke Energy Florida, Inc. (DEF, or the licensee) submitted a license amendment request regarding Crystal River Nuclear Plant Unit 3 (CR-3) Facility Operating License. The proposed amendment would revise the technical specifications and license conditions to create permanently defuel technical specifications for CR3. | MF3089 - Defueled TS Amendment Request for Additrional Information Mr. Westcott, By letter dated October 29, 2013 (Agencywide Documents Access and Management System (ADAMS) | ||
The Nuclear Regulatory Commission (NRC) staff has performed a preliminary review of the request and found that some further information is needed to complete the | Accession No. ML13316C083), Duke Energy Florida, Inc. (DEF, or the licensee) submitted a license amendment request regarding Crystal River Nuclear Plant Unit 3 (CR-3) Facility Operating License. The proposed amendment would revise the technical specifications and license conditions to create permanently defuel technical specifications for CR3. | ||
The Nuclear Regulatory Commission (NRC) staff has performed a preliminary review of the request and found that some further information is needed to complete the staffs review. The staffs draft information request is included below. The NRC considers that timely responses to request for additional information (RAIs) help ensure sufficient time is available for the NRC staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. | |||
Please provide your response by June 13, 2014. | Please provide your response by June 13, 2014. | ||
You may request a conference call to discuss the contents of this draft RAI with the NRC staff, including any change to the proposed schedule. Please send me an email if you do not need a conference call to clarify the draft RAI. If you do not require a call to clarify the draft RAI, the information request will be considered final. | |||
You may request a conference call to discuss the contents of this draft RAI with the NRC staff, including any change to the proposed schedule. Please send me an email if you do not need a conference call to clarify the draft RAI. If you do not require a call to clarify the draft RAI, the information request will be considered final. | Respectfully, Christopher Gratton Sr. Project Manager PM Crystal River Nuclear Generating Plant NRR/DORL/LPL 4-2 and Decommissioning Transition Branch 301-415-1055 Mail Stop O-8G9a Christopher.Gratton@nrc.gov REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION CRYSTAL RIVER NUCLEAR PLANT UNIT 3 DOCKET NO. 50-302 In letter dated October 29, 2013 (Agencywide Documents Access and Management System (ADAMS) | ||
Accession No. ML13316C083), Duke Energy Florida, Inc., (the licensee) submitted a License Amendment Request (LAR) regarding Crystal River Unit 3 Facility Operating License. The amendment proposes to remove or revise certain License Conditions that are no longer applicable to CR-3 in the permanently defueled condition. In addition, the LAR proposes to extensively revise the CR-3 Improved Technical Specifications in order to create the CR-3 Permanently Defueled Technical Specifications (PDTS). | |||
Respectfully, | The NRC staff has reviewed the licensees proposed changes to TS sections 1.0, 2.0, and 3.0 and identified the need for additional information as explained below: | ||
1 | |||
Christopher Gratton Sr. Project Manager PM Crystal River Nuclear Generating Plant NRR/DORL/LPL 4-2 and Decommissioning Transition Branch | |||
301-415-1055 | |||
Mail Stop O-8G9a Christopher.Gratton@nrc.gov | |||
REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION CRYSTAL RIVER NUCLEAR PLANT UNIT 3 DOCKET NO. 50-302 In letter dated October 29, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13316C083), Duke Energy Florida, Inc., (the licensee) submitted a License Amendment Request (LAR) regarding Crystal River Unit 3 Facility Operating License. The amendment proposes to remove or revise certain License Conditions that are no longer applicable to CR-3 in the permanently defueled condition. In addition, the LAR proposes to extensively revise the CR-3 Improved Technical Specifications in order to create the CR-3 Permanently Defueled Technical Specifications (PDTS). | |||
The NRC staff has reviewed the | |||
* Proposed change in Limiting Condition for Operations (LCO) 3.0.1: | * Proposed change in Limiting Condition for Operations (LCO) 3.0.1: | ||
LCO 3.0.1 currently states, | LCO 3.0.1 currently states, LCOs shall be met during the MODES or other-specified conditions in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7 and LCO 3.0.8. One of the proposed changes concerns the deletion of reference to LCO 3.0.2. | ||
in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7 and LCO 3.0.8. | |||
Request for Additional Information #1 LCO 3.0.2, though modified, will still be included in the PDTS. No specific basis for deleting the reference to TS 3.0.2 from TS 3.0.1 is provided in the application. Please provide the basis for deleting the reference to LCO 3.0.2 from TS 3.0.1. | Request for Additional Information #1 LCO 3.0.2, though modified, will still be included in the PDTS. No specific basis for deleting the reference to TS 3.0.2 from TS 3.0.1 is provided in the application. Please provide the basis for deleting the reference to LCO 3.0.2 from TS 3.0.1. | ||
* Proposed change in LCO 3.0.2 | * Proposed change in LCO 3.0.2: | ||
This LCO currently states, Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and 3.0.6. | |||
If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated. | |||
The licensees proposed change to LCO 3.0.2 deletes the above paragraph in bold. The licensees application does not specifically discuss the reason for the proposed change. It simply states, Proposed for revision to be consistent with the permanently defueled condition by removing reference to 3.0.x LCOs that are proposed for removal from the PDTS. | |||
Request for Additional Information #2 The licensee proposes to delete [I]f the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated, from the TS 3.0.2 in the PDTS, but does not provide a basis for the change in the application. | |||
Please provide a basis for the deletion of this text from TS 3.0.2. | |||
* Request for Additional Information #3 SR 3.0.3 currently states, A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed. Please explain the risk evaluation methodology approach that will be used for the defueled reactor. | |||
* Request for Additional Information #4 LCO 3.7.15 Figure 3.7.15-2 on page 3.7-7 in CR 3 PDTS, is applicable to Burnup versus Enrichment Curve for Spent Fuel Storage Pool, whereas, the page heading is titled as Diesel Driven EFW Pump Fuel Oil, Lube Oil and Starting Air 3.7.19. Please make the correction. | |||
2 | |||
Hearing Identifier: NRR_PMDA Email Number: 1278 Mail Envelope Properties (Christopher.Gratton@nrc.gov20140509133800) | |||
Hearing Identifier: | |||
==Subject:== | ==Subject:== | ||
MF3089 - Defueled TS Amendment Request for Additrional Information | MF3089 - Defueled TS Amendment Request for Additrional Information Sent Date: 5/9/2014 1:38:46 PM Received Date: 5/9/2014 1:38:00 PM From: Gratton, Christopher Created By: Christopher.Gratton@nrc.gov Recipients: | ||
"Westcott, Daniel (Daniel.Westcott@duke-energy.com)" <Daniel.Westcott@duke-energy.com> | |||
Options | Tracking Status: None Post Office: | ||
Files Size Date & Time MESSAGE 5150 5/9/2014 1:38:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: | |||
Recipients Received:}} |
Latest revision as of 06:17, 5 December 2019
ML14132A205 | |
Person / Time | |
---|---|
Site: | Crystal River |
Issue date: | 05/09/2014 |
From: | Gratton C Plant Licensing Branch IV |
To: | Westcott D Duke Energy Corp |
References | |
MF3089 | |
Download: ML14132A205 (3) | |
Text
NRR-PMDAPEm Resource From: Gratton, Christopher Sent: Friday, May 09, 2014 1:39 PM To: Westcott, Daniel (Daniel.Westcott@duke-energy.com)
Subject:
MF3089 - Defueled TS Amendment Request for Additrional Information Mr. Westcott, By letter dated October 29, 2013 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML13316C083), Duke Energy Florida, Inc. (DEF, or the licensee) submitted a license amendment request regarding Crystal River Nuclear Plant Unit 3 (CR-3) Facility Operating License. The proposed amendment would revise the technical specifications and license conditions to create permanently defuel technical specifications for CR3.
The Nuclear Regulatory Commission (NRC) staff has performed a preliminary review of the request and found that some further information is needed to complete the staffs review. The staffs draft information request is included below. The NRC considers that timely responses to request for additional information (RAIs) help ensure sufficient time is available for the NRC staff review and contribute toward the NRCs goal of efficient and effective use of staff resources.
Please provide your response by June 13, 2014.
You may request a conference call to discuss the contents of this draft RAI with the NRC staff, including any change to the proposed schedule. Please send me an email if you do not need a conference call to clarify the draft RAI. If you do not require a call to clarify the draft RAI, the information request will be considered final.
Respectfully, Christopher Gratton Sr. Project Manager PM Crystal River Nuclear Generating Plant NRR/DORL/LPL 4-2 and Decommissioning Transition Branch 301-415-1055 Mail Stop O-8G9a Christopher.Gratton@nrc.gov REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION CRYSTAL RIVER NUCLEAR PLANT UNIT 3 DOCKET NO. 50-302 In letter dated October 29, 2013 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML13316C083), Duke Energy Florida, Inc., (the licensee) submitted a License Amendment Request (LAR) regarding Crystal River Unit 3 Facility Operating License. The amendment proposes to remove or revise certain License Conditions that are no longer applicable to CR-3 in the permanently defueled condition. In addition, the LAR proposes to extensively revise the CR-3 Improved Technical Specifications in order to create the CR-3 Permanently Defueled Technical Specifications (PDTS).
The NRC staff has reviewed the licensees proposed changes to TS sections 1.0, 2.0, and 3.0 and identified the need for additional information as explained below:
1
- Proposed change in Limiting Condition for Operations (LCO) 3.0.1:
LCO 3.0.1 currently states, LCOs shall be met during the MODES or other-specified conditions in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7 and LCO 3.0.8. One of the proposed changes concerns the deletion of reference to LCO 3.0.2.
Request for Additional Information #1 LCO 3.0.2, though modified, will still be included in the PDTS. No specific basis for deleting the reference to TS 3.0.2 from TS 3.0.1 is provided in the application. Please provide the basis for deleting the reference to LCO 3.0.2 from TS 3.0.1.
- Proposed change in LCO 3.0.2:
This LCO currently states, Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and 3.0.6.
If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.
The licensees proposed change to LCO 3.0.2 deletes the above paragraph in bold. The licensees application does not specifically discuss the reason for the proposed change. It simply states, Proposed for revision to be consistent with the permanently defueled condition by removing reference to 3.0.x LCOs that are proposed for removal from the PDTS.
Request for Additional Information #2 The licensee proposes to delete [I]f the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated, from the TS 3.0.2 in the PDTS, but does not provide a basis for the change in the application.
Please provide a basis for the deletion of this text from TS 3.0.2.
- Request for Additional Information #3 SR 3.0.3 currently states, A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed. Please explain the risk evaluation methodology approach that will be used for the defueled reactor.
- Request for Additional Information #4 LCO 3.7.15 Figure 3.7.15-2 on page 3.7-7 in CR 3 PDTS, is applicable to Burnup versus Enrichment Curve for Spent Fuel Storage Pool, whereas, the page heading is titled as Diesel Driven EFW Pump Fuel Oil, Lube Oil and Starting Air 3.7.19. Please make the correction.
2
Hearing Identifier: NRR_PMDA Email Number: 1278 Mail Envelope Properties (Christopher.Gratton@nrc.gov20140509133800)
Subject:
MF3089 - Defueled TS Amendment Request for Additrional Information Sent Date: 5/9/2014 1:38:46 PM Received Date: 5/9/2014 1:38:00 PM From: Gratton, Christopher Created By: Christopher.Gratton@nrc.gov Recipients:
"Westcott, Daniel (Daniel.Westcott@duke-energy.com)" <Daniel.Westcott@duke-energy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 5150 5/9/2014 1:38:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: