Letter Sequence Response to RAI |
---|
|
|
MONTHYEARML0831900622008-11-18018 November 2008 Carolina Power and Light Company - Request for Withholding of Proprietary Information from Public Disclosure Project stage: Withholding Request Acceptance HNP-09-007, Supplement to Technical Specifications 5.6.13.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit for Boraflex in BWR Spent Fuel Spent Storage Racks2009-01-16016 January 2009 Supplement to Technical Specifications 5.6.13.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit for Boraflex in BWR Spent Fuel Spent Storage Racks Project stage: Request ML0902100112009-01-27027 January 2009 Acceptance Review Regarding Amendment to Remove Credit for Boraflex in BWR Spent Fuel Pool Storage Racks Project stage: Acceptance Review ML0903603132009-02-0606 February 2009 Acceptance Review Regarding Amendment to Remove Credit for Boraflex in Boiling Water Reactor Spent Fuel Pool Storage Racks Project stage: Acceptance Review ML0912702382009-06-0505 June 2009 Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in BWR Spent Fuel Pool Storage Racks Project stage: RAI HNP-09-081, Response to Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in the Boiling Water Reactor Spent Fuel Pool Storage Racks2009-08-12012 August 2009 Response to Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in the Boiling Water Reactor Spent Fuel Pool Storage Racks Project stage: Response to RAI ML1002508582010-01-18018 January 2010 Holtec Report, No. HI-2043321, Rev. 6, Critically Safety Analyses of BWR Fuel Without Credit for Boraflex in the Racks at the Harris Nuclear Power Station. Project stage: Other HNP-09-087, Second Response to Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in the Boiling Water Reactor Spent Fuel Pool Storage Racks2010-01-18018 January 2010 Second Response to Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in the Boiling Water Reactor Spent Fuel Pool Storage Racks Project stage: Response to RAI ML1007605692010-03-26026 March 2010 Carolina Power and Light Company - Request for Withholding of Proprietary Information from Public Disclosure for the Shearon Harris Nuclear Power Plant, Unit 1 Project stage: Withholding Request Acceptance RS-10-102, ANP-2843Q1NP, Revision 0, LaSalle Unit 2 Nuclear Power Station Spent Fuel Storage Pool Criticality Safety Analysis with Neutron Absorbing Inserts and Without Boraflex - Rais.2010-06-30030 June 2010 ANP-2843Q1NP, Revision 0, LaSalle Unit 2 Nuclear Power Station Spent Fuel Storage Pool Criticality Safety Analysis with Neutron Absorbing Inserts and Without Boraflex - Rais. Project stage: Request ML1019402522010-07-20020 July 2010 Second Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in Boiling-Water Reactor Spent Fuel Pool Storage Racks Project stage: RAI ML1023707682010-08-16016 August 2010 Response to Second Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in Boiling Water Reactor Spent Fuel Pool Storage Racks Project stage: Request HNP-10-110, Withdrawal of BWR Boraflex License Amendment Request2010-09-28028 September 2010 Withdrawal of BWR Boraflex License Amendment Request Project stage: Withdrawal ML1027303492010-09-30030 September 2010 Federal Register Notice - Notice of Withdrawal Project stage: Other ML1026700042010-09-30030 September 2010 Withdrawal of an Amendment Request to Remove Credit for Boraflex in the BWR Spent Fuel Pool Storage Racks Project stage: Withdrawal NRC-2010-0319, Federal Register Notice - Notice of Withdrawal2010-09-30030 September 2010 Federal Register Notice - Notice of Withdrawal Project stage: Other NRC-2010-0286, Withdrawal of an Amendment Request to Remove Credit for Boraflex in the BWR Spent Fuel Pool Storage Racks2010-09-30030 September 2010 Withdrawal of an Amendment Request to Remove Credit for Boraflex in the BWR Spent Fuel Pool Storage Racks Project stage: Withdrawal 2010-01-18
[Table View] |
|
---|
Category:Letter type:HNP
MONTHYEARHNP-18-050, Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date2018-09-17017 September 2018 Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme HNP-18-035, Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval2018-06-0404 June 2018 Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval HNP-18-049, Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 192018-05-0303 May 2018 Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 19 HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2018-05-0202 May 2018 Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes HNP-18-042, Annual Environmental (Non-radiological) Operating Report2018-04-30030 April 2018 Annual Environmental (Non-radiological) Operating Report HNP-18-032, Annual Radiological Environmental Operating Report2018-04-25025 April 2018 Annual Radiological Environmental Operating Report HNP-18-031, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report HNP-18-047, Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation2018-04-20020 April 2018 Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval2018-04-18018 April 2018 Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval HNP-18-044, Cycle 22 Core Operating Limits Report, Revision O2018-04-16016 April 2018 Cycle 22 Core Operating Limits Report, Revision O HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-18-021, Annual Report in Accordance with Technical Specification 6.9.1.22018-02-19019 February 2018 Annual Report in Accordance with Technical Specification 6.9.1.2 HNP-18-020, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-02-16016 February 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-019, Cycle 21 Core Operating Limits Report, Revision 12018-02-14014 February 2018 Cycle 21 Core Operating Limits Report, Revision 1 HNP-18-017, CFR 50.54(q) Evaluations2018-02-0505 February 2018 CFR 50.54(q) Evaluations HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-02-0101 February 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. HNP-18-002, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2018-01-22022 January 2018 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-18-003, Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-01-18018 January 2018 Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-007, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations2018-01-11011 January 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations HNP-18-006, Submittal of 14-Day Special Report for Accident Radiation Monitors2018-01-0404 January 2018 Submittal of 14-Day Special Report for Accident Radiation Monitors HNP-17-093, Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 32017-11-29029 November 2017 Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3 HNP-17-078, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-11-27027 November 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-082, Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In..2017-10-30030 October 2017 Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In.. HNP-17-084, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-10-30030 October 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-025, Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan2017-10-23023 October 2017 Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan HNP-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-10-19019 October 2017 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis HNP-17-077, License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications2017-10-10010 October 2017 License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications HNP-17-076, Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements.2017-10-0202 October 2017 Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements. HNP-17-073, Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-09-14014 September 2017 Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-062, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-09-13013 September 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal HNP-17-061, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-07-20020 July 2017 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-008, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-06-28028 June 2017 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-003, License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection2017-06-0505 June 2017 License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection HNP-17-040, Snubber Program Plan2017-06-0101 June 2017 Snubber Program Plan HNP-17-051, 10 CFR 50.54(q) Evaluation2017-05-24024 May 2017 10 CFR 50.54(q) Evaluation HNP-17-050, Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center2017-05-24024 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du HNP-17-033, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112017-05-22022 May 2017 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 HNP-17-049, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations. HNP-17-047, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-048, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations. HNP-17-046, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-024, Annual Environmental (Nonradiological) Operating Report2017-04-28028 April 2017 Annual Environmental (Nonradiological) Operating Report HNP-17-023, Annual Radioactive Effluent Release Report2017-04-28028 April 2017 Annual Radioactive Effluent Release Report HNP-17-034, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106..2017-04-25025 April 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106.. HNP-17-035, Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator2017-04-12012 April 2017 Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator HNP-17-045, 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation2017-03-30030 March 2017 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation HNP-17-014, Annual Report in Accordance with Technical Specifications, Section 6.9.1.22017-02-16016 February 2017 Annual Report in Accordance with Technical Specifications, Section 6.9.1.2 HNP-17-015, Summary of 10 CFR 50.54(q) Evaluation2017-02-15015 February 2017 Summary of 10 CFR 50.54(q) Evaluation 2018-09-17
[Table view] |
Text
C Progress Energy Christopher L.Burton Vice President Harris Nuclear Plant Progress Energy Carolinas, Inc.
Serial: HNP-09-081 AUG 12 2M09 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT TO REMOVE CREDIT FOR BORAFLEX IN THE BOILING WATER REACTOR SPENT FUEL POOL STORAGE RACKS (TAC NO. ME0012)
References:
- 1. Letter from C. L. Burton to the Nuclear Regulatory Commission (Serial:
HNP-08-075), "Technical Specifications 5.6.1.3.a and 5.6.1.3.b -
Incorporation of Updated Criticality Analyses to Reflect Removal of Credit For Boraflex in BWR Spent Fuel Pool Storage Racks," dated September 29, 2008 (ML082800400)
- 2. Letter from C. L. Burton to the Nuclear Regulatory Commission (Serial:
HNP-09-007), "Supplement to Technical Specifications 5.6.1.3.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit For Boraflex in BWR Spent Fuel Pool Storage Racks," dated January 16, 2009 (ML090230341)
- 3. Letter from M. Vaaler, Nuclear Regulatory Commission, to C. L. Burton, "Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in the Boiling Water Reactor Spent Fuel Pool Storage Racks (TAC NO.
ME0012)," dated June 5, 2009 (ML091270238)
Ladies and Gentlemen:
On June 5, 2009, the Harris Nuclear Plant (HNP) received a request from the NRC (Reference 3) for additional information needed to facilitate the review of the License Amendment Request to revise HNP Technical Specifications to incorporate an updated criticality analyses reflecting the removal of credit for Boraflex in BWR spent fuel pool storage racks. This original request was submitted as HNP-08-075 (Reference 1) and supplemented via HNP-09-007 (Reference 2).
P.O.
Box 165 pýi New Hill, NC 27562 01(z<
T> 919.362.2502 F> 919.362.2095
Serial: HNP-09-081 Page 2 Per discussions with Marlayna Vaaler, NRC Project Manager for HNP, HNP's responses to these questions will be provided in two parts. Submittal to the NRC of the requested additional information needed for question 8 is to be provided by August 12, 2009, and submittal of the remaining responses will be provided in September 2009. Accordingly, the Enclosure to this letter provides the requested additional information for question 8.
This document contains no regulatory commitments.
Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor -
Licensing/Regulatory Programs, at (919) 362-3137.
I declare under penalty of perjury that the foregoing is true and correct. Executed on AUG 12 7!909 Sincerely, Christopher L. Burton Vice President Harris Nuclear Plant CLB/kms Enclosure cc:
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Ms. B. 0. Hall, N.C. DENR Section Chief Mr. L. A. Reyes, NRC Regional Administrator, Region II Ms. M. G. Vaaler, NRC Project Manager, HNP
Enclosure to SERIAL: HNP-09-081 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT TO REMOVE CREDIT FOR BORAFLEX IN BWR SPENT FUEL POOL STORAGE RACKS Summary Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc.,
(PEC) (licensee) submitted a license amendment request to modify Harris Nuclear Plant's (HNP)
Technical Specification (TS) Sections 5.6.1.3.a and 5.6.1.3.b to incorporate the results of a new criticality analysis. Specifically, the TSs would be revised to add new requirements for the Boiling Water Reactor (BWR) spent fuel storage racks containing Boraflex in Spent Fuel Pools A and B. The requirements for the BWR spent fuel racks as currently contained in TS 5.6.1.3 would be revised to specify applicability to the spent BWR spent fuel storage racks containing Boraflex in Spent Fuel Pools A and B. The requirements for the BWR spent fuel racks as currently contained in TS 5.6.1.3 would be revised to specify applicability to the spent fuel storage racks containing Boral in Spent Fuel Pool B.
The U.S. Nuclear Regulatory Commission staff determined that it needed additional information in order to complete its review.
- 8. Since the Boraflex monitoringprogramwill be discontinuedas a result of this proposed license amendment request,please explain how HNP will be able to identify and mitigate any degradationof the Boraflex that may impede other plant operations. Examples may include excessive silica levels impacting the spentfuel pool chemistry or an unforeseen damage mechanism to the Boraflex cladding that may impact safe fuel handling.
Response
After the Boraflex monitoring program is discontinued, several other methods that currently allow HNP to monitor Boraflex degradation via silica sampling for indications that could result in the potential to impede other plant operations will remain in place. HNP's sampling program is contained in CRC-001, HNP Environmental and Chemistry Sampling and Analysis Program.
The basis for primary and secondary system chemistry control at HNP is the System Chemistry Strategic Plan (PLP-715), which details the chemistry plans that meet the guidelines of NEI 97-06, Steam Generator Program Guidelines, NEI 03-08, Guidelines for the Management of Materials Issues, and the EPRI Chemistry Guidelines. In accordance with this guidance, HNP currently monitors the amounts of silica, an indicator of degraded Boraflex, in various systems as follows:
- Spent Fuel Pools: Sampled on a monthly basis as part of the HNP Environmental and Chemistry Sampling and Analysis Program (CRC-001)
Enclosure to SERIAL: HNP-09-081 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT TO REMOVE CREDIT FOR BORAFLEX IN BWR SPENT FUEL POOL STORAGE RACKS Guidelines Table 3-4 for reactor critical reactor coolant system power operation diagnostic parameters (PLP-715)
Reactor Make-up source water: Sampled quarterly with a focus on those hardness elements which may impact fuel performance in accordance with EPRI PWR Primary Chemistry Guidelines Table 3-5 for all modes diagnostic parameters (PLP-715) 8a. (via email)
In the HNP license renewal application, the licensee included an Aging Management Program (AMP) element regardinga Boraflex MonitoringProgram. Does HNP still intend to implement this program in light of the proposedchange?
Response
No, the Aging Management Program element regarding the Boraflex Monitoring Program as contained in the HNP license renewal application will also be removed once the current Boraflex Monitoring Program is discontinued. As discussed in question 8 response (above) there are other monitoring programs currently in place at HNP to detect excessive silica levels which could have a potential to impede other plant operations. These will remain in place after the current Boraflex Monitoring Program is discontinued.
Page 2 of 2