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| | issue date = 02/09/2011 | | | issue date = 02/09/2011 |
| | title = Request for Additional Information Extended Power Uprate - Safety Systems and Component Integrity Review | | | title = Request for Additional Information Extended Power Uprate - Safety Systems and Component Integrity Review |
| | author name = Guzman R V | | | author name = Guzman R |
| | author affiliation = NRC/NRR/DORL | | | author affiliation = NRC/NRR/DORL |
| | addressee name = Belcher S L | | | addressee name = Belcher S |
| | addressee affiliation = Nine Mile Point Nuclear Station, LLC | | | addressee affiliation = Nine Mile Point Nuclear Station, LLC |
| | docket = 05000410 | | | docket = 05000410 |
| | license number = NPF-069 | | | license number = NPF-069 |
| | contact person = Guzman R V, NRR/DORL, 415-1030 | | | contact person = Guzman R, NRR/DORL, 415-1030 |
| | case reference number = TAC ME1476 | | | case reference number = TAC ME1476 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 February 9, 2011 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.2 -RE: THE LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE OPERATION (TAC NO. ME1476) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 9, 2011 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 |
| | |
| | ==SUBJECT:== |
| | REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.2 - RE: THE LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE OPERATION (TAC NO. ME1476) |
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| ==Dear Mr. Belcher:== | | ==Dear Mr. Belcher:== |
| By letter dated May 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091610103), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for Nine Mile Point, Unit No.2 (NMP2). The proposed amendment requests an increase in the maximum steady-state power level at NMP2 from 3467 megawatts thermal (MWt) to 3988 MWt. This represents a 15-percent increase over the current licensed thermal power. Based on its review of the LAR and the supplemental information provided by the NMPNS in letter December 13, 2010 (ADAMS Accession No. ML 103500364), the Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on January 27 and February 8, 2011, and it was agreed that your response would be provided within 60 days from the date of this letter. Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 | | |
| | By letter dated May 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091610103), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for Nine Mile Point, Unit No.2 (NMP2). |
| | The proposed amendment requests an increase in the maximum steady-state power level at NMP2 from 3467 megawatts thermal (MWt) to 3988 MWt. This represents a 15-percent increase over the current licensed thermal power. |
| | Based on its review of the LAR and the supplemental information provided by the NMPNS in letter December 13, 2010 (ADAMS Accession No. ML103500364), the Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on January 27 and February 8, 2011, and it was agreed that your response would be provided within 60 days from the date of this letter. |
| | Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION (RAn FOR LICENSE AMENDMENT REQUEST RE: EXTENDED POWER UPRATE (EPU) NINE MILE POINT NUCLEAR STATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT NO.2 DOCKET NO. | | As stated cc w/encl: Distribution via Listserv |
| By letter dated May 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091610103), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for Nine Mile Point. Unit No.2 (NMP2). The proposed amendment requests an increase in the maximum power level at NMP2 from 3467 megawatts thermal (MWt) to 3966 MWt. This represents a 15-percent increase over the current licensed thermal power. Based on its review of the license amendment request and the supplemental information provided by the NMPNS in letter dated December 13. 2010 (ADAMS Accession No. ML 103500364), the Nuclear Regulatory Commission staff has determined that additional information requested below will be needed to support its review. 1. In letter dated December 13,2010, the licensee stated that: All fuel assembly types were analyzed using CASM04 at 4.95% enrichment (including the manufacturing tolerance of +/- 0.05% enrichment which is equivalent to the 5.0% enrichment discussed in NMP2 Updated Safety Analysis Report Section 9.1.2.2).
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| The above statement appears inadequate to support an enrichment of 5.0%. Analysis at 4.95% with a +/- 0.05% tolerance would justify an enrichment of 4.95%. By the same reason, the updated safety analysis report also appears inadequate.
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| Clarify this statement.
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| The various submittals lack clarity of the licensed enrichment limit. The NMP2 power uprate safety analysis report (PUSAR) Table specifies 5.0%. PUSAR Table specifies 4.9%. The letter dated December 13. 2010, specifies 4.95%. What is the enrichment limit justified by analysiS?
| |
| Specify this limit in the Technical Specifications (TSs) in accordance with Title 10 of the Code of Federal Regulations, (10 CFR) Section 50.36. 2. In letter dated December 13, 2010, the licensee stated that: The current GE14 fuel lattice design satisfies the NMP2 new fuel vault storage criteria outlined in Technical Specification (TS) Section 4.3 provided that the peak, eigenvalue of any constituent fuel lattice, as computed by either the GNF lattice physics codes TGBLA04A or TGBLA06A, does not exceed 1.29. However. the PUSAR lists a peak in-core eigenvalue limit of 1.3392. Clarify this discrepancy and specify this limit in the TSs in accordance with 10 CFR 50.36. In addition, provide the in-Enclosure
| |
| -2 rack maximum k-effective for new fuel storage determined by analysis and the supporting analysis. On page 3 of Attachment 1 of its response dated December 13, 2010, the licensee states that NMP2 added 10 new Holtec Boral spent fuel storage racks in the NMP2 spent fuel pool as part of the Phase I re-rack via a 10 CFR 50.59 evaluation.
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| Afterward, NMP2 performed the Phase II re-rack, similarly using a 10 CFR 50.59 evaluation in support of the modification, which replaced 16 original Boraflex spent fuel storage racks with Holtec Boral racks. The licensee further stated that the new Boral spent fuel storage racks are incorporated into the criticality analysis that has been submitted in support of NMPZs EPU LAR. It is not clear to the NRC staff how the licensee can ensure that the Boral material will continue to perform its intended function in the future. As such, please discuss how the neutron absorber will be monitored and maintained (e.g. use of surveillance program).
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| If a program is utilized, discuss in detail the approach that will be used in the monitoring program, specifically the methods and techniques utilized (e.g., visual, weight, volumetric, surface inspection, neutron attenuation testing), frequency of inspection, sample size, data collection and acceptance criteria.
| |
| : a. Please indicate the installation date for new and replacement Boral storage racks. b. Please discuss whether NMP2 utilizes a Boral coupon program for the new and replacement Boral storage racks. If a coupon program is being used, please describe the program. Specifically: (i) Identify the quantity and location of coupons relative to the spent fuel racks. (ii) Describe how the coupons are mounted and whether they are fully exposed to the spent fuel pool water. (iii) Discuss whether any coupons that are removed and inspected using non destructive techniques will be re-inserted in the spent fuel pool for future evaluation. (iv) Indicate whether the Boral racks in the spent fuel pool are vented or not. Please describe how the areal density of the Boral material will be measured (e.g., neutron attenuation) and maintained to prevent an inadvertent criticality.
| |
| Please include a description of the testing, parameters measured, calculations, and acceptance criteria.
| |
| February 9, 2011 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.2 -RE: THE LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE OPERATION (TAC NO. ME1476)
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| ==Dear Mr. Belcher:==
| | REQUEST FOR ADDITIONAL INFORMATION (RAn FOR LICENSE AMENDMENT REQUEST RE: EXTENDED POWER UPRATE (EPU) |
| By letter dated May 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML09161 01 03), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for Nine Mile Point, Unit No.2 (NMP2). The proposed amendment requests an increase in the maximum steady-state power level at NMP2 from 3467 megawatts thermal (MWt) to 3988 MWt. This represents a 15-percent increase over the current licensed thermal power. Based on its review of the LAR and the supplemental information provided by the NMPNS in letter December 13,2010 (ADAMS Accession No. ML 103500364), the Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on January 27 and February 8, 2011, and it was agreed that your response would be provided within 60 days from the date of this letter. Sincerely, Ira! Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 | | NINE MILE POINT NUCLEAR STATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT NO.2 DOCKET NO. 50~410 By letter dated May 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091610103), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for Nine Mile Point. Unit No.2 (NMP2). |
| | The proposed amendment requests an increase in the maximum steady~state power level at NMP2 from 3467 megawatts thermal (MWt) to 3966 MWt. This represents a 15-percent increase over the current licensed thermal power. |
| | Based on its review of the license amendment request and the supplemental information provided by the NMPNS in letter dated December 13. 2010 (ADAMS Accession No. ML103500364), the Nuclear Regulatory Commission staff has determined that additional information requested below will be needed to support its review. |
| | : 1. In letter dated December 13,2010, the licensee stated that: |
| | All fuel assembly types were analyzed using CASM04 at 4.95% enrichment (including the manufacturing tolerance of +/- 0.05% enrichment which is equivalent to the 5.0% enrichment discussed in NMP2 Updated Safety Analysis Report Section 9.1.2.2). |
| | The above statement appears inadequate to support an enrichment of 5.0%. Analysis at 4.95% |
| | with a +/- 0.05% tolerance would justify an enrichment of 4.95%. By the same reason, the updated safety analysis report also appears inadequate. Clarify this statement. |
| | The various submittals lack clarity of the licensed enrichment limit. The NMP2 power uprate safety analysis report (PUSAR) Table 2.6~10 specifies 5.0%. PUSAR Table 2.6~10 specifies 4.9%. The letter dated December 13. 2010, specifies 4.95%. What is the enrichment limit justified by analysiS? Specify this limit in the Technical Specifications (TSs) in accordance with Title 10 of the Code of Federal Regulations, (10 CFR) Section 50.36. |
| | : 2. In letter dated December 13, 2010, the licensee stated that: |
| | The current GE14 fuel lattice design satisfies the NMP2 new fuel vault storage criteria outlined in Technical Specification (TS) Section 4.3 provided that the peak, in~core eigenvalue of any constituent fuel lattice, as computed by either the GNF lattice physics codes TGBLA04A or TGBLA06A, does not exceed 1.29. |
| | However. the PUSAR lists a peak in-core eigenvalue limit of 1.3392. Clarify this discrepancy and specify this limit in the TSs in accordance with 10 CFR 50.36. In addition, provide the in-Enclosure |
| | |
| | -2 rack maximum k-effective for new fuel storage determined by analysis and the supporting analysis. |
| | : 3. On page 3 of Attachment 1 of its response dated December 13, 2010, the licensee states that NMP2 added 10 new Holtec Boral spent fuel storage racks in the NMP2 spent fuel pool as part of the Phase I re-rack via a 10 CFR 50.59 evaluation. Afterward, NMP2 performed the Phase II re-rack, similarly using a 10 CFR 50.59 evaluation in support of the modification, which replaced 16 original Boraflex spent fuel storage racks with Holtec Boral racks. The licensee further stated that the new Boral spent fuel storage racks are incorporated into the criticality analysis that has been submitted in support of NMPZs EPU LAR. It is not clear to the NRC staff how the licensee can ensure that the Boral material will continue to perform its intended function in the future. As such, please discuss how the neutron absorber will be monitored and maintained (e.g. use of surveillance program). If a program is utilized, discuss in detail the approach that will be used in the monitoring program, specifically the methods and techniques utilized (e.g., visual, weight, volumetric, surface inspection, neutron attenuation testing), frequency of inspection, sample size, data collection and acceptance criteria. |
| | : a. Please indicate the installation date for new and replacement Boral storage racks. |
| | : b. Please discuss whether NMP2 utilizes a Boral coupon program for the new and replacement Boral storage racks. If a coupon program is being used, please describe the program. Specifically: |
| | (i) Identify the quantity and location of coupons relative to the spent fuel racks. |
| | (ii) Describe how the coupons are mounted and whether they are fully exposed to the spent fuel pool water. |
| | (iii) Discuss whether any coupons that are removed and inspected using non destructive techniques will be re-inserted in the spent fuel pool for future evaluation. |
| | (iv) Indicate whether the Boral racks in the spent fuel pool are vented or not. |
| | : 4. Please describe how the areal density of the Boral material will be measured (e.g., neutron attenuation) and maintained to prevent an inadvertent criticality. Please include a description of the testing, parameters measured, calculations, and acceptance criteria. |
| | |
| | ML103500364), the Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on January 27 and February 8, 2011, and it was agreed that your response would be provided within 60 days from the date of this letter. |
| | Sincerely, Ira! |
| | Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Distribution via Listserv DISTRIBUTION: | | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| PUBLIC RidsNrrPMNineMilePoint RidsNrrLASLiUle RidsNrrDorlLpl1-1 LPLI-1 RlF RidsOGCRp RidsRgn 1 MailCenter RidsNrrDssSrxb TNakanishi, NRR EWong, NRR AObodoako, NRR RidsNrrDeCsgb RidsNrrAcrsAcnw&mMailCenter ADAMS A . 0.: ML110400037 | | PUBLIC RidsNrrPMNineMilePoint RidsNrrLASLiUle RidsNrrDorlLpl1-1 LPLI-1 RlF RidsOGCRp RidsRgn 1MailCenter RidsNrrDssSrxb TNakanishi, NRR EWong, NRR AObodoako, NRR RidsNrrDeCsgb RidsNrrAcrsAcnw&mMailCenter ADAMS Accesslon . N0.: ML110400037 *RAI provi'd edb>y memo. No su b t flal h San c anges made. |
| *RAI provi >y memo. o su btflh c anges ma e. ccesslon 'd e db N S an la d NRR 088 [OFFICE LPL1-1/PM LPL1-1/LA CSGB/BC SRXB/BC LPL 1-1/BC NAME RGuzman SUttle RTaylor' AUlses' NSalgado DATE 2/9/11 2/9/11 1/20/11 Memo DTD 1/12/11 Memo DTD 219/11 OFFICIAL RECORD COPY}} | | NRR 088 |
| | [OFFICE LPL1-1/PM LPL1-1/LA CSGB/BC SRXB/BC LPL 1-1/BC NAME RGuzman SUttle RTaylor' AUlses' NSalgado DATE 2/9/11 2/9/11 1/20/11 Memo DTD 1/12/11 Memo DTD 219/11}} |
Letter Sequence RAI |
|---|
TAC:ME1476, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting
Results
Other: ML092460553, ML092460595, ML092460596, ML100190073, ML100190074, ML100190075, ML100190076, ML100190077, ML101300006, ML101900448, ML101900449, ML101900450, ML101950497, ML101950498, ML103050187, ML110460160, ML110880302, ML11171A060, ML111920326, ML111950133, ML112031112, ML112081701, ML112160736, ML11221A013, ML112450479, ML112460008, ML112460009, ML113340186, ML120050150, ML120250137, ML12313A203, ML12313A204, ML12313A206, NRC-2010-0117, Final Environmental Assessment and Finding of No Significant Impact - Federal Register Notice - Related to the Proposed License Amendment to Increase the Maximum Reactor Power Level
|
MONTHYEARML1001900772004-03-31031 March 2004
GE-NE-0000-0024-6517-R0, Safer/Gestr Loss-of-Coolant Accident Analysis for GE14 Fuel.
Project stage: Other
ML0916101032009-05-27027 May 2009
License Amendment Request (LAR) Pursuant to 10 CFR 50.90: Extended Power Uprate
Project stage: Request
ML0918906662009-07-0808 July 2009
E-mail from R. Guzman to J. Dosa Acceptance Review Results of NMP2 Extended Power Uprate Application
Project stage: Acceptance Review
ML0919402542009-07-15015 July 2009
Acceptance Review of License Amendment Request Extended Power Uprate
Project stage: Acceptance Review
ML0924605502009-08-28028 August 2009
Response to Acceptance Review Comments License Amendment Request for Extended Power Uprate
Project stage: Request
ML0924605962009-08-28028 August 2009
Attachment 2 - CDI Report 09-26NP, Revision 0, (Non-Proprietary) Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Part 2 of 2
Project stage: Other
ML0924605952009-08-28028 August 2009
Attachment 2 - CDI Report 09-26NP, Revision 0, (Non-Proprietary) Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Part 1 of 2
Project stage: Other
ML0924605532009-08-28028 August 2009
Attachment 3 - CDI Report 08-08NP, Revision 2, (Non-Proprietary) Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point, Unit 2 Steam Dryer to 250 Hz
Project stage: Other
ML0924502742009-09-0202 September 2009
Acceptance Review Determination of Amendment Request and Supplemental Information Extended Power Uprate
Project stage: Acceptance Review
ML1019704202009-09-18018 September 2009
E-mail from R. Guzman to J. Dosa Request for Additional Information - Clarification of Applicability of GEH Methods
Project stage: RAI
ML0928100032009-10-0808 October 2009
Request for Additional Information Nine Mile Point Unit 2 (NMP2) Extended Power Uprate Application License Amendment Request
Project stage: RAI
ML0930800012009-11-13013 November 2009
Request for Additional Information Extended Power Uprate
Project stage: RAI
ML0931900032009-11-18018 November 2009
Request for Additional Information the License Amendment Request for Extended Power Uprate
Project stage: RAI
ML0934300032009-12-10010 December 2009
Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement Dated August 28, 2009 C.D.I Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2
Project stage: Withholding Request Acceptance
ML0932706132009-12-10010 December 2009
Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation Dated May 27, 2009 C.D.I Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2
Project stage: Withholding Request Acceptance
ML0934106852009-12-10010 December 2009
Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation Dated May 27, 2009 GEH Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2
Project stage: Withholding Request Acceptance
ML0935110252009-12-23023 December 2009
Request for Additional Information Extended Power Uprate License Amendment Request
Project stage: RAI
ML1001900722009-12-23023 December 2009
Response to Request for Additional Information, Regarding License Amendment Request for Extended Power Uprate Operation
Project stage: Response to RAI
ML1001900732009-12-31031 December 2009
C.D.I. Technical Note No. 09-17NP, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Nine Mile Point, Unit 2, Revision 0
Project stage: Other
ML1001900742009-12-31031 December 2009
C.D.I. Report No. 08-08NP, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz, Revision 3
Project stage: Other
ML1001900752009-12-31031 December 2009
CDI Report No. 09-26NP, Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Cover to Page 62, Revision 1
Project stage: Other
ML1001900762009-12-31031 December 2009
CDI Report No. 09-26NP, Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Page 63 Through 130, Revision 1
Project stage: Other
ML1019704362010-01-12012 January 2010
E-mail from R. Guzman to T. Darling Request for Additional Information - Extended Power Uprate LAR Standby Liquid Control System
Project stage: RAI
ML1019704452010-01-27027 January 2010
E-mail from R. Guzman to T. Darling Request for Additional Information Extended Power Uprate - Clarification for Piping NDE Review
Project stage: RAI
ML1019704532010-02-0101 February 2010
E-mail from R. Guzman to T. Darling Request for Additional Information Extended Power Uprate LAR - Clarification in Fire Protection Review RAI D1, D3
Project stage: RAI
ML1005505992010-02-19019 February 2010
Response to Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Operation
Project stage: Response to RAI
ML1006301122010-03-10010 March 2010
Request for Additional Information - Extended Power Uprate License Amendment Request Mechanical & Civil Engineering Review
Project stage: RAI
ML1006902762010-03-10010 March 2010
E-mail from R.Guzman to T.Darling Request for Additional Information - Containment & Ventilation Branch - Extended Power Uprate
Project stage: RAI
ML1006301082010-03-10010 March 2010
Request for Additional Information Steam Dryer Review of the License Amendment Request for Extended Power Uprate Operation
Project stage: RAI
ML1005508412010-03-16016 March 2010
Letter Transmitting the Draft Environmental Assessment for Nine Mile Point Nuclear Station Extended Power Uprate for Unit No. 2
Project stage: Draft Other
ML1006804292010-04-0202 April 2010
Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement Dated December 23, 2009 GEH Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2
Project stage: Withholding Request Acceptance
ML1006804412010-04-0202 April 2010
Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement December 23,2 009 C.D.I Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2
Project stage: Withholding Request Acceptance
ML1006804482010-04-0202 April 2010
Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement February 19, 2010 GEH Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2
Project stage: Withholding Request Acceptance
ML1008500412010-04-0202 April 2010
Summary of Audit Related to the Review of the Extended Power Uprate License Amendment Request of Nine Mile Point Nuclear Station, Unit No. 2
Project stage: Approval
ML1008500512010-04-0202 April 2010
Correction Notice to Draft Environmental Assessment for Nine Mile Point Nuclear Station Proposed Extended Power Uprate Amendment for Unit No. 2
Project stage: Draft Other
ML1008501072010-04-0202 April 2010
Letter Transmitting Correction to the Notice for the Draft Environmental Assessment and Finding of No Significant Impact for Nine Mile Point Nuclear Station, Unit No. 2
Project stage: Draft Other
ML1013000062010-04-14014 April 2010
Follow-Up Questions - EPU Vessels and Integrity Review
Project stage: Other
ML1011206582010-04-16016 April 2010
Response to Request for Additional Information Re License Amendment Request for Extended Power Uprate Operation
Project stage: Response to RAI
ML1013803072010-05-0707 May 2010
Response to Request for Additional Information Regarding Steam Dryer Review of the License Amendment Request for Extended Power Uprate Operation
Project stage: Response to RAI
ML1013200242010-05-10010 May 2010
E-mail from R. Guzman to T. Darling/J. Dosa Request for Additional Information - LOCA Analysis, Extended Power Uprate
Project stage: RAI
ML1012504242010-05-11011 May 2010
Request for Additional Information Extended Power Uprate License Amendment Request - Reactor System Review
Project stage: RAI
ML1016101682010-06-0303 June 2010
Response to Request for Additional Information Regarding the License Amendment Request for Extended Power Uprate Operation- Reactor Systems Review
Project stage: Response to RAI
ML1015908092010-06-0808 June 2010
Request for Additional Information Extended Power Uprate - Probabilistic Risk Assessment Review
Project stage: RAI
ML1015906522010-06-10010 June 2010
Review of Extended Power Uprate Application and Revised Review Schedule
Project stage: Approval
ML1019604812010-06-15015 June 2010
E-mail from R.Guzman to T.Darling Request for Additional Information Follow-up RAI - Reactor Systems/Criticality Analysis
Project stage: RAI
ML1019004492010-06-30030 June 2010
C.D.I. Report No. 10-10NP, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1, Rev. 1
Project stage: Other
ML1019004502010-06-30030 June 2010
Calculation SIA 100632.301, Revision 0, May 2010 Nine Mile Point Unit 2 Main Steam Line Strain Gage Data Reduction.
Project stage: Other
ML1019004482010-06-30030 June 2010
C.D.I. Report No. 10-09NP, ACM Rev. 4.1: Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, Rev. 1 (Non-Proprietary)
Project stage: Other
ML1019004472010-06-30030 June 2010
Response to Request for Additional Information Regarding the License Amendment Request for Extended Power Uprate Operation - Steam Dryer and Probabilistic Risk Assessment
Project stage: Response to RAI
ML1019504952010-07-0909 July 2010
Response to Request for Additional Information Regarding the License Amendment Request for Extended Power Uprate Operation, Non-Proprietary Version of Continuum Dynamics, Inc. Report 10-11
Project stage: Response to RAI
2010-02-01
[Table View] |
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024
Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
IR 05000220/20243022024-10-0303 October 2024
Initial Operator Licensing Examination Report 05000220/2024302
ML24190A0012024-09-26026 September 2024
Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000220/20240052024-08-29029 August 2024
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005)
IR 05000220/20240102024-08-22022 August 2024
Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024
Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000220/20240022024-08-0505 August 2024
Integrated Inspection Report 05000220/2024002 and 05000410/2024002
ML24215A3002024-08-0202 August 2024
Operator Licensing Examination Approval
NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024
Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
ML24213A1412024-07-31031 July 2024
Requalification Program Inspection
NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations
ML24198A0852024-07-16016 July 2024
Senior Reactor and Reactor Operator Initial License Examinations
RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024
Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024
License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
IR 05000220/20244012024-05-30030 May 2024
Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only)
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024
Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request
NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
ML24158A2052024-05-15015 May 2024
Annual Radioactive Environmental Operating Report
NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024
2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2
IR 05000220/20240012024-05-10010 May 2024
Integrated Inspection Report 05000220/2024001 and 05000410/2024001
RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024
Updated Notice of Intent to Pursue Subsequent License Renewal Applications
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024
Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report
NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024
2023 Annual Environmental Operating Report
NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024
Core Operating Limits Report
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24092A3352024-04-0101 April 2024
NRC Office of Investigations Case No. 1-2023-002
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
IR 05000220/20230062024-02-28028 February 2024
Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006)
IR 05000220/20230042024-02-0101 February 2024
Integrated Inspection Report 05000220/2023004 and 05000410/2023004
NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024
Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024
Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater
NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024
CFR 50.46 Annual Report
ML24004A2122024-01-0808 January 2024
Senior Reactor and Reactor Operator Initial License Examinations
ML23354A0012024-01-0404 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023
Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12
NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023
Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station
2024-09-04
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24312A1662024-11-0707 November 2024
Request for Additional Information (11/7/2024 E-mail) - LAR to Revise TSs to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3
ML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
ML23264A7992023-09-21021 September 2023
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC – Fleet Request – License Amendment Request to Adopt TSTF-580, Revision 1
ML23205A2432023-07-19019 July 2023
NRC Staff Follow-up Question on Audit Question 18 TSTF-505 and 50.69 Regulatory Audit (E-mail Dated 7/19/2023) (EPIDs L-2022-LLA-0185 and L-2022-LLA-0186)
ML23087A2912023-03-28028 March 2023
Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld
ML23061A0522023-03-0202 March 2023
Request for Additional Information (3/2/2023 E-mail) - Proposed Alternative Associated with a Weld Overlay Repair to the Torus
ML23012A2002023-01-13013 January 2023
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000220/2023401 and 05000410/2023401
ML22207A2162022-07-26026 July 2022
Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000220/2022010 and 05000410/2022010
ML22194A9412022-07-13013 July 2022
Request for Additional Information Relief Request CS-PR-02 (7/13/2022 e-mail)
ML22041B5362022-02-10010 February 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541
ML22020A0642022-01-13013 January 2022
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles
ML21320A3472021-11-16016 November 2021
Request for Additional Information LAR to Revise TSs to Adopt TSTF-582, Revision 0
ML21306A3312021-11-0202 November 2021
Request for Additional Information Alternative Request GV-RR-10 (11/2/2021 e-mail)
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21144A2132021-05-24024 May 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21117A0342021-05-0505 May 2021
Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893
ML21125A1282021-05-0404 May 2021
OPC Document Request - Feb 2021
ML21110A5112021-04-20020 April 2021
Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582
ML21088A2682021-03-30030 March 2021
Notification of Conduct of a Fire Protection Team Inspection
ML21062A0652021-03-0101 March 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting
ML21049A2572021-02-18018 February 2021
Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237)
ML20365A0092020-12-30030 December 2020
Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114)
ML20358A2602020-12-28028 December 2020
Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency
ML20272A2802020-09-28028 September 2020
Withdrawal and Replacement of Request for Additional Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times
ML20248H5192020-09-28028 September 2020
Changes to Draft Request for Additional Information Regarding Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times
ML20246G6362020-09-0202 September 2020
Request for Additonal Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times
NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-08-28028 August 2020
Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
ML20239A7982020-08-25025 August 2020
NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2
ML20213A9352020-07-30030 July 2020
Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times
ML20212L8702020-07-30030 July 2020
Request for Additonal Information Review of License Amendment Requests Regarding Riskinformed Categorization and Treatment of Structures, Systems and Components (L-2019-LLA-0290)
ML20153A7042020-06-0101 June 2020
NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26
ML20135H1972020-05-14014 May 2020
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval
ML20045E3582020-02-14014 February 2020
Draft Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates
ML19296A1862019-10-23023 October 2019
Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates (L-2019-LLA-0115)
ML19275H1362019-10-0202 October 2019
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879
ML19179A0612019-07-19019 July 2019
Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879
ML19151A8132019-05-31031 May 2019
Licensed Operator Positive Fitness-For-Duty Test
ML19025A1572019-01-25025 January 2019
Request for Additional Information Regarding Primary Containment Oxygen Concentration License Amendment Request
ML19025A1202019-01-24024 January 2019
NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing
ML18341A2212018-12-0707 December 2018
Request for Additional Information Regarding Emergency Tech Spec Change Re HPCS Completion Time (EPID -L-2018-LLA-0491)
ML18228A6932018-08-15015 August 2018
Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426)
ML18205A3922018-07-24024 July 2018
Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426)
ML18184A2882018-07-0303 July 2018
Request for Additional Information Regarding Removal of Boraflex Credit from Spent Fuel Pool License Amendment Request(L-2018-LLA-0039)
ML18102A2372018-04-12012 April 2018
NRR E-mail Capture - Calvert Cliffs, Ginna, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Schemes (EPID-L-2017-LLA-0237)
ML18067A1482018-03-0808 March 2018
Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation)
ML17331B1342017-12-12012 December 2017
2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding
ML17285B1962017-10-27027 October 2017
Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.
ML17272A0112017-10-10010 October 2017
Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control
ML17234A3592017-08-30030 August 2017
Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702
2024-07-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 9, 2011 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.2 - RE: THE LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE OPERATION (TAC NO. ME1476)
Dear Mr. Belcher:
By letter dated May 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091610103), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for Nine Mile Point, Unit No.2 (NMP2).
The proposed amendment requests an increase in the maximum steady-state power level at NMP2 from 3467 megawatts thermal (MWt) to 3988 MWt. This represents a 15-percent increase over the current licensed thermal power.
Based on its review of the LAR and the supplemental information provided by the NMPNS in letter December 13, 2010 (ADAMS Accession No. ML103500364), the Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on January 27 and February 8, 2011, and it was agreed that your response would be provided within 60 days from the date of this letter.
Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION (RAn FOR LICENSE AMENDMENT REQUEST RE: EXTENDED POWER UPRATE (EPU)
NINE MILE POINT NUCLEAR STATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT NO.2 DOCKET NO. 50~410 By letter dated May 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091610103), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for Nine Mile Point. Unit No.2 (NMP2).
The proposed amendment requests an increase in the maximum steady~state power level at NMP2 from 3467 megawatts thermal (MWt) to 3966 MWt. This represents a 15-percent increase over the current licensed thermal power.
Based on its review of the license amendment request and the supplemental information provided by the NMPNS in letter dated December 13. 2010 (ADAMS Accession No. ML103500364), the Nuclear Regulatory Commission staff has determined that additional information requested below will be needed to support its review.
- 1. In letter dated December 13,2010, the licensee stated that:
All fuel assembly types were analyzed using CASM04 at 4.95% enrichment (including the manufacturing tolerance of +/- 0.05% enrichment which is equivalent to the 5.0% enrichment discussed in NMP2 Updated Safety Analysis Report Section 9.1.2.2).
The above statement appears inadequate to support an enrichment of 5.0%. Analysis at 4.95%
with a +/- 0.05% tolerance would justify an enrichment of 4.95%. By the same reason, the updated safety analysis report also appears inadequate. Clarify this statement.
The various submittals lack clarity of the licensed enrichment limit. The NMP2 power uprate safety analysis report (PUSAR) Table 2.6~10 specifies 5.0%. PUSAR Table 2.6~10 specifies 4.9%. The letter dated December 13. 2010, specifies 4.95%. What is the enrichment limit justified by analysiS? Specify this limit in the Technical Specifications (TSs) in accordance with Title 10 of the Code of Federal Regulations, (10 CFR) Section 50.36.
- 2. In letter dated December 13, 2010, the licensee stated that:
The current GE14 fuel lattice design satisfies the NMP2 new fuel vault storage criteria outlined in Technical Specification (TS) Section 4.3 provided that the peak, in~core eigenvalue of any constituent fuel lattice, as computed by either the GNF lattice physics codes TGBLA04A or TGBLA06A, does not exceed 1.29.
However. the PUSAR lists a peak in-core eigenvalue limit of 1.3392. Clarify this discrepancy and specify this limit in the TSs in accordance with 10 CFR 50.36. In addition, provide the in-Enclosure
-2 rack maximum k-effective for new fuel storage determined by analysis and the supporting analysis.
- 3. On page 3 of Attachment 1 of its response dated December 13, 2010, the licensee states that NMP2 added 10 new Holtec Boral spent fuel storage racks in the NMP2 spent fuel pool as part of the Phase I re-rack via a 10 CFR 50.59 evaluation. Afterward, NMP2 performed the Phase II re-rack, similarly using a 10 CFR 50.59 evaluation in support of the modification, which replaced 16 original Boraflex spent fuel storage racks with Holtec Boral racks. The licensee further stated that the new Boral spent fuel storage racks are incorporated into the criticality analysis that has been submitted in support of NMPZs EPU LAR. It is not clear to the NRC staff how the licensee can ensure that the Boral material will continue to perform its intended function in the future. As such, please discuss how the neutron absorber will be monitored and maintained (e.g. use of surveillance program). If a program is utilized, discuss in detail the approach that will be used in the monitoring program, specifically the methods and techniques utilized (e.g., visual, weight, volumetric, surface inspection, neutron attenuation testing), frequency of inspection, sample size, data collection and acceptance criteria.
- a. Please indicate the installation date for new and replacement Boral storage racks.
- b. Please discuss whether NMP2 utilizes a Boral coupon program for the new and replacement Boral storage racks. If a coupon program is being used, please describe the program. Specifically:
(i) Identify the quantity and location of coupons relative to the spent fuel racks.
(ii) Describe how the coupons are mounted and whether they are fully exposed to the spent fuel pool water.
(iii) Discuss whether any coupons that are removed and inspected using non destructive techniques will be re-inserted in the spent fuel pool for future evaluation.
(iv) Indicate whether the Boral racks in the spent fuel pool are vented or not.
- 4. Please describe how the areal density of the Boral material will be measured (e.g., neutron attenuation) and maintained to prevent an inadvertent criticality. Please include a description of the testing, parameters measured, calculations, and acceptance criteria.
ML103500364), the Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on January 27 and February 8, 2011, and it was agreed that your response would be provided within 60 days from the date of this letter.
Sincerely, Ira!
Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrPMNineMilePoint RidsNrrLASLiUle RidsNrrDorlLpl1-1 LPLI-1 RlF RidsOGCRp RidsRgn 1MailCenter RidsNrrDssSrxb TNakanishi, NRR EWong, NRR AObodoako, NRR RidsNrrDeCsgb RidsNrrAcrsAcnw&mMailCenter ADAMS Accesslon . N0.: ML110400037 *RAI provi'd edb>y memo. No su b t flal h San c anges made.
NRR 088
[OFFICE LPL1-1/PM LPL1-1/LA CSGB/BC SRXB/BC LPL 1-1/BC NAME RGuzman SUttle RTaylor' AUlses' NSalgado DATE 2/9/11 2/9/11 1/20/11 Memo DTD 1/12/11 Memo DTD 219/11
