NRC 2013-0080, License Amendment Request 252 Technical Specification 5.6.5. Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) Response to Request for Additional Information
| ML13256A064 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/12/2013 |
| From: | Meyer L Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2013-0080 | |
| Download: ML13256A064 (6) | |
Text
September 12, 2013 NEXT era**
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POINT BEACH NRC 2013-0080 10 CFR 54 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS)
Pressure and Temperature Limits Report (PTLR)
Response to Request for Additional Information
References:
(1)
(2)
(3)
NextEra Energy Point Beach, LLC letter to NRC, dated January 15, 2013, License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
NextEra Energy Point Beach, LLC letter to NRC, dated March 1, 2013, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (ML13063A292)
NRC electronic mail to NextEra Energy Point Beach, LLC, dated July 11, 2013, Point Beach Nuclear Plant, Units 1 and 2-Draft Requests for Additional Information (EVIB) Supporting Review of LAR to Implement New PTLR (TAC Nos. MF0532 and MF0533)
Pursuant to 10 CFR 50.90, NextEra Energy Point Beach, LLC (NextEra) requested to amend renewed Facility Operating Licenses DPR-24 and DPR-27 for Point Beach Nuclear Plant (PBNP), Units 1 and 2, respectively (Reference 1 ). The proposed amendments would revise the PBNP Technical Specifications (TS) to allow the use of two new methodologies; Framatome ANP Topical Report BAW-2308, Revisions 1-A and 2-A, "Initial RT NDT of Linde 80 Weld Materials," and Westinghouse Owners Group (WOG) WCAP-14040-A, Revision 4, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves." The revision would add BAW-2308, Revisions 1-A and 2-A and WCAP-14040-A, Revision 4, as approved methodologies toTS 5.6.5, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)," for determining RCS pressure-temperature (PT) limits. This request was supplemented with additional information in Reference (2).
NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
Document Control Desk Page 2 Via Reference (3), the NRC determined additional information was required to enable the staff's continued review of this license amendment request. Enclosure 1 contains the NextEra response to the NRC staff's request for additional information.
Summary of Regulatory Commitments:
This letter contains the following new commitments and no changes to existing commitments.
NextEra Energy Point Beach, LLC will contract with Westinghouse to provide support in responding to NRC Requests for Additional Information (RAis) #3 and #4. This information will be provided to the NRC within 45 days of receipt from Westinghouse.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on September 12, 2013.
Very truly yours, NextEra Energy Point Beach, LLC
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arr ~
S1 e Vice President Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST 252 TECHNICAL SPECIFICATION 5.6.5, REACTOR COOLANT SYSTEM (RCS)
PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION The NRC staff determined that additional information was required (Reference 1) to enable the continued review of the Point Beach Nuclear Plant (PBNP) License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (References 2 and 3). The following information is provided by NextEra Energy Point Beach, LLC (NextEra) in response to the NRC staff's request.
The submittal and supplemental/etters contain several sets of f/uence values.
Please confirm that the fluence values used in the PTLR were those generated as part of the 2009 extended power uprate effort.
NextEra Response The fluence values for each beltline material used in the PTLR contained in WCAP-16669-NP, Point Beach Units 1 and 2 Heatup and Cooldown Limit Curves for Normal Operation, Revision 1, January 2009, (Reference 4) were compared to corresponding maximum neutron fluence for extended power uprate submitted in license amendment request (LAR) 262, Extended Power Uprate (EPU), (Reference 5) at 50 EFPY as shown in the table below.
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Comparison of Projected Fluence for Point Beach Nuclear Plant Units 1 and 2 ID Fluence (x10 1
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ID Fluence (x10 1
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Component Description Heat or Heat/Lot WCAP-16669-NP (1l LAR 261 (2l 53 EFPY 50 EFPY Unit 1 Nozzle Belt Forging 122P237 0.36 0.36 Intermediate Shell Plate A9811-1 4.90 4.79 Lower Shell Plate C1423-1 4.55 4.35 Nozzle Belt to lntermed.
8T1762 (SA-1426) 0.36 0.36 Shell Circ Weld (100%)
Intermediate Shell Long 1P0815 (SA-812) 3.19 3.13 Seam (ID 27%)
Intermediate Shell Long 1 P0661 (SA-775) 3.19 3.13 Seam (OD 73%)
lntermed. to Lower Shell 71249 (SA-1101) 4.43 4.25 Circ. Weld (100%)
Lower Shell Long Seam 61782 (SA-84 7) 3.05 2.94 (100%)
Unit 2 Nozzle Belt Forging 123V352 0.50 0.49 Intermediate Shell 123V500 5.05 4.76 For~ in~
Lower Shell Forging 122W195 4.90 4.57 Nozzle Belt to lntermed.
21935 0.50 0.49 Shell Circ Weld (100%)
lntermed. to Lower Shell 72442 (SA-1484) 4.65 4.34 Circ. Weld (100%)
(1) WCAP-16669-NP, Table 4-3 (2) LAR 261, Tables 2.1.1-1 and 2.1.1-2 As illustrated in the table above, the projected extended power uprate fluence values for the beltline materials are less than the fluence values used to generate the proposed PTLR curves. Thus, the PTLR curves remain conservative and valid through a 50 EFPY period of applicability for extended power uprate.
The PTLR curves provided in Enclosure 2 to the April 18, 2013, letter are titled "... applicable to 53 EFPY [effective full-power years]...," and elsewhere in the submittal it is stated that these curves are applicable to 50 EFPY by current reckoning.
Please confirm that these labels will be accurately updated if/when placed into use.
NextEra Response The labels will be accurately updated when placed into use.
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Please provide essential parameters such as thermal diffusivity for the NRC staff to validate the difference between the RPV coolant temperature and the RPV metal temperature.
Additionally clarify how RPV metal temperature at the crack tip was derived.
NextEra Response Essential parameters such as thermal diffusivity are contained in a Westinghouse Proprietary document. These essential parameters will be provided in a non-proprietary summary with the response to RAI 4. Also, the method used to derive the RPV metal temperature at the crack tip will be provided. This information is expected to be available by December 15, 2013. This information will be provided to the NRC within 45 days of receipt from Westinghouse.
The regulations in 10 CFR Part 50, Appendix G, Paragraph IV. A state that, "the pressure-retaining components of the reactor coolant pressure boundary [RCPB] that are made of ferritic materials must meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code [ASME Code, Section Ill], supplemented by the additional requirements set forth in [paragraph IV.A.2, "Pressure-Temperature (P-T) Limits and Minimum Temperature Requirements'}... " Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the ferritic materials in the reactor vessel (RV) beltline (neutron fluence ~1 x 1017 nlcm2, E > 1 MeV), as well as ferritic materials not in the RV beltline (neutron f/uence < 1 x 1017 nlcm2, E > 1 MeV). Further, 10 CFR Part 50, Appendix G requires that all RCPB components must meet the ASME Code, Section Ill requirements. The relevant ASME Code, Section Ill requirement that will affect the P-T limits is the lowest service temperature requirement for all RCPB components specified in Section Ill, NB-2332(b).
The P-T limit calculations for ferritic RCPB components that are not RV beltline shell materials may define P-T curves that are more limiting than those calculated for the RV beltline shell materials due to the following factors:
- 1. RV nozzles, penetrations, and other discontinuities have complex geometries that may exhibit significantly higher stresses than those for the RV beltline shell region. These higher stresses can potentially result in more restrictive P-T limits, even if the reference temperature (RT NoT) for these components is not as high as that of RV beltline shell materials that have simpler geometries.
- 2. Ferritic RCPB components that are not part of the RV may have initial RTNoT values, which may define a more restrictive lowest operating temperature in the P-T limits than those for the RV beltline shell materials.
Consequently, please describe how the P-T limit curves submitted for PBNP units and the methodology used to develop these curves, considered all RV materials (beltline and non-beltline) and the lowest service temperature of all ferritic RCPB materials, consistent with the requirements of 10 CFR Part 50, Appendix G.
Your description should include the following:
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Confirm availability of material data (initial RTNor and copper and nickel contents) for all non-beltline terrific materials for all PBNP RPVs and demonstrate that none of them will become limiting under the 50 EFPY f/uence.
Confirm that the lowest service temperatures (LSTs) for all terrific RCPB components that are not part of the RV have been established for both Point Beach units, and the lowest temperature of 60 oF in the proposed P-T limits are higher than these LSTs.
NextEra Response NextEra will contract with Westinghouse to supply the requested information describing how the P-T limit curves submitted for PBNP units and the methodology used to develop these curves, considered all RV materials (beltline and non-beltline) and the lowest service temperature of all ferritic RCPB materials, consistent with the requirements of 10 CFR Part 50, Appendix G. This information is expected to be available by December 15, 2013. This information will be provided to the NRC within 45 days of receipt from Westinghouse.
References
- 1. NRC electronic mail to NextEra Energy Point Beach, LLC, dated July 11, 2013, Point Beach Nuclear Plant, Units 1 and 2-Draft Requests for Additional Information (EVIB) Supporting Review of LAR to Implement New PTLR (TAC Nos. MF0532 and MF0533)
- 2. NextEra Energy Point Beach, LLC letter to NRC, dated January 15, 2013, License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (ML13016A028)
- 3. NextEra Energy Point Beach, LLC letter to NRC, dated March 1, 2013, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (ML13063A292)
- 4. WCAP-16669-NP, "Point Beach Unit 1 and 2 Heatup and Cooldown Limit Curves for Normal Operation", dated December 2006
- 5. FPL Energy Point Beach Nuclear Plant letter to NRC, dated April 7, 2009, License Amendment Request 261 Extended Power Uprate (ML091250564)
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