L-2013-278, RAI Reply for the Application for the Technical Specification Change and Exemption Request Regarding the Use of M5 Alloy Fuel Cladding in Core Reload Applications

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RAI Reply for the Application for the Technical Specification Change and Exemption Request Regarding the Use of M5 Alloy Fuel Cladding in Core Reload Applications
ML13283A002
Person / Time
Site: Saint Lucie 
Issue date: 09/30/2013
From: Jensen J
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2013-278
Download: ML13283A002 (3)


Text

September 30, 2013 L-2013-278 10 CFR 50.90 FP.6iclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re:

St. Lucie Unit I Docket No. 50-335 RAI Reply for the Application for the Technical Specification Change and Exemption Request Regarding the Use of M5 Alloy Fuel Cladding in Core Reload Applications

Reference:

1.

FPL Letter L-2013-139 dated May 10, 2013, "Application for Technical Specification Change and Exemption Request Regarding the Use of M5 Alloy Fuel Cladding in Core Reload Applications" Accession Number ML13135A008.

2. NRC Letter from Siva Lingam, NRC, to Mano Nazar, FPL, dated September 19, 2013, "St. Lucie Plant, Unit 1 - Request for Additional Information Regarding Use of M5 Fuel Cladding License Amendment Request and Exemption Request (TAC NOS. MF1817 AND MF 1820)" Accession Number ML13259A051 In Reference 1, Pursuant to 10 CFR 50.90 and 50.12, Florida Power & Light Company (FPL) requested to amend Facility Operating License DPR-67 and ask for exemption from the regulation for St. Lucie Unit 1 to allow the use of M5 fuel rod cladding material at St. Lucie Unit 1. In Reference 2, the NRC Staff requested additional information in order to complete their review. The Enclosure to this letter provides FPL's response to the information request.

The original no significant hazards evaluation bounds this supplemental submittal.

Please contact Mr. Eric Katzman, Licensing Manager at 772-467-7734 if there are any questions about this submittal.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on September 3)0

, 2013.

Sincerely, ensen Site Vice President St. Lucie Plant

Enclosure:

Reply to Request for Additional Information - License Amendment Request and 10 CFR 50.46 and 10 CFR 50 Appendix K Exemption Request - M5 Fuel Rod Cladding Acr Florida Power & Light Company L

6501 S. Ocean Drive, Jensen Beach, FL 34957

L-2013-278 Enclosure Page I of 2 Reply to Request for Additional Information - License Amendment Request and 10 CFR 50.46 and 10 CFR 50 Appendix K Exemption Request - M5 Fuel Rod Cladding The US NRC issued the following RAI:

Generic Letter (GL) 88-16 "Removal of Cycle-Specific Parameter Limits from Technical Specifications [TSs]" provides guidance for the preparation of a license amendment request to modify TSs that have cycle-specific parameter limits. An acceptable alternative to specifying the values of cycle-specific parameter limits in TSs consists of: (1) the addition of the definition of a named formal report that includes the values of cycle-specific parameter limits that have been established using a Nuclear Regulatory Commission (NRC) approved methodology and consistent with all applicable limits of the safety analysis, (2) the addition of an administrative reporting requirement to submit the formal report on cycle-specific parameter limits to the Commission for information, and (3) the modification of individual TSs to note that cycle-specific parameters shall be maintained within the limits provided in the defined formal report. GL 88-16 further clarifies that in Core Operating Limits Report (COLR) TS [6.9-x] core operating limits shall be established and documented in the COLR before each reload cycle or any remaining part of a reload cycle. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC.

Based on the GL 88-16 guidance, TS 6.9. 1.1 1.b listed all approved methodologies to support all cycle-specific core operating parameters listed in TS 6.9. 1.11.a. Therefore, both TSs 6.9. 1. 11.a and 6.9. 1.11. b in COLR TSs establish a part of an acceptable alternative as stated in item (1) above. Please provide a description and the rationale for the parameters that will be detailed by BAW-1 0240(P)(A) Revision 0, "Incorporation of M5 Properties in Framatome ANP Approved Methods" in the TSs.

FPL RAI Response The rationale for including BAW-10240(P)(A), Revision 0 (Reference 1), in the list of Core Operating Limits Report (COLR) methodologies in TS 6.9.1.11.b is as follows:

1. NRC Final Safety Evaluation (SE) for Topical Report BAW-10240(P) (Reference 2) approved the incorporation of M5 properties in Framatome ANP approved methods, namely the mechanical analysis methodology (Reference 3), the Small Break LOCA (SBLOCA) methodology (Reference 4) and the non-LOCA methodologies (References 5 and 6).

BAW-10240(P)(A) provides the basis for using these methodologies for the applicable analyses to support the COLR limits, stated below in Item 3, for the fuel with M5 cladding.

2. The methodologies in References 3, 4, 5 and 6 are currently listed in TS 6.9.1.11.b (as stated below in References 3, 7, 8 and 6, respectively) as approved in the Extended Power Uprate (EPU) Amendment # 213. These methodologies are used to support the cycle-specific limits for the COLR parameters (see Item 3) listed in TS 6.9.1.11.a.

L-2013-278 Enclosure Page 2of 2

3. The methodologies in References 3, 6, 7 and 8 are used to verify or establish limits for the following COLR parameters:
a. Shutdown Margin,
b. Moderator Temperature Coefficient,
c. DNB Parameters,
d. Total Integrated Radial Peaking factor,
e. Linear Heat rate,
f.

CEA Insertion Limits.

4. Based on the GL 88-16 guidance, TS 6.9.1.11.b listed all approved methodologies to support cycle-specific COLR limits listed in TS 6.9.1.11.a. Since the Reference 1 Topical Report, BAW-10240(P) Revision 0 will be used in conjunction with the above specified COLR methodologies, to support the cycle-specific COLR limits for the parameters stated in Item 3 above, it is considered appropriate to include the Reference 1 Topical Report in the list of COLR methodologies in TS 6.9.1.11.b.

References

1.

Framatome (AREVA) ANP Document BAW-10240(P), Revision 0, "Incorporation of M5 Properties in Framatome ANP Approved Methods," September 2002.

2.

U.S. NRC Letter to Framatome ANP, "Final Safety Evaluation for Topical Report BAW-10240(P), Incorporation of M5 Properties in Framatome ANP Approved Methods (TAC No. MB7553)", dated May 5, 2004.

3.

EMF-92-116(P)(A), Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Design," Siemens Power Corporation, February 1999.

4.

EMF-2328(P)(A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," March 2001.

5.

EMF-2310(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," May 2004.

6.

EMF-1 961 (P)(A), Revision 0, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000.

7.

EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based,"

Revision 0, as supplemented by ANP-3000(P), "St. Lucie Unit 1 EPU - Information to Support License Amendment Request, " Revision 0.

8.

EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Revision 1, as supplemented by ANP-3000(P), "St. Lucie Unit I EPU -

Information to Support License Amendment Request, " Revision 0.