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Category:Code Relief or Alternative
MONTHYEARML12249A2362012-10-11011 October 2012 Nuclear Generating Plant - Relief Request #11-001-MX Related to Suspension of Concrete Containment Examination for the Fourth-10-Year Interval of the Inservice Inspection Program 3F0912-08, Relief Request 11-001-MX, Revision 0, Commitment to Submit Alternate Surveillance Requirements Per 10 CFR 50.55a(a)(3)(i)2012-09-19019 September 2012 Relief Request #11-001-MX, Revision 0, Commitment to Submit Alternate Surveillance Requirements Per 10 CFR 50.55a(a)(3)(i) 3F0412-08, Relief Request (RR) 12-001-MX Revision 0, Approval to Use ASME Code Case N-791 for Containment Repair2012-04-30030 April 2012 Relief Request (RR) #12-001-MX Revision 0, Approval to Use ASME Code Case N-791 for Containment Repair ML1006400842010-03-19019 March 2010 Relief Requests 09 001 II, 09 002 II, and 09 003 II, Third 10-year Interval Inservice Inspection Program Plan. 3F0309-06, Submittal of Relief Request 09-001-IT, Revision 02009-03-30030 March 2009 Submittal of Relief Request #09-001-IT, Revision 0 ML0908204922009-03-20020 March 2009 Submittal of Third Ten-Year Inservice Inspection Interval Relief Requests #09-001-11, #09-002-11 and #09-003-11 ML0822103922008-09-0909 September 2008 Request for Relief No. 07-001-SS Regarding the Fourth 10-Year Interval Inservice Inspection Visual Examination of the Reactor Vessel Support Skirt ML0812604712008-05-22022 May 2008 Relief Request #08-001-RR, Revision 1, to Install a Weld Overlay on the Dissimilar Metal Weld in the Decay Heat Drop Line 3F0907-05, Relief Request 07-003-RR, Revision 1, and Response to Request for Additional Information2007-09-13013 September 2007 Relief Request #07-003-RR, Revision 1, and Response to Request for Additional Information ML0601302032006-02-0101 February 2006 Relief Request Subsequent Edition Letter and Addenda to Section XI of the ASME Code for Repair/Replacement Activities ML0400604752004-01-0606 January 2004 Ltr Safety Evaluation of Relief Request 03-001-RR and 03-0002-RR Concerning Alternative Repair Method and Flaw Characterization for Pressurizer Instrument Nozzle Penetrations 2012-09-19
[Table view] Category:Letter type:
MONTHYEAR3F0824-01, Independent Spent Fuel Storage Installation Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 52024-08-21021 August 2024 Independent Spent Fuel Storage Installation Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5 3F0824-02, Withdrawal of License Amendment Request to Add License Condition 2.C.21, License Termination Plan, Proposed Change Number 2622024-08-12012 August 2024 Withdrawal of License Amendment Request to Add License Condition 2.C.21, License Termination Plan, Proposed Change Number 262 3F0624-02, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-06-13013 June 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0624-01, Response to Questions from the NRC Environmental Assessment Branchs Review of License Termination Plan During Virtual Meeting Dated May 20, 20242024-06-11011 June 2024 Response to Questions from the NRC Environmental Assessment Branchs Review of License Termination Plan During Virtual Meeting Dated May 20, 2024 3F0524-03, Annual Financial Report and Certified Financial Statement2024-05-30030 May 2024 Annual Financial Report and Certified Financial Statement 3F0524-01, Response to Request for Additional Information for the Environmental Assessment of the License Termination Plan2024-05-0909 May 2024 Response to Request for Additional Information for the Environmental Assessment of the License Termination Plan 3F0424-03, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report 3F0424-02, – 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024 – 2023 Annual Radioactive Effluent Release Report 3F0424-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-04-12012 April 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0224-04, Independent Spent Fuel Storage Installation Security Plan, Security Training and Qualification Plan, and Safeguards Contingency Plan, Revision 42024-02-23023 February 2024 Independent Spent Fuel Storage Installation Security Plan, Security Training and Qualification Plan, and Safeguards Contingency Plan, Revision 4 3F0224-05, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-02-22022 February 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0224-03, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-02-0808 February 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0124-03, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-19019 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0124-01, Response to Request for Additional Information for the Additional Information Assessment of the License Termination Plan for Crystal River, Unit 3 Nuclear Generating Plant (Public Version)2024-01-18018 January 2024 Response to Request for Additional Information for the Additional Information Assessment of the License Termination Plan for Crystal River, Unit 3 Nuclear Generating Plant (Public Version) 3F0623-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-06-0101 June 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0423-03, 2022 Annual Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Annual Radiological Environmental Operating Report 3F0423-02, 2022 Annual Radioactive Effluent Release Report2023-04-18018 April 2023 2022 Annual Radioactive Effluent Release Report 3F0423-01, 2022 Individual Monitoring NRC Form 5 Report2023-04-0404 April 2023 2022 Individual Monitoring NRC Form 5 Report 3F0323-03, Decommissioning Funding Plan for Independent Spent Fuel Storage Installation2023-03-31031 March 2023 Decommissioning Funding Plan for Independent Spent Fuel Storage Installation 3F0323-02, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20222023-03-29029 March 2023 Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2022 3F0323-01, Onsite Property Insurance Coverage2023-03-0202 March 2023 Onsite Property Insurance Coverage 3F0123-01, Proof of Financial Protection2023-01-26026 January 2023 Proof of Financial Protection 3F1222-01, Nuclear Power Station - 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0Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10CFR50.55a March 30, 2009 3F0309-06 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - Relief Request #09-001-IT, Revision 0
Dear Sir:
Pursuant to 10 CFR 50.55a(a)(3)(i), Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., is hereby submitting Relief Request #09-001-IT, Revision 0, to request relief from the Comprehensive Pump Test (CPT) requirements of ASME Operations and Maintenance (OM) Code ISTB-5000. The basis for the relief request is that the proposed alternative would provide an acceptable level of quality and safety.
Table ISTB-3400-1 specifies a biennial frequency for CPT of Group A and Group B pumps.
ISTB-5100 and ISTB-5200 describe the specific requirements for performance of CPT for centrifugal pumps. Performance of the biennial CPT on the identified pumps is unnecessary since the existing Group A quarterly pump tests are performed at sufficient flow rates to adequately monitor for pump degradation (i.e., + 20 percent of the pump's design flow). The attachment to this letter contains the proposed alternative, Relief Request #09-001-IT, Revision 0.
No regulatory commitments are contained within this submittal.
The proposed alternative will be implemented during the Fourth Ten-Year Inservice Testing Inspection Interval, which begins on May 11, 2009. FPC requests the review and approval of this proposal by March 31, 2010.
If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Supervisor, Licensing and Regulatory Programs at (352) 563-4796.
Sn e relg ,
Stephen J. Cahill Manager, Engineering Crystal River Nuclear Plant SJC/dwh
Attachment:
Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) xc: NRR Project Manager Regional Administrator, NRC Region II Senior Resident Inspector Progress Energy Florida, Inc.
Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428 ý
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT PROPROSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(i)
U. S. Nuclear Regulatory Commission Attachment 3F0309-06 Page 1 of 2 10 CFR 50.55a Relief Request Number 09-001 -IT Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
1.0 ASME Code Components Affected
BSP-1A, BSP-1B: Reactor Building Spray Pumps CHP-1A, CHP-1 B: Chilled Water Supply Pumps DCP-1A, DCP-1 B: Decay Heat Closed Cycle Cooling Water Pumps DHP-1A, DHP-1B: Decay Heat Pumps EFP-3: Diesel Driven Emergency Feedwater Pump RWP-2A, RWP-2B: Emergency Duty Nuclear Services Raw Water Pumps RWP-3A, RWP-3B: Decay Heat Raw Water Pumps SFP-1A, SFP-1B: Spent Fuel Coolant Pumps SWP-1A, SWP-1 B: Nuclear Services Closed Cycle Cooling Pumps 2.0 Applicable Code Edition and Addenda American Society of Mechanical Engineers (ASME) Operations and Maintenance (OM)
Code, 2001 Edition through OMb-2003 Addenda 3.0 Applicable Code Requirement Table ISTB-3400 Inservice Test Frequency ISTB-5100 - Centrifugal Pumps (Except Vertical Line Shaft Centrifugal Pumps)
ISTB-5200 - Vertical Line Shaft Centrifugal Pumps 4.0 Reason for Request Pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3), relief is requested from the requirements of ASME OM Code ISTB-5000. The basis for the relief request is that the proposed alternative would provide an acceptable level of quality and safety.
Table ISTB-3400-1 specifies a biennial frequency for Comprehensive Pump Testing (CPT) for Group A and Group B pumps. ISTB-5100 and ISTB-5200 describe the specific requirements for performance of CPT for centrifugal pumps. Performance of the biennial CPT on the pumps identified above is unnecessary since the existing Group A quarterly pump tests are performed at sufficient flow rates to adequately monitor for pump degradation (i.e., +/- 20 percent of the pump's design flow).
The ASME Code Committees have approved Code Case OMN-18, "Alternative Testing Requirements for Pumps Tested Quarterly within +/- 20% of Design Flow," which allows owners to perform a Group A test in lieu of the CPT if the Group A test is conducted at the CPT flow rate using pressure instruments that meet the CPT accuracy requirements (e.g., 0.5 percent of full scale for analog gauges). The basis behind this change is that a
U. S. Nuclear Regulatory Commission Attachment 3F0309-06 Page 2 of 2 quarterly Group A pump test, performed at the CPT flow rate, is far more effective in assessing the pump's operational readiness through trending, than a Group A test in conjunction with a biennial CPT. Additionally, when the Group A test is being performed with instrumentation that meets the CPT requirements, there is little added value in performing a CPT with the more stringent acceptance criterion. This Code Case has not been approved for use in Regulatory Guide 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code, June 2003."
5.0 Proposed Alternative and Basis for Use Crystal River Unit 3 (CR-3) proposes to perform modified Group A quarterly tests in lieu of performing the Code required CPT. The modified Group A test will be run at +/- 20 percent of the pump's design flow rate using 0.5 percent accurate gauges to determine pump differential pressure. CR-3 will utilize an acceptance range of 0.90 to 1.06 on the differential pressure, a range that is more restrictive than the current code case (OMN-18).
Using the provisions of this relief request as an alternative to the specific requirements of ISTB-5123 and ISTB-5223 will provide adequate indication of pump performance and continue to provide an acceptable level of quality and safety. Therefore, pursuant to 10CFR50.55a(a)(3)(i), CR-3 requests relief from the specific ISTB requirements identified in this request.
6.0 Duration of the Proposed Alternative The proposed alternative will be used for the remainder of the Fourth Ten-Year Inservice Testing Inspection Interval for CR-3.
7.0 Precedents The ASME Code committees have approved Code Case OMN-18, which allows for the substitution of quarterly Group A pump testing for the biennial CPT. This precedent also requires slight changes to the quarterly pump testing such as use of 0.5 percent accuracy pressure gauges. CR-3 will be imposing the additional measure of a tighter maximum acceptance criterion of 106 percent for differential pressure to these quarterly test results.
8.0 References
- 1. ASME OM Code, 2001 Edition through OMb-2003 addenda, Subsection ISTB
- 2. Code Case OMN-18, "Alternative Testing Requirements for Pumps Tested Quarterly within +/- 20% of Design Flow"