|
|
(One intermediate revision by the same user not shown) |
Line 3: |
Line 3: |
| | issue date = 01/02/2008 | | | issue date = 01/02/2008 |
| | title = 60-Day Response to NRC Order EA-03-009, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors | | | title = 60-Day Response to NRC Order EA-03-009, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors |
| | author name = Corlett D H | | | author name = Corlett D |
| | author affiliation = Progress Energy Carolinas, Inc | | | author affiliation = Progress Energy Carolinas, Inc |
| | addressee name = | | | addressee name = |
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:Progress Energy Serial: HNP-07-160 10 CFR 2.202 U.S. Nuclear Regulatory Commission ATTENTION: | | {{#Wiki_filter:Progress Energy Serial: HNP-07-160 10 CFR 2.202 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63' 60-DAY RESPONSE TO NRC ORDER EA-03-009, "ISSUANCE OF FIRST REVISED NRC ORDER (EA-03-009) ESTABLISHING INTERIM INSPECTION REQUIREMENTS FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS" Ladies and Gentlemen: |
| Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63'60-DAY RESPONSE TO NRC ORDER EA-03-009, "ISSUANCE OF FIRST REVISED NRC ORDER (EA-03-009) | | On February 11, 2003, the NRC issued Order EA-03-009 for interim inspection requirements for reactor pressure vessel (RPV) heads at pressurized water reactor facilities. On February 20, 2004, the NRC issued the First Revised Order EA-03-009, which superseded Order EA-03-009. The revised Order requires that the Licensee submit a report detailing the inspection results within sixty (60) days after each refueling outage. On October 23, 2007, Harris Nuclear Plant (HNP) of Carolina Power and Light Company (CP&L) doing business as Progress Energy Carolinas, Inc., completed Refueling Outage 14 (RFO-14). provides the required examination results for RFO-14. In summary, the inspections revealed no evidence of recent boric acid leakage. |
| ESTABLISHING INTERIM INSPECTION REQUIREMENTS FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS" Ladies and Gentlemen: | | This document contains no new Regulatory Commitment. |
| On February 11, 2003, the NRC issued Order EA-03-009 for interim inspection requirements for reactor pressure vessel (RPV) heads at pressurized water reactor facilities. | | Please refer any question regarding this letter to me at (919) 362-3137. |
| On February 20, 2004, the NRC issued the First Revised Order EA-03-009, which superseded Order EA-03-009. The revised Order requires that the Licensee submit a report detailing the inspection results within sixty (60) days after each refueling outage. On October 23, 2007, Harris Nuclear Plant (HNP) of Carolina Power and Light Company (CP&L) doing business as Progress Energy Carolinas, Inc., completed Refueling Outage 14 (RFO-14).Attachment 1 provides the required examination results for RFO-14. In summary, the inspections revealed no evidence of recent boric acid leakage.This document contains no new Regulatory Commitment. | | Sincerely, Dave Corlett Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant DHC/kms |
| Please refer any question regarding this letter to me at (919) 362-3137.Sincerely, Dave Corlett Supervisor | |
| -Licensing/Regulatory Programs Harris Nuclear Plant DHC/kms | |
|
| |
|
| ==Attachment:== | | ==Attachment:== |
| | 60-Day Response Summarizing Inspection Results for RFO-14 Progress Energy Carolinas, Inc. |
| | Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 |
|
| |
|
| 60-Day Response Summarizing Inspection Results for RFO-14 Progress Energy Carolinas, Inc.Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 I-NP-07-160 Page 2 cc: Mr. P. B. O'Bryan, NRC Sr. Resident Inspector Ms. B. 0. Hall, N.C. DENR Section Chief Mr. V. M. McCree, NRC Acting Regional Administrator Ms. M. G. Vaaler, NRC Project Manager Attachment to SERIAL: HINP-07-160 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 60-DAY RESPONSE DETAILING RPV HEAD INSPECTION RESULTS FOR RFO-14 During the recently completed Refueling Outage 14 (RFO-14) from September 29, 2007, through October 23, 2007, Harris Nuclear Plant (HNP) performed Reactor Pressure Vessel (PRV) head inspections in accordance with the First Revised NRC Order (EA-03-009) dated February 20, 2004. As required by Section IV.E of the Order, HNP details the following results of the inspections required by Sections IV.C and IV.D of the Order.IV.A Susceptibility Category The Harris Plant is in the category of plants considered to be of low susceptibility to Primary Water Stress Corrosion Cracking (PWSCC) based on calculations performed in accordance with Section IV.A of the Order, as well as on the absence of previous inspection findings indicating the presence of leakage.IV.C.(5)(a)
| | I-NP-07-160 Page 2 cc: Mr. P. B. O'Bryan, NRC Sr. Resident Inspector Ms. B. 0. Hall, N.C. DENR Section Chief Mr. V. M. McCree, NRC Acting Regional Administrator Ms. M. G. Vaaler, NRC Project Manager |
| Bare Metal Visual The First Revised NRC Order requires that a 100% Bare Metal Visual (BMV) Examination of the RPV head surface (including 3600 around each RPV head penetration nozzle) be completed at least every third refueling outage or every 5 years, whichever occurs first. When HNP performed this inspection during RFO-1 1 (April 26, 2003, through May 18, 2003), no evidence of recent boric acid leakage or RPV head degradation was found, as reported to the NRC on July 16, 2003 (Serial: HNP-03-070). | | |
| In accordance with the First Revised Order, this BMV examination was again performed during the recently completed RFO-14 (September 29, 2007, through October 23, 2007). The inspection included a BMV inspection of 100% of the upper RV head surface and 360' around each penetration, with video and digital pictures capturing areas examined via rover. No evidence of boric acid residue was found.IV.C.(5)(b) | | Attachment to SERIAL: HINP-07-160 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 60-DAY RESPONSE DETAILING RPV HEAD INSPECTION RESULTS FOR RFO-14 During the recently completed Refueling Outage 14 (RFO-14) from September 29, 2007, through October 23, 2007, Harris Nuclear Plant (HNP) performed Reactor Pressure Vessel (PRV) head inspections in accordance with the First Revised NRC Order (EA-03-009) dated February 20, 2004. As required by Section IV.E of the Order, HNP details the following results of the inspections required by Sections IV.C and IV.D of the Order. |
| Nonvisual Nondestructive Examination (NDE)The First Revised Order requires a nonvisual NDE be performed for each penetration at least once prior to February 11, 2608, and thereafter, at least every 4 refueling outages or every 7 years, whichever occurs first. HNP satisfactorily performed the required nonvisual examinations during RFO-13 (April 8, 2006, through May 16, 2006) as reported to the NRC on July 14, 2006 (Serial: HNP-06-080). | | IV.A Susceptibility Category The Harris Plant is in the category of plants considered to be of low susceptibility to Primary Water Stress Corrosion Cracking (PWSCC) based on calculations performed in accordance with Section IV.A of the Order, as well as on the absence of previous inspection findings indicating the presence of leakage. |
| Since no evidence of PWSCC was identified during that inspection, a nonvisual NDE for each penetration was not required to be performed during RFO-14.IV.D Visual Inspection No evidence of leakage was identified by these inspections and no boric acid deposits were found.Summary In accordance with Section IV.E of the First Revised NRC Order (EA-03-009), HNP submits this letter documenting the results of the required inspections of Sections IV.C and IV.D of the Order. All inspections were performed as required, with no evidence of recent boric acid leakage detected.}} | | IV.C.(5)(a) Bare Metal Visual The First Revised NRC Order requires that a 100% Bare Metal Visual (BMV) Examination of the RPV head surface (including 3600 around each RPV head penetration nozzle) be completed at least every third refueling outage or every 5 years, whichever occurs first. When HNP performed this inspection during RFO-1 1 (April 26, 2003, through May 18, 2003), no evidence of recent boric acid leakage or RPV head degradation was found, as reported to the NRC on July 16, 2003 (Serial: HNP-03-070). |
| | In accordance with the First Revised Order, this BMV examination was again performed during the recently completed RFO-14 (September 29, 2007, through October 23, 2007). The inspection included a BMV inspection of 100% of the upper RV head surface and 360' around each penetration, with video and digital pictures capturing areas examined via rover. No evidence of boric acid residue was found. |
| | IV.C.(5)(b) Nonvisual Nondestructive Examination (NDE) |
| | The First Revised Order requires a nonvisual NDE be performed for each penetration at least once prior to February 11, 2608, and thereafter, at least every 4 refueling outages or every 7 years, whichever occurs first. HNP satisfactorily performed the required nonvisual examinations during RFO-13 (April 8, 2006, through May 16, 2006) as reported to the NRC on July 14, 2006 (Serial: HNP-06-080). Since no evidence of PWSCC was identified during that inspection, a nonvisual NDE for each penetration was not required to be performed during RFO-14. |
| | IV.D Visual Inspection No evidence of leakage was identified by these inspections and no boric acid deposits were found. |
| | Summary In accordance with Section IV.E of the First Revised NRC Order (EA-03-009), HNP submits this letter documenting the results of the required inspections of Sections IV.C and IV.D of the Order. All inspections were performed as required, with no evidence of recent boric acid leakage detected.}} |
|
---|
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
Progress Energy Serial: HNP-07-160 10 CFR 2.202 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63' 60-DAY RESPONSE TO NRC ORDER EA-03-009, "ISSUANCE OF FIRST REVISED NRC ORDER (EA-03-009) ESTABLISHING INTERIM INSPECTION REQUIREMENTS FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS" Ladies and Gentlemen:
On February 11, 2003, the NRC issued Order EA-03-009 for interim inspection requirements for reactor pressure vessel (RPV) heads at pressurized water reactor facilities. On February 20, 2004, the NRC issued the First Revised Order EA-03-009, which superseded Order EA-03-009. The revised Order requires that the Licensee submit a report detailing the inspection results within sixty (60) days after each refueling outage. On October 23, 2007, Harris Nuclear Plant (HNP) of Carolina Power and Light Company (CP&L) doing business as Progress Energy Carolinas, Inc., completed Refueling Outage 14 (RFO-14). provides the required examination results for RFO-14. In summary, the inspections revealed no evidence of recent boric acid leakage.
This document contains no new Regulatory Commitment.
Please refer any question regarding this letter to me at (919) 362-3137.
Sincerely, Dave Corlett Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant DHC/kms
Attachment:
60-Day Response Summarizing Inspection Results for RFO-14 Progress Energy Carolinas, Inc.
Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562
I-NP-07-160 Page 2 cc: Mr. P. B. O'Bryan, NRC Sr. Resident Inspector Ms. B. 0. Hall, N.C. DENR Section Chief Mr. V. M. McCree, NRC Acting Regional Administrator Ms. M. G. Vaaler, NRC Project Manager
Attachment to SERIAL: HINP-07-160 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 60-DAY RESPONSE DETAILING RPV HEAD INSPECTION RESULTS FOR RFO-14 During the recently completed Refueling Outage 14 (RFO-14) from September 29, 2007, through October 23, 2007, Harris Nuclear Plant (HNP) performed Reactor Pressure Vessel (PRV) head inspections in accordance with the First Revised NRC Order (EA-03-009) dated February 20, 2004. As required by Section IV.E of the Order, HNP details the following results of the inspections required by Sections IV.C and IV.D of the Order.
IV.A Susceptibility Category The Harris Plant is in the category of plants considered to be of low susceptibility to Primary Water Stress Corrosion Cracking (PWSCC) based on calculations performed in accordance with Section IV.A of the Order, as well as on the absence of previous inspection findings indicating the presence of leakage.
IV.C.(5)(a) Bare Metal Visual The First Revised NRC Order requires that a 100% Bare Metal Visual (BMV) Examination of the RPV head surface (including 3600 around each RPV head penetration nozzle) be completed at least every third refueling outage or every 5 years, whichever occurs first. When HNP performed this inspection during RFO-1 1 (April 26, 2003, through May 18, 2003), no evidence of recent boric acid leakage or RPV head degradation was found, as reported to the NRC on July 16, 2003 (Serial: HNP-03-070).
In accordance with the First Revised Order, this BMV examination was again performed during the recently completed RFO-14 (September 29, 2007, through October 23, 2007). The inspection included a BMV inspection of 100% of the upper RV head surface and 360' around each penetration, with video and digital pictures capturing areas examined via rover. No evidence of boric acid residue was found.
IV.C.(5)(b) Nonvisual Nondestructive Examination (NDE)
The First Revised Order requires a nonvisual NDE be performed for each penetration at least once prior to February 11, 2608, and thereafter, at least every 4 refueling outages or every 7 years, whichever occurs first. HNP satisfactorily performed the required nonvisual examinations during RFO-13 (April 8, 2006, through May 16, 2006) as reported to the NRC on July 14, 2006 (Serial: HNP-06-080). Since no evidence of PWSCC was identified during that inspection, a nonvisual NDE for each penetration was not required to be performed during RFO-14.
IV.D Visual Inspection No evidence of leakage was identified by these inspections and no boric acid deposits were found.
Summary In accordance with Section IV.E of the First Revised NRC Order (EA-03-009), HNP submits this letter documenting the results of the required inspections of Sections IV.C and IV.D of the Order. All inspections were performed as required, with no evidence of recent boric acid leakage detected.